LER-1980-049, /03L-0:on 800822,operating in Mode 2 at 3% Power, Loops a & C Channel Tour Steam/Flow Bistables Were Tripped to Allow Mod to Condensate Pots.Upon Return to Svc,A Failed High.Caused by Instrument Drift & Improper Valve Lineup |
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| 3391980049R03 - NRC Website |
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U.S. NUCLEAR REGULATORY *0MMISSION 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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DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
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On August 22, 1980, while operating in Mode 2 at 3% power, the channel IV steam /
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flow bistables for loops A and C were placed in the tripped condition to allow /
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modifiration to the associated condensate pots. After being returned to ser- /
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vice, the loop A channel failed high and was again placed in the tripped mode. /
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Also, that evening due to erroneous indication, the transmitter for the loop C /
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steam flow channel was inspected and found to be still isolated. The public
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health and safety were not affected by these events.
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SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE CCMPONENT CODE SUBCODE SUBCODE
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/H/B/ (11) /B/ (12) /A/ (13) /I/N/S/T/R/U/ (14) g/ (15)
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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 SHUIDOWN ATTACIDfENT NPRD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
/F/ (18) /Z/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) d/ (23) /N/ (24) /N/ (25) /R/3/6/9/ (26:
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)
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The bistables were tripped to allow holes to be drilled through the caps above /
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the condensate pot vent valves in an attempt to prevent water from accumulating /
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in the pressure sensing lines. The high loop A steam flow indication was
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caused by instrumeqt drift which was corrected by recalibration and the im-
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proper loop C transmitter valve lineup vias the result of personnel error.
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FACILITY METHOD OF STATUS
% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION (32)
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/ Operator Observation /
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)
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LOSS OF OR DAMA".2 TO FACILITY (43)
TYPE
DESCRIPTION
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PUBLICITY ISSUED DESCRIPTION (45)
NRC USE ONLY
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NAME OF PREPARER __
W. R. CARTWRIGHT PHONE (703) 894-5151 NAWa
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Virginia Electric and Power. Company
- - North Anna Power Station,, Unit 2 Attachment: Page 1 of 1 Docker No. 50-339 Report No..LER 80-049/03L-0
Description of Event
~
{:
.On' August 22,.1980, while operating in Mode 2 at 3% power, the channel.IV steam flow bistables for A and-C loops (F-2475 and F-2495):
l were placed in the tripped: condition to accomplish a modification to the.
l transmitter. condensing pots., After being returned to service, the' loop A steam flow channel failed.high and was again placed in the tripped.
i a
- - mode. Also, due to erroneous indication', the transmitter for the loop C steam flow ~ channel was inspected and found to be.still isolated. These l
events are reportable pursuant to T.S. 6.9.1.9.b and T.S. 6.9.1.9.c.
Probable Consequences of Occurrence i
l' The cons'equences of these events were limited because the steam.
flow channels were placed in the tripped mode as specified by T.S.
l 3.3.1.1 and 3.3.2.1 and redundant instrumentation was available. As a result, the health and safety'of the general public were not affected.
Cause of Event
The: steam flow bistables were placed in the tripped condition to allow holes to be drilled through the caps above the vent valve on the condensate pots in'an attempt to prevent steam from condensing in the 1 pressure sensing lines.
The high loop A steam flow indication later that day was caused by instrument drift ~and the improper valve lineup for the loop C transmitter was the result of. personnel error.
Immediate Corrective Action
l '
the desired modification performed.
The: loop A and C steam flow bistables (channel IV) were tripped and
+
When the. loop.A steam flow' channel failed high, the bistable was
~ placed in the tripped condition within one hour as specified by T.S.
3.3.1.1 and 3.3.2.1 and the channel was satisfactorily recalibrated.
j Upon-discovering the loop C steam flow transmitter isolated, the-transmitter root valves were immediately reopened and proper indication
- - was verified.
I Scheduled Corrective Action
~No scheduled. corrective action is required.
Actions Taken'to Prevent Reccurrence
. To eliminate the condensation problem in the pressure sensing line,
- - all twelve steam flow transmitter condensate pots.have been relocated closer to their respective venturi.' Also, personnel were reinstructed-fon'the importance.of proper valve lineup.
! Generic Implicationsi t
There.are no? generic implications.
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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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