LER-1980-005, /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel |
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U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL-BLOCK / / / / / / / (1)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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/V/A/N/A/S/2/ (2)
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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT
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OU E DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
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At 0640 on May 17, 1980, with Unit 2 at Hot Shutdown, "2J" emergency diesel
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generator tripped af ter starting.
The operability of the "2H" diesel
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generator was not verified within one hour as required by the ACTION
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statement of T.S. 3.8.1.1 and reportable by T.S. 6.9.1.9.b.
The health
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and safety of the public were not affected since both off-site sources
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were available and the "2H" diesel was still operable
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SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
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SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO.
CODE TYPE NO.
(17) REPORT NUMBER
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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP.
COMPONENT.
TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MAhTFACTURER
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/Z/ (21) /0/0/0/0/ (22) [Y/ (23)
/N/ (24) /A/ (25) /C/4/7/0/ (2(.
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)
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The "2H" diesel generator was not tested within one hesc bace9se existing
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procedures did not specify the test connections required to test the diesel
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to prove operability.
The off-site power breaker alignment was verified
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at 1130 on May 17, 1980 and a test procedure was temporarily changed to allow /
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testing of "2J" diesel which was declared operable at 1438 on May 17, 1980.
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FACILITY METHOD OF DISCOVERY DESCRIPTION (32)
STATUS
% POWER OTHER STATUS
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/B/ (31)
/ OPERATOR OBSERVATION /
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/B/ (28)
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NA ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)
LOCATION OF RELEASE (36)
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PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)
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PERSONNEL INJURIES NUMBER DESCRIPTION (41)
[1/1[ /0/0/0/ (40) /
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LOSS OF OR DAMACE TG FACILITY (
TYPE
DESCRIPTION
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PUBLICITY ISSUED DESCRIPTION (45)
NRC USE ONLY
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8 00617 W S NAME OF PREPARER W. R._CARTWRIGHT P40NE (703) 894-5151
4 s
Virginia Electric and Power Company ISrth Anna Power Station, Unit #2
Attachment:
Page 1 of 1 Docket No. 50-339 neport No. LER 80-5/03L-0
Description of Event
At 0640 on 5-17-80 with Unit 2 at hot shutdown, "2J" emergency diesel generator tripped after starting.
The "2J" diesel generator was
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being started to prove operability prior to performing maintenance on
'"2H" diesel generator.
The operability of the "2H" diesel generator was not verified within one hour as required by the ACTION statement of T.S.
3.8.1.1 and reportable by T.S. 6.9.1.9.b.
Probable Consequences of Occurrence The health and safety of the public were not affected since both offsite sources were available and the "2H" diesel was still operable.
In addition, the "2J" diesel generator shutdown relays were reset and the control switch placed in " Manual-Remote".
Since it is believed that "2J" diesel trip was due to high crankcase pressure, an emergency start signal would have started the diesel and high crankcase pressure would not have caused a trip.
Cause of Event
The "2J" diesel generator trip was,pparently due to high crankcase pressure since the trip occurred approximately 20 seconds after the start signal and the diesel had reached 900 RPM in less than 10 seconds.
Since the "2J" diesel generator tripped, personnel referred to the ACTION statement of T.S. 3.8.1.1 which requires testing the frequency and voltage response of the other diesel generator.
However no procedures were written which included instructions for connecting test equipment necessary for verifying frequency and voltage response as required by T.S. 4.8.1.1.2.a.4.
Greater than one hour passed before procedure changes required for testing could be written and approved.
In addition, the Maintenance Operating Procedure, 2-M0P-6.90 was in error in that it did not contain requirements for testing frequency and voltage response as required by T.S. 4.8.1.1.2.a.4.
Immediate Corrective Action
The "2J" diesel generator shutdown relays were reset and the control switch placed in " Manual-Remote". The offsite power breaker alignment wat 'erified as per T.S. 4.8.1.1.1.a at 1130 on 5-17-80.
Temporary change > sere made to the diesel periodic test 2-PT-82.1B, and the diesel was satisfatuorily tested and returned to operable status at 1438 on 5-17-80.
Scheduled Corrective Action Maintenance Operating Procedures for the diesel will be changed to include testing requirements of T.S. 4.8.1.1.2.a.4.
Actions Taken to Prevent Recurrence Periodic Tests have been changed to include the connection of test equipment necessary to meet testing requirements of T.S. 4.8.1.1.2.a.4.
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| 05000338/LER-1980-001-01, /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | | | 05000338/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000339/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000339/LER-1980-001-03, /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | | | 05000338/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000338/LER-1980-002-01, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | | | 05000339/LER-1980-002-01, /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | | | 05000339/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000339/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-003-03, /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | | | 05000338/LER-1980-003-03, /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | | | 05000338/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000339/LER-1980-004-03, /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | | | 05000338/LER-1980-004-03, /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | | | 05000338/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000338/LER-1980-005-03, /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | | | 05000338/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-005-03, /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | | | 05000339/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000339/LER-1980-006-03, /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | | | 05000338/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000338/LER-1980-006-03, /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | | | 05000338/LER-1980-007-03, /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | | | 05000339/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000339/LER-1980-007-03, /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | | | 05000339/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000338/LER-1980-008-01, /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | | | 05000339/LER-1980-008-03, /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | | | 05000338/LER-1980-009-03, /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | | | 05000339/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000339/LER-1980-009-03, /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | | | 05000338/LER-1980-010-01, /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | | | 05000339/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000339/LER-1980-010-01, /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | | | 05000339/LER-1980-011-03, /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | | | 05000339/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011-03, /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | | | 05000339/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000339/LER-1980-012-03, /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | | | 05000338/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000338/LER-1980-012-03, /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | | | 05000338/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-013-03, /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | | | 05000339/LER-1980-013-03, /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | | | 05000339/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000338/LER-1980-014-03, /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | |
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