LER-1979-022, /03L-0:on 791208,following Return to Svc After refueling,drywell-to-suppression Chamber Differential Pressure Could Not Be Maintained Per Tech Spec.Caused by Leak at Hatch Door Due to Loosened Bolts |
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| 2961979022R03 - NRC Website |
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F i NIIC HIRICI 366 (7.77' v. EbbuuE.cPEn ncEEub.n8 un 8 uubbbbEEEowu89 Q3 Q4~
QE 25 26 LICENSE TYPE 30 57 CAT 58 Qso l
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QB 74
. 75 REPORT DATE 80 LICENSEE EVENT REPORT CONTROL BLOCK:
Qi (PLEABE PRINT oR TYPE ALLREQUIRED INFORMATIDNI Eb 6
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LICENSEE CODE 14 15 LICENSE NUMBER CON'T KEI SOURCE L~JQ 7
1 2
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60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO With unit 3 at 200 MWe following unit return to servi ce after
~03 refueling outage, the drywe 11 to suppression chamber diffe rent ial pressure could not be maintained at or above 1.3 psid per technical specification 3.7.A.6.a.
An orderly shutdown of unit 3 was initiated.
There was no danger to the health or ssf et of the ub 1ic no previous simi1ar occurrences.
Redundancy is not app 1icable
~OB 7
8
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'1 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SVBCODE COMPONENT CODE SVBCOOE SUBCODE
~ZA QII
~AQ12
~O QIE Z
Z Z
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2 QR
~ZQE
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10 11 12 13 18 19 20 SEOVENTIAL OCCURRENCE REPORT REVISION FVENT YEAR REPORT NO.
CODE TYPE NO.
QIT REPORT
~79
~
~02 2
21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDA PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER OIB ~G QIB
~Q20
~AQ21 0
0 0
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~024 ~ 02 Qzo 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o
ast dr ell e ui ment hatch i htened bolts.
Bolts were reti dministrative controls are bein develo ed t 3
dditional verifications and the use of a k
atch is not moved without ro er a ro 7
8 9
FACILITY STATUS
% POWER OTHER STATUS Q 8
0 Q28 ~02 0
QEE NA 7
8 9
10 12 13 44 ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNTOF ACTIVITY~B Z
Q33
~ZQ34
~A 7
8 9
10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q38
~00 QET Z
QEE NA 7
8 9
11'2 13 PERSONNCL INJURIES NUMBER OESCRIPTIONQ41 8
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Q48 45 NA METHOD OF DISCOVERY L~JQ>>
45 46 DISCOVERY DESCRIPTION Q32 Maintenance Personnel Observed LOCATIONOF RELEASE Q 80 80 80 80 7
8 7
8 9
11 12 LOSS OF OR DAMAGETo FACIUTY Q43 TYPE
DESCRIPTION
Z Q42 NA 9
10 PUBLICITY ISSUED DESCRIPTION~
L~JS
~A 9
10 80 80 8881888 EE- "'""""
NAb!E OF PREPARER PHONE:
68 69 80 48 0
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Tert>><<ssee Valley Authority,
'Br owns l'er ry Nuclcrrr l'lanl, For'rn V.I'- l (
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r/10/'('4 LER SUPPLENENTAL INFORi~lATION HFPO 296 /
7922 Techrric;rl Specificat.ion Involvcii 3 ~ 7'
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Repvrted Under 'I'cchnical Spcciricatinn 6 ~ 7 2 b. <2>
Date of Occur'rene(:
12/8/79 Time of Orcurr.ence 1235 Urrit Id>>>>tiiication and Dose: iption 'of Occrr r r'errce:
Drywell to suppression chamber differential pressure could not be maintained at or above 1.3 psid per technical specification 3.7.A.6.a.
Cond'Ion.'> Pl'ror ro Occur'rc neo'.
Unit 1 8 970 MWe Unit 2 6 880 MWe Unit 3 8 200 MWe Unit in test program following return to service after refueling outage.
Action specified in the Technical Specification Surveillanc" R<<quir ements:;.ret due to inoperable e~u~iment.
Descrihe.
Differential pressure between drywell and suppression chamber must be established within 24 hrs of achieving operating temperature and pressure.
~A apparent Cause of Occurrence:
Leak around east equipment hatch seal due to unevenly tightened bolts.
Anal;.,is of Occurr <:nc>>:
h There was no danger to health or safety of the public, no activity release, no damage to plant equipment.
East equipment hatch was installed and initially failed a local leak rate test on 11/14/79.
The hatch was retorqued and passed the local leak rate test on ll/14/79.
An integrated leak rate test was conducted between 11/21/79 and ll/26/79 and no leakage was detected on the hatch.
No other.work was performed on the hatch until the subject occurrence on 12/8/79.
Cor'rcctr ve Act(OI1:
Retightening of fasteners corrected leakage.
Developing administrative controls including detailed instructions and procedures which incorporate appropriate signoffs and a lock that will insure that the hatch is not moved without proper approval.
Farlur(. Data:
NA
- ~:lt:".t'"ntion:
Period
- - Lifetime; Bespo>>siL'ility - Administrative Superv.'"or.
"Revisron:
~e, 4
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| 05000296/LER-1979-001-03, /03L-0 on 790111:switch on LIS-3-56B Failed to Trip Reactor Recirculation Pump Motor Generator.Caused by Misadjusted Switch on Yarway Model 4418CE.Switch Recalibr & Tested Satisfactorily | /03L-0 on 790111:switch on LIS-3-56B Failed to Trip Reactor Recirculation Pump Motor Generator.Caused by Misadjusted Switch on Yarway Model 4418CE.Switch Recalibr & Tested Satisfactorily | | | 05000296/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000259/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000259/LER-1979-001-01, /01T-0 on 790118:reactor Scrammed Due to High Flux Actuating Intermediate Range Monitor high-high Neutron Monitoring Circuit;Reactor Neared Criticality.Caused by Withdrawal of High Reactivity Worth Rod | /01T-0 on 790118:reactor Scrammed Due to High Flux Actuating Intermediate Range Monitor high-high Neutron Monitoring Circuit;Reactor Neared Criticality.Caused by Withdrawal of High Reactivity Worth Rod | | | 05000260/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000260/LER-1979-001-03, /03L-0 on 790113:during Test of high-pressure Injection Coolant Sys,Steam Supply Valve FCV-73-16 Failed to Open,Rendering Sys Inoperative.Caused by Failure of Limitorque Valve Operator Limit Switch | /03L-0 on 790113:during Test of high-pressure Injection Coolant Sys,Steam Supply Valve FCV-73-16 Failed to Open,Rendering Sys Inoperative.Caused by Failure of Limitorque Valve Operator Limit Switch | | | 05000296/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000259/LER-1979-002-03, /03L-0 on 790129:during Normal Operation While Performing Surveillance Test,Standby Liquid Control Pump 1B Relief Valve Opened Below Tech Spec Min.Caused by Valve Seat Surface Deterioration | /03L-0 on 790129:during Normal Operation While Performing Surveillance Test,Standby Liquid Control Pump 1B Relief Valve Opened Below Tech Spec Min.Caused by Valve Seat Surface Deterioration | | | 05000259/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000260/LER-1979-002-03, /03L-0 on 790203:alarm for Fire Protection Panel 25-236 Annunciated in Control Room.Panel Was Not Alarmed Condition.Caused by Normal End of Life Electrical Failure of Annunciator Point Card.Card Replaced & Sys Normalized | /03L-0 on 790203:alarm for Fire Protection Panel 25-236 Annunciated in Control Room.Panel Was Not Alarmed Condition.Caused by Normal End of Life Electrical Failure of Annunciator Point Card.Card Replaced & Sys Normalized | | | 05000260/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000296/LER-1979-002-03, /03L-0 on 790117:during Maintenance of Reset Switch,Short Circuit Damaged Power Supply & Sensor Circuit Board,Rendering Fixed Spray Automatic Initiation Circuit for Fire Protection Inoperable | /03L-0 on 790117:during Maintenance of Reset Switch,Short Circuit Damaged Power Supply & Sensor Circuit Board,Rendering Fixed Spray Automatic Initiation Circuit for Fire Protection Inoperable | | | 05000296/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000259/LER-1979-003-01, /01T-1 on 790120:during Cold Shutdown,Local Leak Rate Test Indicated Excessive Total Leakage.Caused by Leaking Valve Seating Surface in Eight Valves.Valves Repaired & Retested | /01T-1 on 790120:during Cold Shutdown,Local Leak Rate Test Indicated Excessive Total Leakage.Caused by Leaking Valve Seating Surface in Eight Valves.Valves Repaired & Retested | | | 05000259/LER-1979-003, Forwards LER 79-003/01T-1 | Forwards LER 79-003/01T-1 | | | 05000260/LER-1979-003-01, /01T-0 on 790214:rod Position Info Sys Power Supply Ps X-5 Failed,Causing Loss of Rod Position Indication in Bottom Half of Vertical Core Display.Caused by Failure of Cooling Fan in Trygon Model L5B6-70-OVS4989 | /01T-0 on 790214:rod Position Info Sys Power Supply Ps X-5 Failed,Causing Loss of Rod Position Indication in Bottom Half of Vertical Core Display.Caused by Failure of Cooling Fan in Trygon Model L5B6-70-OVS4989 | | | 05000259/LER-1979-003-03, /03L-2 on 790120:during Cold Shutdown,Local Leak Rate Test Revealed Total Leakage Exceeded Allowable 60% La Per 24-h.Caused by Excessive Leakage of Valve Seating Surface.Eight Leaking Valves Were Repaired & Retested | /03L-2 on 790120:during Cold Shutdown,Local Leak Rate Test Revealed Total Leakage Exceeded Allowable 60% La Per 24-h.Caused by Excessive Leakage of Valve Seating Surface.Eight Leaking Valves Were Repaired & Retested | | | 05000296/LER-1979-003-03, /03L-0 on 790202:linear Heat Generation Rate Out of Tech Spec Limits.Caused by Operation Close to Limiting Values & Increase in Reactivity Due to Gadolina Burnup. Greater Margin to Limiting Value Will Be Maintained | /03L-0 on 790202:linear Heat Generation Rate Out of Tech Spec Limits.Caused by Operation Close to Limiting Values & Increase in Reactivity Due to Gadolina Burnup. Greater Margin to Limiting Value Will Be Maintained | | | 05000260/LER-1979-003, Forwards LER 79-003/01T-0 | Forwards LER 79-003/01T-0 | | | 05000260/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000259/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000259/LER-1979-004-03, /03L-0 on 790227:during Normal Operation,Review of Surveillance Test Data Indicated Monthly Samples of Diesel Fuel Taken in Dec 1978 Have Not Been Analyzed.Caused by Loss of Samples in Transit.Will Try to Measure Samples on | /03L-0 on 790227:during Normal Operation,Review of Surveillance Test Data Indicated Monthly Samples of Diesel Fuel Taken in Dec 1978 Have Not Been Analyzed.Caused by Loss of Samples in Transit.Will Try to Measure Samples on Site | | | 05000296/LER-1979-004-03, /03L-0 on 790411:during Normal Operation,Heat Detector Alarmed & Would Not Clear.Alarm Would Have Masked Signals from Other Detector,Required to Be Operational.Caused by Personnel Damaging Detector | /03L-0 on 790411:during Normal Operation,Heat Detector Alarmed & Would Not Clear.Alarm Would Have Masked Signals from Other Detector,Required to Be Operational.Caused by Personnel Damaging Detector | | | 05000260/LER-1979-004-03, /03L-0 on 790414:reactor Bldg,Turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Failed Surveillance Test SI 4.8.B-4.3,Section 4e.Caused by Failure of Input Card for Radiation Monitor | /03L-0 on 790414:reactor Bldg,Turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Failed Surveillance Test SI 4.8.B-4.3,Section 4e.Caused by Failure of Input Card for Radiation Monitor | | | 05000296/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000296/LER-1979-005, Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved | Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved | | | 05000296/LER-1979-005-01, /01T-1:on 790506,BHR Water Supply Isolation to 2B RHR Heat Exchanger Isolated Standby Coolant Supply to Unit 3.Caused by Lack of Administrative Control Over Sys Cross Connect Valves.Administrative Controls Have Been Improved | /01T-1:on 790506,BHR Water Supply Isolation to 2B RHR Heat Exchanger Isolated Standby Coolant Supply to Unit 3.Caused by Lack of Administrative Control Over Sys Cross Connect Valves.Administrative Controls Have Been Improved | | | 05000259/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000259/LER-1979-005-03, /03L-0 on 790225:reactor,turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Became Inoperable.Caused by Moisture Collection in Detector SC-2.-1.S.Detector Replaced & Moisture Removed | /03L-0 on 790225:reactor,turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Became Inoperable.Caused by Moisture Collection in Detector SC-2.-1.S.Detector Replaced & Moisture Removed | | | 05000260/LER-1979-005-03, /03L-0 on 790419:broken Terminal Discovered on Shutdown Board D Battery.Cause Unknown.Affected Cells Replaced & Personnel Instructed in Proper Tightening Methods | /03L-0 on 790419:broken Terminal Discovered on Shutdown Board D Battery.Cause Unknown.Affected Cells Replaced & Personnel Instructed in Proper Tightening Methods | | | 05000260/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000296/LER-1979-006-03, During Normal Operation, Erratic Indication of Torus Hydrogen Sensor Observed. Hydrogen Sensor Replaced & Tested Satisfactory.Design Change Request Initiated | During Normal Operation, Erratic Indication of Torus Hydrogen Sensor Observed. Hydrogen Sensor Replaced & Tested Satisfactory.Design Change Request Initiated | | | 05000296/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000260/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000259/LER-1979-006-03, /03L-0 on 790228:reactor,turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable for 3.5-h.Caused by Moisture in SC-2B Detector & Leaking Flanges.Moisture Removed & Flanges Tightened | /03L-0 on 790228:reactor,turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable for 3.5-h.Caused by Moisture in SC-2B Detector & Leaking Flanges.Moisture Removed & Flanges Tightened | | | 05000259/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000260/LER-1979-006-03, /03L-0 on 790427:prior to Refueling Shutdown, Drywell Prepurge Tritium Sample Not Taken.Caused by Lack of Understanding Between Operational & Lab Personnel.Operating Instructions Amended to Prevent Recurrence | /03L-0 on 790427:prior to Refueling Shutdown, Drywell Prepurge Tritium Sample Not Taken.Caused by Lack of Understanding Between Operational & Lab Personnel.Operating Instructions Amended to Prevent Recurrence | | | 05000260/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000296/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000296/LER-1979-007-03, /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr | /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr | | | 05000260/LER-1979-007-03, /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested | /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested | | | 05000260/LER-1979-008-01, /01T-0 on 790504:while Preparing for Refueling Outage,Secondary Containment Integrity Was Not Conclusively Demonstrated Prior to Breaking Primary Containment.Test Improperly Performed Due to Personnel Error | /01T-0 on 790504:while Preparing for Refueling Outage,Secondary Containment Integrity Was Not Conclusively Demonstrated Prior to Breaking Primary Containment.Test Improperly Performed Due to Personnel Error | | | 05000259/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000259/LER-1979-008-03, /03L-0 on 790612:during Normal Operation, Pressure Switches PS-1-81 a & B & PS-1-91 a & B Setpoints Exceeded Tech Specs by 3-15 Psig. Caused by Model B2T-A12SS Switches Drifting | /03L-0 on 790612:during Normal Operation, Pressure Switches PS-1-81 a & B & PS-1-91 a & B Setpoints Exceeded Tech Specs by 3-15 Psig. Caused by Model B2T-A12SS Switches Drifting | | | 05000296/LER-1979-008-03, /03L-0 on 790627:no Speed Indication Noted on Reactor Core Isolation Coolant.Caused by Broken Wires to Magnetic Pickup EG-M Box.Wires Repaired | /03L-0 on 790627:no Speed Indication Noted on Reactor Core Isolation Coolant.Caused by Broken Wires to Magnetic Pickup EG-M Box.Wires Repaired | | | 05000260/LER-1979-008, Forwards LER 79-008/01T-0 | Forwards LER 79-008/01T-0 | | | 05000296/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000296/LER-1979-009-03, /03L-0 on 790717:hydrogen Ignition Damaged HEPA Filters.Caused by Improper Offgas Recombiner Preheater Operation.Sys HEPA Filters & Charcoal Bed Inspected.Three Filters Replaced.Procedures Will Be Revised | /03L-0 on 790717:hydrogen Ignition Damaged HEPA Filters.Caused by Improper Offgas Recombiner Preheater Operation.Sys HEPA Filters & Charcoal Bed Inspected.Three Filters Replaced.Procedures Will Be Revised | | | 05000260/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000296/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | |
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