Category:Letter
MONTHYEARML24330A1232024-12-20020 December 2024 Issuance of Amendment Nos. 251, 248, 226, and 208 Revising TS to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24351A0402024-12-19019 December 2024 Authorization of Proposed Alternative RR-PR-04 Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves IR 05000348/20240122024-12-11011 December 2024 Biennial Problem Identification and Resolution Inspection Report 05000348/2024012 and 05000364/2024012 NL-24-0406, Response to Request for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0032024-11-15015 November 2024 Response to Request for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-003 ML24320A1342024-11-15015 November 2024 Regulatory Audit in Support of Review of the Exemption Requests Regarding Physical Barriers EPIDs L-2023-LLE-0018 and -0021 (Nonproprietary Cover Letter) NL-24-0397, Response to Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement2024-11-15015 November 2024 Response to Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement IR 05000348/20240032024-11-13013 November 2024 Integrated Inspection Report 05000348/2024003, 05000364/2024003 and 07200042/2024001 IR 05000348/20244032024-11-13013 November 2024 – Security Baseline Inspection Report 05000348/2024403 & 05000364/2024403 NL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 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 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 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 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 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 NL-24-0315, – ISFSI, Registration of Spent Fuel Cask Use2024-08-0909 August 2024 – ISFSI, Registration of Spent Fuel Cask Use 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-24-0230, 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-24-0234, 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-24-0143, 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 05000348/LER-2024-002-01, 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) 05000348/LER-2024-001, 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 2024-09-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000348/LER-2024-002-01, 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 05000348/LER-2024-001, 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 05000364/LER-2024-002, 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 05000364/LER-2024-001, Manual Reactor Trip Due to Rising Steam Generator Levels2024-01-11011 January 2024 Manual Reactor Trip Due to Rising Steam Generator Levels 05000364/LER-2023-003, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits2023-12-0707 December 2023 Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000348/LER-2023-003, Emergency Diesel Generator (Eog) Lube Oil Pwnp Outlet Coupling Leak2023-12-0707 December 2023 Emergency Diesel Generator (Eog) Lube Oil Pwnp Outlet Coupling Leak 05000364/LER-2023-002, 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 05000348/LER-2023-002, Residual Heat Removal Pump Inoperable for Longer than Allowed by Technical Specifications2023-11-29029 November 2023 Residual Heat Removal Pump Inoperable for Longer than Allowed by Technical Specifications 05000364/LER-2023-001, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits2023-09-28028 September 2023 Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000348/LER-2023-001, Automatic Reactor Trip Due to DC Ground on Turbine Trip Solenoid2023-03-30030 March 2023 Automatic Reactor Trip Due to DC Ground on Turbine Trip Solenoid 05000348/LER-2022-001, Outdated Relay Settings Resulted in an Automatic Reactor Trip After a Floor Tile Was Dropped in High Voltage Switch House2022-09-30030 September 2022 Outdated Relay Settings Resulted in an Automatic Reactor Trip After a Floor Tile Was Dropped in High Voltage Switch House 05000348/LER-2021-001, Automatic Reactor Trip Due to Turbine Generator Trip2021-06-21021 June 2021 Automatic Reactor Trip Due to Turbine Generator Trip 05000364/LER-2020-001-01, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2021-03-25025 March 2021 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 05000364/LER-2020-002, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2020-12-21021 December 2020 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 05000364/LER-2020-001, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2020-12-0303 December 2020 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 05000348/LER-2019-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2019-12-0909 December 2019 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 05000364/LER-2019-003, Manual Reactor Trip Due to 2C Reactor Coolant Pump High Vibration Indication2019-11-12012 November 2019 Manual Reactor Trip Due to 2C Reactor Coolant Pump High Vibration Indication 05000364/LER-2019-002, Manual Reactor Trip Due to Misaligned Rod During Low Power Physics Testing2019-06-27027 June 2019 Manual Reactor Trip Due to Misaligned Rod During Low Power Physics Testing 05000364/LER-2019-001, Inoperable Containment Isolation Valve Due to Design Control Error2019-06-10010 June 2019 Inoperable Containment Isolation Valve Due to Design Control Error 05000364/LER-1917-005, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector2018-01-11011 January 2018 Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector 05000364/LER-1917-004, Regarding Turbine-Driven Auxiliary Feedwater Pump Steam Admission Valve Air Leak Resulted in a Condition Prohibited by Technical Specifications2017-12-22022 December 2017 Regarding Turbine-Driven Auxiliary Feedwater Pump Steam Admission Valve Air Leak Resulted in a Condition Prohibited by Technical Specifications 05000364/LER-1917-003, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits2017-12-20020 December 2017 Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-1917-002, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits2017-12-19019 December 2017 Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000348/LER-1917-001, Regarding Entry Into Mode of Applicability with Component Cooling Water (CCW) Isolation Valve Inoperable Due to Configuration Error2017-09-28028 September 2017 Regarding Entry Into Mode of Applicability with Component Cooling Water (CCW) Isolation Valve Inoperable Due to Configuration Error 05000364/LER-1917-001, Regarding 28 Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak Without Makeup Capability2017-08-21021 August 2017 Regarding 28 Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak Without Makeup Capability 05000348/LER-2016-009, Regarding Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications2017-02-0202 February 2017 Regarding Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications 05000348/LER-2016-008, Regarding Manual Reactor Trip Due to Generator Voltage Swings2017-01-23023 January 2017 Regarding Manual Reactor Trip Due to Generator Voltage Swings 05000348/LER-2016-007, Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters2017-01-13013 January 2017 Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters 05000348/LER-2016-005, Regarding Toxic Gas Event2016-12-28028 December 2016 Regarding Toxic Gas Event 05000348/LER-2016-006, Regarding Manual Reactor Trip Due to Loss of Speed Control on 1A Steam Generator Feed Pump2016-12-19019 December 2016 Regarding Manual Reactor Trip Due to Loss of Speed Control on 1A Steam Generator Feed Pump 05000348/LER-2016-004, Regarding Unapproved Environmental Qualification Material Caused Lnoperability of One Containment Cooling Train2016-12-19019 December 2016 Regarding Unapproved Environmental Qualification Material Caused Lnoperability of One Containment Cooling Train 05000348/LER-2016-003, Regarding Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band2016-12-12012 December 2016 Regarding Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band 05000348/LER-2016-002, Regarding Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve2016-11-30030 November 2016 Regarding Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve 05000364/LER-2016-001, Regarding Manual Reactor Trip Due to High Steam Generator Level2016-07-0505 July 2016 Regarding Manual Reactor Trip Due to High Steam Generator Level 05000348/LER-2015-005-01, Regarding Condition Prohibited by Technical Specifications Due to Turbine Driven Auxiliary Feedwater Design Issue2016-07-0101 July 2016 Regarding Condition Prohibited by Technical Specifications Due to Turbine Driven Auxiliary Feedwater Design Issue 05000348/LER-2016-001, Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications2016-06-0909 June 2016 Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications 05000348/LER-2015-005, Regarding Condition Prohibited by Technical Specifications Due to Turbine Driven Auxiliary Feedwater Design Issue2016-01-15015 January 2016 Regarding Condition Prohibited by Technical Specifications Due to Turbine Driven Auxiliary Feedwater Design Issue 05000364/LER-2015-002, Regarding Entry Into Condition Prohibited by Technical Specifications Due to All Containment Cooling Level Monitoring Systems Inoperable2016-01-0808 January 2016 Regarding Entry Into Condition Prohibited by Technical Specifications Due to All Containment Cooling Level Monitoring Systems Inoperable 05000348/LER-2015-004, Re Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band2015-10-0909 October 2015 Re Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band 05000348/LER-2015-003, Cancellation of LER 15-003-00, Failure to Meet a Technical Specification Completion Time for Reportability2015-09-11011 September 2015 Cancellation of LER 15-003-00, Failure to Meet a Technical Specification Completion Time for Reportability 05000348/LER-2015-001, Regarding Automatic Actuation of the Auxiliary Feedwater System When the 1B SGFP Was Tripped2015-07-0202 July 2015 Regarding Automatic Actuation of the Auxiliary Feedwater System When the 1B SGFP Was Tripped 05000348/LER-2015-002, Regarding Technical Specification Shutdown Due to Reactor Coolant Pump Trip2015-07-0202 July 2015 Regarding Technical Specification Shutdown Due to Reactor Coolant Pump Trip 05000364/LER-2015-001, Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue2015-03-0909 March 2015 Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue 05000364/LER-2014-003, Unit 2 Regarding Reactor Protection System Actuation Due to Invalid Digital Rod Position Indication Signal2015-01-13013 January 2015 Unit 2 Regarding Reactor Protection System Actuation Due to Invalid Digital Rod Position Indication Signal 05000364/LER-2014-002, Regarding Manual Reactor Trip Due to Loss of 2B Startup Auxiliary Transformer and Loss of Offsite Power2014-12-12012 December 2014 Regarding Manual Reactor Trip Due to Loss of 2B Startup Auxiliary Transformer and Loss of Offsite Power 05000348/LER-2014-003, Regarding Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer than Allowed by Technical Specifications2014-06-0202 June 2014 Regarding Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer than Allowed by Technical Specifications 05000348/LER-2014-002, Regarding B-Train RHR Inoperable for Longer than Allowed by Technical Specifications Due to Misadjusted Flow Control Valve Linkage2014-04-29029 April 2014 Regarding B-Train RHR Inoperable for Longer than Allowed by Technical Specifications Due to Misadjusted Flow Control Valve Linkage 05000348/LER-2014-001, Regarding Failure to Comply with Technical Specification 3.4.3 During Reactor Coolant System Vacuum Refill2014-04-15015 April 2014 Regarding Failure to Comply with Technical Specification 3.4.3 During Reactor Coolant System Vacuum Refill 05000364/LER-2014-001, Regarding Inoperable S-Train Solid State Protection System Results in Technical Specification Required Shutdown2014-03-12012 March 2014 Regarding Inoperable S-Train Solid State Protection System Results in Technical Specification Required Shutdown 05000348/LER-2013-004, Regarding Unfused DC Ammeter Circuits Results in an Unanalyzed Condition2014-02-14014 February 2014 Regarding Unfused DC Ammeter Circuits Results in an Unanalyzed Condition 2024-06-19
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