05000354/LER-2002-007, Core Spray Discharge Line Alarms Inoperable
M170181, GE Hitachi Nuclear Energy - Supplement 2 to Amendment 24 for the Ntr Facility, License R-33, to Support Potential Vnc Site Land Sale
LR-N10-0355, Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation.
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
LR-N04-0563, Response to Request for Information Regarding B Reactor Recirculation Decontamination Connection Leakage
PLA-4055, Forwards Proposed Amend 117 to License NPF-22 Re Power Uprate W/Increased Flow
05000373/LER-1995-001, Cancels LER 95-001-00 for Facility.Licensee Determined That LaSalle County Station Not in Condition Prohibited by TS 3.4.3.2
NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals
NRC-92-0075, Application for Amend to License NPF-43,changing RCS Unidentified Leakage Rate of Change Limit Applicable in Operational Condition 1,per NRC Position on Leak Detection in GL 88-01
NRC-97-0043, Provides Info Re Recently Identified Issued Involving Effects of Postulated HELBs Inside Containment on EECWs & Utils Basis for Conclusion
BSEP-98-0156, Forwards Revs to Bsep,Units 1 & 2 Emergency Procedures,Per 10CFR50-54(g) & 10CFR50 App E.List of Revised Procedures, Summary of Changes & Copies of Revised Procedures,Encl
B17028, Application for Amend to License NPF-49,revising TS 3/4.4.3 by Replacing Pressurizer Max Water Inventory Requirements W/ Pressurizer Level Requirement
RBG-25222, Notification of Unusual Event:On 870112,reactor Shut Down Due to Unidentified Leakage from Rcs.Rhr B Testable Injection Check Valve 1E12*AOVF041B Identified as Major Contributor to Leakage
AECM-89-0130, Forwards Addl Info Re Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, Per 890517 Request
SNRC-1479, Forwards Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
AECM-88-0218, Submits Addl Info Re 880819 Application for Amend to License NPF-29,per NRC 881006 Request.Proposed Administrative Changes to Fire Protection Specs Per Generic Ltr 87-09, Included in Amend Request
RBG-22-457, Forwards Composite List of Requested Tech Spec Changes for Full Power Ol,Discussions,Justification & Proposed Markup for Each Change.No Change to License NPF-40 Requested
HL-1446, Application for Amends to Licenses DPR-57 & NPF-5 Revising Tech Specs Re Generic Ltr 88-01, NRC Position on IGSCC Austenitic Stainless Steel Piping
RBG-39894, Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-08
PY-CEI-NRR-1502, Confirms That Commitment,Contained in ,To Incorporate New Limit on Drywell Unidentified Leakage Rate Increase Limit Into Plant Procedures Completed.Sections of Applicable Procedures Encl
W3F1-2020-0043, Response to NRC Request for Additional Information Regarding License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual
AECM-90-0135, Application for Amend to License NPF-29,revising 900427 & 0705 Applications Re Changes to Tech Spec Due to Addition of Alternate DHR & Addressing NRC Concerns Re Manual Realignment of LPCI Emergency Core Cooling Subsystems
05000366/LER-1987-010-02, :on 870818,reactor Shut Down Due to Leak Observed in 1-inch Instrument Line.Caused by Failure in Instrument Line in Heat Affected Zone Adjacent to Socket Weld.Weld Overlay Designed,Installed & Tested
05000341/LER-1987-018, :on 870520,during Troubleshooting of Leakage Discovered in Drywell,Rwcu Inboard Isolation Valve Isolated Twice & Outboard Isolation Valve Once.Caused by Latent Heat Migration in Sys Piping.Valve Repacked
05000458/LER-1987-002, :on 870112,reactor Shutdown Initiated for Unidentified Drywell Leakage Exceeding 5 Gpm.Caused by Packing Leaks on Several Valves W/Rhr B Testable Injection Check Valve as Primary Contributer
05000341/LER-1988-026, :on 880723,unit Shut Down.Caused by Leakage in Valves E51-F007 & G33-F100 Which Developed Following Stroking of Valves While Plant in Operation.Stems on Valves Replaced & Valves Repacked
05000373/LER-1997-021-02, :on 970512,undrainable Low Areas in Drywell Floor Resulting in Degradation of Lds Due to Increased Delays in Detection of Unidentified Leakage.Caused by Design Specification.Declared Lds Inoperable
05000388/LER-1986-010-01, :on 860717,reactor Manually Shut Down Due to Excessive Unidentified Drywell Leakage.Caused by Leaking RHR Loop B Injection Testable Check Valve HV-251-F050B.Valve Repacked & Returned to Svc
NRC-87-0176, Responds to NRC Re Violations Noted in Insp Rept 50-341/87-26.Corrective Actions:Detailed Review of Tech Spec Surveillance Requirements & Procedures Will Be Performed
05000327/LER-1988-020-01, :on 880512,potential Operation Outside Design Basis Noted.Caused by Unanalyzed Single Failure That Could Cause Inadvertent Actuation of Cold Overpressure Protection Sys During Postulated Main Steamline Break
05000366/LER-1987-010, :on 870818,failed Instrument Line Leakage Exceeds Allowable Limits Resulting in Reactor Shutdown. Caused by High Cycle (Vibration) Fatigue.Plant Shut Down & Weld Overlay Installed
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000352/LER-1988-005, :on 880219,determined One of Four Reactpr Coolant Leakage Monitoring Sys Inoperable in Violation of Tech Spec 3.4.3.1.Investigation Continuing.Wiring Restored to as-built Condition & Sys Declared Operable
05000373/LER-1996-010-06, :on 960829,determined Conditions Outside of Design Basis.Caused by Inadequate Standards for TS Clarifications.Implemented Development of TS Clarifications & Evaluates TS Interpretations
05000458/LER-1992-021, :on 921006,discovered That Drywell Pedestal Floor Drain Sump Overflowed to Pedestal Room.On 920928, Discovered Floor Drain Pumps Inoperable.Caused by Sump Pump Malfunction.Pumps Will Be Repaired
05000373/LER-1984-065-01, :on 841012,RHR LPCI B Testable Check Valve IE12-F041B Failed to Hold Pressure Per Tech Specs.Caused by Valve Binding Open Due to Abnormally Tight Packing & Shaft Corrosion
05000302/LER-1983-041-03, /03L-0:on 830927,while Performing Quarterly Cycling of Valves,Porv RCV-11 Failed to Close.Caused by Torque Switch Failure.Switch Replaced W/Upgraded Model. RCV-11 Stroked
05000416/LER-1983-157-03, LPCS Injection Valve Leakage Pressure Monitor Alarm Setpoint Found at 52 Psig. Caused by Use of Unstable Digital Readout Assembly to Calibr Device.Rosemount Trip Unit 510DU Recalibr
05000327/LER-1983-063-03, While in Mode 3,following Maint,Porv 1-PCV-68-340 Found Leaking.Caused by Associated Block Valve Not Closing Fully.Porvs Will Be Replaced During Refueling Outage
05000373/LER-1983-066-03, /03L-0:on 830617,HPSC Testable Check Valve 1E22-F005 Failed to Close.Caused by Failure of Bypass Valve. Work Request Generated & Completed on 830703.Spring Tension to Rack & Gear Assembly Increased
05000440/LER-1991-010, :on 910401,failure of Reactor Recirculation Pump Resulted in Shutdown of Plant.Caused by Component Malfunction.Contractor Replaced & Recirculation Pump Verified to Operate Properly in Low Speed
05000339/LER-1991-001-03, :on 910318,surveillance Not Performed on PORV Control Circuitry.Caused by Incorrect Interpretation of TS & Administrative Error.Appropriate Procedure Will Be Revised Prior to Next Scheduled Surveillance
05000328/LER-1982-045-03, /03L-0:on 820327,power Operated Relief Block Valve 2-FCV-68-333 Declared Inoperable When Valve Would Not Close Completely.Cause Not Stated.On 820407,valve Stroked & Worked Properly.Torque Switch Setting Increased
U-601703, Proposed Tech Specs 4.0.5,3/4.4.3.1, RCS Leakage Detection Sys, 3/4.4.3.2, Operational Leakage, 3/4.8.3.1, Onsite Power Distribution Sys-Operating & 3/4.8.1.1, AC Sources - Operating
05000327/LER-1981-128-03, /03L-0:on 811026,pressurizer Power Operated Relief Valve 1-PCV-68-340A Found Leaking to Pressurizer Relief Tank.Apparently Caused by Improper Adjustment of Valve Stem Operator Coupling.Stem Coupling Adjusted
05000354/LER-1989-026-01, :on 891231,leak from Weld on Reactor Recirculation Sys Flow Transmitter Instrument Line Joint Discovered.Cause Not Stated.Instrument Line Cut Out & Replaced W/New Section of Piping
05000344/LER-1989-032, :on 891205,incomplete Surveillance of PORV Occurred Due to Inadequate Procedure Review Upon Issuance of License Amend.Block Valves Closed Until Surveillance Performed.All Circuits Using Relays Reviewed
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
05000354/LER-1989-026, :on 891231,leak from Weld on 1-inch Reactor Recirculation Sys Elbow Tap Flow Transmitter Instrument Line Joint Discovered.Caused by Equipment Failure Due to Installation Deficiency During Plant Const
3F1089-23, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 174 Re Proposed Heatup,Cooldown & Inservice Leak & Hydrostatic Testing Pressure/Temp Limits. Rept Re Low Temp Overpressure Protection Withheld
05000353/LER-2017-004-01, Degraded Condition Due to RPV Instrument Nozzle Leakage
05000529/LER-1995-002-01, :on 950519,TS LCO 3.1.2.2 & LCO 3.1.2.4 Action Statements Not Met.Caused by an Unsatisfactory Swagelok Compression at Union of Flexible Tubing & Rigid Tubing. Pressure Transmitter Sensing Line Repaired
05000397/LER-1992-013, :on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared
GO2-88-164, Responds to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, Dtd 880125.Util Will Comply W/Staff Positions Delineated in Generic Ltr to Extent Described in Response
GO2-84-220, Confirms Info Provided in Gc Sorensen to a Schwencer Re Tech Spec 3.4.3.2 Change Request.Unit May Not Immediately Proceed to Mode 2 (Startup) W/O Avoiding Reinitiation of 7-day Surveillances,Unless Approved by NRC
GO2-83-522, Forwards Response to Request for Supporting Documentation & Per Tech Spec Second Draft Discussed During 830523-26 Meetings.Tentative Schedule for Preparation of Proof & Review Copy Listed
05000353/LER-1917-004, Regarding Degraded Condition Due to PV Instrument Nozzle Leakage
W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual
AECM-90-0198, Forwards Response to Recommendations Noted in NRC Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
05000354/LER-2005-003, Regarding Reactor Coolant System Leak from Check Valve Position Indicator
05000382/LER-2025-002, Auxiliary Pressurizer Spray Train Inoperable Resulting in a Condition Prohibited by Technical Specifications