LER-1980-078, /03L-0:on 800908,w/unit in Startup Mode,Governor Valve for Steam Driven Auxiliary Feedwater Pump Discovered in Tripped Position.Cause of Overspeed Trip Due to Incorrect Governor Setting.Governor Valve Reset |
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LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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/V/A/N/A/S/1/ (2)
/0/0/-/0/0/0/0/0/-/0/0/ (3)
/4/1/1/1/1 (4)
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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT
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/L/ (6)
/0/5/0/0/0/3/3/8/
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/0/9/0/8/8/0/
(8) /1/o/o/7 /8/o / (9)
DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
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On September 8,1980 with the unit in startup mode, the governor valve for the /
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steam driven auxiliary feedwater pump was found to be in the tripped condition /
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rendering the pump inoperable contrary to T.S. 3.7.1.2 and reportable by
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T.S. 6.9.1.9.b.
Since the other auxiliary feedwater pumps were operable, the /
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health and safety of the public were not affected. The incident is not
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generic.
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SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
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/H/H/ (11) /A/ (12) /X/ (13) /T/U/R/B/I/N/ (14) /Z/ (15)
/Z/ (16)
SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 P1ENT YEAR REPORT NO.
CODE TYPE NO.
(17) BEPORT NUMBER
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ACTIGN FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
/E/ (18) /Z/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) /j[/ (23) /N/ (24) /A/ (25) /T/1/4/7/ (26)
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)
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The governor valve apparently tripped due to pump overspeed following a unit
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trip on September 8, 1980. The cause of the overspeed was apparently an
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incorrect governor setting. The governor valve was reset, the governor valve /
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setting adjusted to its proper setting and the periodic test on the auxiliary /
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feedwater pump was completed satisfactorily.
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FACILITY METHOD OF STATUS
% POWER OTHER STATUS
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/( ) DISCOVERY DISCOVERY DESCRIPTION (32)
/A/ (31)
/ Operator Observation
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ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)
LOCATION OF RELEASE (36)
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PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)
/1/7/ /0/0/0/ (37) /Zf[ (38) /
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PERSONNEL INJURIES NUMBER DESCRIPTION (41)
/1/8/ /0/0/0/ (40) /
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LOSS OF OR DAMAGE TO FACILITY
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DESCRIPTION
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Z PUBLICITY ISSUED DESCRIPTION (45)
NRC USE ONLY
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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 l
8 910140 %
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Virginia Electric and Power Company North Anna Power Station, Unit 1
Attachment:
Page 1 of 2 Docker No. 50-338 Report No. LER 80-078/03L-0 l
Description of Event
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At 2300 on September 8, 1980 with the unit in startup mode, the l
governor valve for the steam driven auxiliary feedwater pump was found l
to be in the tripped condition rendering the pump inoperable. The l
governor valve apparently tripped following a reactor trip at 1956 that l
day. Following the reactor trip there was no flow indication from the steam driven auxiliary feedwater pump to the "A" steam generator (S/G)
I but the "A" steam generator level was adequate and increasing.
A nonlicensed operator was sent to verify proper valve lineup. The operator verified proper valve lineup and reported that uater was leaking from the flow orifice in the line to "A" S/G. Since the level was increasing in "A" S/G and since during normal valve lineup "A" S/G is l
supplied exclusively by either normal feedwater pumps (which were tripped) or the steam driven auxiliary feedwater pump, faulty flow indication was suspected. An emergency maintenance report was issued on the auxiliary feedwater flow channel for "A" S/G.
Unit startup commenced but the unit tripped due to hi-hi S/G level.
Unit startup was again in progress when the " TURBINE DRIVEN AUX. FD.
PUMP TRAIN A NON-AUTO CONTROL" alarm and the same alarm for Train B were noted. Investigation revealed that the governor valve had tripped closed. The valve was reset and unit startup resumed.
Probable Consequences of Occurrence Since the other auxiliary feedwater pumps were operable to remove core heat, the health and safety of the public were not affected.
Cause of Event
The cause of the governor overspeed trip was apparently an incorrect govere r setting. The setting on the governor was 3.8 rather than 1.9 as require: by the periodic test for Unit 1 (Unit 2 governor valve setting is 3.8).
The periodic test for Unit 1 steam driven auxiliary feedwater pump had previously been satisfactorily completed on August 13, 1980 following maintenance. It could not be determined who chane i the governor setting to 3.8 or when this was done.
The reason the water level in "A" S/G was increasing was apparently level " swell" following the overfeeding of the generator. The overfeeding of "A" S/G was caused by the loss of Vital Bus IV (see LER 80-080) which caused the main feed reg. val e to open prior to the reactor trip at 1956.
Immediate Corrective Action
l The governor valve was reset on September 8,1980 which operating i
personnel thought returned the steam driven feedwater pump to operable status. On September 9,1980 at approximately 1000 it was decided to perform the periodic test on the pump. While verifying initial conditions for the test, it was discovered that the governor setting was incorrect.
The setting was changed to the correct setting of 1.9 and the test satisfactorily-completed at 1124 on September 9.
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Page 2 of 2 Scheduled Corrective Action None scheduled.
Actions Taken to Prevent Reccurrence A memorandum from the Superintendent of Operations was issued reminding operators of the importance of proper operation of the auxiliary feedwater system and methods of verifying proper operation. This memorandum was placed in required reading for the operators.
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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. 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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. 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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. 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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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