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'e NIC Form 364 U.$. NUCLEAR 7;EQULATO2Y COMMi&SION ATPROVED OMB NO 3160 0104 LICENSEE EVENT REPORT (LER)
Expire $ s<3vns F ACILITY NAME til DOCKET NUMBER (2l PAGEt3a Joseph M. Farley - linit 2 0istololol316l4 1 lOFl 013 Technical Specification Action Gtatement Requirement Not Met For Inoperaale Fire Protection System Due To Personnel Error EVENT DATE (6)
LER NUM8ER 16)
REPORT DATE (7)
OTHER F ACILITIES INVOLVED (8)
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NAMg TELEPHONE NUMBER ARE A CODE D. N. Morey, General Manager-Nuclear Plant 2O5 899 5
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I I I I I I SUPPLEMENTAL REPORT E xFECTED (14)
MONTH DAY YEAR SU8M3S$10N YES (!! res comprete 4XPECTED SUGMIS$ TON CA TE' NO l
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ABST R ACT llomst10 1400speces o e, ocoronometeiy torteen tongre speco troewritten Imeri (16) l At 1927 on 2-25-89, with the unit operating in steady state at 100% reactor l
power, a system operator (S0) was making routine rounds and questioned why fire protection sprinkler system (FPS) 2A-59 was in the override position.
The system was removed from override at 1933 and an immediate investigation I
was begun to determine why the switch was in the override position.
Technical Specification 3.7.11.2 requires that continuous fire watches or hourly fire watch patrols (as appropriate) be maintained for the full length of time that the fire protection system is inoperable.
The system had been placed in the override position on 2-24-89 at 0830 in accordance with FNP-0-FSP-28.0 (Smoke Detectors - Clean and Calibrate Procedure).
However, the Shift Foreman - Operating (SFO) secured the required fire watch for FPS 2A-59 at 1500 on 2-24-89 without verifying that the system was operable.
This event was caused by cognitive personnel error. The SF0 who secured the fire watch when the system was still in override has been counseled.
A contributing cause of this event was that FSP-28.0 did not require that the system be taken out of the override position when the maintenance was completed. This procedure vill be revised to include a step that requires that the system be removed from override when maintenance is complete.
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. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ApeRovfo ous No. siso-oion EXPIRES: 8/31/98 -
FA CILITY NAME 11)
DOCKET NUMBER (2).
, LER NUMBER (6)
PAOf 13).
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"^a Farley Nuclear Plant - Unit 2-'
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Plant and System Identification
Vsstinghouse 1 Pressurized. Vater Reactor Energy Industry Identification System codes are identified in the. text as [XX].
Summary of Event At 1927 on,2-25-89, with the unit operating in steady state at 100% reactor
- - power, a: system operator-(50) was making routine rounds and questioned why fire protection sprinkler. system (FPS) [KP] 2A-59 was in'the override position.- The
. system was removed from. override at 1933 and an immediate investigation'vas-
.bzgun to determine why'the'svitch was in the override position.. Technical Specification 3.7.11.2 ';eauires that continuous fire watches or hourly fire watch patrols (as appropriate) be maintained for the full length of time that j
the fire protection system is inoperable. The system had been placed in the; override position on 2-24-89 in accordance with FNP-0-FSP-20.0 (Smoke Detectors -
Clean and Calibrate Procedure). However, the' Shift Foreman - Operating'(SFO)-
)
secured the required fire watch for FPS '2A-59 at:1500 on~ 2-24-89 without verifying that the system was operable.
Description of Event
At 1927 on 2-25-89, while making routine rounds, a system operator (S0) questioned why FPS 2A-59 was in the override position. After ensuring that the switch should not be in that position, the SF0 instructed him to reset it at 1933.
An immediate investigation was begun to determine why the switch was in the override position, The investigation revealed that.on 2-24-89, personnel were psrforming FNP-0-FSP-28.0 (Smoke Detectors - Clean and Calibrate Procedure). In accordance with this procedure, FPS 2A-59 (139 Foot Elevation - Vest Corridor) vss placed in override at 0830. A Limiting Condition for Operation (LCO) was entered and the fire watch required by Technical Specification 3.7.11.2 was posted. Vork on FPS 2A-59 continued during the Day' Shift.
During SFO shift turnover, at approximately 1430, the status of FPS 2A-59 was-discussed. It was noted that the work on FPS 2A-59 was complete and the LCO and fire watch could be cleared as soon as FSP-28.0 had been received and functionally accepted. This procedure did not include a requirement.to remove the system from override when the maintenance was complete.
The associated FSP was received and functionally accepted. The Evening Shift SFO cleared the LCO and secured the fire watch associated with the work on 2A-59 at 1500 on 2-24-89 without ensuring that FPS 2A-59 had been returned to service (taken out of override).
FPS 2A-59 remained inoperable from 0830 on 2-24-89 until 1933 on'2-25-89.
However, the Technical Specification action for establishment of the needed fire-watch was not met from 1500 on 2-24-89 until 1933 on 2-25-89 since it was not realized that the switch was in override.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AreRovEo ous wo. sino-oio4
' EXPIRES: 8/31/8B FACILlVY NAME (1)
DOCKET NUMBER (21 LER NUMBER 16)
PAGE (3) j 8'$M
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.Farley Nuclear Plant - Unit 2 o l5 l0 [o l0 l3 l6 l4 8I9 0l0l1 0 10 0 l3 0F 0l 3 Tw~ iir
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C:use of Event This event was caused by cognitive personnel error in that the SFO failed to ensure that the svi.:ch was in the correct position.
A contributing cause of this event was that FSP-28.0 did not require that the system be taken out of the ovxride position when the maintenance was completed.
Rzportability Analysis and Sd ety Assessment This event is reportable because the continuous fire vatch required by Technical Specification 3.7.11.2 was not maintained for the full length of time that the
'3 fire protection system was inoperable.- The inoperability of this system had no i
effect on plant operation. Also, an hourly fire watch patrol was in the area coch hour that the system was inoperable. No fire occurred during.the time that i
the system was inoperable. The health and safety of the public were not affected by this event. This event would not have a en more severe-if'it had occurred under a different operating condition.
Corrective Action
The SFO who secured the fire watch when the system was still in override has' i
bsen counseleo, Also, FSP-28.0 vill be revised to include a step that requires that the system be removed from override when maintenance is complete.
Additional Information
The folla.ng LERs involved personnel errors by the Shift Foreman in the establ'shing and maintaining of fire watchect Unit 1 (Docket 14 umber 05000348):
87-006-00, and 88-004-00 84-013-00, 84-015-00, 84-022-00, 86-013-00, Unit 2 LERs:
84-007-00, 85-007-00, 85-013-00, 88-004-00, and 88-003-00 l
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NRC FORPA 366A
.u,5, GPO 1988-520 5CO M010 19 B3h w
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w Alabama Powar Company 40 inverness Center Parkway Post Ofhce Box 1295 Birmingham, Alabama 35201 Talephone 205 868 5581 W. G. Hairston, Ill L
Senior Vice President Nuclear Operations AlabamaPower the southern electnc systern I
March 23, 1989 i
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1 1
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I Docket No. 50-364 l
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk j
Vashington, D.C.
20555 J
l Dear Sir 1
l Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report No. LER 89-001-00 l
Joseph H. Farley Nuclear Plant, Unit 2, Licensee Event Report No. LER 89-001-00 is being submitted in accordance with 10CFR50.73.
If you have any questions, please advise.
Respectfully submitted, (Al k, h: ? A C~~
V. G. Hairston, III J
VGH,III/ JAR:pr-8.13 Enclosure cc:
IE, Region II i
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| 05000348/LER-1989-001-01, :on 890328,fire Door 401 Declared Inoperable Because of Cracks Through Metal Around Striker Plate.On 890414,addl Fire Doors Declared Inoperable Due to Cracks. Fire Watches Established |
- on 890328,fire Door 401 Declared Inoperable Because of Cracks Through Metal Around Striker Plate.On 890414,addl Fire Doors Declared Inoperable Due to Cracks. Fire Watches Established
| | | 05000364/LER-1989-001, :on 890225,Tech Spec Action Statement Requirement Not Met for Inoperable Fire Protection Sys. Caused by Personnel Error.Procedure Revised to Include Step Requiring Sys Be Removed from Override |
- on 890225,Tech Spec Action Statement Requirement Not Met for Inoperable Fire Protection Sys. Caused by Personnel Error.Procedure Revised to Include Step Requiring Sys Be Removed from Override
| | | 05000364/LER-1989-002, :on 890402,fire Damper Inoperable Due to Failure to Close W/Air Flow.Design Change Initiated to Install Replacement Damper |
- on 890402,fire Damper Inoperable Due to Failure to Close W/Air Flow.Design Change Initiated to Install Replacement Damper
| | | 05000348/LER-1989-002-01, :on 890428,fire Door 2480 Declared Inoperable Due to Securing Door in Open Position.On 890501,fire Doors in Auxiliary Bldg Declared Inoperable Due to Minor Cracks Through Door Skin.Fire Watches Established |
- on 890428,fire Door 2480 Declared Inoperable Due to Securing Door in Open Position.On 890501,fire Doors in Auxiliary Bldg Declared Inoperable Due to Minor Cracks Through Door Skin.Fire Watches Established
| | | 05000348/LER-1989-003-01, :on 890531-0609,five Fire Dampers Tested Below Acceptance Criterion of Closing W/Air Flow in Sys.Caused by Different Conditions in Summer Mode.Design Change Initiated to Determine How Dampers Should Be Modified |
- on 890531-0609,five Fire Dampers Tested Below Acceptance Criterion of Closing W/Air Flow in Sys.Caused by Different Conditions in Summer Mode.Design Change Initiated to Determine How Dampers Should Be Modified
| | | 05000364/LER-1989-003, :on 890420,27 Tube Exceeded Pluggable Limit & 137 Tubes Designated F*.Cause Not Stated.Reported Per Tech Specs 4.4.6.5.a.Complete Results Will Be Reported in Tech Specs 4.4.6.5.b |
- on 890420,27 Tube Exceeded Pluggable Limit & 137 Tubes Designated F*.Cause Not Stated.Reported Per Tech Specs 4.4.6.5.a.Complete Results Will Be Reported in Tech Specs 4.4.6.5.b
| | | 05000364/LER-1989-004, :on 890419,refueling Containment Integrity Breached During Fuel Movement When Packing Removed from Valve (Chemical Injection to Steam Generator 2A).Caused by Personnel Error.Personnel Counseled |
- on 890419,refueling Containment Integrity Breached During Fuel Movement When Packing Removed from Valve (Chemical Injection to Steam Generator 2A).Caused by Personnel Error.Personnel Counseled
| | | 05000348/LER-1989-004, :on 890616,determined That Calculations Unavailable to Demonstrate That Svc Water Sys Capable of Maintaining Design Flow to safety-related Loads. Documentation Found Deficient |
- on 890616,determined That Calculations Unavailable to Demonstrate That Svc Water Sys Capable of Maintaining Design Flow to safety-related Loads. Documentation Found Deficient
| | | 05000348/LER-1989-004-01, :on 890616,determined That Calculations Were Not Available to Demonstrate That Svc Water Sys Capable of Supplying Design Flow to safety-related Loads Under Scenario of Seismic Event |
- on 890616,determined That Calculations Were Not Available to Demonstrate That Svc Water Sys Capable of Supplying Design Flow to safety-related Loads Under Scenario of Seismic Event
| | | 05000364/LER-1989-005, :on 890429,ESF Actuation Occurred When Safety Injection Signal Generated After Train a Solid State Selector Switch Placed in Operate Mode.Caused by Personnel Error.Disciplinary Action Administered |
- on 890429,ESF Actuation Occurred When Safety Injection Signal Generated After Train a Solid State Selector Switch Placed in Operate Mode.Caused by Personnel Error.Disciplinary Action Administered
| | | 05000348/LER-1989-005-01, :on 890930 & 1001,core Alterations Performed W/O Establishing Containment Refueling Integrity.Caused by Cognitive Personnel Error.Personnel Involved in Event Counseled.Containment Procedure Strengthened |
- on 890930 & 1001,core Alterations Performed W/O Establishing Containment Refueling Integrity.Caused by Cognitive Personnel Error.Personnel Involved in Event Counseled.Containment Procedure Strengthened
| | | 05000364/LER-1989-006, :on 890501,containment Personnel & Equipment Hatches Open for More than 7 Days to Support Outage Activities,Constituting Breach of Fire Barrier.Containment Hatch Closed on 890505 |
- on 890501,containment Personnel & Equipment Hatches Open for More than 7 Days to Support Outage Activities,Constituting Breach of Fire Barrier.Containment Hatch Closed on 890505
| | | 05000348/LER-1989-006-01, :on 891112,safety Injection & Reactor Trip Initiated Due to Low Steam Line Pressure.Caused by Personnel Error Involving Misconfiguration of Circuit Valve.Personnel Involved Counseled |
- on 891112,safety Injection & Reactor Trip Initiated Due to Low Steam Line Pressure.Caused by Personnel Error Involving Misconfiguration of Circuit Valve.Personnel Involved Counseled
| | | 05000348/LER-1989-007-01, :on 891112,both Motor Driven Auxiliary Feedwater Pumps Failed to Start Manually by Operator.Caused by Cognitive Personnel Error Re Design Change.Wiring Discrepancy Corrected & Pump Returned to Svc |
- on 891112,both Motor Driven Auxiliary Feedwater Pumps Failed to Start Manually by Operator.Caused by Cognitive Personnel Error Re Design Change.Wiring Discrepancy Corrected & Pump Returned to Svc
| | | 05000364/LER-1989-007, :on 890522,reactor Tripped Due to lo-lo Steam Generator Level.Caused by Loose Electrical Connector on Steam Generator Feed Pump 2A Thrust Bearing Wear Device. Preventive Maint Task Will Be Developed |
- on 890522,reactor Tripped Due to lo-lo Steam Generator Level.Caused by Loose Electrical Connector on Steam Generator Feed Pump 2A Thrust Bearing Wear Device. Preventive Maint Task Will Be Developed
| | | 05000364/LER-1989-008, :on 890527,reactor Trip Occurred.Caused by Inadequate Procedure for Verifying Proper Insulation After Reassembly of Bearing Oil Piping.New Bearing & Permanent Magnet Generator Stator Installed |
- on 890527,reactor Trip Occurred.Caused by Inadequate Procedure for Verifying Proper Insulation After Reassembly of Bearing Oil Piping.New Bearing & Permanent Magnet Generator Stator Installed
| | | 05000348/LER-1989-008-03, :on 891113,containment Integrity Not Maintained for Approx 30 S.Caused by Personnel in That Inner Door Was Left Blocked Open.Personnel Counseled & Interim Administrative Controls Established |
- on 891113,containment Integrity Not Maintained for Approx 30 S.Caused by Personnel in That Inner Door Was Left Blocked Open.Personnel Counseled & Interim Administrative Controls Established
| | | 05000364/LER-1989-009, :on 890525,determined That Power Range Nuclear Instrumentation Channels Reading Approx 7% Low.Equalizing Valves on Two of Three Instruments Were Leaking.Valves Repaired & Power Range Instruments Adjusted |
- on 890525,determined That Power Range Nuclear Instrumentation Channels Reading Approx 7% Low.Equalizing Valves on Two of Three Instruments Were Leaking.Valves Repaired & Power Range Instruments Adjusted
| | | 05000364/LER-1989-010, :on 890920,reactor Tripped Manually Following Loss of Operating Steam Generator Feed Pump.Caused by Inadvertent Opening of Overspeed Trip Test Valve.Individual Involved in Event Counseled to Be More Aware |
- on 890920,reactor Tripped Manually Following Loss of Operating Steam Generator Feed Pump.Caused by Inadvertent Opening of Overspeed Trip Test Valve.Individual Involved in Event Counseled to Be More Aware
| | | 05000364/LER-1989-011, :on 890925,discovered That Tech Spec 4.6.3.1.a Surveillance Requirement Re Containment Air Lock Outer Door Not Done.Caused by Personnel Error.Individuals Involved Counseled Re Importance of Subj Requirements |
- on 890925,discovered That Tech Spec 4.6.3.1.a Surveillance Requirement Re Containment Air Lock Outer Door Not Done.Caused by Personnel Error.Individuals Involved Counseled Re Importance of Subj Requirements
| | | 05000364/LER-1989-012, :on 891018,reactor Tripped Due to lo-lo Steam Generator Level Due to Closure of Governor Valves.Caused by Design Error in Digital electro-hydraulic Control Sys.Valve Position Limiter Feature Removed |
- on 891018,reactor Tripped Due to lo-lo Steam Generator Level Due to Closure of Governor Valves.Caused by Design Error in Digital electro-hydraulic Control Sys.Valve Position Limiter Feature Removed
| | | 05000364/LER-1989-013, :on 891019,reactor Tripped Due to lo-lo Level in Steam Generator 2C.Caused by Operator Incorrectly Transferring Steam Generator Level Control to Main Feedwater.Involved Personnel Counseled |
- on 891019,reactor Tripped Due to lo-lo Level in Steam Generator 2C.Caused by Operator Incorrectly Transferring Steam Generator Level Control to Main Feedwater.Involved Personnel Counseled
| | | 05000364/LER-1989-014, :from 891115-16,Tech Spec 3.0.3 Entered Voluntarily to Repair Leaking Containment Purge Isolation Dampers.Caused by Need to Repair Dampers.Dampers Closed & Automatic Isolation Feature Restored |
- from 891115-16,Tech Spec 3.0.3 Entered Voluntarily to Repair Leaking Containment Purge Isolation Dampers.Caused by Need to Repair Dampers.Dampers Closed & Automatic Isolation Feature Restored
| | | 05000364/LER-1989-015, :on 891118,reactor Tripped Due to Turbine Trip. Caused by Voltage Transient in Power Circuit to Digital electro-hydraulic Control Sys & Inverter Failure.Inverter Repaired & Returned to Svc |
- on 891118,reactor Tripped Due to Turbine Trip. Caused by Voltage Transient in Power Circuit to Digital electro-hydraulic Control Sys & Inverter Failure.Inverter Repaired & Returned to Svc
| | | 05000364/LER-1989-016, :on 891228,discovered That Required Surveillance for Plant Vent Stack Radioactive Gas Monitor Not Performed.Caused by Personnel Improperly Scheduling Surveillance for Time Later than Due Date |
- on 891228,discovered That Required Surveillance for Plant Vent Stack Radioactive Gas Monitor Not Performed.Caused by Personnel Improperly Scheduling Surveillance for Time Later than Due Date
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