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.TENNESCEE VALLEY AUTHORITY 6N 38A Lookout Place January 16, 1990 I
U.S. Nuclear Regulatory Conunission ATTN Document Control Desk
- - Washington, D.C.
20555 Gentlemen TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 1 - DOCKET NO.
50-327 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-327/89034 The enclosed LER provides details of an event wherein an increased airborne activity level in the auxiliary building resulted in suspension of the hourly
' fire watch patrol and subsequent noncompliance with Technical Specification 3.7.12.
This' event is being reported in accordance with 10 CFR 50.73, paragraph a.2.i.
Very truly yours.
TENNESSEE VALLEY AUTHORITY w-R. Byn Vice President L
Nuclear Power Production Enclosure cc (Enclosure):
Regional Administration U.S. Nuclear Regulatory Commission i
Office of Inspection and Enforcement i
Region II l
101 Marietta Street Suite 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway Suite 1500 Atlanta, Georgia 30339 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy Tennessee 37379 9001230218 900116 PDR ADOCK 05000327
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"' Increased airborne activity in the auxiliary building resulted in the suspension of fire watch patrols and subsequent noncompliance with Technical Specifications 3.7.12.
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At 1533 Eastern standard time (EST) on December 15, 1989, with Unit 1 at 100 percent power and Unit 2 at 80 percent power, the hourly fire watch patrol through the auxiliary building could not be completed because of increased levels of airborne radioactivity.
At 1430 EST a leak was identified from a fitting on a Unit 1 volume control tank (VCT) i Isvel transmitter. At 1500 EST entry into the auxiliary building was restricted, and at 1525 EST, the auxiliary building was evacuated. As a result, the fire watch patrol was not allowed to enter the auxiliary building for the hourly rounds required by Action Statement (a) of Limiting Condition for Operation 3.7.12.
Personnel were allowed to roturn to the auxiliary building at 1800 EST when air samples showed airborne activity h:d returned to an acceptable level, and the hourly fire watch patrol was resumed.
The root cause of this event was the VCT level transmitter leak, which was the source of the l
cirborne activity. The corrective action taken to eliminate the source of the airborne l
ectivity was to isolate the VCT level transmitter and tighten the leaking fitting. A work request was written to replace the fitting.
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Description of Event
t At 1533 Eastern standard time (EST) on December 15, 1989, with Unit 1 in Mode 1 at 100 percent power, 2.235 pounds per square inch gauge (psig), 578 degrees Fahrenheit (F), and Unit 2 in Mode 1 at 80 percent power, 2,235 psig, 568 degrees F, the hourly.
fire watch patrol through the auxiliary building (EIIS Code NF) could not be completed b3cause of increased-levels of airborne radioactivity. Higher than normal dose rates w;re first detected at 1415 EST in the Unit 1 Elevation 690 penetration room. At 1630 EST a leak was identified from a sample cap fitting on a Unit 1 volume control tank (VCT) level transmitter (1-LT-62-129A).
The VCT is a holding and processing tank for tha chemical and volume control system (EIIS Code CB). The Unit 1 operator was notified cf the leak, and arrangements were made for instrument mechanics to isolate the level trcasmitter. At 1500 EST entry into the auxiliary building was restricted, and at 1525 EST the auxiliary building was evacuated. As a result, the fire watch patrol was not allowed to enter the auxiliary building for the hourly rounds as required by Limiting Condition for Operations (LCO) 3.7.12.
The VCT level transmitter was isolated, cnd the leaking fitting tightened. A work request has been written to replace the fitting.
The appropriate radiological surveys were made, and air sampics were taken and l
cn21yzed. Personnel were allowed to reenter the auxiliary building at 1800 EST, and the h:urly fire watch patrol was resumed.
Cause of Event
i Tha immediate cause of this event was the failure to complete the required hourly fire patrol because of an increase in the level of airborne radioactivity in the auxiliary building. This condition represented an ALARA (as low as reasonably achievable) concern and access to the area had been restricted.
Th3 root cause of this event was the VCT level transmitter fitting leak that was the source of the airborne activity. The threads on the fitting.had deteriorated or been damaged causing the sample cap to leak.
Annlysis of Event This event is being reported in accordance with 10 CFR 50.73, paragraph a.2.1, as an ep; ration prohibited by technical specifications because the action requirements of LCO 3.7.12 were not met.
Tho hourly fire watch patrol was being performed as required by Action Statement (a) of LCO 3.7.12 because of nonfunctioning fire barriers and as required by commitments to maintain hourly fire watches until certain Appendix R modifications are completed during th3 Cycle 4 refueling outage for each unit. Although the auxiliary building was not visually inspected for fires during the interval from 1533 to 1800 EST, automatic fire dstectors and fire suppression systems were in service and operable during this time.
Th refore, there was no significant degradation in the overall level of fire protection at the plant.
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.m w= ace amawnri Currective Action The immediate action taken was to restrict entry to and subsequently evacuate the cuxiliary building as a conservative protective action.
The corrective action taken to oliminate the source of the airborne activity was to isolate the VCT level transmitter cnd tighten the leaking fitting. A work request has been written to replace the fitting.
Personnel were allowed to return to the auxiliary building when air samples showed airborne activity had returned to an acceptable level.
Additional Information
There have been 36 previous reported occurrences of a failure to perform required fire watch patrolst however, only three of these occurrences were caused by personnel access r:strictions resulting from high airborne activity levels. These three occurrences are datalled in LER 50-327/88028, 88031, and Special Report 88-11.
Because this airborne ovent resulted from unexpected equipment degradation, corrective actions for previous events could not be expected to have prevented this event.
Crmmitments None.
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| | | Reporting criterion |
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| 05000328/LER-1989-001-04, :on 890212,reactor Trip Signals Generated from Electromagnetic Interference When Spike Received on source- Range Channel N-31.Caused by Noise Induced Into Channel Cabling Due to Welding.Welding Suspended |
- on 890212,reactor Trip Signals Generated from Electromagnetic Interference When Spike Received on source- Range Channel N-31.Caused by Noise Induced Into Channel Cabling Due to Welding.Welding Suspended
| | | 05000328/LER-1989-002-04, :on 890325,two Reactor Trips Occurred During Performnace of Instrument Maint Instruction RT-601A Re Response Time Test for Turbine Trip.Caused by Deficient Procedure.Procedure Temporarily Changed |
- on 890325,two Reactor Trips Occurred During Performnace of Instrument Maint Instruction RT-601A Re Response Time Test for Turbine Trip.Caused by Deficient Procedure.Procedure Temporarily Changed
| | | 05000328/LER-1989-003-04, :on 890401,containment Ventilation Isolation Actuation & Momentary Loss of RHR Occurred.Caused by Removal of Power from Vital Instrument Power Board.Vital Inverters Verfied to Synchronize W/Instrument Board |
- on 890401,containment Ventilation Isolation Actuation & Momentary Loss of RHR Occurred.Caused by Removal of Power from Vital Instrument Power Board.Vital Inverters Verfied to Synchronize W/Instrument Board
| | | 05000327/LER-1989-003-02, :on 890218,motor-driven Auxiliary Feedwater Pump 1A-A Started Following Control Power Interruption to 6.9 Kv Shutdown Board 1A-A.Caused by Breaker 204 Opening. Personnel Verified Pump 1A-A Starting |
- on 890218,motor-driven Auxiliary Feedwater Pump 1A-A Started Following Control Power Interruption to 6.9 Kv Shutdown Board 1A-A.Caused by Breaker 204 Opening. Personnel Verified Pump 1A-A Starting
| | | 05000327/LER-1989-004, :on 890127,seismic Monitor Annunciator Switches Outside Acceptable Limits Due to Inadequate Instruction. Personnel Involved Will Be Counseled & Advised of Proper Actions to Take Under Similar Situation |
- on 890127,seismic Monitor Annunciator Switches Outside Acceptable Limits Due to Inadequate Instruction. Personnel Involved Will Be Counseled & Advised of Proper Actions to Take Under Similar Situation
| | | 05000328/LER-1989-004-03, :on 890416,Mode 1 Entered W/Rod Position Indicator H-12 Inoperable.Caused by Connector Failure Due to Moisture Deterioration.Connector Replaced |
- on 890416,Mode 1 Entered W/Rod Position Indicator H-12 Inoperable.Caused by Connector Failure Due to Moisture Deterioration.Connector Replaced
| | | 05000327/LER-1989-005, :on 890210,reactor Trip Occurred Resulting from Closure of Main Feedwater Regulating Valves on Loss of Power to Valve Controllers.Caused by Personnel Error.Event Discussed W/Instrument Maint Planners |
- on 890210,reactor Trip Occurred Resulting from Closure of Main Feedwater Regulating Valves on Loss of Power to Valve Controllers.Caused by Personnel Error.Event Discussed W/Instrument Maint Planners
| | | 05000328/LER-1989-005-01, :on 890415,16 & 19,three Unit 2 Reactor Trips Occurred Due to Lo Lo Steam Generator Level During Startup. Cause for 890419 Trip Was Operating Loops Bypass Valves in Manual |
- on 890415,16 & 19,three Unit 2 Reactor Trips Occurred Due to Lo Lo Steam Generator Level During Startup. Cause for 890419 Trip Was Operating Loops Bypass Valves in Manual
| | | 05000327/LER-1989-006, :on 890216,discovered That Auxiliary Bldg Waste Packaging Area Door Breached W/O Issuance of Breaching Permit.Caused by Inadequate Training & Programmatic controls.Plant-wide Dispatch Issued on 890223 |
- on 890216,discovered That Auxiliary Bldg Waste Packaging Area Door Breached W/O Issuance of Breaching Permit.Caused by Inadequate Training & Programmatic controls.Plant-wide Dispatch Issued on 890223
| | | 05000328/LER-1989-006-03, :on 890505,determined That Unit Operated in Noncompliance W/Limiting Condition for Operation Since 890411 & Reactor Trip Setpoints Nonconservative.Caused by Detectors Being Placed in Withdrawn Position.W/Undated Ltr |
- on 890505,determined That Unit Operated in Noncompliance W/Limiting Condition for Operation Since 890411 & Reactor Trip Setpoints Nonconservative.Caused by Detectors Being Placed in Withdrawn Position.W/Undated Ltr
| | | 05000327/LER-1989-006-02, :on 890216,auxiliary Bldg Waste Packaging Area Door A111 Breached W/O Issuance of Breaching Permit.Caused by Incomplete Door Identification,Inadequate Programmatic Control & Personnel Oversight.Door A111 Closed |
- on 890216,auxiliary Bldg Waste Packaging Area Door A111 Breached W/O Issuance of Breaching Permit.Caused by Incomplete Door Identification,Inadequate Programmatic Control & Personnel Oversight.Door A111 Closed
| | | 05000328/LER-1989-007-03, :on 890601,discovered Inconsistency in Reactor Coolant Pump Manual Dc Control Power Transfer Switch Positions.Caused by Mislabeling of Switch Position.Proper Labeling Completed |
- on 890601,discovered Inconsistency in Reactor Coolant Pump Manual Dc Control Power Transfer Switch Positions.Caused by Mislabeling of Switch Position.Proper Labeling Completed
| | | 05000327/LER-1989-007, :on 890319,train a Control Room Isolation Occurred.Caused by Incompatibility of Replacement Smoke Detector Unit Relay Contact Configuration W/Application Requirements.Work Request Initiated |
- on 890319,train a Control Room Isolation Occurred.Caused by Incompatibility of Replacement Smoke Detector Unit Relay Contact Configuration W/Application Requirements.Work Request Initiated
| | | 05000327/LER-1989-007-01, :on 890319,train a Control Room Isolation (Cri) Occurred.Caused by Personnel Error.Facility Assistance Shift Operations Supervisor Suspended Maint Activity on Smoke Detectors & Verified Train a Cri for Radiation |
- on 890319,train a Control Room Isolation (Cri) Occurred.Caused by Personnel Error.Facility Assistance Shift Operations Supervisor Suspended Maint Activity on Smoke Detectors & Verified Train a Cri for Radiation
| | | 05000327/LER-1989-008-01, :on 890320,control Room Emergency Ventilation Sys Declared Inoperable Following Tornado Dampers Closure. Caused by Incomplete Evaluation of Effect of Closing Tornado Dampers by Licensed Operator.Dampers Opened |
- on 890320,control Room Emergency Ventilation Sys Declared Inoperable Following Tornado Dampers Closure. Caused by Incomplete Evaluation of Effect of Closing Tornado Dampers by Licensed Operator.Dampers Opened
| | | 05000328/LER-1989-008-03, :on 890710,reactor Trip Occurred on High Negative Flux Rate as Noted on first-out Annunciator.Caused by Dropped Rod.Action Plan Established to Systematically Troubleshoot Sys to Determine Operability |
- on 890710,reactor Trip Occurred on High Negative Flux Rate as Noted on first-out Annunciator.Caused by Dropped Rod.Action Plan Established to Systematically Troubleshoot Sys to Determine Operability
| | | 05000327/LER-1989-009, :on 890319,discovered That Switch on Local Control Panel for CO2 Fire Suppression Sys Protecting Computer Room in Off Position.Caused by Personnel Error. Identification Tags Placed on Control Panels |
- on 890319,discovered That Switch on Local Control Panel for CO2 Fire Suppression Sys Protecting Computer Room in Off Position.Caused by Personnel Error. Identification Tags Placed on Control Panels
| | | 05000328/LER-1989-009-03, :on 890629,Limiting Condition for Operation 3.0.3 Entered Due to Failure to Comply W/Action Statement in Tech Spec.On 890504,discovered That Ice Condenser Bed Temp Recorder Not Printing |
- on 890629,Limiting Condition for Operation 3.0.3 Entered Due to Failure to Comply W/Action Statement in Tech Spec.On 890504,discovered That Ice Condenser Bed Temp Recorder Not Printing
| | | 05000328/LER-1989-010-03, :on 890817,discovered That Tech Spec Surveillance Requirement Not Performed within Required Time. Caused by Personnel Error on Part of Periodic Test Personnel.Surveillance Subsequently Performed |
- on 890817,discovered That Tech Spec Surveillance Requirement Not Performed within Required Time. Caused by Personnel Error on Part of Periodic Test Personnel.Surveillance Subsequently Performed
| | | 05000327/LER-1989-010-02, :on 890329,review of Surveillance Instruction Packages Determined That SI-307.2 Was Out of 18-month Tech Spec Required Frequency.Caused by Scheduled Date Based on Incomplete Package.Personnel Counseled |
- on 890329,review of Surveillance Instruction Packages Determined That SI-307.2 Was Out of 18-month Tech Spec Required Frequency.Caused by Scheduled Date Based on Incomplete Package.Personnel Counseled
| | | 05000328/LER-1989-011, :on 890823,discovered That Requirement to Source Check Radioactive Gaseous Effluent Monitors Not Met. Caused by Previous Lack of Emphasis on Requirements Recognition.Monitors Source Checked |
- on 890823,discovered That Requirement to Source Check Radioactive Gaseous Effluent Monitors Not Met. Caused by Previous Lack of Emphasis on Requirements Recognition.Monitors Source Checked
| | | 05000327/LER-1989-011-01, :on 890413,shift Supervisor Notified That Unit Entered Limiting Conditions for Operations During Surveillance Instruction for RHR Pump.Caused by Inadequate Procedure Rev & Oversight.Fsar Revised.W/Undated Ltr |
- on 890413,shift Supervisor Notified That Unit Entered Limiting Conditions for Operations During Surveillance Instruction for RHR Pump.Caused by Inadequate Procedure Rev & Oversight.Fsar Revised.W/Undated Ltr
| | | 05000328/LER-1989-011-03, :on 890823,discovered That Tech Spec Surveillance Requirement to Source Check Radioactive Gaseous Effluent Monitors on Condenser Vacuum Pump Exhaust Not Fully Met.Root Cause Being Investigated |
- on 890823,discovered That Tech Spec Surveillance Requirement to Source Check Radioactive Gaseous Effluent Monitors on Condenser Vacuum Pump Exhaust Not Fully Met.Root Cause Being Investigated
| | | 05000327/LER-1989-012, :on 890410,containment Ventilation Isolation Occurred Due to High Radiation Spike on Radiation Monitor. Cause of Spike Undetermined.Containment Ventilation Isolation Reviewed to Evaluate ESF Actuations |
- on 890410,containment Ventilation Isolation Occurred Due to High Radiation Spike on Radiation Monitor. Cause of Spike Undetermined.Containment Ventilation Isolation Reviewed to Evaluate ESF Actuations
| | | 05000327/LER-1989-012-01, :on 890410,containment Ventilation Isolation Occurred Due to Spurious High Radiation Spike on Noble Gas Channel of Lower Containment Radiation Monitor.Investigation of Incident to Be Completed by 890531 |
- on 890410,containment Ventilation Isolation Occurred Due to Spurious High Radiation Spike on Noble Gas Channel of Lower Containment Radiation Monitor.Investigation of Incident to Be Completed by 890531
| | | 05000328/LER-1989-012-03, :on 890912,reactor Vessel Level Instrumentation Sys Level Indicator Failed Monthly Channel Check & Declared Inoperable.Caused by Inadequate Training for Two Craft Personnel That Performed Vlave |
- on 890912,reactor Vessel Level Instrumentation Sys Level Indicator Failed Monthly Channel Check & Declared Inoperable.Caused by Inadequate Training for Two Craft Personnel That Performed Vlave
| | | 05000327/LER-1989-013, :on 890503,train B Control Room Isolation Signal Received in Main Control Room.Caused by Operator Bumping Radiation Monitor Pump Motor Breaker While Changing Recorder Chart Paper.Chart Paper Replaced |
- on 890503,train B Control Room Isolation Signal Received in Main Control Room.Caused by Operator Bumping Radiation Monitor Pump Motor Breaker While Changing Recorder Chart Paper.Chart Paper Replaced
| | | 05000328/LER-1989-013-01, :on 890914,found That Min Number of Operable Photoelectric Fire Detectors Not Maintained for Zone 374. Caused by Identification & Ordering of Incorrect Replacement Fire Detectors.Hourly Fire Watch Established |
- on 890914,found That Min Number of Operable Photoelectric Fire Detectors Not Maintained for Zone 374. Caused by Identification & Ordering of Incorrect Replacement Fire Detectors.Hourly Fire Watch Established
| | | 05000328/LER-1989-014-03, :on 891110 & 11,containment Ventilation Isolations Occurred.Caused by Personnel Error.Procedure to Be Issued for Use While Venting Sys Known or Suspected to Contain Radioactive Noble Gases |
- on 891110 & 11,containment Ventilation Isolations Occurred.Caused by Personnel Error.Procedure to Be Issued for Use While Venting Sys Known or Suspected to Contain Radioactive Noble Gases
| | | 05000327/LER-1989-014, :on 890506,limiting Condition for Operation Entered When Both Trains of Auxiliary Bldg Gas Treatment Sys Inoperable.Caused by Opening Control Power Fuse During Replacement of Indicating Lamp.Fuse Replaced.W/Undated Ltr |
- on 890506,limiting Condition for Operation Entered When Both Trains of Auxiliary Bldg Gas Treatment Sys Inoperable.Caused by Opening Control Power Fuse During Replacement of Indicating Lamp.Fuse Replaced.W/Undated Ltr
| | | 05000327/LER-1989-015, :on 890513,Train B Control Room Isolation Occurred.Caused by Defective Auxiliary Contacts of Manual 480 Volt Motor Starter.Contacts Replaced |
- on 890513,Train B Control Room Isolation Occurred.Caused by Defective Auxiliary Contacts of Manual 480 Volt Motor Starter.Contacts Replaced
| | | 05000327/LER-1989-016, :on 890516,train a Containment Ventilation Isolation Occurred.Caused by Inadequate Corrective Action. Operations Personnel Reset Containment Ventilation Isolation.Instruction 90.1B Revised |
- on 890516,train a Containment Ventilation Isolation Occurred.Caused by Inadequate Corrective Action. Operations Personnel Reset Containment Ventilation Isolation.Instruction 90.1B Revised
| | | 05000327/LER-1989-017-01, :on 890613,observed That Auxiliary Control Room Pressurizer Level Indicators Indicating High.Caused by Failure to Properly Calibr Pressurizer Level Transmitters During Calibr Check.Instructions to Be Revised |
- on 890613,observed That Auxiliary Control Room Pressurizer Level Indicators Indicating High.Caused by Failure to Properly Calibr Pressurizer Level Transmitters During Calibr Check.Instructions to Be Revised
| | | 05000327/LER-1989-017, :on 890613,observed That Auxiliary Control Room Pressurizer Level Indicators Were Indicating High as Compared to Main Control Room Level Indicators.Caused by Improper Calibr.Part 21 Related |
- on 890613,observed That Auxiliary Control Room Pressurizer Level Indicators Were Indicating High as Compared to Main Control Room Level Indicators.Caused by Improper Calibr.Part 21 Related
| | | 05000327/LER-1989-018-01, :on 890619,discovered That Both Trains of Auxiliary Bldg Gas Treatment Sys (ABGTS) Automatic Actuation Could Have Been Rendered Inoperable.Caused by Removal of Radiation Monitor During Testing |
- on 890619,discovered That Both Trains of Auxiliary Bldg Gas Treatment Sys (ABGTS) Automatic Actuation Could Have Been Rendered Inoperable.Caused by Removal of Radiation Monitor During Testing
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000327/LER-1989-018, :on 890619,0726 & 1010 & 890628,four Events Occurred Re Auxiliary Bldg Gas Treatment Sys During Periods When Radiation Monitor Was Removed from Sys.Caused by Inappropriate Inclusion of Monitor |
- on 890619,0726 & 1010 & 890628,four Events Occurred Re Auxiliary Bldg Gas Treatment Sys During Periods When Radiation Monitor Was Removed from Sys.Caused by Inappropriate Inclusion of Monitor
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000327/LER-1989-019-01, :on 890713,containment Ventilation Isolation Occurred from Radiation Monitor 1-RM-90-131.Caused by Grounding of Handswitch HS-90-136A2.Operations Supervisor Verified Alarm to Be False & Unit Recovered |
- on 890713,containment Ventilation Isolation Occurred from Radiation Monitor 1-RM-90-131.Caused by Grounding of Handswitch HS-90-136A2.Operations Supervisor Verified Alarm to Be False & Unit Recovered
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000327/LER-1989-020-01, :on 890705,observed That Reactor Vessel Level Indicating Sys upper-range Indicator Was Indicating High as Compared to Redundant Channel.Caused by Inadequate Channel Checks Due to Inadequate Procedure |
- on 890705,observed That Reactor Vessel Level Indicating Sys upper-range Indicator Was Indicating High as Compared to Redundant Channel.Caused by Inadequate Channel Checks Due to Inadequate Procedure
| | | 05000327/LER-1989-021-02, :on 890713,diesel Generator Board Room Fire Protection Sys Inoperable Due to Failure to Close During Performance of Surveillance Instruction.Caused by Inadequate Technical Review of Surveillance.Door Repaired |
- on 890713,diesel Generator Board Room Fire Protection Sys Inoperable Due to Failure to Close During Performance of Surveillance Instruction.Caused by Inadequate Technical Review of Surveillance.Door Repaired
| | | 05000327/LER-1989-021-01, :on 890713,fire Protection Sys Questioned When Fire Door Failed to Close During Surveillance Instruction 237.2.Caused by Inadequate Technical Evaluation of Deficiency.Work Request B252362 Replanned |
- on 890713,fire Protection Sys Questioned When Fire Door Failed to Close During Surveillance Instruction 237.2.Caused by Inadequate Technical Evaluation of Deficiency.Work Request B252362 Replanned
| | | 05000327/LER-1989-022-01, :on 890722,power Range Excore Detector N-43 on Unit Failed During Operation & Declared Inoperable.Caused by Inadequate Procedure.Surveillance Instruction SI-178 Revised to Correct Deficiencies |
- on 890722,power Range Excore Detector N-43 on Unit Failed During Operation & Declared Inoperable.Caused by Inadequate Procedure.Surveillance Instruction SI-178 Revised to Correct Deficiencies
| | | 05000327/LER-1989-023-01, :on 890728,Limiting Condition for Operation 3.4.11 Not Entered After RCS Head Vents Inoperable.Caused by Personnel Error.Plant Drawing Changes & Procedures Revs Will Be Implemented |
- on 890728,Limiting Condition for Operation 3.4.11 Not Entered After RCS Head Vents Inoperable.Caused by Personnel Error.Plant Drawing Changes & Procedures Revs Will Be Implemented
| | | 05000327/LER-1989-024-01, :on 890805,inadvertent Train B Containment Vent Isolation Occurred While Performing Surveillance Testing. Caused by Difficult man-machine Interfaces.Operators Verified No High Radiation Condition Existed |
- on 890805,inadvertent Train B Containment Vent Isolation Occurred While Performing Surveillance Testing. Caused by Difficult man-machine Interfaces.Operators Verified No High Radiation Condition Existed
| | | 05000327/LER-1989-025, :on 890815,all Four Emergency Diesel Generators Declared Inoperable Because Fuel Oil Not Sampled.Caused by Inadequate Procedure Due to Chemistry Personnel Omission. Samples Obtained & Analyzed |
- on 890815,all Four Emergency Diesel Generators Declared Inoperable Because Fuel Oil Not Sampled.Caused by Inadequate Procedure Due to Chemistry Personnel Omission. Samples Obtained & Analyzed
| | | 05000327/LER-1989-026-01, :on 891107,Limiting Condition for Operation 3.0.3 Entered as Result of More than One Rod Position Indicator (RPI) Per Bank Being Inoperable.Caused by Lack of Preventive Maint.Rpis Adjusted |
- on 891107,Limiting Condition for Operation 3.0.3 Entered as Result of More than One Rod Position Indicator (RPI) Per Bank Being Inoperable.Caused by Lack of Preventive Maint.Rpis Adjusted
| | | 05000327/LER-1989-027-01, :on 891027,spray &/Or Sprinkler Sys Declared Inoperable as Result of Failure to Perform Surveillance Requirement within Required 18-month Frequency.Caused by Inadequate Procedure.Procedure Revised |
- on 891027,spray &/Or Sprinkler Sys Declared Inoperable as Result of Failure to Perform Surveillance Requirement within Required 18-month Frequency.Caused by Inadequate Procedure.Procedure Revised
| 10 CFR 50.73(a)(2)(1) | | 05000327/LER-1989-028, :on 891115,penetration Room Developed Noble Gas High Airborne Radioactivity Excursion of 86.1 Max Permissible Concentration Fraction.Caused by Inadequate Latching Mechanism on Access Door |
- on 891115,penetration Room Developed Noble Gas High Airborne Radioactivity Excursion of 86.1 Max Permissible Concentration Fraction.Caused by Inadequate Latching Mechanism on Access Door
| | | 05000327/LER-1989-029, :on 891121,spurious Train B Control Room Isolation Occurred.Caused by Accidental Bumping of Relays & Degraded Fuse in Circuit.Fuses Replaced & Relays Removed & Replaced |
- on 891121,spurious Train B Control Room Isolation Occurred.Caused by Accidental Bumping of Relays & Degraded Fuse in Circuit.Fuses Replaced & Relays Removed & Replaced
| | | 05000327/LER-1989-030, :on 891204,fire Suppression Sys Deluge Valve Isolated More than 1 H W/O Required Continuous Fire Watch Establishment.Caused by Personal Communication Breakdown. Valve Opened & Foreman in Charge Counseled |
- on 891204,fire Suppression Sys Deluge Valve Isolated More than 1 H W/O Required Continuous Fire Watch Establishment.Caused by Personal Communication Breakdown. Valve Opened & Foreman in Charge Counseled
| | | 05000327/LER-1989-031, :on 891205,RHR Pumps Determined to Have Deadheading Problem Identified by NRC Bulletin 88-004.Caused by Inadequate Technical Response to Bulletin.Training Ltr Issued to 10CFR50.59 Reviewers |
- on 891205,RHR Pumps Determined to Have Deadheading Problem Identified by NRC Bulletin 88-004.Caused by Inadequate Technical Response to Bulletin.Training Ltr Issued to 10CFR50.59 Reviewers
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