ML20078A505
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| ML20078A505 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/15/1983 |
| From: | Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8309230294 | |
| Download: ML20078A505 (1) | |
Similar Documents at Cook | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20114E6191996-06-20020 June 1996
[Table view]Forwards Event Notification Worksheet Re 960413 Event Concerning Defective Cam Follower Springs for Edgs. Replacement Springs Obtained from Mfg W/O Defect ML20205R8981987-03-30030 March 1987 Followup Ro:On 870317,portion of Fire Suppression Water Sys Made Inoperable Due to Leak in Piping.Small Hole Discovered in Cement Asbestos Pipe Used for Fire Protection Piping. Parts Ordered & Sys Expected to Be Back in Svc by 870430 ML20204B5401987-03-18018 March 1987 Ro:On 870318,portion of Tech Spec 3.7.9.1b Re Fire Suppression Sys Made Inoperable in Order to Perform Corrective Maint.Leak Developed on East Leg of Outside Fire Protection Ring Header.Broken Pipe Suspected ML20211G5621987-02-19019 February 1987 Special Rept:On 870212,fire Protection Sys Inoperable for More than 14 Days Due to Incomplete Calibr Procedure.Caused by Scheduling Methodology & Personnel Error.Fire Detection Sys Returned to Operation on 870212 ML20207P7871987-01-16016 January 1987 Ro:On 870114,fire Suppression Water Sys Inoperable,Per Tech Spec 3.7.9.1,due to Isolation of West Leg of Unit 2 Turbine Bldg Fire Header to Allow for Replacement of Pipe on Fire Hose Standpipe 48.Item Not Reportable ML20214K4351986-11-20020 November 1986 Followup Ro:On 861106,north Leg of Fire Suppression Water Sys Outside Ring Header Between Valves FP-109 & FP-112 Inoperable.Section Isolated to Replace Piping.Pipe Replacement Underway & Will Be Returned to Svc by 861215 ML20215E0441986-10-0202 October 1986 Ro:Fire Door 227 Inoperable Since 860826 Due to Operator Failure & Fire Door 350 Inoperable Between 860912 & 22 Due to Supervisor Failure.Design Change for Door 227 Initiated & Door 350 Repaired ML20197D6631986-05-0101 May 1986 Special Rept:Min Lower Limits of Detectability in Lake Water Sampling & Drinking Water Stations Exceeded Limits of Tech Specs.Caused by Inefficient Radiochemistry Counting Equipment.Water Samples Sent to Contractor ML20151R8001986-01-24024 January 1986 Special Rept:On 841202,fire Protection Deluge Sys for ESF Ventilation Sys 1-HV-AES-1 Charcoal Filters Inoperable in Excess of 14 Days.Fire Suppression Sys Manually Isolated. Tech Spec Change Request Being Processed ML20137L8511986-01-0909 January 1986 Ro:On 851121 & 1212,high-range Area Radiation Monitor Failed.Caused by Inadequate analog-to-digital Inherent Drift Considerations During Calibr.Monitor Recalibr & Restored to Svc on 860102.Info Submitted Per Util ML20141F2041985-12-27027 December 1985 Ro:On 851227,fire Suppression Water Sys Inoperable.Caused by Leak in Sys Which Resulted in Sectionalizing Outside Ring Header.Backup Fire Suppression Available from Nearby Hose Station & Dedicated Plant Fire Truck ML20137M0931985-12-0909 December 1985 Ro:On 851029,while in Mode 3,steam Generator PORV Radiation Monitor MRA-1701 Failed to High Alarm Status.Caused by Defective Detector.Detector Replaced & Sys Restored to Operable Status on 851113 ML20107K1311985-02-20020 February 1985 Ro:On 850107,low Pressure CO2 Sys Declared Inoperable When Common Halon/CO2 Piping Header Modified by Design Change DC-12-2624 & Remained Inoperable in Excess of 14 Days.Design Change Implemented to Maintain Halon Concentrations ML20101L7451984-12-28028 December 1984 Special Rept Re 11 Inoperable Fire Doors in Excess of 7 Days.Caused by New Door Assemblies Not Fitting Designated Location & Scheduling Problems Due to Unforeseen Installation & Hardware Problems ML20099B8631984-11-0808 November 1984 RO-84-021-0.Due to Complexity of Event,Updated Submission Delayed Until 841207 ML20083J8331983-12-20020 December 1983 Ro:On 831220,discovered That Action Statement in Tech Spec Table 3.3-13 Not Met.Samples Required for Weekly Analysis Not Continuously Collected W/Auxiliary Sampling Equipment. Followup Rept Will Be Submitted within 14 Days ML20082T1251983-12-0505 December 1983 RO SI-07/08:on 831104,steam Line Pressure Safety Injection Signal Switch Placed in Reset Instead of in-block Position. Train B Safety Injection Occurred.Caused by Personnel Error. Operator Counseled ML20082F6971983-11-21021 November 1983 Ro:On 831119,while Performing Investigation Into Why High Oxygen Level Existed in One Gas Decay Tank,Action Statement (B) of Tech Spec 3.11.2.5 Not Complied With.On 831103,waste Gas Holdup Tank Concentration Exceeded 4% ML20082J5881983-11-21021 November 1983 Ro:On 831119,while Performing Investigation Why High Oxygen Level Existed in Gas Decay Tank,Discovered That Concentration in Waste Gas Holdup Tank Exceeded 4% for Both Oxygen & Hydrogen on 831103 ML20082J7001983-11-18018 November 1983 Ro:On 831117,Loop 1 Overpower Delta Temp Rod Stop & Reactor Trip Bistable Failed & Loop 2 Overtemp Delta Temp Bistable Failed High.Module Replaced,Recalibr & Returned to Svc ML20082C6101983-11-14014 November 1983 Ro:On 831028,during Containment Purge,Two Radioactive Gaseous Monitoring Instruments Inoperable for 6 Hrs & 2 Minutes,Contrary to Tech Specs.Tech Spec Change Will Be Initiated to Remove Requirement for Monitors ML20081H8671983-10-28028 October 1983 Ro:On 831028,during Contamination Purge in Mode 5,two Radioactive Gaseous Monitoring Instruments Inoperable, Violating Tech Specs.Initially Reported 831028.Followup Rept Will Be Submitted within 14 Days ML20081G0391983-10-27027 October 1983 Suppl to RO Reported on 831020 Re Unit Operating in Mode 4 W/Automatic Actuation Logic Inoperable.Subsequent Review Revealed Automatic Actuation Logic Operable.Ro Retracted ML20081G3431983-10-25025 October 1983 Ro:On 831024,while in Operational Mode 4,for Steam Generator Crevice Flushing,Esf Automatic Actuation Logic Sys Inoperable Per Tech Specs.Followup Rept Will Be Submitted within 14 Days ML20081G9851983-10-20020 October 1983 Ro:On 831020,due to Misunderstanding in Communicating Requirements for Fire Protection,Hourly Fire Watch Checks for Drumming Room Not Performed as Required.Min Number of Detectors Required Not Violated.Rept Retracted ML20085K7691983-10-11011 October 1983 Ro:On 831003,24 H Rept Notification Made Re Incorrect Installation of Containment Hydrogen Monitoring Sys.Sys Modified & Reinstalled Correctly on 831005 ML20080R1141983-10-10010 October 1983 Ro:On 831007,wrong Valves Used for Ep(Z) in-core Detector Computer Code During Cycle Viii Operation ML20080Q3801983-10-0404 October 1983 Ro:On 831004,steam Jet Air Ejector Monitor (SRA-2905) Determined Inoperable & 8 H Grab Sample Not Completed within Required Time Frame.Followup Rept Expected within 14 Days ML20080Q1091983-10-0303 October 1983 Ro:On 830930,while Making pre-startup Valve Lineups, Discovered Pump Reversal on Component Cooling Water Supply & Return Piping for Containment H Sampling Sys.Sys Being Reviewed to Determine Effect During Accident Conditions ML20080P2391983-09-29029 September 1983 Ro:On 830929,during Insp of Containment Lower Vol,One Drop Per Second Leak Discovered on Nonessential Svc Water Sys. Leak Originated at Packing on Manual Isolation Valve. Followup Rept Will Be Submitted within 14 Days ML20078G4301983-09-27027 September 1983 Ro:On 830927,during Sampling Process,Sample Valve on Boron Injection Tank Found Partially Open Allowing Boric Acid Solution to Drain Out.Caused by Personnel Error.Boron Injection Tank Brought Back Into Spec ML20080Q1081983-09-27027 September 1983 Ro:On 830926,carbon Dioxide Sys for Diesel Generator Room Left in Isolated Condition W/No Personnel in Attendance.Upon Discovery,Sys Immediately Returned to Operable Status ML20078A5051983-09-15015 September 1983 Ro:Penetration Cable Tunnel in Quadrant 2 Left in Isolated Condition W/O Fire Watch for Approx 2 H.Equipment in Area Not Required to Be Operable ML20077P1121983-09-0606 September 1983 Ro:On 830903,carbon Dioxide Protected Area Left in Isolated Condition W/No One Working in Area.Sys Restored to Operable Status.Followup Rept Will Be Submitted in 14 Days ML20076K7891983-07-0505 July 1983 Ro:On 830704,during Routine Tour of Containment,Leak Discovered in Nonessential Svc Water Sys.Written Rept Will Be Forwarded within 14 Days,Per IE Bulletin 80-24 ML20072J2421983-06-17017 June 1983 Ro:On 830612,performance of Train B Boron Injection Tank Inlet Piping Heat Trace Circuitry Questioned,But Train Not Declared Inoperable Until 830616.Investigation Underway ML20072C9581983-06-0303 June 1983 Ro:On 830603,maint Personnel Discovered Gauge Had Been Removed from Outside Wall of Outer Airlock Door Providing Vent Path from Containment to Auxiliary Bldg When Inner Airlock Door Open.Pressure Gauge Reinstalled ML20072C4631983-06-0303 June 1983 Ro:On 830603,during Operational Surveillance Test,Both Containment Spray Sys Made Inoperable for Approx 15 Minutes. Error Discovered in Independent Verification of Valve Lineup.Immediate Action Taken to Restore Spray Sys ML20074A6061983-05-0909 May 1983 Ro:On 830506,discovered That Chemical Vol Control Sys Holdup Tanks Not Sampled in 12 H Time Period Required When Automatic Gas Analyzer Inoperable.Sample Performed Approx 4-5 H Late ML20069L8081983-04-20020 April 1983 Ro:On 830420,waste Gas Holdup Sys Exceeded Oxygen & Hydrogen Limits.Cause Not Stated.Proposed Tech Spec Changes Increasing Oxygen Concentration Limit Will Be Reviewed by 830422.Followup Rept Will Be Submitted within 14 Days ML20073M5991983-04-15015 April 1983 Ro:On 830414,following Nonroutine Concentration Test,Control Room Cable Vault Halon Sys Declared Inoperable ML20073F0081983-04-0606 April 1983 Ro:On 830405,halon Sys Declared Inoperable Following Completion of Nonroutine Concentration Test.Followup Rept Will Be Submitted within 14 Days ML20072H3061983-03-17017 March 1983 Ro:On 830219,reservoir Containing Lubricating Oil for Turbine 2 Leaked Into Lake Mi.Caused by Tube Failure.Tube Plugged ML20069E5481983-03-14014 March 1983 Ro:On 830311,fire Door in Boron Injection Tank Room Found Not to Have Label to Substantiate Ul Certification.Cause Not Stated.Continuous Fire Watch Posted ML20072C4471983-02-24024 February 1983 Ro:On 830224,during Review of Computerized Printout Which Delineates Calibr Surveillance Test Schedules,Discovered That Containment Fire Detector Instrumentation Surveillance Test Not Performed ML20070T1751983-02-0101 February 1983 Ro:On 830201,outlet Valve of Spray Additive Tank Discovered in Closed Position.Valve Immediately Opened ML20064G5361983-01-0303 January 1983 Ro:On 821223,presence of Obstruction in Valve SI-152-S Prevented Attainment of Min Required Flow Through South Safety Injection Header.Caused by Unattached Disc from Previous Repair of SI-152-S Lodged W/Valve.Disc Removed ML20067C6251982-12-0202 December 1982 Ro:On 821201,west Centrifugal Charging Pump Rendered Inoperable Following Mod on East & West Centrifugal Pump Common Mini Flow Line.Caused by Cut Made on Pressurized Portion of Piping.Investigation in Progress ML20067B0531982-11-24024 November 1982 Ro:On 821123,essential Svc Water Sys Motor Operated Valve WMO-753 Failed to Open.Caused by Reverse Operation of Valve Due to Incorrect Installation of Cable Feeding Motor Control Ctr During 821117 Design Change ML20066A8891982-10-27027 October 1982 Ro:On 821027,informed That in Past Instances,Plant Did Not Correctly Implement Tech Spec 3.3.3.7 Re Defective Pyrotronics Ionization Detection.Annunciator Response Procedures Revised & Spare Detectors Provided 1996-06-20 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 |
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,,, KIN 0 LANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458 Bridgman Michigan 49106 (616) 465-5901 September 15, 1983 Mr. J.G. Keppler, Regional Administrator United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315
Dear Mr. Keppler:
On September 3, 1983, we informed the NRC that a CO 7 protected area in Unit No. 1 (Penetration Cable Tunnel, Quadrant 27 was left in an isolated condition with no fire watch in the area for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 7 minutes. We also stated at the time that the event may not be reportable if there was no equipment in the area that was required to be operable. At the time of the event Unit I was in Cold Shutdown, Mode 5, with the Reactor Coolant System at half-loop.
We have completed a thorough investigation of the equipment and the cables installed in the area and have concluded that none of the equipment or the cables passing through were required to be operable at the time. Therefore the event did not constitute operation of the unit in a condition less conservative than the limiting condition for operation, Technical Specification Section 3.7.9.3.
Sincerely,
.) Smith,
.G. .
/bab cc: John E. Dolan INPO M.P. Alexich PNSRC R.F. Kroeger J.F. Stietzel H. Brugger E.L. Townley E. Swanson/N. DuBry, RO:III Dir., IE (40 copies)
R.C. Callen, MPSC Dir., MIPC (4 copies)
G. Charnoff, Esq.
J.M. Hennigan R.O. Bruggee 8309230294 830915 PDR ADOCK 05000315 h S PDR
$[p n maa h 'h l*
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