Pages that link to "NRC Form 356A"
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The following pages link to NRC Form 356A:
Displayed 36 items.
- 05000315/LER-1991-003, :on 910308,liquid Release to Unrestricted Area in Violation of Tech Spec.Caused by Failure of Hi Fail Status of RRS-1000 to Produce Trip.Operations Procedure 12 Ohp Revised (← links)
- 05000315/LER-1990-008, :on 900619,discovered That Isolation Relay Circuitry for Low Header Pressure Auto Start Switch for Essential Svc Water Pumps Installed Incorrectly.Caused by Design Errors.Plant Mod Packet Initiated (← links)
- 05000315/LER-1989-002-01, :on 890303,failure of MSIVs to Meet Tech Spec Lift Setpoint Requirements Occurred.Safety Valve Setpoints Reset within Specified Ranges (← links)
- 05000315/LER-1987-005, :on 870408,during Cooldown & Depressurization, Pressure/Temp Limits of Tech Spec 3.4.9.1 Exceeded.Caused by Personnel Error.Administrative Controls & Procedural Enhancements Incorporated (← links)
- 05000316/LER-1987-001-01, :on 870303,spurious Signal from Source Range Instrument Channel N-31 Resulted in ESF Actuation.Caused by Malfunction of Detector.Source Range Instrument Detector Removed,Replaced & Declared Operable on 870314 (← links)
- 05000529/LER-1990-010-01, :on 901110,EDG Jacket Cooling Water Line Inadequately Supported (← links)
- 05000529/LER-1990-011, :on 901113,inadvertent Control Room Essential Filtration ESF Actuation Occurred (← links)
- 05000528/LER-1990-009, :on 900620,identified That License Holders Had Not Received Biennial Medical re-exams,per 10CFR55.21.Caused by Inadequate Tracking Sys & Medical Personnel Failure to Follow Procedures.Procedures Developed (← links)
- 05000397/LER-1997-003, :on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time Exemption (← links)
- 05000397/LER-1991-024, :on 910909,unanalyzed Condition Associated W/ Postulated Main Steam Line Failure Outside Containment Discovered by Ge.Caused by Failure to Consider Iodine Source Term.Procedure Re Cold Startup Changed (← links)
- 05000397/LER-1991-013, :on 910507,non-compliances W/Tech Specs Identified as Part of Program of Surveillance Procedure Verification.Further Evaluation Performed.Quality Action Team to Be Chartered to Evaluate Program (← links)
- 05000397/LER-1991-015, :on 910602,high HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred.Caused by Personnel Error.Operator Involved Ack & Reset Alarm (← links)
- 05000397/LER-1989-011, :on 890502,determined That Eight Valve Motors Did Not Meet Plant Commitment Made in Response to IE Circular 81-13.Caused by Less than Adequate Design Basis Documentation.Plant Mod Request Revised (← links)
- 05000397/LER-1990-014, :on 900703,HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred Due to Suppression Pool High Water Level Condition.Caused by Procedural Inadequacy.Procedures Modified (← links)
- 05000397/LER-1990-013, :on 900610,ESF Isolations & Actuations Occurred Due to Breaker Trip.Cause of Event Not Determined.Power Restored to E-MC-7A & Isolations Restored (← links)
- 05000397/LER-1989-033, :on 890811,RWCU Isolation Occurred When Fuse in Power Supply to Leak Detection Monitor Blew,Giving False High Alarm Signal to Isolation Logic.Cause Unknown.Fuse Replaced & RWCU Sys Restored to Operation (← links)
- 05000244/LER-1995-009, :on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ (← links)
- 05000244/LER-1992-006, :on 920518,main FW Isolations Occurred on SG a Due to Overfeeding SG a While in Manual Control.Caused by Heater Drain Tank Level Control Sys Problem.Administrative Controls Instituted to Ensure Valve Not Open (← links)
- 05000389/LER-1999-003, :on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With (← links)
- 05000335/LER-1996-002-01, :on 960222,control Element Assembly Dropped on Unit 1 During Periodic Testing.Caused by Failed Silicon Control Rectifier in Upper Gripper Power Switch Module.Power Switch Modules Replaced (← links)
- 05000389/LER-1992-004-03, :on 920708,reactor Manually Tripped Due to Low SG Water Level.Caused by Failed Lead/Lag Circuit in Feedwater Regulating Valve Sys.Design Change Will Delete Circuits from SG Water Level Circuitry (← links)
- 05000335/LER-1990-010-02, :on 900720,erroneous Low Temp Overprotection (LTOP) Setpoint Put in Place & Unit Entered Mode 3 on 900805.Caused by Personnel Error & Failure to Utilize Design Control Process.Setpoints Changed (← links)
- 05000461/LER-1917-004, For Clinton Power Station, Unit 1 Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage (← links)
- 05000219/LER-2015-003, Regarding Failure of the No. 1 Emergency Diesel Generator to Start During Surveillance Testing (← links)
- 05000390/LER-2015-002, Regarding Unanalyzed Condition Related to Spurious Opening of a Pressurizer Power Operated Relief Valve During a Postulated Appendix R Fire (← links)
- 05000280/LER-2012-001, Regarding Oil Foaming in Speed Increaser Results in Inoperable Charging Pump (← links)
- 05000272/LER-2006-001, Re Plant Turbine Trip - Reactor Trip with Reactor Power Above P-9 (← links)
- 05000440/LER-2006-001, Re Incorrect Wiring in the Remote Shutdown Panel Results in a Fire Protection Program Violation (← links)
- 05000454/LER-2005-004, Regarding Technical Specification Required Action Not Satisfied Due to Ambiguous Implementing Procedure (← links)
- 05000397/LER-2004-004, Regarding Items of Reportability and Corrective Actions Taken (← links)
- 05000321/LER-2003-001, Edwin I.Hatch Nuclear Plant - Unit 1 Regarding Broken Reactor Protection System Neutral Bolt Results in RPS Bus Trip (← links)
- 05000390/LER-2003-002, Failure in Power Distribution Panel in Reactor Protection Panel 1-R-9 (← links)
- 05000313/LER-2002-003, For Arkansas Unit 1 Reactor Coolant System Pressure Boundary Leakage from a Crack in a Control Rod Drive Mechanism Nozzle Reactor Vessel Head Penetration Weld Due to Previous Weld Repair Method (← links)
- 05000483/LER-2002-011, For Callaway Plant Unit 1 Regarding a Steam Generator Tube Inspection Results Classified as C-3 (← links)
- 05000335/LER-2002-001, As-Found Cycle 17 Main Steam Safety Value Setpoints Outside Technical Specification Limits (← links)
- 05000316/LER-2002-001, Containment Isolation Valve Alignment Error During Local Leak Rate Testing (← links)