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| CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I YES (If yes, complete EXPECTED SUBMISSION DATE). | | CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I YES (If yes, complete EXPECTED SUBMISSION DATE). |
| XI NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) | | XI NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
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| On October 11 , 1997, with Unit 2 at Refueling Shutdown, an inadvertent actuation of the Unit 2 "B,, train of the High-Consequence Limiting Safeguards (Hi-CLS) system occurred at 14:22 during the replacement of electrical relay 2-CLS-RLY-1812. As designed, the Hi-CLS signal initiated a Unit 2 "B" train Safety Injection (SI) system actuation. Plant systems and components responded to the Hi-CLS and SI signals, as designed. After verifying that the Hi-CLS signal was not valid, the affected systems were restored to their pre-event configuration. | | On October 11 , 1997, with Unit 2 at Refueling Shutdown, an inadvertent actuation of the Unit 2 "B,, train of the High-Consequence Limiting Safeguards (Hi-CLS) system occurred at 14:22 during the replacement of electrical relay 2-CLS-RLY-1812. As designed, the Hi-CLS signal initiated a Unit 2 "B" train Safety Injection (SI) system actuation. Plant systems and components responded to the Hi-CLS and SI signals, as designed. After verifying that the Hi-CLS signal was not valid, the affected systems were restored to their pre-event configuration. |
| A Root Cause Evaluation concluded that this event was caused by personnel errors. To prevent recurrence, training will be conducted to discuss the lessons learned. The event did not affect Unit 2 reactor core cooling, or result in any radiological releases or personnel injuries. | | A Root Cause Evaluation concluded that this event was caused by personnel errors. To prevent recurrence, training will be conducted to discuss the lessons learned. The event did not affect Unit 2 reactor core cooling, or result in any radiological releases or personnel injuries. |
| Although the engineered safety feature actuations were invalid, the CLS and SI systems were not completely removed from service. Therefore, the NRC was notified pursuant to 10 CFR 50. 72 (b)(2)(ii) on October 11, 1997, at 16:39. This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(iv). | | Although the engineered safety feature actuations were invalid, the CLS and SI systems were not completely removed from service. Therefore, the NRC was notified pursuant to 10 CFR 50. 72 (b)(2)(ii) on October 11, 1997, at 16:39. This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(iv). |
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| 9711120275 971107 PDR ADOCK 05000280 s PDR NRG FORM 366 (4-95) | | 9711120275 971107 PDR ADOCK 05000280 s PDR NRG FORM 366 (4-95) |
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| LICENSEE EVENT REPORT (LER) | | LICENSEE EVENT REPORT (LER) |
| TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3) ! | | TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3) ! |
| YEAR I SEQUENTIAL NUMBER l REVISION NUMBER | | YEAR I SEQUENTIAL NUMBER l REVISION NUMBER Surry Power Station Unit 1 05000 - 280 97 --008 -- 00 30F 5 TEXT (If more space is requirea. use additional copies of NRC Form 366A) (17) |
| * Surry Power Station Unit 1 05000 - 280 97 --008 -- 00 30F 5 TEXT (If more space is requirea. use additional copies of NRC Form 366A) (17)
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| ==1.0 DESCRIPTION== | | ==1.0 DESCRIPTION== |
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| * LER 50-280/50-281 /95-009-00, "Personnel Error Results in Loss of 4160V Transfer Bus and Start of Emergency Diesel Generators" | | * LER 50-280/50-281 /95-009-00, "Personnel Error Results in Loss of 4160V Transfer Bus and Start of Emergency Diesel Generators" |
| * LER 50-281 /95-006-00, "Unit 2 Auto Reactor Trip Due to Main Transformer Protective Differential Relay Actuation" | | * LER 50-281 /95-006-00, "Unit 2 Auto Reactor Trip Due to Main Transformer Protective Differential Relay Actuation" |
| * LER 50-280/~3-001-00, "Reactor Trip and Safety Injection Due to Spurious High Consequence Limiting Safeguards Signal Caused by Malfunctioning Relay" | | * LER 50-280/~3-001-00, "Reactor Trip and Safety Injection Due to Spurious High Consequence Limiting Safeguards Signal Caused by Malfunctioning Relay" 8.0 ADDITIONAL INFORMATION Although EDG No. 3 had been conservatively declared inoperable, it would have responded automatically to a Unit 1 demand signal after the Unit 2 SI signal had been reset, except for a brief period during the EOG shutdown evolution. |
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| 8.0 ADDITIONAL INFORMATION Although EDG No. 3 had been conservatively declared inoperable, it would have responded automatically to a Unit 1 demand signal after the Unit 2 SI signal had been reset, except for a brief period during the EOG shutdown evolution. | |
| The status of the Unit 2 charging pumps and the associated ventilation system dampers would not have affected the ability of the Auxiliary Ventilation system to respond to a Unit 1 SI signal. During this event, the Auxiliary Ventilation system would have automatically responded to a Unit 1 demand signal, except for the momentary reset of the low air flow trip signal for 1-VS-F-58A/B. | | The status of the Unit 2 charging pumps and the associated ventilation system dampers would not have affected the ability of the Auxiliary Ventilation system to respond to a Unit 1 SI signal. During this event, the Auxiliary Ventilation system would have automatically responded to a Unit 1 demand signal, except for the momentary reset of the low air flow trip signal for 1-VS-F-58A/B. |
| Unit 1 was operating at 100% power during this event and was otherwise not affected. | | Unit 1 was operating at 100% power during this event and was otherwise not affected. |
| NRG FORM 366A (4-95)}} | | NRG FORM 366A (4-95)}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. 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Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket ML18153A2201998-02-0606 February 1998 LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr ML18153A2071998-01-13013 January 1998 LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors ML18153A2101998-01-13013 January 1998 LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status ML18153A1911997-11-26026 November 1997 LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised ML18153A1971997-11-26026 November 1997 LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset ML18153A1921997-11-25025 November 1997 LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr ML18153A1831997-11-12012 November 1997 LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause ML18153A1791997-11-0707 November 1997 LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. 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Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr ML18153A1191997-03-19019 March 1997 LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr ML18153A1201997-03-19019 March 1997 LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr ML18153A1131997-02-20020 February 1997 LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr ML18153A1101997-02-13013 February 1997 LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr ML18153A0951997-01-0202 January 1997 LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown ML18153A0931996-12-12012 December 1996 LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr ML18153A0691996-09-19019 September 1996 LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr ML18153A0481996-08-26026 August 1996 LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr ML18153A0521996-08-20020 August 1996 LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr ML18153A0321996-07-30030 July 1996 LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr ML18153A0281996-07-17017 July 1996 LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr ML18153A0141996-07-0202 July 1996 LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr 1999-08-27
[Table view] Category:RO)
MONTHYEARML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket ML18153A2201998-02-0606 February 1998 LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr ML18153A2071998-01-13013 January 1998 LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors ML18153A2101998-01-13013 January 1998 LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status ML18153A1911997-11-26026 November 1997 LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised ML18153A1971997-11-26026 November 1997 LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset ML18153A1921997-11-25025 November 1997 LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr ML18153A1831997-11-12012 November 1997 LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause ML18153A1791997-11-0707 November 1997 LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset ML18153A1721997-10-30030 October 1997 LER 97-007-00:on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage ML18153A1421997-06-10010 June 1997 LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr ML18153A1391997-05-28028 May 1997 LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled ML18153A1291997-04-18018 April 1997 LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr ML18153A1281997-04-15015 April 1997 LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr ML18153A1241997-04-0808 April 1997 LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr ML18153A1191997-03-19019 March 1997 LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr ML18153A1201997-03-19019 March 1997 LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr ML18153A1131997-02-20020 February 1997 LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr ML18153A1101997-02-13013 February 1997 LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr ML18153A0951997-01-0202 January 1997 LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown ML18153A0931996-12-12012 December 1996 LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr ML18153A0691996-09-19019 September 1996 LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr ML18153A0481996-08-26026 August 1996 LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr ML18153A0521996-08-20020 August 1996 LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr ML18153A0321996-07-30030 July 1996 LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr ML18153A0281996-07-17017 July 1996 LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr ML18153A0141996-07-0202 July 1996 LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr 1999-08-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30
[Table view] |
Text
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3150-0104 (4-95) EXPIRES 4/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33),
U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC (See reverse for required number of digits/characters for each block) 20555-0001. AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104 ), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) PAGE(3)
SURRY POWER STATION, Unit 1 05000 - 280 1 OF5 TITLE (4)
Invalid Actuation of Engineered Safety Features Due to Personnel Errors EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED 8)
SEQUENTIAL REVISION FACILITY NAME DOCUMENT NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER Surry Power Station, Unit 2 05000-281 FACILITY NAME DOCUMENT NUMBER 10 11 97 97 -- 008 -- 00 11 07 97 05000-OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)
MODE (9) N 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50. 73(a)(2)(viii)
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50.73(a)(2)(x)
LEVEL (10) 100 ,, 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71
~
): 20.2203(a)(2)(ii) 20.2203(a)(4) X 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) Specify in Abstract below 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) or in NRG Form 366A LICENSEE CONTACT FOR THIS LER (12)
NAME D. A. Christian, Station Manager I ( ; ; ; ~ N ; ; ; : ; ~ ~ ~ d e Area Code)
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131
~
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I YES (If yes, complete EXPECTED SUBMISSION DATE).
XI NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On October 11 , 1997, with Unit 2 at Refueling Shutdown, an inadvertent actuation of the Unit 2 "B,, train of the High-Consequence Limiting Safeguards (Hi-CLS) system occurred at 14:22 during the replacement of electrical relay 2-CLS-RLY-1812. As designed, the Hi-CLS signal initiated a Unit 2 "B" train Safety Injection (SI) system actuation. Plant systems and components responded to the Hi-CLS and SI signals, as designed. After verifying that the Hi-CLS signal was not valid, the affected systems were restored to their pre-event configuration.
A Root Cause Evaluation concluded that this event was caused by personnel errors. To prevent recurrence, training will be conducted to discuss the lessons learned. The event did not affect Unit 2 reactor core cooling, or result in any radiological releases or personnel injuries.
Although the engineered safety feature actuations were invalid, the CLS and SI systems were not completely removed from service. Therefore, the NRC was notified pursuant to 10 CFR 50. 72 (b)(2)(ii) on October 11, 1997, at 16:39. This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(iv).
9711120275 971107 PDR ADOCK 05000280 s PDR NRG FORM 366 (4-95)
- rr==============t NR_C FORM 366A U.S. NUCLEAR REGULATORY COMMISSION
, (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)
YEAR I SEQUENTIAL NUMBER I REVISION NUMBER Surry Power Station Unit 1 05000 - 280 97 --008 -- 00 20F 5 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
1.0 DESCRIPTION
OF THE EVENT On October 11, 1997, with Unit 2 at Refueling Shutdown (RSD), an inadvertent actuation of the Unit 2 "B" train of the High-Consequence Limiting Safeguards (Hi-CLS) system
[EIIS-JE] occurred at 14:22 during the replacement of electrical relay 2-CLS-RL Y-1812.
As designed, the Hi-CLS signal initiated a Unit 2 "B" train Safety Injection (SI) system actuation.
Plant systems and components responded to the Hi-CLS and SI signals as designed.
After verifying that the Hi-CLS signal was spurious and that the containment was at atmospheric pressure, control room operators reset the SI signal. The actuations resulting from tlie SI signal and the operator response actions are described below.
- SI system valve, 2-SI-MOV-2867D, opened and was immediately closed by a control room operator. The brief opening of the valve allowed gravity driven flow from the refueling water storage tank [EIIS-BP,TK] to the reactor vessel [EIIS-RPV], resulting in a vessel level increase of 0.2 feet.
[EIIS-EK,DG] was conservatively declared inoperable. The requirements of Technical Specification (TS) 3.16. B.1.a were verified to be satisfied and the EOG was returned to an operable status at 16:35.
- One bank of the Main Control Room Bottled Air system [EIIS-VI] actuated. The system was isolated and the affected bank was returned to service at 16:08.
- Auxiliary Building Ventilation system fans, 1-VS-F-58A/B, started and the system realigned, as expected. The air flow through the fans was lower than normal since two Unit 2 charging pumps [EIIS-CB, P] and the associated ventilation system dampers [EIIS.:.VF,DMP] were out of service. While control room operators attempted to remedy the low air flow condition, the fans tripped. The low air flow trip signal was immediately cleared and the ventilation system was restored to its normal configuration.
- The containment hydrogen analyzer heat tracing [EIIS-FE] received an actuation signal, which initiated a time-delayed start of the system. The signal was manually reset before the heat tracing began to operate.
NRG FORM 366A (4-95)
- rr============j NR.C FORM 366A U.S. NUCLEAR REGULATORY COMMISSION
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3) !
YEAR I SEQUENTIAL NUMBER l REVISION NUMBER Surry Power Station Unit 1 05000 - 280 97 --008 -- 00 30F 5 TEXT (If more space is requirea. use additional copies of NRC Form 366A) (17)
1.0 DESCRIPTION
OF THE EVENT (Continued)
- Containment integrity valves closed as follows:
- Component Cooling system valve, 2-CC-TV-209B, closed. While the closure of 2-CC-TV-209B did not affect the operating train of the residual heat removal (RHR) system, the valve was promptly reopened by a control room operator to ensure the standby train of the RHR system [EIIS-BP] remained available.
- Aerated Drains system valve, 2-DA-TV-200B, Charging system valve, 2-CH-TV-2204B, and Gaseous Vents system valve, 2-VG-TV-2098, closed. The valves were immediately reopened.
Although the engineered safety feature (ESF) actuations described above were invalid, the CLS and SI systems were not completely removed from service. Therefore, the NRC was notified pursuant to 10 CFR 50.72 (b)(2)(ii) on October 11, 1997, at 16:39. This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(iv).
2.0 SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS The Hi-CLS actuation resulted from an invalid signal that was inadvertently generated during a maintenance activity. The unit conditions (i.e., RSD) did not warrant the initiation of the Hi-CLS signal, nor was the Hi-CLS system required to be operable. The other ESF actuations described above occurred as a result of the Hi-CLS signal and were also invalid.
After verifying that the Hi-CLS signal was not valid, the affected systems were restored to the pre-event configuration. The event did not affect Unit 2 reactor core cooling or result in any radiological releases or personnel injuries. Therefore, this event resulted in no safety consequences or significant implications and the health and safety of the public were not affected at any time.
3.0 CAUSE A Category 2 Root Cause Evaluation (RCE) was performed to determine the cause of this event and to recommend corrective actions. The RCE concluded that this event was caused by 1) a "slip" (i e., an unintentional error of execution of a correctly intended action) by utility maintenance personnel during the replacement of electrical relay 2-CLS-RLY-1B12 [EIIS-JE,RLY] and, 2) an error by utility personnel in that the assumed limiting conditions in the Safety Evaluation for the relay replacement were not properly incorporated into the appropriate implementing document. These causes are discussed in more detail below.
NRC FORM 366A (4-95)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)
YEAR I SEQUENTIAL NUMBER I REVISION NUMBER Surry Power Station Unit 1 05000 - 280 97 --008 -- 00 40F 5 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) 3.0 CAUSE (Continued)
While attempting to connect an electrical lead to the appropriate contact during the replacement of 2-CLS-RL Y-1B12, an electrician inadvertently touched the lead to an adjacent contact, thereby creating a short circuit. This "slip" was caused by the confined space and location of 2-CLS-RLY-1B12 within the electrical cabinet, which made the relay replacement difficult to accomplish. The short circuit caused a CLS system fuse [EIIS-JE,FU] to fail, which allowed the Hi-CLS signal to be generated.
The potential for a Hi-CLS signal had been recognized and addressed in tr-s Safety Evaluation for the relay replacement. The Safety Evaluation also recognized that a Hi-CLS signal would initiate an SI system actuation, but noted that the Unit 2 "B" train of the SI system would be defeated by a procedurally controlled temporary modification (TM), which was associated with an unrelated maintenance activity. The use of the TM to prevent a potential SI system actuation was valid. However, the Safety Evaluation preparer failed to utilize an adequate tracking mechanism, as required by Station Administrative Procedure VPAP-3001, "Safety Evaluations," to ensure that the TM would be in place during the relay replacement. This inadequacy was also not detected by the personnel who reviewed and approved the Safety Evaluation. As a result, the personnel involved with the replacement of 2-CLS-RL Y-1 B12 were not aware that the TM had been removed when the relay replacement began. The absence of the TM allowed the SI system to actuate in response to the Hi-CLS signal.
4.0 IMMEDIATE CORRECTIVE ACTION(S)
Control room operators verified that the Hi-CLS signal was spurious and that the containment was at atmospheric pressure. The SI signal was subsequently reset and valves 2-SI-MOV-28670 [EIIS-BP,20], 2-FW-MOV-251 B/0/F [EIIS-BA,20],
2-CC-TV-209B [EIIS-CC,ISV], 2-DA-TV-200B [EIIS-WD,ISV], 2-CH-TV-2204B
[EIIS-CB, ISV], and 2-VG-TV-209B [EIIS-WE, ISV] were repositioned to their pre-event configuration.
The Main Control Room Bottled Air system was isolated and the containment hydrogen analyzer heat tracing actuation signal was reset.
The low air flow trip signal for 1-VS-F-58A/B [EIIS-VF, FAN] was immediately cleared and the ventilation system was restored to its normal configuration.
EOG No. 3 was declared inoperable and two independent offsite power sources were verified to be operable in accordance with TS 3.16. B.1.a.
A Deviation Report was submitted to document the deviating condition and to initiate corrective actions.
NRC FORM 366A (4-95)
,rr==============1 NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)
" LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)
YEAR I SEQUENTIAL NUMBER I REVISION NUMBER Surry Power Station Unit 1 05000 - 280 97 --008 -- 00 SOF 5 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) 5.0 ADDITIONAL CORRECTIVE ACTIONS The affected bank of the Main Control Room Bottled Air system was returned to service at 16:08.
The failed CLS fuse and 2-CLS-RLY-1 B12 were replaced. The Hi-CLS system was reset at 16:12.
EOG No. 3 was secured and returned to an operable status at 16:35.
6.0 ACTIONS TO PREVENT RECURRENCE The lessons learned from this event will be presented to Safety Evaluation preparers/reviewers. This event will also be discussed in Technical Staff Continuing training.
7.0 SIMILAR EVENTS
- LER 50-280/~3-001-00, "Reactor Trip and Safety Injection Due to Spurious High Consequence Limiting Safeguards Signal Caused by Malfunctioning Relay" 8.0 ADDITIONAL INFORMATION Although EDG No. 3 had been conservatively declared inoperable, it would have responded automatically to a Unit 1 demand signal after the Unit 2 SI signal had been reset, except for a brief period during the EOG shutdown evolution.
The status of the Unit 2 charging pumps and the associated ventilation system dampers would not have affected the ability of the Auxiliary Ventilation system to respond to a Unit 1 SI signal. During this event, the Auxiliary Ventilation system would have automatically responded to a Unit 1 demand signal, except for the momentary reset of the low air flow trip signal for 1-VS-F-58A/B.
Unit 1 was operating at 100% power during this event and was otherwise not affected.
NRG FORM 366A (4-95)