ML17325A350: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| (One intermediate revision by the same user not shown) | |||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:svsoaaossv evxoao PDR ADOCK OM003ib P r PDR ATTACHMENT 1 TO AEP:NRC;0775AP COOK NUCLEAR PLANT UNIT 2 LICENSEE EVENT REPORT (LER) NO. 86-031-00}} | ||
Latest revision as of 02:21, 4 February 2020
| ML17325A350 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/20/1987 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17198A322 | List: |
| References | |
| NUDOCS 8710260367 | |
| Download: ML17325A350 (2) | |
Similar Documents at Cook | |
|---|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17335A5451999-09-28028 September 1999
[Table view]Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B5661999-01-27027 January 1999 Unit 1 Steam Generator Layup Chemistry Out of Specification During 970924 Through 971231. ML17325B4511998-12-15015 December 1998 Rev 1 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies. ML17335A2741998-09-0101 September 1998 Rev 0 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies. ML17335A1921998-07-10010 July 1998 Non-proprietary Cook Unit 1 SG Operability Re-Review. ML17334A6151998-01-0606 January 1998 Containment Sump Operability Determination. ML17333B0921997-10-0909 October 1997 MAAP4 Analyses of DC Cook Containment Response to Small Break Loca. ML17333B0041997-08-14014 August 1997 Responses to RAI on Holtec Rept HI-951389 DC Cook Spent Fuel Pool. ML17333A9561997-07-21021 July 1997 Generator U1R97 Condition Monitoring & Operational Assessment. ML17333A9571997-07-21021 July 1997 Generators U1R97 2 Volt Interim Plugging Criteria Rept. ML17333A5641996-08-31031 August 1996 Final Rept, Reactor Vessel Nozzle Bore Data Evaluation. ML17333A2821995-12-31031 December 1995 DC Cook Nuclear Plant USI A-46 Seismic Evaluation Rept. ML17333A2801995-12-31031 December 1995 DC Cook Nuclear Plant USI A-46 Safe Shutdown Equipment List Rept. ML17333A2761995-12-31031 December 1995 DC Cook Unit 1 1995 Interim Plugging Criteria 90 Day Rept. ML17333A2891995-12-22022 December 1995 Updated Thermal-Hydraulic Analysis of Spent Nuclear Fuel Pool DC Cook Nuclear Plant Indiana Michigan Power Co. ML17333A3251995-11-30030 November 1995 Criticality Analysis of DC Cook Nuclear Plant New Fuel Storage Vault W/Credit for Integral Fuel Burnable Absorbers, for Nov 1995 ML17333A2831995-11-0606 November 1995 DC Cook Nuclear Plant USI A-46 Relay Evaluation Rept. ML17333A3321995-07-31031 July 1995 DC Cook Nuclear Plant Boric Acid Concentration Reduction. ML17333A9051995-07-25025 July 1995 Rev 0 to NRC GL 86-10 Technical Evaluation App R Section III.G.2(b) Twenty Foot Separation Between Redundant Components W/No Intervening Combustibles,Fire Zone 6M & Fire Zone 6S. ML17332A8021995-06-15015 June 1995 EDG Load-Run Performance & Reliability During Short & Long Duration Test Periods TER ML17333A9061995-06-0505 June 1995 Rev 0 to NRC GL 86-10 Technical Evaluation,App R Section III.G.2(b) Twenty Foot Separation Between Redundant Components W/No Intervening Combustibles Fire Zone 44N & Fire Zone 44S. W/Two Oversize Drawings ML17332A7611995-05-0505 May 1995 Svc Water Sys Operational Performance Insp (Swsopi) Self- Assessment Rept. ML17332A5841995-02-28028 February 1995 DC Cook Nuclear Plant IPE for External Events Revised Fire Pra. ML17332A5851995-02-28028 February 1995 DC Cook Nuclear Plant Units 1 & 2 Addendum to Seismic PRA Notebook. ML17332A7121994-12-0505 December 1994 Evaluation of Cook Ipe/Hra Matls. ML17332A3731994-10-24024 October 1994 Assessment of Indications in DC Cook Unit 2 Head Penetration 75. ML17332A4141994-08-25025 August 1994 Rev 0 to HI-941183, Spent Nuclear Fuel Pool Thermal- Hydraulic Analysis Rept for DC Cook Nuclear Plant. ML17331B4301994-06-13013 June 1994 Rev 0 to DC Cook Nuclear Plant E-Plan Classification Vs NUMARC/NESP-007 Deviation Basis Document. ML17331B4391994-06-0909 June 1994 1 Cycle 13 IPC Assessment. ML17331B1331993-12-31031 December 1993 DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation. ML17331B1411993-12-0909 December 1993 Suppl Info for DC Cook Unit 1 Ipc. ML17331B1691993-12-0707 December 1993 Reactor Protection & Control Process Instrumentation Replacement Project at Donald C Cook Nuclear Plant Units 1 & 2,Reactor Protection Sys Functional Diversity Assessment. ML17331B1961993-09-30030 September 1993 Control Rod Misalignment Analysis. ML17331A0631993-02-28028 February 1993 DC Cook Nuclear Plant Hydrogen Control Evaluation Summary Rept. ML17329A7141992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Reliability & Mtbf Analysis Reactor Protection & Control Sys Replacement Project. ML17329A7161992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Response Time Evaluations Reactor Protection & Control Sys Replacement Project. ML17329A7071992-12-16016 December 1992 Engineering Analysis of Temperature & Humidity Effects on Foxboro Spec 200 Instrumentation Reactor Protection & Control Sys Replacement Project. ML17329A7091992-12-16016 December 1992 Preliminary Emi/Rfi Evaluation Aepsc Reactor Protection & Control Sys Replacement Project. ML17329A7131992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Failure Modes & Effect Analysis (FMEA) Protection Set 1 Foxboro Spec 200 Reactor Protection & Control Sys Replacement Project. ML17329A7111992-12-16016 December 1992 Engineering Analysis of Grounding Issues Reactor Protection Process Control Group Replacement Project DC Cook Nuclear Plants Units 1 & 2. ML17329A7101992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Sys Power Quality Evaluation Reactor Protection & Control Sys Replacement Project. ML17329A7171992-12-15015 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 TS Compliance Assessment. ML17329A7121992-12-15015 December 1992 Regulatory Requirements & Industry Standards Associated W/Reactor Protection Portion of Reactor Protection & Control Process Instrumentation Replacement Project. ML17329A7201992-12-14014 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Reactor Protection Sys Functional Diversity Assessment. ML17329A7181992-12-14014 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plants Units 1 & 2 Qualification Compliance. ML17329A7151992-12-10010 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Functional Requirement Summary. ML17329A7191992-12-10010 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Test Program Summary. 1999-09-28 Category:TEXT-SAFETY REPORT MONTHYEARML17335A5641999-10-18018 October 1999
[Table view]LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17335A5631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr ML17335A5621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr ML17335A5481999-09-30030 September 1999 Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3). ML17335A5451999-09-28028 September 1999 Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17326A1211999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr ML17326A1201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17326A0871999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr ML17326A0861999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0511999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr ML17326A0501999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17335A5301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr ML17335A5291999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B4631999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr ML17325B4621999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors 1999-09-30 |
Text
svsoaaossv evxoao PDR ADOCK OM003ib P r PDR ATTACHMENT 1 TO AEP:NRC;0775AP COOK NUCLEAR PLANT UNIT 2 LICENSEE EVENT REPORT (LER) NO. 86-031-00
Retrieved from "https://kanterella.com/w/index.php?title=ML17325A350&oldid=2426476"