2-2-2017 | On 12/7/16 Units 1 and 2 were in Mode 1 at 100 percent rated thermal power. Engineering personnel determined that the Unit 1 and Unit 2 Service Water Intake Structure ( SW IS) intake and exhaust ventilation hoods were not adequately protected from tornado generated missiles. Subsequent evaluations on 1/26/17 resulted in the determination that the emergency diesel generator ( EDG) fuel oil storage tank ( FOST) vents were also not adequately protected from tornado generated missiles. Operations subsequently declared the affected systems inoperable, implemented Enforcement Guidance Memorandum (EGM) 15-002, " Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance" and the required compensatory measures, and then declared the affected equipment operable but non-conforming.
This comition is an original plant design legacy issue. Immediate compensatory measures included actions to take if needed as described in severe weather procedures, and monitoring of system parameters on the MCB in accordance with annunciator response procedures. A risk based evaluation will be performed or plant modifications will be undertaken to establish compliance with the site's tornado missile protection design basis. |
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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 teamed are incorporated into the licensing process and led back to industry.
Send coents renaming burden esbmate to the FOIA, Privacy and Information Collections Branch sail (53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internal e-m lo InfocoLlects.Resourceenrc. . and to the Desk Officer, Office ol Information and Regulatory Affairs, NEOB-10202, (31 104). Orme of Management and Budget, Washington, DC 20503.11a means used to impose an intonation collecbon does not dmplay a 4:nub/valid ONE control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the intonation collection.
Joseph M. Farley Nuclear Plant, Unit 1 05000- 348 No,
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor
A. UNIT STATUS AT TIME OF EVENT
Unit 1, Mode 1, 100 percent power Unit 2, Mode 1, 100 percent power No plant transients were associated with this event. Thus, no structures, systems, or components (SSC) were inoperable at the start of this event which contributed to this condition.
Background NRC documents:
Enforcement Guidance Memorandum (EGM) 15-002, "Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance," provides guidance to exercise enforcement discretion when an operating power reactor licensee does not comply with a plant's current site-specific licensing basis for tornado-generated missile protection. Specifically, discretion would apply to the applicable Technical Specification (TS) Limiting Condition(s) for Operation (LCO) that would require a reactor shutdown or mode change in the event a licensee could not meet TS LCO required action(s) within the TS completion time.
Interim Staff Guidance DSS-ISG-2016-01, "Clarification of Licensee Actions in Receipt of Enforcement Discretion Per Enforcement Guidance Memorandum EGM 15-002," provides interim staff guidance to facilitate staff understanding of expectations for consistent oversight associated with implementing enforcement discretion for tornado missile protection noncompliance(s) per EGM 15-002.
Appendix A to DSS-ISG-2016-01 provides guidance for acceptable initial and comprehensive compensatory measures for licensee use in implementing the enforcement discretion outlined in EGM 15-002. The licensee should declare (log) the utilization of EGM 15-002, inform the resident inspector, and enter the issue into the corrective action program. For initial compensatory measures, it is expected that the measures listed are already in place at sites that may be affected by severe weather, such as tomados and/or hurricane force winds. The measures should be verified as current and readily deployable within a very short timeframe.
B. DESCRIPTION OF EVENT
On 12/7/16 during the evaluation of protection of Technical Specification (TS) equipment from damage from tornado generated missiles, Farley site engineering identified nonconforming conditions in the plant design such that the specified TS equipment did not meet the current design basis for protection against tornado generated missile impacts. Specifically, the Unit 1 and Unit 2 Service Water (SW) [BI] pumps could be rendered inoperable due to a tornado generated missile strike on the Service Water Intake Structure (SWIS) intake and exhaust ventilation hoods. This vulnerability was not included in the site's tornado missile risk analysis (TORMIS).
The SWIS intake and exhaust ventilation hoods, located on the roof of the SWIS, could be crimped as a result of a tornado missile strike, thus reducing air flow and challenging the performance of their heating and cooling safety functions. In addition, if the SWIS ventilation hoods were damaged or removed by a tornado missile strike, rainwater may enter the area below the hoods. The SWIS batteries and breakers internet e-mail to Infocollects.Resourcefitnrc , and to the Desk Officer, Off ce of Information and Regulatory Affairs, NEOB-10202, .1 r ti:14),. Office .o Management arid Budget, Washington, DC 29503. It a means used to mpose an *mat on ccilection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person Is not reqi:red to respond to, the intormaton collection Joseph M. Farley Nuclear Plant, Unit 1 05000- 348 n YEAR SEOUEhr AL Ni.,V3i.R C.
D.
for the 1C and 2C SW pump motors could be rendered inoperable due electrical shorts caused by intrusion of rainwater.
Subsequent evaluations on 1/26/17 resulted in the determination that the emergency diesel generator (EDG) fuel oil storage tank (FOST) [DC] vents were also not adequately protected from tornado generated missiles. Each EDG FOST is provided with a 1-inch vent pipe that extends above the ground and is exposed to tornado missiles. If these vent pipes were hit by a tornado missile they could become crimped and impede the transfer of fuel oil thereby resulting in failure of the associated EDGs to perform their safety functions.
These SSCs were declared inoperable and EGM 15-002 was invoked. To meet the intent of EGM 15-002 to restore the SW Pumps to an operable but degraded / non-conforming (OBDN) status, existing measures were verified as current and readily deployable for both units and were implemented as initial compensatory measures within the allowed time by the applicable LCOs. These measures included actions to take if needed as described in severe weather procedures, and monitoring of system parameters on the MCB in accordance with annunciator response procedures. In addition, new Compensatory Measures were established to inspect, protect, and restore function to the ventilation hoods and affected areas in the SWIS, and similar measures are being established for the FOST vent pipes.
CAUSE OF EVENT
This condition is an original plant design legacy issue. Due to the historical nature of this vulnerability, a specific cause has not been identified.
REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT
This event is reportable as required by:
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- 10 CFR 50.73(a)(2)(v)(D) for a condition that at the time of discovery could have prevented the fulfillment of a safety function of structures or systems needed to mitigate the consequences of an accident.
As documented in EGM 15-002, tornado missile scenarios that may lead to core damage are very low probability events because safety-related SSCs are typically designed to withstand effects of tomados.
For a tornado missile-induced scenario to occur, a tornado would have to hit the site and result in the generat on of missiles that would hit and fail vulnerable, unprotected safety-related equipment, and/or unprotected safety-related subcomponents in a manner that is non-repairable and non-recoverable. In addition, because plants are designed with redundancy and diversity, the tornado missiles would have to affect mulliple trains of safety systems and/or means of achieving safe shutdown.
The NRC has completed a generic risk analysis of potential tornado missile protection noncompliances to examine the risk s:gnificance of these scenarios. This assessment documents a conservative, bounding-type analysis of the risk significance for plant facilities. The generic analysis assumed that core damage would occur if a tornado hit a plant located in the most active tornado region in the country and Reported lessons learned are incorporated into the Ircersng process and led back to industry.
Send comments roguing burden estimate to the FOIA, Privacy and Information Collections Branch (1.5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to trifccollects.Resourceeruc.gov, arid to the Desk Of5cer, Office of Information and Regulatory Affairs, NEB0202, (3150-0104),. Moe of Management end Budget Washington, DC 20503. II a means used to [moose an mlortnahon osllectuxi does not display a curie* valid OMB control number, the NRC. may not conduct or sponsor, and a person Is not reqL, red to respond to, the information collection.
Joseph M. Farley Nuclear Plant, Unit 1 05000- 348 .. YEAR SEOUENT1AL No.
that it caused a tornado-generated missile to fail all emergency core cooling equipment at the plant with no ability to recover. Given this conservative assumption, the staff's study established that the core damage frequency (CDF) associated with tornado missile-related noncompliances are well below CDFs requiring immediate regulatory action. In summary, the generic bounding risk analysis performed by the NRC concluded that this issue is of low risk significance.
During a postulated design basis tornado, the conditions documented could have resulted in a loss of function for the SW pumps or a loss of the safety function for the EDGs. The SW pumps mitigate the effects of postulated accidents by providing essential plant cooling to safety related systems and components, including those required for emergency core cooling. The EDGs are used to mitigate the effects of a loss of offsite power by providing an emergency AC power source. This condition had no actual safety consequences impacting plant or public safety as Farley did not experience an actual tornado missile event. Compensatory measures were and continue to be in place to mitigate the effects of a tornado missile strike. Also, only three of six exhaust ventilator fans are required to handle the heating load of the pump room. This redundancy reduces the risk of the postulated conditions from occurring during a tornado missile event. Therefore, enforcement discretion until June 10, 2018, will not impose significant additional risk to public health and safety.
E. CORRECTIVE ACTION
A risk based evaluation will be performed or a plant modification will be undertaken to establish compliance with the site's tornado missile protection design basis.
F. ADDITIONAL INFORMATION
1) Previous Similar Events: No other similar previous events have been reported.
2) Commitment Information: This report does not create any licensing commitments.
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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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