RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
TMI-11-075, Response to Request for Additional Information Related to Technical Specification Change Request No. 351 Maximum Allowable Power with Inoperable Main Steam Safety Valves
PMNS20180935, Pre-Licensing Meeting with Duke Energy Carolinas, LLC, for the McGuire Nuclear Station, Unit 2
SECY-18-0088, Weekly Information Report - Week Ending August 31, 2018
RA-18-0114, License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies
GNRO-2007/00004, License Amendment Request, Request for a Technical Specification Change to Allow Use of Control Rod Assemblies with Different Control Material
RA-18-0184, Withdrawal of License Amendment Request to Revise Technical Specification (TS) 4.2.2, Control Rod Assemblies
05000267/LER-1981-019, Forwards LER 81-019/03L-0.Detailed Event Analysis Encl
CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)
ND-18-0067, Request for License Amendment: Fuel Management Related Technical Specifications (LAR-18-005)
05000267/LER-1982-031, Forwards LER 82-031/03L-0.Detailed Event Analysis Encl
NL-03-026, Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval
05000267/LER-1982-029, Forwards LER 82-029/03X-1.Detailed Event Analysis Encl
RS-02-102, Additional Information Regarding License Amendment Request to Eliminate Requirement for Continuous Control Room Watch When Nuclear Fuel Stored in Spent Fuel Pool
NL-02-001, License Amendment Request - Detection of Technical Specifications for Reactor Vessel Material Surveillance Program
CNL-20-042, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05)
CNL-20-045, Supplement to Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05)
05000267/LER-1982-034, Forwards LER 82-034/03L-0.Detailed Event Analysis Encl
05000289/LER-1997-010, Forwards LER 97-010-00,concerning Inoperable PORV Resulting from Violation of TS 4.2.2,in that,post-maintenance Test Was Not Performed on PORV Following Replacement During 11R Refueling
05000409/LER-1983-001, Forwards LER 83-001/03L-0 & Updated LER 82-020/03X-1. Detailed Event Analysis Encl
1CAN118604, Discusses Results of Volumetric Exam of Reactor Coolant Pump a Welds as Required by First 10-yr Inservice Insp Program. Analysis Shows Pump Casing to Be Structurally Sound W/Flaw Present.Calculation Repts Encl
LR-N970670, Application for Amend to License NPF-57,requesting Rev to App B of TS 4.2.2, Terrestrial Ecology Monitoring, by Rewording Section to Include Completion of Salt Drift Monitoring Program Which Was Completed in Mar 1989
ST-HL-AE-2493, Forwards Radial Peaking Factor Limit Rept Per Tech Specs 4.2.2.2e & 6.9.1.6
05000289/LER-1997-010-01, :on 971012,PORV Inoperability Was Determined. Caused by mis-wiring & Failure to Perform post-maintenance Test Following Replacement During 11R Refueling Outage.Porv Replaced During 12R Refueling Outage Was Wired Correctly
05000409/LER-1986-005, :on 860124,high Pressure Svc Water/Alternate Core Spray Diesel 1A Removed from Svc to Replace Weeping Cooling Water Pump Discharge Hose.Surveillance Test Conducted Following Hose Replacement
05000409/LER-1985-020, :on 851231,high Pressure Svc Water Diesel Pump 1A Failed Following Addition of Fuel Additive.Caused by Faulty Fuel Injection Pump.Pump Replaced.Periodic Pump Replacement Will Be Added to Maint Program
05000409/LER-1985-013, :on 850701,09,10 & 12,high Pressure Svc Water diesel-driven Pump 1A Malfunctioned.Caused by Air in Fuel Line.Priming Tank Refilled & Diesel Fuel Filters Vented
05000409/LER-1985-007, :on 850412,after Reactor Vessel Hydrostatic Test Performed,Alternate Core Spray Sys Noticed to Be Manually Lined Up to River,Rather than Reactor Vessel.Caused by Personnel Error.Procedure Modified
05000369/LER-1992-002-02, :on 920117,error Detected in Results from Computer Program Used to Perform Power Distribution Surveillance Calculations.Caused by Design Deficiency. Program Corrected
05000267/LER-1983-044-03, /03L-0:on 831011,bearing Water Makeup Pump P-2105 Removed from Svc W/Reactor Operating at 65% Power.Caused by Two Leaking Valves & Two Leaking Filters in Need of Repair. Pump Returned to Svc within 24 H
05000267/LER-1983-036-03, /03L-0:on 830928,emergency Feedwater Supply Header to Loop I Helium Circulator Water Turbine Drives Isolated Twice to Perform Maint on Two Leaking Header Safety Valves & One Pressure Control Valve.Valves Repaired
05000267/LER-1983-037-03, /03L-0:on 830928,one Bearing Water Makeup Pump Taken Out of Svc While Reactor at 65% Power.Caused by Leaking Mechanical Seal Due to Normal Operation & Wear.Seal Replaced.Pump Returned to Svc
05000267/LER-1983-035-03, /03L-0:on 830922,emergency Feedwater to Loop 1 Helium Circulator Water Turbine Drives Isolated to Allow Repair of Leaking Relief Valve & Calibr of Two Associated Pressure Control Valves.Valve Repaired
05000387/LER-1982-080-03, /03L-0:on 821226,surveillance Per Tech Spec 4.2.2 Could Not Be Performed within Time Limits.Caused by Failure of Nuclear Steam Sys Processor Due to Interaction Between Transversing in-core Probe Switch Position & Processor
05000267/LER-1983-053-03, /03L-0:on 831210,bearing Water Makeup Pump Removed from Svc W/Reactor Operating at Approx 25% Power,To Repair Associated Leaking Valves & Filters.Caused by Component Failure.Valve & Filters Repaired or Replaced
05000387/LER-1983-121-03, /03L-0:on 830902,average Power Range Monitor Flow Biased Simulated Thermal Power - Upscale Scram & Neutron Flux - Upscale Control Rod Block Trip Setpoints Higher than Tech Spec Limit.Caused by Power Peaking
05000267/LER-1982-029-03, /03X-1:on 820712,20 & 21,emergency Feedwater Headers to Helium Circulator Pelton Wheel Drives Isolated to Perform Maint on Leaking Header Safety Valves.Cause of Leakage Not Stated
05000409/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Submitted
05000409/LER-1982-015, Forwards LER 82-015/01T-0.Detailed Event Analysis Submitted
05000271/LER-1993-007, :on 930609,determined That Daily Instrument Checks Required by TS Were Not Included in Operator Rounds. Caused by Mgt & Human Factors Weakness.Ts Proposed Change & Amend Issue Process Will Be Performed
05000304/LER-1988-001-03, :on 880108,nuclear Station Operator Failed to Log Delta I W/Nuclear Instrumentation Channel Test in Test. Caused by Personnel Error.Operator Reviewed Program Description of Delta I Program
1CAN028209, Responds to NRC Re Violations Noted in IE Insp Rept 50-313/81-34.Corrective Actions:Scheduled Nozzle Insp During Next Two Refueling Outages,Reviewed Tech Specs & Requested Approval of 771019 Tech Specs Change Requests
05000409/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted
05000267/LER-1981-054, Forwards LER 81-054/03L-0.Detailed Event Analysis Encl
05000267/LER-1983-023-03, /03L-0:on 830701 & 02,emergency Feedwater Unavailable to Drive Loop I Helium Circulation Water Turbines.Caused by Normal Wear of Valve PV-21243.Valve Internals Replaced & Valve Calibr
05000267/LER-1983-020-03, /03L-0:on 830604,emergency Feedwater Header Supply to Loop I Helium Circulator Turbine Water Drive Isolated & Bearing Water Make Up Pump Taken Out of Svc.Caused by Flexitallic Gasket Failure Due to Normal Wear
05000267/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-060, Forwards LER 81-060/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-052-03, /03L-0:on 810812,standby Bearing Water Makeup Pump Removed from Svc.Caused by Need to Repair Bonnet Leak in Valve in Suction Line to Pump.Pump Returned to Svc After Repair Completed
05000267/LER-1981-052, Forwards LER 81-052/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-046, Forwards LER 81-046/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-046-03, /03L-0:on 810728,emergency Feedwater Supply to Loop 1 Helium Circular Water Turbines Isolated to Repair Leaking 2-inch Consolidated Safety Relief Valves.Caused by Valve Leakage Downstream of Pressure Control Valve
05000409/LER-1981-003, Forwards LER 81-003/03L-0.Detailed Event Analysis Encl
05000409/LER-1981-006, Forwards LER 81-006/01T-0.Detailed Event Analysis Encl
05000267/LER-1980-077-03, /03L-0:on 801224,one Bearing Water Makeup Pump Removed from Svc During Normal Operation.Caused by Need to Repair Valve Leak.Valves Repaired & Pump Returned to Svc
05000267/LER-1980-023-03, /03L-0:from 800507-17,plant Was Operated W/Emergency Feedwater Header Supply to Helium Circulator Water Turbine Drives of One Loop Isolated on Four Separate Occasions.Caused by Valve Leakage & Line Leakage
05000366/LER-1980-074-03, /03L-0:on 800427,core Max Fraction of Limiting Power Density Found in Excess of Tech Spec.Cause Not Stated. Average Power Range Monitor Adjusted,Power Reduced & Process Computer Updated,Run & Verified
05000267/LER-1980-032-03, /03L-0:on 800617,w/plant Operating at Approx 68% Thermal Power & 193MW,PV-21243 Was Not Controlling at Appropriate Setpoint.Caused by Defective Masoneilan Pv. Devcon Applied to Seal Ring Gasket Stopped Valve Leakage
05000267/LER-1980-015-03, /03L-0:on 800320,during Operation at Approx 60% Power,Emergency Feedwater Header Supply to Loop 2 Helium Circulation Water Turbine Drives Was Isolated to Repair Leaking Pressure Control Valve.Caused by Loose Block Bolt
05000267/LER-1979-017-01, /01T-0 on 790626:fault Current Trip Occurred, Causing Reactor Scram & Interrupted Reactor Cooling.Caused by Water Spray in Switchgear,Resulting in Short Circuit Due to Voltage Perturbation
05000267/LER-1979-026-03, /03L-0:on 790807,bearing Water Makeup Pump P-2105 Removed from Svc to Perform Line Repair W/Reactor at 65% Power.Caused by Hole in Recirculation Line of Pump,Requiring Removal from Svc.Line Repaired.Pump Returned to Svc
05000409/LER-1985-009, :on 850421,leak Developed in Seal Inject Supply Line to CRD Mechanisms.Caused by Rupture in High Pressure Hose Between Flow Orifice & Transmitter.Reactor Shutdown & Hose Plugged
ULNRC-06915, Proposed Change to Technical Specifications to Allow H-08 Control Rod to Be Removed for Cycle 28 (LDCN 25-0005)
CNL-19-119, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)
CNL-21-039, Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)
05000267/LER-1983-054-03, /03L-0:on 831213,emergency Feedwater Supply Header to Loop I Helium Circulators Unavailable to Drive Circulator Water Turbines.Caused by Repair to Safety Relief Valves & Pressure Control Valve