05000315/LER-1982-029
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| ML20053E348 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/27/1982 |
| From: | Palmer R INDIANA MICHIGAN POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20053E330 | List: |
| References | |
| LER-82-029-03L-01, LER-82-29-3L-1, NUDOCS 8206070818 | |
| Download: ML20053E348 (1) | |
Similar Documents at Cook | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20203L0281986-04-25025 April 1986
[Table view]Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000316/LER-1985-043, Resubmitted LER 85-043-00:on 851227,auxiliary Bldg Ventilation Grab Sample Not Obtained within Tech Spec Time Constraints.Caused by Personnel Error.Administrative Action Taken W/Individual Involved1986-03-20020 March 1986 Resubmitted LER 85-043-00:on 851227,auxiliary Bldg Ventilation Grab Sample Not Obtained within Tech Spec Time Constraints.Caused by Personnel Error.Administrative Action Taken W/Individual Involved 05000315/LER-1982-003, Corrected LER 82-003/04T-1:on 820115,unplanned Gas Release Detected by Elevated Vent Stack Monitor Reading.Exact Cause Undetermined.Helium Leak Testing of Waste Gas Sys Probable Cause.Test Procedure Changed1985-05-0303 May 1985 Corrected LER 82-003/04T-1:on 820115,unplanned Gas Release Detected by Elevated Vent Stack Monitor Reading.Exact Cause Undetermined.Helium Leak Testing of Waste Gas Sys Probable Cause.Test Procedure Changed ML20101F5691984-12-12012 December 1984 LER 316/84-005-00 Withdrawn 05000316/LER-1984-003, Updated LER 84-003-01:on 840311 & 17,upper Containment Area Radiation Monitor VRS-2201(IL) Received High Alarm.Caused by Equipment Malfunction Due to Software Problems.New Software Installed1984-07-16016 July 1984 Updated LER 84-003-01:on 840311 & 17,upper Containment Area Radiation Monitor VRS-2201(IL) Received High Alarm.Caused by Equipment Malfunction Due to Software Problems.New Software Installed 05000316/LER-1984-008, Updated LER 84-008-01:on 840419 & 24,containment Purge Isolated Due to Radiation Monitor High Alarms on Containment Area Radiation Monitor Train A.Caused by Software Error. Resolution Under Evaluation by Manufacturer1984-05-31031 May 1984 Updated LER 84-008-01:on 840419 & 24,containment Purge Isolated Due to Radiation Monitor High Alarms on Containment Area Radiation Monitor Train A.Caused by Software Error. Resolution Under Evaluation by Manufacturer 05000315/LER-1982-061, Updated LER 82-061/03X-1:on 820726,discovered That Alarm/ Trip Setpoint Values in Newly Installed Containment Air Gaseous & Particulate Monitors Higher than Tech Specs.Caused by Personnel Error.Procedure revised.W/840313 Ltr1984-03-13013 March 1984 Updated LER 82-061/03X-1:on 820726,discovered That Alarm/ Trip Setpoint Values in Newly Installed Containment Air Gaseous & Particulate Monitors Higher than Tech Specs.Caused by Personnel Error.Procedure revised.W/840313 Ltr 05000316/LER-1983-081, Updated LER 83-081/03X-1:on 830822 & 25,during Normal Operation,Reactor Trips Occurred as Result of Failures of 120-volt Ac Vital Bus Inverter.Caused by Operating Temps Above Rated Design Temps.Forced Air Cooling Installed1984-01-18018 January 1984 Updated LER 83-081/03X-1:on 830822 & 25,during Normal Operation,Reactor Trips Occurred as Result of Failures of 120-volt Ac Vital Bus Inverter.Caused by Operating Temps Above Rated Design Temps.Forced Air Cooling Installed ML20066A5241982-10-27027 October 1982 LER-082/03L-0:on 821007,during Test on Fire Protection Carbon Dioxide Sys,Weld Leak Developed on One Leg of 4-inch Tee Fitting.Caused by Defective Weld.Weld Repaired & Inspected 05000315/LER-1982-0441982-06-23023 June 1982 LER 82-044/03L-0:on 820526,security Personnel Discovered AB Emergency Diesel Generator Carbon Dioxide Sys Isolated,No Names on Entry Board & No Personnel in Room.Caused by Personnel Error.Administrative Action Taken 05000315/LER-1982-0451982-06-23023 June 1982 LER 82-045/03L-0:on 820528,security Officer Discovered Low Pressure Carbon Dioxide Sys for Auxiliary Cable Vault Isolated W/O Personnel on Duty.Caused by Personnel Error. Need for Full Compliance W/Fire Protection Emphasized 05000315/LER-1982-0421982-06-18018 June 1982 LER 82-042/03L-0:on 820524,during Operation,Containment Air Particulate Radiation Monitoring Sys (R-11) Found Operating Erratically.Caused by High Ac Ripple on Low Voltage Dc Power Sys.Low Voltage Dc Power Sys Replaced 05000315/LER-1982-0411982-06-18018 June 1982 LER 82-041/03L-0:on 820520,during Normal Startup,Feedwater Isolation Valve FMO-202 Failed While Being Utilized to Regulate Feedwater Flow.Caused by Heat Buildup Due to Frequent Cycling.Stem Nut & Motor Replaced 05000316/LER-1982-0451982-06-11011 June 1982 LER 82-045/03L-0:on 820513,during Normal Operation,Operator Noted Fire Door 461 Would Not Latch Properly Due to Loose Latch Cover.Caused by Screws Used to Secure Cover in Place Falling Out.New Screws Installed 05000316/LER-1982-0441982-06-11011 June 1982 LER 82-044/03L-0:on 820512,during Surveillance Testing,Loss of Bistable FB-445A Setpoint for Loop 4 Reactor Coolant Detected.Caused by Instrument Setpoint Drift.Model 63U-AC-OHAAF Replaced,Calibr & Returned to Svc 05000315/LER-1982-0351982-06-0404 June 1982 LER 82-035/03L-0:on 820507 & 10,fire Detector 1-HV Acrf Charcoal Filter Instrumentation Declared Inoperable to Troubleshoot & Repair Automatic Reset Function on Fire Detection Actuation Sys.Caused by Defective Transistor 05000315/LER-1982-0341982-06-0404 June 1982 LER 82-034/03L-0:on 820508,operator Discovered Safety Stop Pin in Track of Pressurizer Heaters Transformer Room Overhead Door.Caused by Pin Not Being Removed Upon Exit by Unknown Personnel.Pin Immediately Removed 05000315/LER-1982-0311982-06-0303 June 1982 LER 82-031/03L-0:on 820510,operator on Tour Discovered That Fire Door 227 Would Not Latch.Caused by Slight Misalignment Between Latch & Latch Plate.Latch Plate Adjusted & Door Operated Satisfactorily 05000315/LER-1982-0321982-06-0303 June 1982 LER 82-032/03L-0:on 820518,fire Hose Station 33 Near Emergency Diesel Generator Rooms Access Removed from Svc to Replace Leaking Drain Valve.Seat Leakage Caused by Normal Wear.Drain Valve Replaced 05000315/LER-1981-002, Updated LER 81-002/03X-1:on 810215,west Motor Driven Auxiliary Feed Pump Removed from Svc to Repair Emergency Leakoff Line Check Valve FW-160.Caused by Dirt in Valve Causing Valve to Stick.Valve Cleaned & Returned to Svc1982-06-0303 June 1982 Updated LER 81-002/03X-1:on 810215,west Motor Driven Auxiliary Feed Pump Removed from Svc to Repair Emergency Leakoff Line Check Valve FW-160.Caused by Dirt in Valve Causing Valve to Stick.Valve Cleaned & Returned to Svc 05000315/LER-1982-0331982-06-0303 June 1982 LER 82-033/03L-0:on 820510,operator on Tour Discovered That Fire Door 226 Would Not Fully Close.Caused by Insufficient Closure Mechanism Against Flow of Thermostatically Controlled Ventilation Supply Fan.Addl Mechanism Added 05000315/LER-1982-0281982-05-27027 May 1982 LER 82-028/03L-0:on 820429,during Power Ascension Loop,One Wide Range RCS Pressure indication,NPS-122,failed High. Replacement Read Low on 820523.Caused by Open Stain Gauge & Faulty Calibr,Respectively 05000315/LER-1982-0291982-05-27027 May 1982 LER 82-029/03L-0:on 820503,during Surveillance Test,Low Pressure Alarm XPA-152 for Emergency Air Supply to NRV-152 Actuated at Less than 900 Psig.Caused by Faulty Calibr. Setpoint Increased 05000316/LER-1982-020, Updated LER 82-020/04T-0:on 820401,unplanned Gas Release Detected by Elevated Vent Stack Gaseous Monitor (R-26) Reading.Caused by Small Leak from Seal on East Centrifugal Charging Pump.Coolant Filter Changed1982-04-13013 April 1982 Updated LER 82-020/04T-0:on 820401,unplanned Gas Release Detected by Elevated Vent Stack Gaseous Monitor (R-26) Reading.Caused by Small Leak from Seal on East Centrifugal Charging Pump.Coolant Filter Changed ML20062E5311978-12-0606 December 1978 /03L-0 on 781125:One RHR sub-sys Made Inoperable W/Reactor in Mode 2,less than 5% Pwr,Due to Assumption That Plant Was Still in Mode 1 at Greater That 5% Pwr.New Safety Sys Unit start-up Instructions Issued ML20062E5181978-12-0101 December 1978 /03L-0 on 781101:rod H-8 Rod Position Remained at 220 Steps After Control Bank D Position Reduced from 220 to 207 Steps.Caused by Drift for H-8 Signal Conditioning Module.Was Reset to Correct Position ML20153A8401978-11-0101 November 1978 /03L-0 on 781003:rounding Off of T(Z) Resulted in Fz Calculations Being non-conservative in Top of the Core. Caused Apdms to Perform Stairstep Comparison to Fz Limit in the Top 1/2 of Core Height ML20150C6941978-11-0101 November 1978 /03L-0 on 781002:result of Study Declared Pump Inoperable.Caused by Inconsistency of Pump'S Ability to Achieve Its Rated Speed,Which Was Traced to Pump Speed Governor.Governor Replaced ML20147B2861978-09-29029 September 1978 /03L-0 on 780905:interlock on 650 Ft Level Containment Air Lock Failed to Function During Test, as Interlock Cable Was Too Loose to Operate Locking Mechanism. Tension Adjustment Was Added to Maintenance Prog ML20147B3011978-09-29029 September 1978 /03L-0 on 780901:viscosity of Diesel Lube Oil Was Low During Routine Check Due to Fuel Oil Contamination; for Fuel Oil Injection Pumps & 1 Fuel Injectors Were Replaced ML20147A9781978-09-19019 September 1978 /03L-0 on 780820:While Test Closing Turbine Valves at 99% Pwr,Steam Flow Was Reduced.Reactor Coolant Heated to 577F Degrees & Pressure Dropped to 2185 Psia Caused by Testing Valve at Too High Pwr Level ML20147B1261978-09-18018 September 1978 /03L-0 on 780613:during Mode 1 Oper AB Emergencey Diesel Generator Was Inoper from 2110 Hours on Available.Due to Defective Diodes.(Encl to ML20147A9831978-09-18018 September 1978 /03L-0 on 780602:boron Injection Throttle Valve Positions Were Out of Adjustment & Were Repositioned,Leaving the Valves W/Unknown Flow Capacity Until 780818.Caused by an Engr Error.(Encl to 7809280065) ML20147A8491978-09-12012 September 1978 /03L-0 on 780728:Rpts That Surveillance Test on 2AB Diesel Generator Resulted in Overspeed Trip as Generator Was Unloaded.Caused by Linkage Cap Screw Breaking in Governor Linkage.(Encl to 7809190315) ML20147A8521978-09-12012 September 1978 /03L-0 on 780802:Rpts While in Hot Standby Above P-11,pressurizer Level Indication Channel 3 Found to Be Different from Other Channels.Caused by Gas Pocket in Sensing Line.(Encl to 7809190315) ML20150A6281978-09-12012 September 1978 /03l-0 on 780912:when the Operator Cycle Tested the Valve Upon Returning It to Svc.He Failed to Realize That an Isolation Time Test Was Required.Times Were Posted as Corrective Action,For All Valves.(Encl to 7809190209) ML20150A6351978-09-0808 September 1978 /03L-0 on 780809:with Reactor Pwr at 97% Computer Failed to Printout All F Scans. Investgation Determined Cause to Be Apdms Computer (Encl to 7809190234) ML20150A6321978-09-0808 September 1978 /03L-1 on 780806:reactor Pwr Increased Above Admin Level of 91% & Tech Spec 4.2.6.1 Limit of 94% W/O Determining Axial Pwr Dist Factor Fz. Caused by Personnel Error. (Encl to 78809190234) ML20150A6201978-09-0808 September 1978 /03L on 780810:After a Control Rod Movement of 5 Steps,The Apdms Failed to Perform Scans to Determine F(Z). Procedureal Change Has Been Issued & Opers Instructed in Its Use. (Encl to 7809190196) 1986-04-25 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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| 3152082029R00 - NRC Website | |
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