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Category:Letter
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 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 ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions 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 IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter 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) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations 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 ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions 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 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 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 IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 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 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 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. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 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 2024-09-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEARNL-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-24-0221, 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-24-0123, 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-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 ML23333A2152023-11-29029 November 2023 Residual Heat Removal Pump Inoperable for Longer than Allowed by Technical Specifications 05000364/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-2016-0062016-12-19019 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-2016-0042016-12-19019 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-2016-0032016-12-12012 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 2024-06-19
[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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