LER-1982-051, /03L-0:on 820820 & 28,nitrogen Pressure in PORV Reservoir Dropped Below Min Pressure Required to Consider PORV Operable.Caused by Rapid Depletion of Nitrogen Supply Due to Leak in Nitrogen Supply Piping |
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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)
/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
/L/ (6)
/0/5/0/0/0/3/3/9/
(7)
/0/8/2/0/8/2/
(8)
/0/9/1/3/8/2/ (9) 0 RC DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
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/ On August 20, 1982, and three more times on August 28, 1982, while in Modes 4 and/
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/ 5, the nitrogen pressure in the PORV (PCV-2455C) reservoir dropped below the min-/
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/ imum pressure required to consider the PORV operable. Since the unit conditions /
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/ changed to a Mode that did not require the nitrogen back-up within the required /
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/ time frame of the Action Statement of T.S. 3.4.9.3 and the redundant PORV
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/ remained operable, the health and safety of the public were not affected.
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SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
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/C/J/ (11)
/B/ (12)
/A/ (13) /V/A/L/V/E/X/ (14)
/F/ (15)
/B/ (16)
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 MANUFACTURER
/X/ (18) /F/ (19)
/Z/ (20)
/Z/ (21) /0/0/0/0/ (22) /Y/ (23) /N/ (24) /A/ (25) /M/1/2/0/ (26)
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)
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/ Leakege in the nitrogen supply piping caused the rapid depletion of the nitrogen /
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/ supply. This leak could not be located during the time available. A design
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/ study has been completed to correct the system deficiencies.
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FACILITY METHOD OF STATUS
% POWER OTHER STATUS ( 0) DISCOVERY DISCOVERY DESCRIPTION (32)
/1/5/
/C/ (28)
/0/0/0/ (29)
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NA
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/A/ (31)
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Operational Event
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ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)
LOCATION OF RELEASE (36)
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fZ/ (33)
/Z/ (34)
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PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)
/1/7/ /0/0/0/ (37) /Z/ (38) /
NA
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PERSONNEL INJURIES NUMBER DESCRIPTION (41)
/1/8/ /0/0/0/ (40) /
NA
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LOSS OF OR DAMAGE TO FACILITY 43)
TYPE
DESCRIPTION
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/Z/ (42)
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PUBLICITY ISSUED DESCRIPTION (45)
NRC USE ONLY
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/N/ (44)
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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 Oh$h9 PDR
l Virginia Electric and Power Company North Anna Power Station, Unit No. 2 Attachment: 1 of 2 Docket No.,50-339 Attachment to LER 82-051/03L-0
Description of Event
On August 20, 1982, while in Mode 5, and again on August 28, 1982, at 0552 and 1013 while in Mode 5 and again at 2000 in Mode 4, the
- - nitrogen supply that provides the operating medium for.the PORV de-creased to below the minimum pressure required to maintain the PORV operable (T.S.
3.4.9.3).
PORV operability is based on the design requirement for 120 valve cycles (1775 psig).
These events are reportable pursuant to T.S. 6.9.1.9.b.
Probable Consequences of Occurrence The operability of the PORV's in cold shutdown conditions is required to ensure that the reactor coolant pressure boundary is not pressurized in the non-ductile range.
The Action Statement of T.S.
3.4.9.3 was cleared within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on August 21, 1982 due to the mode change (to Mode 3).
On August 28, 1982, several attempts were made to repressurize the system.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially entering Mode 4, the unit was returned to Mode 3.
Since the redundant PORV remained operable throughout these events, and the Action Statement was cleared within the required time frame, the health and safety of the public were not affected.
In addition, even though the valve was declared inoperable due to low nitrogen pressure, there was sufficient nitrogen available to cycle the valves for a limited number of events.
Insufficient nitrogen pressure, indicated by the low pressure annunciator in the control room renders the valve incapable of meeting the valve cycle design criteria of 120 operations.
Cause of Event
This event was caused by an excessive leak that occurred through a system piping connection.
This caused the rapid depletion of the nitrogen supply to PCV-2455C.
Inmediate Corrective Action When the system alarms occurred, a containment entry was made to repressorize the system and to attempt to locate the leakage.
Efforts to bubble test the system connections and tighten the system threaded joints were unsuccessful.
e Attachment: Page 2 of 2 Scheduled Corrective Action A setpoint change has been approved to increase the alarm setpoint for low nitrogen pressure to provide an earlier warning of system
- - leakage and to allow time for operator response prior to entering the Action Statement.
Action Taken To Prevent Recurrence The nitrogen system has been reviewed to correct the operational problems.
As a result, a design change is being developed.
When implemented, the leakage experienced should be reduced and an adequate method for replenishing nitrogen supplies provided.
Generic Implications North Anna Units 1 and 2 have experienced excessive nitrogen system leakage since the system was installed.
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| 05000339/LER-1982-001, Forwards LER 82-001/03L-0 | Forwards LER 82-001/03L-0 | | | 05000339/LER-1982-001-03, /03L-0:on 820101,RCS Leakage Increased to 15-30 Gpm.Caused by Missing Packing on RHR Isolation Valve. Packing Had Deteriorated & Passed Through Valve Leadoff Line.Valve Repacked,Leak Tested & Returned to Svc | /03L-0:on 820101,RCS Leakage Increased to 15-30 Gpm.Caused by Missing Packing on RHR Isolation Valve. Packing Had Deteriorated & Passed Through Valve Leadoff Line.Valve Repacked,Leak Tested & Returned to Svc | | | 05000338/LER-1982-001-03, /03L-0:on 820107,power Range Detector N-44 Drifted Low & Was Declared Inoperable.Quadrant Power Tilt Ratio Found Below Tech Spec Limit.Caused by Faulty Power Range Detector.Detector to Be Replaced During Refueling Outage | /03L-0:on 820107,power Range Detector N-44 Drifted Low & Was Declared Inoperable.Quadrant Power Tilt Ratio Found Below Tech Spec Limit.Caused by Faulty Power Range Detector.Detector to Be Replaced During Refueling Outage | | | 05000338/LER-1982-001, Forwards LER 82-001/03L-0 | Forwards LER 82-001/03L-0 | | | 05000338/LER-1982-002-03, /03L-0:on 820111,containment Particulate Activity detector,RM-159 & Containment Gaseous Activity Detector, RM-160,failed Low.Caused by Loose Electrical Connector on RM-159 & Drive Motor Failure on RM-160 | /03L-0:on 820111,containment Particulate Activity detector,RM-159 & Containment Gaseous Activity Detector, RM-160,failed Low.Caused by Loose Electrical Connector on RM-159 & Drive Motor Failure on RM-160 | | | 05000338/LER-1982-002, Forwards LER 82-002/03L-0 | Forwards LER 82-002/03L-0 | | | 05000339/LER-1982-002-03, /03L-0:on 820110,during Mode 1 Operation at 20% Power,C Reactor Coolant Loop Flow Lost.Caused by Loss of Power During Transfer from Reserve Transformer.Unit Tripped Manually & Pump Restarted When Power Restored | /03L-0:on 820110,during Mode 1 Operation at 20% Power,C Reactor Coolant Loop Flow Lost.Caused by Loss of Power During Transfer from Reserve Transformer.Unit Tripped Manually & Pump Restarted When Power Restored | | | 05000339/LER-1982-002, Forwards LER 82-002/03L-0 | Forwards LER 82-002/03L-0 | | | 05000338/LER-1982-003-03, /03L-0:on 820201 & 08,fire Door Between Rod Drive Room & Outside Would Not Latch.On 820203,1H Emergency Diesel Generator Access Door Would Not Latch.Caused by Inadequately Lubricated Latching Mechanisms | /03L-0:on 820201 & 08,fire Door Between Rod Drive Room & Outside Would Not Latch.On 820203,1H Emergency Diesel Generator Access Door Would Not Latch.Caused by Inadequately Lubricated Latching Mechanisms | | | 05000338/LER-1982-003, Forwards LER 82-003/03L-0 | Forwards LER 82-003/03L-0 | | | 05000339/LER-1982-003, Forwards LER 82-003/03L-0 | Forwards LER 82-003/03L-0 | | | 05000339/LER-1982-003-03, /03L-0:on 820110,individual Rod Position Indication(Ipri)For Rod J-07 & Group Demand Position for Shutdown Bank B Differed by 12 Steps.On 820111,IRPI for Rod B-08 Drifted.Caused by Voltage Drift in Circuitry | /03L-0:on 820110,individual Rod Position Indication(Ipri)For Rod J-07 & Group Demand Position for Shutdown Bank B Differed by 12 Steps.On 820111,IRPI for Rod B-08 Drifted.Caused by Voltage Drift in Circuitry | | | 05000338/LER-1982-004-03, /03L-0:on 820116,at 100% power,1J Emergency Diesel Generator Door Would Not Latch.Fire Watch Posted.Caused by Loose Latch Cover Plate Preventing Door from Latching Properly.Latch Repaired | /03L-0:on 820116,at 100% power,1J Emergency Diesel Generator Door Would Not Latch.Fire Watch Posted.Caused by Loose Latch Cover Plate Preventing Door from Latching Properly.Latch Repaired | | | 05000338/LER-1982-004, Forwards LER 82-004/03L-0 | Forwards LER 82-004/03L-0 | | | 05000339/LER-1982-004, Forwards LER 82-004/03L-0 | Forwards LER 82-004/03L-0 | | | 05000339/LER-1982-004-03, /03L-0:on 820110,containment Isolation Steam Operator Blowdown Valve TV-BD-200C Would Not Remain Closed from Control Room.Caused by Excessive Moisture in Limit Switch Housing.Housing Drained | /03L-0:on 820110,containment Isolation Steam Operator Blowdown Valve TV-BD-200C Would Not Remain Closed from Control Room.Caused by Excessive Moisture in Limit Switch Housing.Housing Drained | | | 05000339/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000339/LER-1982-005-03, /03L-0:on 820222,in Mode 1,2J Emergency Diesel Generator Fire Door (S71-16) Between Diesel Room & Turbine Bldg Would Not Latch.Caused by Door Lock Tumbler Rotating on Axis & Not Engaging Latch.Lock Tumbler Tightened | /03L-0:on 820222,in Mode 1,2J Emergency Diesel Generator Fire Door (S71-16) Between Diesel Room & Turbine Bldg Would Not Latch.Caused by Door Lock Tumbler Rotating on Axis & Not Engaging Latch.Lock Tumbler Tightened | | | 05000338/LER-1982-005-03, /03L-0:on 820211,w/unit in Mode 1,RCS Unidentified Leakage Was Determined in Excess of Tech Specs.Caused by Packing Leak on 1-RC-129 Level Instrument Isolation Valve. Valves 1-RC-129 & 1-RC-130 Closed | /03L-0:on 820211,w/unit in Mode 1,RCS Unidentified Leakage Was Determined in Excess of Tech Specs.Caused by Packing Leak on 1-RC-129 Level Instrument Isolation Valve. Valves 1-RC-129 & 1-RC-130 Closed | | | 05000338/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000338/LER-1982-006, Forwards LER 82-006/03L-0 | Forwards LER 82-006/03L-0 | | | 05000338/LER-1982-006-03, /03L-0:on 820305,during Mode 1 at 100% Power,A Svc Water Return Header from Units 1 & 2 Charging Pumps & Air Compressors Were Isolated to Repair Pinhole Leak in Return Line.Caused by Aggressive Water Corrosion | /03L-0:on 820305,during Mode 1 at 100% Power,A Svc Water Return Header from Units 1 & 2 Charging Pumps & Air Compressors Were Isolated to Repair Pinhole Leak in Return Line.Caused by Aggressive Water Corrosion | | | 05000339/LER-1982-006-03, /03L-0:on 820216,during Mode 1 Operation,B Quench Spray Subsystem Removed from Svc Contrary to Tech Specs. Subsystem Removed from Svc to Repair body-to-bonnet Leak on B Quench Spray Pump Suction valve,MOV-QS-200B | /03L-0:on 820216,during Mode 1 Operation,B Quench Spray Subsystem Removed from Svc Contrary to Tech Specs. Subsystem Removed from Svc to Repair body-to-bonnet Leak on B Quench Spray Pump Suction valve,MOV-QS-200B | | | 05000339/LER-1982-006, Forwards LER 82-006/03L-0 | Forwards LER 82-006/03L-0 | | | 05000339/LER-1982-007, Forwards LER 82-007/03L-0 | Forwards LER 82-007/03L-0 | | | 05000338/LER-1982-007-03, /03L-0:on 820214,in Mode 1,fire Door S71-7 Declared Inoperable.On 820216,fire Doors A19-1 & A44-1 Declared Inoperable.Caused by Failure of Closures & Latching Mechanisms Due to Excessive Use.Locks Readjusted/Repaired | /03L-0:on 820214,in Mode 1,fire Door S71-7 Declared Inoperable.On 820216,fire Doors A19-1 & A44-1 Declared Inoperable.Caused by Failure of Closures & Latching Mechanisms Due to Excessive Use.Locks Readjusted/Repaired | | | 05000338/LER-1982-007, Forwards LER 82-007/03L-0 | Forwards LER 82-007/03L-0 | | | 05000339/LER-1982-007-03, /03L-0:on 820312,during Mode 5,emergency Diesel Generators 2H & 2J Were Not Operable.Caused by Failure of Voltage Regulator for 2J Causing Bus Voltage to Peg High & Open 1J Output Breaker 25J2 | /03L-0:on 820312,during Mode 5,emergency Diesel Generators 2H & 2J Were Not Operable.Caused by Failure of Voltage Regulator for 2J Causing Bus Voltage to Peg High & Open 1J Output Breaker 25J2 | | | 05000338/LER-1982-008, Forwards LER 82-008/01T-0 | Forwards LER 82-008/01T-0 | | | 05000338/LER-1982-008-01, /01T-0:on 820329,Westinghouse Determined That Six Output Slave Relays Did Not Have Qualified Latching Mechanisms.Caused by Use of Two Different Types of Latches. Latching Mechanisms Will Be Replaced | /01T-0:on 820329,Westinghouse Determined That Six Output Slave Relays Did Not Have Qualified Latching Mechanisms.Caused by Use of Two Different Types of Latches. Latching Mechanisms Will Be Replaced | | | 05000339/LER-1982-008-01, /01T-0:on 820307,prior to Refueling Outage,Power Restored to Accumulator Isolation Valves & Valves Closed W/ Pressurizer Pressure 1,000 Psig.Caused by Personnel Error. Valves Automatically Reopened W/Increased Pressure | /01T-0:on 820307,prior to Refueling Outage,Power Restored to Accumulator Isolation Valves & Valves Closed W/ Pressurizer Pressure 1,000 Psig.Caused by Personnel Error. Valves Automatically Reopened W/Increased Pressure | | | 05000339/LER-1982-008, Forwards LER 82-008/01T-0 | Forwards LER 82-008/01T-0 | | | 05000338/LER-1982-009, Forwards LER 82-009/99L-0 | Forwards LER 82-009/99L-0 | | | 05000338/LER-1982-009-99, /99L-0:on 820216,electric Driven Fire Pump 1-FP-P-1 Was Tagged Out & Declared Inoperable for Longer than 7 Days.Caused by Required Maint on 1B Circulating Water Pump.Redundant Source of Fire Water Provided | /99L-0:on 820216,electric Driven Fire Pump 1-FP-P-1 Was Tagged Out & Declared Inoperable for Longer than 7 Days.Caused by Required Maint on 1B Circulating Water Pump.Redundant Source of Fire Water Provided | | | 05000339/LER-1982-009-03, /03L-0:from 820308-10,pressurizer Power Operated Relief Valves Declared Inoperable Three Times While Cooling Down for Refueling Outage.Caused by Excessive Nitrogen Sys Demand,Excessive Sys Leakage & Inadequate Makeup Supply | /03L-0:from 820308-10,pressurizer Power Operated Relief Valves Declared Inoperable Three Times While Cooling Down for Refueling Outage.Caused by Excessive Nitrogen Sys Demand,Excessive Sys Leakage & Inadequate Makeup Supply | | | 05000339/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000339/LER-1982-010, Forwards LER 82-010/03L-0 | Forwards LER 82-010/03L-0 | | | 05000338/LER-1982-010, /03L-0:on 820505,valves MOV-FW-154A,B & C & TV-1884A,B & C Found W/Identical Control Circuits as Reported in LER 82-010 for Unit 2.Design Permits Operator to Open Valves W/O Resetting Phase a Isolation Signal | /03L-0:on 820505,valves MOV-FW-154A,B & C & TV-1884A,B & C Found W/Identical Control Circuits as Reported in LER 82-010 for Unit 2.Design Permits Operator to Open Valves W/O Resetting Phase a Isolation Signal | | | 05000338/LER-1982-010-03, /03L-0:on 820223,post-reactor Trip Specific Activity Samples of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit.Caused by Fuel Element Defect.Sampling Frequency Accelerated | /03L-0:on 820223,post-reactor Trip Specific Activity Samples of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit.Caused by Fuel Element Defect.Sampling Frequency Accelerated | | | 05000338/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000339/LER-1982-011-03, /03L-0:on 820410,fire Door M-80-2 Blocked Open W/O Fire Watch.On 820412,fire Door A-80-2 Would Not Close & Latch.Caused by Failure to Follow Procedures for Breeching Fire Barriers & Reclosure Device Being Out of Adjustment | /03L-0:on 820410,fire Door M-80-2 Blocked Open W/O Fire Watch.On 820412,fire Door A-80-2 Would Not Close & Latch.Caused by Failure to Follow Procedures for Breeching Fire Barriers & Reclosure Device Being Out of Adjustment | | | 05000338/LER-1982-011-03, /03L-0:on 820223,at 90% Power & Decreasing,Axial Flux Difference Deviated Greater than -5% from Target for 23 Minutes.Caused by Rapid Power Reduction Necessitated by Leak in Turbine Gland Steam Exhaust Sys | /03L-0:on 820223,at 90% Power & Decreasing,Axial Flux Difference Deviated Greater than -5% from Target for 23 Minutes.Caused by Rapid Power Reduction Necessitated by Leak in Turbine Gland Steam Exhaust Sys | | | 05000339/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000339/LER-1982-012-03, /03L-0:on 820313,fire Door M80-2 Between Rod Control Room & Outside Would Not Close.On 820326,fire Door A80-2 Between Rod Control Room & Auxiliary Bldg Would Not Close.Caused by Improper Alignment Due to Excessive Use | /03L-0:on 820313,fire Door M80-2 Between Rod Control Room & Outside Would Not Close.On 820326,fire Door A80-2 Between Rod Control Room & Auxiliary Bldg Would Not Close.Caused by Improper Alignment Due to Excessive Use | | | 05000339/LER-1982-012, Forwards LER 82-012/03L-0 | Forwards LER 82-012/03L-0 | | | 05000338/LER-1982-012, Forwards LER 82-012/03L-0 | Forwards LER 82-012/03L-0 | | | 05000338/LER-1982-012-03, /03L-0:on 820223,emergency Condensate Storage Tank (Ecst) Dropped Below Min Required Vol Twice.Caused by Adding Water from Ecst to Steam Generators Due to Inoperable Condensate Sys | /03L-0:on 820223,emergency Condensate Storage Tank (Ecst) Dropped Below Min Required Vol Twice.Caused by Adding Water from Ecst to Steam Generators Due to Inoperable Condensate Sys | | | 05000339/LER-1982-013-03, During Periodic Surveillance Test,One Diesel Generator & One Offsite Power Supply for Emergency Bus 2H Became Temporarily Inoperable. Caused by Deficiency in Procedure.Periodic Test Changed | During Periodic Surveillance Test,One Diesel Generator & One Offsite Power Supply for Emergency Bus 2H Became Temporarily Inoperable. Caused by Deficiency in Procedure.Periodic Test Changed | | | 05000338/LER-1982-013-03, /03L-0:on 820401,post-reactor Trip Specific Activity Samples of RCS Indicated Dose Equivalent Level Greater than Tech Spec Limit.Caused by Fuel Element Defect in Reactor Core.Accelerated Sampling Frequency Implemented | /03L-0:on 820401,post-reactor Trip Specific Activity Samples of RCS Indicated Dose Equivalent Level Greater than Tech Spec Limit.Caused by Fuel Element Defect in Reactor Core.Accelerated Sampling Frequency Implemented | | | 05000338/LER-1982-013, Forwards LER 82-013/03L-0 | Forwards LER 82-013/03L-0 | |
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