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Issue date | Site | Title | |
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ML24011A149 | 11 January 2024 | Callaway | Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) |
ML23046A382 | 12 January 2023 | Comanche Peak | Comment (714) of William Smith III on Notice of Intent to Conduct Scoping Process and Prepare Environmental Impact Statement; Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Units 1 and 2 |
ML20265A201 | 21 September 2020 | Indian Point | Aam - Questions from Utility Workers Union of America Local 1-2 |
ML100910533 | 5 April 2010 | Nine Mile Point Fermi Watts Bar Summer Turkey Point Callaway Vogtle Comanche Peak Bellefonte Levy County 05200012 05200013 05200017 Bell Bend 05200022 05200023 05200016 05200024 Lee | U.S. Nuclear Regulatory Commission Staff Review of the Department of Homeland Security Consultation Reports |
ML100570200 | 26 February 2010 | Harris | Notice of Closed Meeting with Progress Energy to Observe a Live Test Fire of Mackenzie River Partner'S Remotely Operated Weapon System at the Shearon Harris Nuclear Plant |
ML083430012 | 3 December 2008 | Calvert Cliffs | Bg&E Calculation CA00800, Total Loop Uncertainty Calculation for the Plant Computer'S Determination of Main Feedwater Pump Discharge Pressure, Revision 1 |
ML080990550 | 5 April 2008 | Mcguire McGuire | G20080204 - William E. Smith Ltr. Request That McGuire Nuclear Station Not Start Up Due to a Potential Melt Down (Ref 10 CFR 2.206) |
ML080850518 | 24 March 2008 | Mcguire McGuire | G20080204/EDATS: OEDO-2008-0250 - William E. Smith Ltr. 2.206, McGuire Nuclear Station |
ML061730206 | 1 November 2004 | Vermont Yankee | Letter from W. Smith of Valley Environmental Services Wetland Delineation, VYNPS Nov 1, 2004 |
ML042390211 | 1 July 2004 | Robinson | Calculation RNP-I/INST-1128, Rev 5, RCS Flow Instrument Uncertainty and Scaling Calculation. |
ML042390217 | 13 September 2002 | Robinson | Calculation RNP-I/INST-1041, Rev 3, Feedwater Flow Loop Uncertainty and Scaling Calculation, for H. B. Robinson Unit 2 |
ML042390215 | 13 August 2002 | Robinson | Calculation RNP-I/INST-1043, Rev 5, Main Steam Pressure Uncertainty and Scaling Calculation, for H. B. Robinson Unit 2 |
PNO-IV-97-043A, on 970724,licensee Entered Forced Shutdown of Reactor,Due to Decreasing Second Stage Pressure on Reactor Recirculation Pump a Seal & Rising Drywell Unidentified Leakage.Inspectors Will Continue to Monitor Startup | 31 July 1997 | River Bend | PNO-IV-97-043A:on 970724,licensee Entered Forced Shutdown of Reactor,Due to Decreasing Second Stage Pressure on Reactor Recirculation Pump a Seal & Rising Drywell Unidentified Leakage.Inspectors Will Continue to Monitor Startup |
PNO-IV-97-026A, on 970507,shutdown Greater than 72 H After Manual Scram Update Made.Workers Removing Fire Seal Matl from Penetration in Turbine Bldg to Run Addl Cable Through Penetration in Accordance W/Authorized Station Mod | 8 May 1997 | River Bend | PNO-IV-97-026A:on 970507,shutdown Greater than 72 H After Manual Scram Update Made.Workers Removing Fire Seal Matl from Penetration in Turbine Bldg to Run Addl Cable Through Penetration in Accordance W/Authorized Station Mod |
PNO-IV-97-026, on 970506,shutdown Greater than 72 H After Manual Scram Occurred.Div II & III EDGs Started Automatically & Provided Power to safety-related Loads. Licensee Plans to Commence Outage to Repair | 6 May 1997 | River Bend | PNO-IV-97-026:on 970506,shutdown Greater than 72 H After Manual Scram Occurred.Div II & III EDGs Started Automatically & Provided Power to safety-related Loads. Licensee Plans to Commence Outage to Repair |
ML20080J824 | 17 February 1995 | Peach Bottom Limerick | Notifies of Change in Limited SRO License Issued to Gf Ruppert,License SOP-10931.License No Longer Needed Due to Permanent Reassignment of Ruppert |
ML20077D250 | 30 November 1994 | Peach Bottom Limerick | Notifies of Change in Status of Lsro License Issued to Pj Berry Due to Permanent Reassignment of Duties & Determination That No Longer Need for License as Originally Certified Under Requirements of 10CFR55.31(a)(3) |
ML20078D607 | 28 October 1994 | Limerick | Forwards Limerick Generating Station,Units 1 & 2,Updated Final Safety Analysis Rept, Rev 4 |
ML17332A202 | 5 July 1994 | Cook | Informs That Util Submitting Encl Scope & Objectives for 941004 Emergency Plan Exercise to J McCormick-Barger.Subj Exercise Is Util Only One.Complete Exercise Scenario Package Will Be Submitted 60 Days in Advance of Exercise |
ML20070C188 | 29 June 1994 | Peach Bottom | Forwards Rev 12 to Updated FSAR for Peach Bottom Atomic Power Station Units 2 & 3,including Annual Rev to QA Program Description |
ML17331B282 | 31 December 1993 | Cook | DC Cook Nuclear Plant 1993 Annual Operating Rept. |
ML17331A312 | 31 July 1993 | Cook | Updated QA Program Description for Cook Nuclear Plant. |
ML20115C638 | 30 September 1992 | Browns Ferry | Part 21 Rept Re Failure to Provide Sufficient Evidence That Eight Solenoid Manifold Valves,W/Codes GRE-001 Through GRE-008,mfg by Automatic Valve,Qualified to Wyle Rept 17514-1,Rev A.Return of Defective Valves Requested |
ML17329A470 | 21 April 1992 | Cook | Updated QA Program Description for Cook Nuclear Plant. |
ML17328A154 | 14 September 1989 | Cook | LER 89-009-01:on 890705,disovered That Testing Document for Valve 1-CS-443-2 Not Signed Off.Record Search Conducted & No Evidence Found to Indicate That post-maint Testing Performed.Caused by Personnel error.W/890914 Ltr |
ML17328A155 | 13 September 1989 | Cook | LER 89-014-00:on 890814,reactor Protection Sys Actuation Occurred Due to Failure of Class 1E Power Supply Inverter. Caused by Failed Silicon Controlled Rectifier in Static Transfer Switch.Inverter repaired.W/890913 Ltr |
ML17334B330 | 11 September 1989 | Cook | Forwards Response to 890809 Request to Investigate Allegation RIII-89-A-0093 Re Alleged Drug Use by Employee at Plant.Search of Employee Personal Automobile W/Use of Trained Drug Dog Revealed No Controlled Substances |
ML17328A148 | 11 September 1989 | Cook | LER 88-003-04:on 880311,4 Kv Bus Loss of Voltage Relays & Degraded Voltage Relays Found Beyond Tech Spec Allowable Values.Cause Unknown.Relays Recalibr to within Allowable values.W/890911 Ltr |
ML17328A150 | 8 September 1989 | Cook | Ro:On 890908,fire Suppression Water Sys Determined Inoperable,Per Tech Spec 3.7.9.1.b Requirement.Caused by Planned Isolation of Portion of East & South Legs of Fire Ring Protection Header.Valve 12-FP-133 Replaced on 890921 |
ML17328A149 | 8 September 1989 | Cook | Special Rept:Seven Fire Dampers Inoperable for Longer than 7 Days Permitted Under Tech Spec 3.7.10 Action A.Caused by Incorrect Development of Task Sheet from Data Base of nonsafety-related Dampers.Maint Procedure Revised |
ML17328A126 | 31 August 1989 | Cook | LER 89-004-01:on 890324,leakage Found on Containment Penetrations Exceeded Tech Spec 3.6.1.2.b Requirement.Caused by Excessive Leakage Rate of Valves WCR-924,ECR-26 & ECR-31. Faulty Valves Repaired & restested.W/890831 Ltr |
ML17328A105 | 23 August 1989 | Cook | Special Rept:On 890717,two Fire Barriers Inoperable Longer than 7 Days Allowed by Tech Spec 3.7.10.Engineering Analysis Being Performed to Determine How Best to Reapply Fire Proofing Matl |
ML17334B320 | 4 August 1989 | Cook | Forwards Monthly Operating Rept for Jul for DC Cook Unit 1 & Corrected Rept for June 1989 |
ML17325B258 | 4 August 1989 | Cook | Forwards Monthly Operating Rept for Jul 1989 for DC Cook 2 & Corrected Rept for June 1989 Re Monthly Operating Activities & Major safety-related Maint |
ML17328A102 | 4 August 1989 | Cook | LER 89-010-00:on 890705,determined That 414 Seismic/ Expansion Gap Seals Should Have Been Included in Formal Fire Seal Insp Program.Caused by Failure to Recognize Seals as Requiring Surveillance Per Tech Specs.W/890804 Ltr |
ML17328A094 | 4 August 1989 | Cook | LER 89-009-00:on 890705,discovered That post-maint Testing Documentation for Job Order on Valve 1-CS-442-2 Not Signed Off as Completed.Unit Entered Hot Shutdown W/Type C Testing Not Performed on 890620.W/890804 Ltr |
ML17328A101 | 28 July 1989 | Cook | Special Rept:On 890217,gap Between Top of Removable Walls & Permanent Structure Separating Fire Zones 63A,63B & 63C from Fire Zone 5 Discovered During Insp.Plant Mods Will Be Completed & Fire Walls Restored to Operability by Mid 1990 |
ML17328A082 | 18 July 1989 | Cook | LER 88-003-03:on 880311,repetitive Violation of ESF Instrumention Limiting Conditions for Operation Tolerances Found to Be Beyond Tech Spec Allowable Values.Caused by Restrictive Allowable values.W/890718 Ltr |
ML17328A084 | 17 July 1989 | Cook | LER 89-013-00:on 890617,reactor Trip Breakers Opened When ESF Signal Initiated from Set I,Intermediate Range Nuclear Instrumentation Channel.Caused by Miscommunication. Importance of Complete Turnover stressed.W/890717 Ltr |
ML17328A083 | 14 July 1989 | Cook | LER 89-012-00:on 890624,monthly Channel Checks Required by Tech Spec 3.3.3.6,Table 3.3-10 for Containment Water Level Instruments Not Included in Surveillance Procedure.Caused by Personnel Error.Procedure Revised on 890624.W/890714 Ltr |
ML17328A075 | 13 July 1989 | Cook | LER 89-011-00:on 890613,discrepancies Determined to Have Rendered Sys Outside of Design Basis Error Allowances During post-accident Conditions.Caused by Failure to Install Outer Heat Shrink.Splice Boxes corrected.W/890713 Ltr |
ML17328A064 | 6 July 1989 | Cook | Advises That Listed Actions Will Be Performed to Return Facility to Svc.All Unit 1 safety-related & Tech Spec Equipment Job Orders,Performed During 1989 Refueling Outage, Will Be Reviewed to Confirm post-work Testing Completed |
ML17328A065 | 5 July 1989 | Cook | Special Rept:On 890531,declared Fire Door 392,auxiliary Bldg Access Control Entry Door Inoperable.Caused by Failure of Door Knob Mechanism.Fire Retardant Matl Removed from Fire Panel & Entire Door Replaced |
ML17328A067 | 30 June 1989 | Cook | Monthly Operating Rept for June 1989 for DC Cook Nuclear Plant Unit 1.W/890710 Ltr |
ML17328A068 | 30 June 1989 | Cook | Monthly Operating Rept for June 1989 for DC Cook Nuclear Plant Unit 2.W/890710 Ltr |
ML17334B313 | 26 June 1989 | Cook | Ro:On 890611,pressurizer PORV NRV-153 Opened Automatically. PORV Opened After Starting Reactor Coolant Pump 13 During RCS Fill & Vent Procedure.Setpoints Recalculated & Instrument Uncertainties Removed |
ML17334B314 | 23 June 1989 | Cook | LER 89-010-00:on 890524,control Room Operators Observed That Loop 2 delta-T Reactor Power Indication Approx 4% Lower than Remaining Loops.Caused by Replacement of Steam Generators Resulting in Change in Flow distribution.W/890623 Ltr |
ML17328A062 | 21 June 1989 | Cook | Responds to NRC 890517 Request to Investigate Allegation RIII-89-A-0058 Re Lost Keys |
IR 05000315/1989005 | 9 June 1989 | Cook | Advises That Failure of Component Cooling Water Containment Isolation Valve 1-CCM-458 to Close Not Reportable Per 10CFR50.73.LER 50-315/89-05 Retracted & LER Number Will Not Be Reissued |
ML17325B249 | 9 June 1989 | Cook | Advises That Failure of Component Cooling Water Containment Isolation Valve 1-CCM-458 to Close Not Reportable Per 10CFR50.73.LER 50-315/89-05 Retracted & LER Number Will Not Be Reissued |