On June 16, 2016, the Davis-Besse Nuclear Power Station ( DBNPS) was in Mode 1'and 100 percent reactor power. At 1137 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.326285e-4 months <br />, during review of industry operating experience, an issue was identified for the potential impact of low barometric pressure associated with a tornado on the Emergency Diesel Generators ( EDGs). The EDGs are equipped with a crankcase positive pressure trip with a set point of approximately 1 inch of water. It was determined that a design basis tornado could create sufficient low pressure to potentially actuate the crankcase positive pressure trip due to different vent paths between the EDG Room and the EDG crankcase. If the crankcase pressure trip occurs before the EDG starts on an emergency signal due to the tornado, the crankcase pressure trip would cause an EDG lockout. The EDG lockout would then prevent either an EDG normal or emergency start until operators could manually reset the lockout. This condition could potentially affect both EDGs simultaneously.
This was an original EDG protective logic circuitry design issue that did not anticipate the interaction between the crankcase pressure trip and the outside atmospheric pressure. Corrective actions included temporarily disabling this trip and longer-term plant modification to make the change permanent.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(ii)(B), and 10 CFR 50.73(a)(2)(v)(A) through (D).
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Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23160A2342023-06-13013 June 2023 Confirmation of Initial License Examination L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models IR 05000346/20235012023-06-13013 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501 L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection IR 05000346/20230102023-05-0909 May 2023 Commercial Grade Dedication Inspection Report 05000346/2023010 ML23123A1272023-05-0303 May 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station IR 05000346/20230012023-05-0101 May 2023 Integrated Inspection Report 05000346/2023001 and 07200014/2022001 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 ML23111A1972023-04-26026 April 2023 Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station ML23114A1062023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23096A1382023-04-11011 April 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage ML23066A2892023-03-14014 March 2023 Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement ML23066A2592023-03-14014 March 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 2024-02-02
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000346/LER-2017-0022017-11-27027 November 2017 Auxiliary Feed Water Pump Turbine Bearing Damaged due to Improperly Marked Lubricating Oil Sight Glass, LER 17-002-00 For Davis-Besse Nuclear Power Station, Unit 1, Regarding Auxiliary Feed Water Pump Turbine Bearing Damaged due to Improperly Marked Lubricating Oil Sight Glass 05000346/LER-2017-0012017-09-18018 September 2017 Emergency Diesel Generator Fuel Oil Storage Tank Vents Not Adequately Protected from Tornado-Generated Missiles, LER 17-001-00 for Davis-Besse, Unit 1, Regarding Emergency Diesel Generator Fuel Oil Storage Tank Vents Not Adequately Protected from Tornado-Generated Missiles 05000346/LER-2016-0082017-02-27027 February 2017 Application of Technical Specification for the Safety Features Actuation System Instrumentation, LER 16-008-01 for Davis-Besse Nuclear Power Station Unit 1 Regarding Application of Technical Specification for the Safety Features Actuation System Instrumentation 05000346/LER-2016-0092016-11-0909 November 2016 Reactor Trip due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level, LER 16-009-00 for Davis-Besse Nuclear Power Station, Unit 1 Regarding Reactor Trip due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level 05000346/LER-2016-0072016-08-22022 August 2016 Pressurizer Code Safety Valve Setpoint Test Failures, LER 16-007-00 for Davis-Besse, Unit 1 Regarding Pressurizer Code Safety Valve Setpoint Test Failures 05000346/LER-2016-0062016-08-15015 August 2016 Potential to Trip Emergency Diesel Generator on High Crankcase Pressure, LER 16-006-00 for Davis-Besse Nuclear Power Station Unit 1 RE: Potential to Trip Emergency Diesel Generator on High Crankcase Pressure 05000346/LER-2016-0052016-07-11011 July 2016 - , Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass, LER 16-005-00 for Davis-Besse, Unit 1, Regarding Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass 05000346/LER-2016-0042016-06-0606 June 2016 Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation, LER 16-004-00 for Davis-Besse Nuclear Power Station, Unit 1 Regarding Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation 05000346/LER-2016-0032016-05-31031 May 2016 Leak from Reactor Coolant Pump Seal Piping Flexible Hose due to Undetected Manufacture Weld Defect, LER 16-003-00 for Davis-Besse Nuclear Power Station, Unit 1 Regarding Leak from Reactor Coolant Pump Seal Piping Flexible Hose due to Undetected Manufacture Weld Defect 05000346/LER-2016-0022016-03-29029 March 2016 Unanticipated Steam and Feedwater Rupture Control System Actuation, LER 16-002-00 for Davis-Besse Nuclear Power Station, Unit 1, Regarding Unanticipated Steam and Feedwater Rupture Control System Actuation 05000346/LER-2016-0012016-03-29029 March 2016 1 OF 7, LER 16-001-00 for Davis-Besse Nuclear Power Station Unit 1 Regarding Reactor Trip During Nuclear Instrumentation Calibrations and Steam Feedwater Rupture Control System Actuation on High Steam Generator Level ML0409003422004-03-26026 March 2004 LER 97-004-01 for Davis-Besse, Unit 1 Regarding Reactor Coolant Pump Motor Oil Piping Not Protected from Leakage as Required Per 10CFR50, Appendix R ML0404901932004-02-13013 February 2004 LER 99-003-01 for Davis-Besse, Unit 1 Regarding Failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding Technical Specification Limit ML0331701982003-11-0707 November 2003 LER 98-002-01 for Davis-Besse Unit 1 Regarding Plant Trip Due to High Pressurizer Level as a Result of Loss of Letdown Capability 2017-09-18
[Table view] |
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
DESCRIPTION OF OCCURRENCE:
System Description:
The on-site electric power system [EB] standby power at the Davis-Besse Nuclear Power Station (DBNPS) is provided by two separate and redundant Emergency Diesel Generators (EDG) [EK-DG] each connected to its respective 4160 Volt Essential Bus [EB-BU]. Each EDG is designed to start and reach stabilized voltage and frequency within ten seconds after receiving the starting signal. Upon receiving an emergency start signal from Safety Feature Actuation Signal (SFAS) [JE] or on a loss of essential bus voltage, the EDG is automatically isolated and loaded according to a predetermined sequence. All safety loads are assumed to be loaded within 35 seconds including the 10-second starting interval.
Each diesel engine is a General Motors, Bruce, 2-cycle, 20-cylinder, turbocharged diesel. Each engine drives a generator, which is nominally rated for 2600 kilowatts continuous electric service.
Each EDG is equipped with mechanical and electrical interlocks to ensure personnel protection and to prevent or limit equipment damage. During a non-emergency diesel generator operation (for example, on- line testing) each of the EDGs is provided with mechanical and electrical protective devices capable of initiating an EDG trip. However, during an emergency operation, namely on a loss of essential bus voltage or an SFAS Level 2, controls limit the EDG trip to generator differential relay action and engine overspeed.
This measure is taken to minimize the possibility of the protective devices needlessly preventing the EDG from operating when required, as during a Design Basis Accident. However, alarms are still provided for high crankcase pressure, low lube oil pressure, high engine temperature, and electrical protective relays.
Mechanical protection is provided for the EDG engine by monitoring crankcase pressure to protect the engine from damage. If crankcase pressure increases above the setpoint of 1 inch of water gauge (WG) (with a range of 0.8 to 3 inches WG), the engine will trip and a local alarm will be actuated. The trip function is bypassed by an EDG emergency start signal. The EDG High Crankcase Pressure Switches [PS] are pressure-sensitive devices used to determine abnormal condition of the crankcase. A negative pressure is normally maintained in the crankcase with the engine running. When the EDG is in standby, the crankcase directly communicates with the EDG exhaust and the crankcase pressure would be similar to atmospheric pressure outside of the EDG Rooms in the Auxiliary Building. Therefore, if the pressure of the EDG rooms would be 0.8 inches WG less than the pressure in the crankcase, the EDG High Crankcase Pressure Switches could trip.
Each EDG is provided with storage tanks having a fuel oil capacity sufficient to operate that diesel for a period of 7 days following a Loss of Offsite Power. This onsite fuel oil capacity is based on the fact that 7 days is sufficient time to replenish the onsite tank inventory from outside sources. Additionally, one non- class 1 E diesel generator can be aligned to power either 4160 Volt essential bus in the event of a station blackout.
Technical Specifications:
DBNPS Technical Specification (TS) Limiting Condition for Operation (LCO) 3.8.1.b requires two separate and independent EDGs to be Operable while the plant is operating in Modes 1, 2, 3, and 4. With one EDG inoperable, the Operability of the remaining A.C. sources must be demonstrated by performing Surveillance Requirement 3.8.1.1 (verification of correct breaker alignments and indicated power availability) within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter and by performing Surveillance Requirement 3.8.1.2 (verification that the Operable EDG starts and accelerates up to 900 rpm) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Two EDGs must be restored to Operable status within 7 days or the plant must be in Hot Standby (Mode 3) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown (Mode 5) completed within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. With two EDGs inoperable, the Operability of one EDG must be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the plant must be in Hot Standby (Mode 3) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown (Mode 5) completed within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
DESCRIPTION OF EVENT:
An industry operating experience report in June 2016 identified the potential for differential pressure changes caused by a tornado to actuate the plant's EDG High Crankcase Pressure switches during normal, stand-by mode, locking-out the EDGs prior to receiving an emergency mode start signal.
Review of the DBNPS Auxiliary Building Tornado Depressurization calculation on June 16, 2016, determined the specific scenario had not been previously considered, and the calculated pressure differences between the EDG rooms and outside atmosphere caused by a design basis tornado could exceed the EDG High Crankcase Pressure Switch setting of 1 inch WG (nominal), creating the same situation at the DBNPS.
The scenario assumes a tornado lowers atmospheric pressure in both EDG rooms, and the pressure inside the engines remains slightly higher, such that the high crankcase pressure switches trip. Although the crankcase pressure trips are bypassed on an emergency start of the engines, the scenario assumes the trips happen before the EDGs are required to start fora Loss of Offsite power (or other bus undervoltage condition). The DBNPS review of the operating experience concluded this scenario could possibly cause the differential pressure necessary to trip the crankcase pressure switches on the DBNPS EDGs. A trip of the crankcase pressure switches, while in standby, causes actuation of the shutdown relays, which in turn causes engine lockouts, keeping the EDGs from being able to start during an emergency condition.
CAUSE OF EVENT
The original design of the EDGs' protective devices did not anticipate the interaction between the High Crankcase Pressure switch and atmospheric pressure outside of the EDG Rooms of the Auxiliary Building during a tornado event. Additionally, there were no means to bypass or delay a trip signal in normal, stand- by mode which contributed to the susceptibility of the High Crankcase Pressure switch to possibly actuate during a tornado event.
Neither the DBNPS nor, others in the nuclear industry recognized that differential pressures due to a tornado could actuate an EDG High Crankcase Pressure Switch until this recent industry operating experience discovery.
ANALYSIS OF EVENT:
This issue is considered to have at most a substantial safety significance. The delta Core Damage Frequency (CDF) of 3.42E-05, when calculated and using the most conservative assumptions is within the substantial safety significance range of significance. However, the conservative assumptions include any tornados striking the site would lockout the DBNPS EDGs because of this condition.
The conservative nature of this assumption is evidenced by the fact that the tornado which did strike the facility in June 1998 did not result in an EDG lockout. As a result, sensitivity studies using less conservative probabilities that a tornado would travel the specific path needed to lockout the EDGs were performed. These studies show that the delta CDF could be as low as 5.8E-07, which is within the very low safety significance range. Also, credit was not taken for operator actions to reset the EDGs. If an operator action with a 1 percent failure rate is taken into consideration, the delta CDF would be 5.8E-07, which is within the very low safety significance range. Combining both operator action credit (1 percent failure rate) with less conservative tornado pathing (1 percent chance to cause the condition) results in a delta CDF of 2.4E-07, which is within the very low safety significance range.
Additionally, since the EDG crankcase pressure lockout is bypassed during an emergency start, it may be assumed that the tornado does not cause a loss of offsite power as it approaches the site in order for this scenario to occur. The prevailing winds at the site and tornados in this geographical area, generally travel from West to East. It is likely that the switchyard and/or offsite power sources would be disabled prior to the tornado impacting the EDG Rooms and actuating the crankcase pressure switches. It is also noted that in the past 3 years, there has only been one tornado in Ottawa County, Ohio, which occurred on November 17, 2013. The tornado was classified as an EF1 and was never within 11 miles of the site.
Reportability Discussion:
The EDG crankcase pressure switch actuation due to pressure differentials during a tornado event is an unanalyzed condition and because it affects both EDGs simultaneously, it would affect all safety related onsite AC power. Therefore, this condition represents an unanalyzed condition that significantly degrades plant safety, and therefore is reportable per 10 CFR 50.73(a)(2)(ii)(B). The NRC was verbally notified of this event per 10 CFR 50.72(b)(3)(ii)(B) at 1459 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.551495e-4 months <br /> on June 16, 2016, via Event Number 52010.
A further review of this condition, concluded that because this condition was present from the original design and affected both EDGs simultaneously, coupled with the complexity of the tornado / Auxiliary Building analysis, there was not sufficient evidence to support a reasonable expectation that either EDG could have performed their safety function in the past if a design basis tornado had struck the Davis-Besse site.
Because this condition would have affected both of the EDGs simultaneously, this condition is reportable per 10 CFR 50.73(a)(2)(v) as a condition that could have prevented the fulfillment of the safety function of a system needed to: (A) shutdown the reactor and maintain it in a safe shutdown condition; (B) remove residual heat; (C) control the release of radioactive material; and (D) mitigate the consequences of an accident.
ANALYSIS OF EVENT (Reportability Discussion continued) Furthermore, because both of the EDGs, in the postulated tornado scenario with the EDG crankcase pressure switch actuation, were simultaneously affected and would not have fulfilled their safety function, and since the plant operated with the subject equipment in this condition for longer than the TS LCO Action Time; this issue represents an operation prohibited by the Technical Specifications, which also is reportable as a LER in accordance with 10 CFR 50.73(a)(2)(i)(B).
CORRECTIVE ACTIONS:
Completed Actions:
Direction was provided to the operators on June 16, 2016, to implement maintenance activities to remove the Crankcase Pressure Relay/trip, as a compensatory measure, should a local Tornado Watch or Warning be issued.
A Prompt Operability Determination was completed on June 17, 2016, formalizing the compensatory measure to be implemented through the Corrective Action Program. As noted in the Prompt Operability Determination, the engine vendor has agreed that removal of the Crankcase Pressure Relay/trip relay does not adversely impact engine operation.
An Operations Standing Order was developed and issued on June 17, 2016, to provide direction to the operators to implement the compensatory measure during weather conducive to the formation of a tornado as identified by notification of a locally declared Tornado Watch or Warning.
A temporary modification was developed and implemented on June 25, 2016, to disable the EDG Crankcase Pressure Switch trip function for EDG 1 and 2.
Scheduled Actions:
A modification will be developed to permanently disable the EDG High Crankcase Pressure switches trip logic.
PREVIOUS SIMILAR EVENTS
There have been no LERs at the DBNPS in the past three years involving the inoperability of the Emergency Diesel Generators or latent system design issues.
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05000346/LER-2016-001 | 1 OF 7 LER 16-001-00 for Davis-Besse Nuclear Power Station Unit 1 Regarding Reactor Trip During Nuclear Instrumentation Calibrations and Steam Feedwater Rupture Control System Actuation on High Steam Generator Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000346/LER-2016-002 | Unanticipated Steam and Feedwater Rupture Control System Actuation LER 16-002-00 for Davis-Besse Nuclear Power Station, Unit 1, Regarding Unanticipated Steam and Feedwater Rupture Control System Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000346/LER-2016-003 | Leak from Reactor Coolant Pump Seal Piping Flexible Hose due to Undetected Manufacture Weld Defect LER 16-003-00 for Davis-Besse Nuclear Power Station, Unit 1 Regarding Leak from Reactor Coolant Pump Seal Piping Flexible Hose due to Undetected Manufacture Weld Defect | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000346/LER-2016-004 | Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation LER 16-004-00 for Davis-Besse Nuclear Power Station, Unit 1 Regarding Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2016-005 | - , Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass LER 16-005-00 for Davis-Besse, Unit 1, Regarding Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2016-006 | Potential to Trip Emergency Diesel Generator on High Crankcase Pressure LER 16-006-00 for Davis-Besse Nuclear Power Station Unit 1 RE: Potential to Trip Emergency Diesel Generator on High Crankcase Pressure | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2016-007 | Pressurizer Code Safety Valve Setpoint Test Failures LER 16-007-00 for Davis-Besse, Unit 1 Regarding Pressurizer Code Safety Valve Setpoint Test Failures | 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 | 05000346/LER-2016-008 | Application of Technical Specification for the Safety Features Actuation System Instrumentation LER 16-008-01 for Davis-Besse Nuclear Power Station Unit 1 Regarding Application of Technical Specification for the Safety Features Actuation System Instrumentation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2016-009 | Reactor Trip due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level LER 16-009-00 for Davis-Besse Nuclear Power Station, Unit 1 Regarding Reactor Trip due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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