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I NRC perm 386 U S. NUCLE Al KETULATOAV COMMIS$10N APPROVED OMS NO 315v4104 LICENSEE EVENT REPORT (LER)
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F ACILITV NAME (11 DOCKET NUMBER (2)
PAGEa3a Joseph M. Farley - Unit 1 o1s1010101 31418 iloFl0I3
'"""' Technical Specification Action Statements Not Met When Radiation Monitor R-11 Was Inoperable EVENT DATE 158 LER NUMBER del REPORT DATE 171 OTHER F ACILITIES INVOLVED (BI 54 1AL MONTH DAV YEAR YEAR v s.
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LICENSEE CONTACT FOR THIS LER (127 NAME TELEPHONE NLYSER ARE A CODE J. D. Woodard, General Manager - Nuclear Plant 210 5 R19 to I -15 n I si Fi COMPLETE ONE LINE FOR E ACH COMPONENT FAILURE DESCRISED IN THIS REPORT (131 uYE
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At 0730 on 1-5-87 during normal plant operations at 100% reactor power, it was discovered that the containment atmosphere particulate radioactivity monitor (R-11) was inoperable due to improper valve alignment.
Investigation revealed that R-11 had been inoperable since approximately 1225 on 12-31-86.
Since it had not been realized at the time that R-11 was inoperable, the Technical l
Specification 3.4.7.1 requirement to obtain and analyze samples of the containment atmosphere once per twenty-four hours was not met. Upon discovery on 1-5-87, R-11 was returned to service.
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NAC Form 3SSA U.S. NUCLEA7 [EiULATORY COMMIS$10N LICENTEE EVENT REPORT (LER) TEXT C!lNTINUATION uraovEo oss No siso-om EXPIRES: 8/31/88
. ACILITY NAME (Il DOCKEI NUMSER 12)
LER NUMSER (61 PAGE(3)
VEAR EE I
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Joseph M. Farley - Unit 1 o ls j o lo l o l 3l 4l8 8l 7 0 j0 [ 1 0l 0 0l 2 0l3 oF TEXT IWmore space k requeet use encone!NRC form 388Ks)(1n
Plant and System Identification
Westinghouse - Pressurized Water Reactor Energy Industry Identification System codes are identified in the text as [XX].
Sunanary of Event At 0730 on 1-5-87 during normal plant operations at 100% reactor power, it 5:as discovered that the containment atmosphere particulate radioactivity monitor (R-11) [IL] was inoperable due to improper valve alignment.
Investigation revealed that R-11 had been inoperable since approximately 1225 on 12-31-86.
Since it had not been realized at the time that R-11 was inoperable, the Technical Specification 3.4.7.1 requirement to obtain and analyze samples of the containment atmosphere once per twenty-four hours was not met. Upon discovery on 1-5-87, R-11 was returned to service.
Description of Event
At approximately 0730 on 1-5-87, it was discovered that the containment atmosphere particulate radioactivity monitor (R-11) had been inoperable from 12-31-86 until 1-5-87 due to improper valve alignment. Since it had not been realized at the time that R-11 was inoperable, the Technical Specification 3.4.7.1 requirement to obtain and analyze samples of the containment atmosphere once per twenty-four hours was not met.
During a routine log review by Health Physics (HP) Supervision on 1-5-87, it was observed that the R-11 reading had decreased from approximately 5000 counts per minute on 12-30-86 to approximately 2000 counts per minute on 12-31-86 and had remained at approximately 2000 counts per minute. Upon investigation, it was found that the valve V-1 (the R-11 bypass valve) was open and V-2 (the R-11 inlet valve) was closed which made R-11 inoperable.
Further investigation revealed that procedure FNP-1-STP-227.2B had been performed by Instrumentation and Controls (I&C) personnel on 12-31-86.
Apparently, the valves had not been restored to the proper position following performance of the STP. Upon completion of the STP on 12-31-86, the shift supervisor had noticed the reduced R-11 reading. He requested HP personnel to verify the valve positions on R-11.
This verification was completed at 2030 on 12-31-86 and the shift supervisor was informed that R-11 was operating properly. Apparently, the HP technicians performing the valve alignment verification had not detected the valve alignment problem. HP personnel reasoned that the reduced count rate was due to changes in the environmental conditions.
R-11 was restored to proper operation and declared operable at 0901 on 1-5-87.
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NRC Form 304A U.S. NUCLE A3 E El ULATORY Commission LICEN!EE EVENT REPORT (LER) TEXT CONTINUATIJN urzovEo ows No aiso-oio4 EXPIRES: 8/31/8B F ACILITY NAME (1)
DOCKET NUMSER (2)
LER NUMSER 16)
PAGE (3)
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Cause of Event
The inoperability of R-11 was due to errors committed by I&C personnel in conducting an STP (FNP-1-STP-227.2B). A contributing cause was that the procedure grouped several actions, including the manipulation of V-1 and V-2, into one step. Apparently, HP personnel subsequently committed the same errors in conducting the lineup verification specifically requested by the Shift Supervisor although the HP verification was documented by individual valve steps.
Reportability Analysis and Safety Assessment This event is reportable because of the failure to meet the Technical Specification 3.4.7.1 requirement to obtain and analyze samples of the containment atmosphere once per twenty-four hours. However, containment atmosphere particulate monitor R-12 was not affected by this event. No radiological hazards were associated with this event and therefore the health and safety of the public were not affected by this event.
Corrective Action
The I&C technician and the HP technicians involved in' this event have been counseled for failure to properly follow approved procedures. The I&C procedures for R-11 will be revised to place valve manipulations in separate steps.
Additional Information
LER 86-001-00 reported Technical Specifications action statements not being met when R-11 was inoperable, although the cause of this previous event was unrelated to the cause of the current event.
No components failed during this event.
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Alabama Power Company 600 North 18th Street Post Office Bcx 2641 Birmingham, Alabama 35291-o400 Telephone 205 250-1835 AlabamaPower R. P. Mcdonald the southern electro system Senior Vice President February 3,1987 Docket No. 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
Dear Sir:
Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report No. LER 87-001-00 Joseph M. Farley Nuclear Plant, Unit 1, Licensee Event Report No. LER 87-001-00 is being submitted in accordance with 10CFR50.73.
If you have any questions, please advise.
Respectfully s i ted, u //
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R. P. Mcdonald RPM / JAR: dst-D-LER Enclosure l
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| 05000364/LER-1987-001-01, :on 870228,reactor Tripped.Caused by Spike on Channel 1 of Over temp-delta-t While Channel 3 in Test. Investigation Into Cause of 7300 Series lead-lag Cards Continuing |
- on 870228,reactor Tripped.Caused by Spike on Channel 1 of Over temp-delta-t While Channel 3 in Test. Investigation Into Cause of 7300 Series lead-lag Cards Continuing
| | | 05000348/LER-1987-001, :on 870105,containment Atmosphere Particulate Radioactivity Monitor Discovered Inoperable Due to Improper Valve Alignment.Caused by Personnel Failure to Follow Procedures.Personnel Counseled |
- on 870105,containment Atmosphere Particulate Radioactivity Monitor Discovered Inoperable Due to Improper Valve Alignment.Caused by Personnel Failure to Follow Procedures.Personnel Counseled
| | | 05000364/LER-1987-002-01, :on 870903,determined That Train a & B Svc Water Battery Changer Room Coolers Water Supplies Crossed. Caused by Design Error.Design Change Will Be Implemented & Completed During Refueling Outage in Oct 1987 |
- on 870903,determined That Train a & B Svc Water Battery Changer Room Coolers Water Supplies Crossed. Caused by Design Error.Design Change Will Be Implemented & Completed During Refueling Outage in Oct 1987
| | | 05000348/LER-1987-002, :on 870108,reactor Tripped Due to Manual Tripping of Main Turbine to Investigate Leak in Msiv.Caused by Cracked Air Supply Line to MSIV & Inadequate Clearance for Main Steam Line.Air Line Replaced |
- on 870108,reactor Tripped Due to Manual Tripping of Main Turbine to Investigate Leak in Msiv.Caused by Cracked Air Supply Line to MSIV & Inadequate Clearance for Main Steam Line.Air Line Replaced
| | | 05000364/LER-1987-003-01, :on 871017,continuous Iodine & Particulate Sampling of Plant Vent Stack by R-29A Interrupted Due to Tagging Error.Auxiliary Sampling Not Initiated.Caused by Personnel Error.Personnel Counseled |
- on 871017,continuous Iodine & Particulate Sampling of Plant Vent Stack by R-29A Interrupted Due to Tagging Error.Auxiliary Sampling Not Initiated.Caused by Personnel Error.Personnel Counseled
| | | 05000348/LER-1987-003, :on 870109,reactor Tripped on lo-lo Steam Generator Level Following Manual Tripping of Main Turbine. Caused by Failure to Monitor Steam Generator Feed Pumps Suction Pressure Adequately.Procedure Revised |
- on 870109,reactor Tripped on lo-lo Steam Generator Level Following Manual Tripping of Main Turbine. Caused by Failure to Monitor Steam Generator Feed Pumps Suction Pressure Adequately.Procedure Revised
| | | 05000364/LER-1987-004-01, :on 871113,steam Generator Tube Degradation Observed.Investigations & Evaluations Performed Identified Four Areas Where Tube Degradation Observed.Tubes Have Been Plugged as Required & Listed Actions Taken |
- on 871113,steam Generator Tube Degradation Observed.Investigations & Evaluations Performed Identified Four Areas Where Tube Degradation Observed.Tubes Have Been Plugged as Required & Listed Actions Taken
| | | 05000348/LER-1987-004, :on 870122,during Nuclear Instrumentation Sys Power Channel N-42 Calibr & Functional Test Reactor Tripped. Caused by Failure of Inverter 1A.Four Blown Fuses Replaced & Inverter Returned to Svc |
- on 870122,during Nuclear Instrumentation Sys Power Channel N-42 Calibr & Functional Test Reactor Tripped. Caused by Failure of Inverter 1A.Four Blown Fuses Replaced & Inverter Returned to Svc
| | | 05000364/LER-1987-004, :on 871113,steam Generator Tube Degradation Discovered.Caused by Antivibration Bar Wear, Primary Water Stress Corrosion Cracking in Tubesheet Area,& OD Stress Corrosion Cracking at Support Plates. |
- on 871113,steam Generator Tube Degradation Discovered.Caused by Antivibration Bar Wear, Primary Water Stress Corrosion Cracking in Tubesheet Area,& OD Stress Corrosion Cracking at Support Plates...
| | | 05000364/LER-1987-005-01, :on 871111,actuation of ESF Equipment Occurred. Caused by Personnel Error.Personnel Counseled |
- on 871111,actuation of ESF Equipment Occurred. Caused by Personnel Error.Personnel Counseled
| | | 05000348/LER-1987-005, :on 870118,two Containment Isolation Valves in Sump Discharge Line Penetration Failed to Close During Surveillance.Caused by Faulty Solenoid Valve.Solenoid Replaced & Valve Returned to Svc |
- on 870118,two Containment Isolation Valves in Sump Discharge Line Penetration Failed to Close During Surveillance.Caused by Faulty Solenoid Valve.Solenoid Replaced & Valve Returned to Svc
| | | 05000364/LER-1987-006-01, :on 871115,ESF Actuation Occurred When Diesel Generator 1-2A Autostarted & Supplied Power to 2F & 2K 4160 Volt Buses.Caused by Personnel Error.Personnel Counseled |
- on 871115,ESF Actuation Occurred When Diesel Generator 1-2A Autostarted & Supplied Power to 2F & 2K 4160 Volt Buses.Caused by Personnel Error.Personnel Counseled
| | | 05000348/LER-1987-006, :on 870324,discovered That Hourly Fire Watch Not Performed in Room 223.Caused by Personnel Error. Individuals Involved Counseled |
- on 870324,discovered That Hourly Fire Watch Not Performed in Room 223.Caused by Personnel Error. Individuals Involved Counseled
| | | 05000348/LER-1987-007, :on 870405,w/unit in Mode 3,reactor Trip Signal Generated When Source Range Nuclear Instrument N-31 Failed High.Caused by Failed Detector.Source Range Detector Replaced |
- on 870405,w/unit in Mode 3,reactor Trip Signal Generated When Source Range Nuclear Instrument N-31 Failed High.Caused by Failed Detector.Source Range Detector Replaced
| | | 05000364/LER-1987-007-01, :on 871123,fire Barrier Penetration 03-139-33 Nonfunctional for More than 7 Days.Cause Not Stated.Sound Powered Phone Cord Was Placed Through Fire Damper to Facilitate Valve Lineups |
- on 871123,fire Barrier Penetration 03-139-33 Nonfunctional for More than 7 Days.Cause Not Stated.Sound Powered Phone Cord Was Placed Through Fire Damper to Facilitate Valve Lineups
| | | 05000364/LER-1987-008-01, :on 871127,reactor Coolant Sys Relief Valve Opened.Caused by Localized Pressure Pulse Created When RHR Containment Sump Suction Valves Opened.Procedure Re Leak Rate Testing Changed |
- on 871127,reactor Coolant Sys Relief Valve Opened.Caused by Localized Pressure Pulse Created When RHR Containment Sump Suction Valves Opened.Procedure Re Leak Rate Testing Changed
| | | 05000348/LER-1987-008, :on 870504,fire Watch Discovered Not Posted as Required by Tech Spec 3.7.11.2 & Fire Door Left W/O Being Properly Closed.Caused by Personnel Error.Door Closed Immediately.Warehouseman Counseled |
- on 870504,fire Watch Discovered Not Posted as Required by Tech Spec 3.7.11.2 & Fire Door Left W/O Being Properly Closed.Caused by Personnel Error.Door Closed Immediately.Warehouseman Counseled
| | | 05000348/LER-1987-009, :on 870510,during Performance of Svc Water (SW) Flowpath Verification,Rhr Pump 1B Room Cooler SW Isolation Valves Found Closed.Caused by Personnel Not Ensuring That Valves Repositioned.Personnel Counseled |
- on 870510,during Performance of Svc Water (SW) Flowpath Verification,Rhr Pump 1B Room Cooler SW Isolation Valves Found Closed.Caused by Personnel Not Ensuring That Valves Repositioned.Personnel Counseled
| | | 05000364/LER-1987-009-01, :on 871203,reactor Tripped Due to Low Water Level in 2A Steam Generator Coincident W/Feedwater Less than Steam Flow Signal.Caused by Personnel Error.Operator Involved Counseled |
- on 871203,reactor Tripped Due to Low Water Level in 2A Steam Generator Coincident W/Feedwater Less than Steam Flow Signal.Caused by Personnel Error.Operator Involved Counseled
| | | 05000348/LER-1987-010, :on 870514,w/unit Operating at 100% Reactor Power,Reactor Tripped Due to Steam Flow Greater than Feedwater Flow Coincident W/Low Steam Generator Level.Caused by Personnel Error.Individual Counseled |
- on 870514,w/unit Operating at 100% Reactor Power,Reactor Tripped Due to Steam Flow Greater than Feedwater Flow Coincident W/Low Steam Generator Level.Caused by Personnel Error.Individual Counseled
| | | 05000364/LER-1987-010-01, :on 871209,unit Shutdown Due to Pressure Boundary Leakage on RCS Loop B Cold Safety Injection Line Between Check Valve & Loop.Caused by Cracked Joint Due to Fatigue.Defective Pipe Section Replaced |
- on 871209,unit Shutdown Due to Pressure Boundary Leakage on RCS Loop B Cold Safety Injection Line Between Check Valve & Loop.Caused by Cracked Joint Due to Fatigue.Defective Pipe Section Replaced
| | | 05000364/LER-1987-010, :on 871209,leak Discovered in Section of Safety Injection Piping on RCS Loop B Cold Leg.Caused by Defect in Welded Joint Between Long Radius Elbow & Straight Section of Pipe.Cooldown Commenced |
- on 871209,leak Discovered in Section of Safety Injection Piping on RCS Loop B Cold Leg.Caused by Defect in Welded Joint Between Long Radius Elbow & Straight Section of Pipe.Cooldown Commenced
| | | 05000348/LER-1987-011, :on 870611,results of Testing of Fire Dampers Declared Inoperable on 870605,determined That Dampers Would Not Fully Close & Latch W/Air Flow.Caused by Design Deficiency.Design Change Being Developed |
- on 870611,results of Testing of Fire Dampers Declared Inoperable on 870605,determined That Dampers Would Not Fully Close & Latch W/Air Flow.Caused by Design Deficiency.Design Change Being Developed
| | | 05000348/LER-1987-012, :on 870721,problems W/Configuration of Environ Qualification Solenoid Valve Splices & Terminations Noted. Caused by Unapproved Methods for Installation.Solenoid Valves Modified |
- on 870721,problems W/Configuration of Environ Qualification Solenoid Valve Splices & Terminations Noted. Caused by Unapproved Methods for Installation.Solenoid Valves Modified
| | | 05000348/LER-1987-013, :on 870710,five Sectors of Land Identified W/Increased Calculated Dose.Caused by Presence of Indicator Milk Animal & Movement of Residents Into or Outside Area |
- on 870710,five Sectors of Land Identified W/Increased Calculated Dose.Caused by Presence of Indicator Milk Animal & Movement of Residents Into or Outside Area
| | | 05000348/LER-1987-014, :on 870717,fire Damper 1-116-15 in Nonradiation Ventilation Sys Tested & Would Not Close W/Air Flow.Caused by Design Deficiency.Design Change Initiated to Evaluate Options Available & Provide Appropriate Design |
- on 870717,fire Damper 1-116-15 in Nonradiation Ventilation Sys Tested & Would Not Close W/Air Flow.Caused by Design Deficiency.Design Change Initiated to Evaluate Options Available & Provide Appropriate Design
| | | 05000348/LER-1987-015, :on 870831,0914 & 22,control Room Fire Dampers Did Not Close W/Air Flow During Testing.Caused by Design Deficiency in That Dampers Will Not Close Fully & Latch W/ Air Flow.Design Changes Will Be Initiated |
- on 870831,0914 & 22,control Room Fire Dampers Did Not Close W/Air Flow During Testing.Caused by Design Deficiency in That Dampers Will Not Close Fully & Latch W/ Air Flow.Design Changes Will Be Initiated
| | | 05000348/LER-1987-016, :on 870917,fire Dampers Inoperable Due to Failure to Close W/Air Flow.Caused by Improper Installation. Damper Removed from Sys & re-installed Correctly |
- on 870917,fire Dampers Inoperable Due to Failure to Close W/Air Flow.Caused by Improper Installation. Damper Removed from Sys & re-installed Correctly
| | | 05000348/LER-1987-017, :on 871001,Fire Door 496 Declared Inoperable & Could Not Be Repaired within 7 Days Violating Tech Spec 3.7.12.Caused by Door Being Bent & Latch Mechanism Stuck.New Door Ordered.Fire Watch Will Be Maintained |
- on 871001,Fire Door 496 Declared Inoperable & Could Not Be Repaired within 7 Days Violating Tech Spec 3.7.12.Caused by Door Being Bent & Latch Mechanism Stuck.New Door Ordered.Fire Watch Will Be Maintained
| | | 05000348/LER-1987-018, :on 871013,discovered That Drawing Error Existed Showing Locations of 1A & 1B Containment Hydrogen Recombiners 1A & 1B to Be Reversed.Caused by Use of Incorrect Drawing.Drawing Corrected |
- on 871013,discovered That Drawing Error Existed Showing Locations of 1A & 1B Containment Hydrogen Recombiners 1A & 1B to Be Reversed.Caused by Use of Incorrect Drawing.Drawing Corrected
| | | 05000348/LER-1987-019, :on 871013,visitor Found Unescorted in Vital Area.Caused by Visitor & Escort Becoming Separated.Escort Retrained in Security Requirements & Moves Taken to Min Number of Visitors Requiring Access |
- on 871013,visitor Found Unescorted in Vital Area.Caused by Visitor & Escort Becoming Separated.Escort Retrained in Security Requirements & Moves Taken to Min Number of Visitors Requiring Access
| | | 05000348/LER-1987-020, :on 871015,contractor Employee Gained Unauthorized Access to Main Control Room Causing Alarm to Be Generated in Security Central Alarm Station.Caused by Personnel Error.Personnel Counseled |
- on 871015,contractor Employee Gained Unauthorized Access to Main Control Room Causing Alarm to Be Generated in Security Central Alarm Station.Caused by Personnel Error.Personnel Counseled
| | | 05000348/LER-1987-023, :on 871127,control Room Fire Dampers Inoperable Due to Failure to Close W/Air Flow.Caused by Design Deficiency.Implementation of Design Changes Expected within Next 6 Months |
- on 871127,control Room Fire Dampers Inoperable Due to Failure to Close W/Air Flow.Caused by Design Deficiency.Implementation of Design Changes Expected within Next 6 Months
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