LER-1981-036, /03L-0:on 810616,containment Radiation post- Accident monitor,RE-5030,found Not Running.Caused by Low Flow Due to Bypass Discharge Hose Falling Off During Routine Maint.Hose Reconnected & Monitor Restarted |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461981036R03 - NRC Website |
|
text
U. 9$. MCLLGt J WLWLGALnf@tNTMgamessww
.t AC FORM 36G
- 7-77)
LICENSEE EVENT REPORT ONTROL BLOCK: l l
l l
l'l lh' (PLEASE PRINT OR TYPE ALL REQO RED INFORMATION) 1 6
l0 l l l 0 l H l D l B l S l 1 l@l_ 0 l 0 l - l 0 l 0 l 0 l 6 l e l _ l 6 l 6 l@l 4 l 1 l 1 l 1 l 1 l
l@
7 8 9 LICENSEE CODE 14 15 uCENSE w.*uER 25 26 LICENSE T4 PE JO
$1 GA T 58
- jo i; lL 0 l 5 l 0 l 0 l 0 l 3 l 4 l 6 @l 0 l 6 l 1 l 6 l 8 l 1 l@l 01 7 l Il 6 l 8 l 1 l@
CON'T REPO 60 61 OOCKET WYBER bd 63 EV ENT D ATE 14 15 RE*OR T D ATE 80 7
8 EVENT DESCRIPTION AND PROBABLE CONSEOUENCES h Radiation!
g-l l (NP-33-81-42) At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on 6/16/81, a reactor operator found Containment Post Accident Monitor RE 5030 not running. The pump could be restarted but would not !
gg,3, g g l remain running. Technical Specification 3.3.3.6 requires both radiation monigors be l
,,,gjgoperable in Modes 1, 2, and 3.
There was no danger to the health and safety of the 1
l Public or station personnel. The containment was isolated and no releases occurred.
I 0 6 I
go,7gl Containment Radiation Post Accident Monitor RE 5029 was verified operable.
I I o 18 I I 80 E
CODE SL8C E COYPONENT CODE S BC OE SU E
Q lB lB lh l X lh l Z lh l P l Il P l r l y l y lh l A l@ y @
7 8
9 to 11 12 13 18 19 20 REVISION SEQUE NTI AL OCCURRENCE REFORT EVENT YE AR REPORT NO.
CODE TYPE NO.
@,afg'fio 18ill l-l 10l3161 M
10131 L_LJ l_J La_I LE R r
,_21 22 23 24 26 27 28 29 JJ 31 32 u
KN AC oN PL NT EH HOURS 22 SB i FO d 8.
SV PLIE VA F CT FIR lAlgl34Z l g
]35g l36Z lg l1 d j 0 l 0 l '- l lYl@
l Nl@
l Al@
l Zl 1l 6l 5l@
3 40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 11 l o l l The pump stopped due to low flow caused by the bypass discharge hose falling off.
Thel gexact cause is unknown, but it may be that the hose was inadvertently knocked loose j
The hose was reconnected and RE 5030 restarted. RE 5030 i
[duringroutinemaintenance.
was verified operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Maintenance Work Order 81-2741 was issued to i
, investigate cther radiation monitors for similar problems.
g T
8 9 OTHER STATUS ISCO RY OlSCoV ERY DESCRIPTION R {_yjh l0l7l9lhl
_l l B l@l Operator observation l
STA S
". POWER.
NA ACTIVITY CONTENT LOCATION OF RELEASE liEL EASED of RELE ASE AVOUNT OF ACTivlTY l
g l NA j
i NA 1 6 80 44 45 7
8 9 to 11 PERSONNEL EltPOSURES N
TYPE
DESCRIPTION
l l 0lUMaERl0l@jZl@lNA 1 7
,ERSONNE L imu'4 ES DESCmPTiONh l
uvaeR FTTl I dl01Ol@l NA 7
8 9 11 12 LOSS OF OR OAYAGE To FACILITY l
TYPE D ESCniPTION NA [8,lf,j (_Zjhl 7
8 9 10 8107240228 810716 NRC ust ONLY PusuC Tv issuen oESCmPTios PDR ADOCK 05000346 l Sl Un l NA S
PDR l
llIIIIIIIII!l2 m
2 o 68 69 80 5 DVR 81-082 Mark E. Rowinnd PHONE NAME OF PREPARER
e
~
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UN11 ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-42 DATE OF EVENT: ' June 16, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Containment Radiation Post Accident Monitor RE 5030 Failure Conditions Prior to Occurren 3: The unit was in Mode 1 with Power (MWT) = 1988 End Load (Gross MWE) = 654 Description of Occurrence: On June 16, 1981 at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, a reactor operator found RE 5030 not. running. There are two containment post accident radiation monitors whose functica is to sample containment atmosphere-fellowing an accident. One of these monitors is kept running at all times, and RE 5030 was the one that had been running. Since the pump would not remain running when restarted, the monitor was declared inoperable, and the station entered the action statement of Technical Speci-fication 3.3.3.6.
The Technical Specification requires both monitors to be operable in Modes 1, 2, and 3.
The action statement requires the failed acnitor be restored to operable status within 30 days or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Designation of Apparent Cause of Occurrence: The bypass discharge hose was found dis-connected.. The cause of this occurrence is unknown. It may be that the hose was in-advertently knocked loose while performing maintenance.. Discharge pressure eventually forced the hose off. The pump shutdown automatically due to low flow.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel.
The containment was isolated and no releases occurred.
RE 5029 was verified operable.
Corrective Action
The hose was reconnected and RE 5030 was verified operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Maintenance Work Order 81-2741 was issued to check the other radiation j
monitors for similar problems.
t i
Failure Data: Previous similar reported occurrences of inoperable radiation monitors
~
were reported in Licensee Event Reports NP-33-78-143, NP-33-78-91, NP-33-78-111, l
NP-33-78-45, NP-33-78-30.
This occurrence is an isolated event and not related to cny previous modes of failure.
LER #81-036 4
_mg
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000346/LER-1981-001, Forwards LER 81-001/01X-1 | Forwards LER 81-001/01X-1 | | | 05000346/LER-1981-001-01, /01X-1:on 810107,discovered Contractor Personnel on 801204 Disassembled Restraints Other than Those Requested & Failed to Perform Reassembly in Timely Manner. Caused by Inadequate Procedural Control | /01X-1:on 810107,discovered Contractor Personnel on 801204 Disassembled Restraints Other than Those Requested & Failed to Perform Reassembly in Timely Manner. Caused by Inadequate Procedural Control | | | 05000346/LER-1981-002-03, /03L-0:on 810102,reactor Coolant Pump 1-2 Was Shutdown Due to High Seal Return Temp & Deteriorating Seal Staging & on 810106,pump 2-1 Was Shutdown for Deteriorating Seal Staging.Caused by Seal Degradation.Seals Replaced | /03L-0:on 810102,reactor Coolant Pump 1-2 Was Shutdown Due to High Seal Return Temp & Deteriorating Seal Staging & on 810106,pump 2-1 Was Shutdown for Deteriorating Seal Staging.Caused by Seal Degradation.Seals Replaced | | | 05000346/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000346/LER-1981-003-03, /03L-0:on 810106,breaker HX02B Tripped, de-energizing Bus B Which Reduced Electrical Distribution Less than Tech Specs Required.Caused by Personnel Error. Breakers Restored.Operators Counselled Re Attentiveness | /03L-0:on 810106,breaker HX02B Tripped, de-energizing Bus B Which Reduced Electrical Distribution Less than Tech Specs Required.Caused by Personnel Error. Breakers Restored.Operators Counselled Re Attentiveness | | | 05000346/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000346/LER-1981-004, Forwards LER 81-004/03X-1 | Forwards LER 81-004/03X-1 | | | 05000346/LER-1981-005-03, /03L-0:on 810114,RCS Chloride Concentration Exceeded Tech Spec Limit.Caused by Use of Spotcheck in Cleaning Reactor Coolant Pump Seal Cavities.Instructions Issued for Use of Solvents in RCS | /03L-0:on 810114,RCS Chloride Concentration Exceeded Tech Spec Limit.Caused by Use of Spotcheck in Cleaning Reactor Coolant Pump Seal Cavities.Instructions Issued for Use of Solvents in RCS | | | 05000346/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000346/LER-1981-006-03, /03L-0:on 810119,power Lost to Safety Features Actuation Sys Channel 1 Cabinet.Caused by Blown Supply Fuse from Panel Y-1 Due to Procedure Deficiency.Fuse Replaced & Procedure Modified | /03L-0:on 810119,power Lost to Safety Features Actuation Sys Channel 1 Cabinet.Caused by Blown Supply Fuse from Panel Y-1 Due to Procedure Deficiency.Fuse Replaced & Procedure Modified | | | 05000346/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000346/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000346/LER-1981-007-03, /03L-0:on 810122,door 306 Found Partially Open,So That Spent Fuel Pool Emergency Ventilation Sys Could Not Have Maintained Area at Correct Pressure.Caused by Maladjusted Door Closure.Maint Work Order Issued | /03L-0:on 810122,door 306 Found Partially Open,So That Spent Fuel Pool Emergency Ventilation Sys Could Not Have Maintained Area at Correct Pressure.Caused by Maladjusted Door Closure.Maint Work Order Issued | | | 05000346/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000346/LER-1981-008-03, /03L-0:on 810127,345 Kv Switchyard Bus K Tripped & Locked out,de-energizing Startup Transformer 02.Caused by Action from Directional Ground Current Relay & Charred Phase Lightning Arrestor C on Startup Transformer | /03L-0:on 810127,345 Kv Switchyard Bus K Tripped & Locked out,de-energizing Startup Transformer 02.Caused by Action from Directional Ground Current Relay & Charred Phase Lightning Arrestor C on Startup Transformer | | | 05000346/LER-1981-009-03, /03L-0:on 810128,diesel Generator 1-2 Could Not Be Started W/Left Side Set of Air Start Motors During Diesel Generator Surveillance Test 5081.01.Caused by Failure of One Air Start Motor Due to Broken Solenoid Drive Shaft | /03L-0:on 810128,diesel Generator 1-2 Could Not Be Started W/Left Side Set of Air Start Motors During Diesel Generator Surveillance Test 5081.01.Caused by Failure of One Air Start Motor Due to Broken Solenoid Drive Shaft | | | 05000346/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000346/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000346/LER-1981-010-03, /03L-0:on 810202,MSIV Bypass Valve Ms 100 a Failed to Close.Probably Caused by Component Failure.Actuator Spring Adjusted to Increase Tension Until Valve Would Close | /03L-0:on 810202,MSIV Bypass Valve Ms 100 a Failed to Close.Probably Caused by Component Failure.Actuator Spring Adjusted to Increase Tension Until Valve Would Close | | | 05000346/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000346/LER-1981-011-03, /03L-0:on 810205,post-accident Monitoring Instrument HPI Flow 1-2 Was Declared Inoperable.Caused by Bad Current Buffer.Current Buffer Was Repaired,Recalibr & Reinstalled.Hpi Flow 1-2 Was Returned to Operable Status | /03L-0:on 810205,post-accident Monitoring Instrument HPI Flow 1-2 Was Declared Inoperable.Caused by Bad Current Buffer.Current Buffer Was Repaired,Recalibr & Reinstalled.Hpi Flow 1-2 Was Returned to Operable Status | | | 05000346/LER-1981-012-03, /03L-0:on 810212,control Rod 1-3 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals Causing Asymmetric Rod Alarms.Exact Cause Undetermined,But Absolute Position Indication Leads Picking Up Noise | /03L-0:on 810212,control Rod 1-3 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals Causing Asymmetric Rod Alarms.Exact Cause Undetermined,But Absolute Position Indication Leads Picking Up Noise | | | 05000346/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000346/LER-1981-013-03, /03L-0:on 810218,control Room Normal Ventilation Dampers Tripped Shut Resulting in No Power Available to Chlorine Detector 1 Above Control Room or in Block House. Caused by Failure of 10 Amp Fuse of Circuit Y111 | /03L-0:on 810218,control Room Normal Ventilation Dampers Tripped Shut Resulting in No Power Available to Chlorine Detector 1 Above Control Room or in Block House. Caused by Failure of 10 Amp Fuse of Circuit Y111 | | | 05000346/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000346/LER-1981-014-03, /03X-1:on 810226,decay Heat Valve 64 Would Not Open During Testable ECCS Valves Quarterly Test.Caused by Loose Set Rod Bushing,Allowing Gear Box Set Rod to Move Which Unlocked Limit Switches from Adjusted Position | /03X-1:on 810226,decay Heat Valve 64 Would Not Open During Testable ECCS Valves Quarterly Test.Caused by Loose Set Rod Bushing,Allowing Gear Box Set Rod to Move Which Unlocked Limit Switches from Adjusted Position | | | 05000346/LER-1981-014, Forwards LER 81-014/03X-1 | Forwards LER 81-014/03X-1 | | | 05000346/LER-1981-015-03, /03L-0:on 810227,access Door 107 Found Propped Open from ECCS 2 Pump Room 115 to Miscellaneous Waste Monitor Tank & Pump Room 114.Caused by Failure to Follow Posted Signs While Clearing Odor from Room | /03L-0:on 810227,access Door 107 Found Propped Open from ECCS 2 Pump Room 115 to Miscellaneous Waste Monitor Tank & Pump Room 114.Caused by Failure to Follow Posted Signs While Clearing Odor from Room | | | 05000346/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000346/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000346/LER-1981-016-03, /03L-0:on 810308,dose Equivalent I-131 Level Exceeded Tech Spec Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored | /03L-0:on 810308,dose Equivalent I-131 Level Exceeded Tech Spec Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored | | | 05000346/LER-1981-017-03, /03L-0:on 810309,train 2 Hpi/Low Pressure Injection cross-connect Isolation Valve Dh 63 Would Not Open from Control Room During Quarterly Valve Surveillance Test 5051.13.Caused by Faulty Torque Switch in Valve Operator | /03L-0:on 810309,train 2 Hpi/Low Pressure Injection cross-connect Isolation Valve Dh 63 Would Not Open from Control Room During Quarterly Valve Surveillance Test 5051.13.Caused by Faulty Torque Switch in Valve Operator | | | 05000346/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000346/LER-1981-018-03, /03L-0:on 810322 & 0401,chlorine Detector Ae 5358B Tripped.First Trip Probably Caused by Fouled Detector. Detector Cleaned.Detector & Circuit Board Replaced After Second Failure | /03L-0:on 810322 & 0401,chlorine Detector Ae 5358B Tripped.First Trip Probably Caused by Fouled Detector. Detector Cleaned.Detector & Circuit Board Replaced After Second Failure | | | 05000346/LER-1981-018, Forwards LER 81-018/03L-0 | Forwards LER 81-018/03L-0 | | | 05000346/LER-1981-019-03, /03L-0:on 810323,fluctuating Signals W/Numerous Asymmetric Rod Alarms Received,Resulting in Control Rod 4-7 Absolute Position Indication Inoperability.Probably Caused by Electrical Penetration Module Deficiency | /03L-0:on 810323,fluctuating Signals W/Numerous Asymmetric Rod Alarms Received,Resulting in Control Rod 4-7 Absolute Position Indication Inoperability.Probably Caused by Electrical Penetration Module Deficiency | | | 05000346/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000346/LER-1981-020-03, /03L-0:on 810324,valve CV5011A,on Containment Air Sample Inlet Line to Hydrogen Analyzer,Would Not Stroke Closed W/Monitor Operator.Caused by Badly Worn Tripper in Motor Operator.Tripper Levers Replaced | /03L-0:on 810324,valve CV5011A,on Containment Air Sample Inlet Line to Hydrogen Analyzer,Would Not Stroke Closed W/Monitor Operator.Caused by Badly Worn Tripper in Motor Operator.Tripper Levers Replaced | | | 05000346/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000346/LER-1981-021-03, /03L-0:on 810401,half Trip Occurred from Steam & Feedwater Rupture Control Sys Channel 1 Low Steam Generator Level Trip.Caused by Power Supply Failure.Power Supply Replaced Per Work Order on 810402 | /03L-0:on 810401,half Trip Occurred from Steam & Feedwater Rupture Control Sys Channel 1 Low Steam Generator Level Trip.Caused by Power Supply Failure.Power Supply Replaced Per Work Order on 810402 | | | 05000346/LER-1981-021, Forwards LER 81-021/03L-0 | Forwards LER 81-021/03L-0 | | | 05000346/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000346/LER-1981-022-03, /03L-0:on 810316,NRC Site Inspector Reported Finding Four 0.5-inch Holes Through Control Room Equipment Room East Fire Wall.On 810403,two Holes Found in Wall of Room 427B.Caused by Personnel Error | /03L-0:on 810316,NRC Site Inspector Reported Finding Four 0.5-inch Holes Through Control Room Equipment Room East Fire Wall.On 810403,two Holes Found in Wall of Room 427B.Caused by Personnel Error | | | 05000346/LER-1981-023-03, /03L-1:on 810403,decay Heat Cooler Outlet Valve CC1467 Stroked Closed During Component Cooling Water Monthly Test & Would Not Reopen.Caused by Excessive Wear on Actuator Due to Design Deficiency.Actuator Rebuilt | /03L-1:on 810403,decay Heat Cooler Outlet Valve CC1467 Stroked Closed During Component Cooling Water Monthly Test & Would Not Reopen.Caused by Excessive Wear on Actuator Due to Design Deficiency.Actuator Rebuilt | | | 05000346/LER-1981-023, Forwards LER 81-023/03L-1 | Forwards LER 81-023/03L-1 | | | 05000346/LER-1981-024, Forwards LER 81-024/03L-0 | Forwards LER 81-024/03L-0 | | | 05000346/LER-1981-024-03, /03L-0:on 810418,bus J Was Rapidly Taken Out of Svc W/O Providing for Alternate Power Supply for Decay Heat Pump 1-1.Caused by Personnel Error.Procedure Modified & Operator Informed of Mods | /03L-0:on 810418,bus J Was Rapidly Taken Out of Svc W/O Providing for Alternate Power Supply for Decay Heat Pump 1-1.Caused by Personnel Error.Procedure Modified & Operator Informed of Mods | | | 05000346/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000346/LER-1981-025-03, /03L-0:on 810423,during Review of Safety Tagging Log,Unit Entered Mode 4 W/O Required Two Makeup Pumps Operable.Caused by Personnel Error.Pumps Restored to Operation.Personnel Reinstructed in Procedures | /03L-0:on 810423,during Review of Safety Tagging Log,Unit Entered Mode 4 W/O Required Two Makeup Pumps Operable.Caused by Personnel Error.Pumps Restored to Operation.Personnel Reinstructed in Procedures | | | 05000346/LER-1981-026-03, /03L-0:on 810428,reactor Protection Sys Channel 1 Tripped on Flux/Delta Flux/Flow.Caused by Failure of Flow Differential Pressure Transmitter Primary Power Transformer Shorting to Ground.New Amplifier Installed & Calibr | /03L-0:on 810428,reactor Protection Sys Channel 1 Tripped on Flux/Delta Flux/Flow.Caused by Failure of Flow Differential Pressure Transmitter Primary Power Transformer Shorting to Ground.New Amplifier Installed & Calibr | |
|