LER-1980-205, /03L-0:on 801229 & 810105,two Ice Condenser Intermediate Deck Doors Below AHU-3A Found Frozen Closed. Caused by Overflow from Drip Pan Freezing Around Doors.Ice Removed |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3271980205R03 - NRC Website |
|
text
-
v LICENSEE EVF.NT REPORT 9
CONTROL 8 LOCK: l l
l l
l !.!h (PLE ASE PRINT OR TYPE ALL nEQUIRED INFORMATIONI R l T l N l S l N l P l 1 l@! O! 0l -l O l O! 0 l 0 l 0 l - l 0 l 0 !@l 4 l1 l1 l1 l 1 l@[
l l@
p a 9 LICENstt COOL to 16 LICENst NuvotH 26 26 LICE Nst t vrt 40 67 Cat w CON'T lol'l
,Q,'lL @l0 l 51010 l0 13 l2 17 '@l 112 l 2 l 9 l 8 l 0 l@l 0l 1l 2l 618 l 1l@
l 8
60 66 DOCKtfNVvotM 68 69 Evf NT D ATE 74
?S RtPORfDAft to EVEt47 DESCRIPTION AND PROS A8LE CONSEQUENCES Q l o 12 l l Unit in Mode 1 at 86% reactor power. On 12-29-80 and again on 1-5-81. two ice i
I o 131 ] condenser intermediate deck doors below AHU-3A were found frozen closed. LCO 3.6.5.3 I
l o l a 1 l was entered on both occasions. There was no effect upon public health or safety.
I ITTTl i Previous occurrences - 2 (Reference SQRO-50-327/80170 and 80203).
I 101611 I
o i l l
Ioie11 I
systtu CAust CAust tous-vatvg Co0E Co0F suscoDE Cou*oNE NT Co0E SutCoct susCOQt l S l B I@ (E,jh l B lh l P l E l N l E lT lR lh Wh,[_Z_j h lo191 3
g 9
10 11 12 12 18 19 20 stouf NTI AL OCCun at NCE mErom?
REV85 ton g ming (Vt47 YE AR R(POn T No.
4coE fvPt No.
O,a(5,',o,af18 l 01 1-1 L210 i s l g
l0 3 l Lt_j t._.j m
9
_ 21 22 23 24 26 27 28 29 20 3,
32 suPah, a i K F A 7 or o PtaNT ii u Houns 72 se if Fon 6.
uaNusaCfunta l B lgj X lg lSZ l g LZJ @
l0l0l0l l gg l Nlg lN [g l Wl 1l 2 l 0l JJ J4 J
26 37 40 41 42 43 44 47 CAUSE DESCntPTION AND CCA AECTIVE ACTIONS h lTTh'] l Ice was runoved from doors within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on both occasions. Water frozen in ANU-3A 1
I i i i l 1 drain line did not allow water to pass durina defrost eveles. The unter snillad over i,i2j l from drip pan onto the doors causing doors to become frozen closed.
ii iil I f
11,*Il s
6 i 80
's",'Et t [
ovutn status @
$isNin 0 sCovEnv 0tsCnipitow h I'
assenta l: 13 l l Bl@ l0 l 8 [ 6 l@l NA l
lBl@l Operator observation i
',C%.tv Co'a t,,,
80 l i l G l l Z l @ l Z l@l AuouNT oF ACTivtfY @ l LoCAftoN oF RELE ASE @
artsasto os nettav NA l
NA l
2.
4 Pf nsoNNEL E mPosuats Nuve t a tvrt ogsCarevroN l : l il l O l O l 0 l@W@l NA
,cosoNNt t,~,u'4 s L,'_Lij l 0I o I o 18l sC 1 oN@
Nuo.t :1 Di NA l
,2
.o
',S't ' " s'C f,','o'N C' " @
E L,LL1] LZj@l NA l
,o so 8 LN]e8loEscar*' ion h
,ssu NA l
lllllllIlIIIl 7
8 9 10 69 et Name o 810202 o MPreparer J. M. McGriff Phone 615-842-8317
i r
Tennessee Valley Authority Sequoyah Nuclear Plant LER SUPPI.EMENTAL INFORMATION SQRO-50-327/80205 Technical Specification Involved:
3.6.5.3 Reported Under Technical Specification:
6.9.1.13.b Date of Occurrences:
12-29-80, 1-5-81 Time of occurrences: 0118 CST, 1815 CST Identification and Description of Occurrences:
During routine inspection of ice condenser on 12-29-80, and again on 1-5-81, two ice condenser intermediate deck doors under AHU-3A were found frozen closed daring each inspection.
4 Conditions Prior to Occurrence:
Unit 1 in Mode 1 at 86% reactor power on 12-29-80 and at 90% reactor power on 1-5-81.
Apparent Cause of Occurrence:
j Water froze in AHU-3A defrost drain line blocking flow during subsequent Water spilled from drip defrost cycles and caustry drain line :o rupture.
pan onto doors and froze.
I Analysis of Occurrence:
On the first occurrence (12-29-80), water had frozen in the defrost drain line of AHU-3A causing both flow blockage and the drain line to rupture.
On 1-2-81, insulation was removed Water epilled from drip pan onto doors.
from the drain line, heat tracing removed, and a temporary heat tape installed so that the line could be repaired. The second occurrence (1-5-81) can be First, water spilling over drip pan during defrost attributed to two causes.
12-29-80 and 1-2-81.
Second, water from melting ice in drain cycles between line.. af ter installation of temporary heat tape, dripping from rupture in drain line.
Corrective Action
The ice was removed from the doors on both occasions within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Ruptured drain line was repaired by.1-6-81.
An investigation has begun to determine why the drain line has been freezing.
Failure Data:
None
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000327/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000327/LER-1980-001-01, /01T-0:on 800301-03,during Initial Fuel Loading, Licensee Failed to Estimate Flowrate from Svc Bldg Exhaust at 4-h Intervals.Caused by Misunderstanding of Tech Spec Requirements.Plant Instructions Revised | /01T-0:on 800301-03,during Initial Fuel Loading, Licensee Failed to Estimate Flowrate from Svc Bldg Exhaust at 4-h Intervals.Caused by Misunderstanding of Tech Spec Requirements.Plant Instructions Revised | | | 05000327/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000327/LER-1980-002-01, /01T-0:on 800306,contents of Task Decontamination Collector Tank Discharged Via Liquid Radwaste Effluent Line to Cooling Tower Blowdown W/O Flow Estimates Being Performed.Caused by Misunderstanding of Tech Specs | /01T-0:on 800306,contents of Task Decontamination Collector Tank Discharged Via Liquid Radwaste Effluent Line to Cooling Tower Blowdown W/O Flow Estimates Being Performed.Caused by Misunderstanding of Tech Specs | | | 05000327/LER-1980-003-01, /01T-0:on 800310,following Initial Fuel Loading, Flow Through Auxiliary Bldg Exhaust Sampler Not Maintained for 3.25-h.Caused by Misunderstanding of Tech Specs. Personnel Reinstructed in Applicable Requirements | /01T-0:on 800310,following Initial Fuel Loading, Flow Through Auxiliary Bldg Exhaust Sampler Not Maintained for 3.25-h.Caused by Misunderstanding of Tech Specs. Personnel Reinstructed in Applicable Requirements | | | 05000327/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000327/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000327/LER-1980-004-01, /01T-0:on 800311,following Initial Fuel Loading, Flow Estimates for Auxiliary Bldg Vent Monitor Not Performed for 10-h.Caused by Misunderstanding of Tech Specs.Personnel Reinstructed Re Applicable Requirements | /01T-0:on 800311,following Initial Fuel Loading, Flow Estimates for Auxiliary Bldg Vent Monitor Not Performed for 10-h.Caused by Misunderstanding of Tech Specs.Personnel Reinstructed Re Applicable Requirements | | | 05000327/LER-1980-005-03, /03L-0:on 800311,while Performing SI-247.605, Reactor Solid State Protection Sys Was Placed in Input Inhibit Mode,Removing High Voltage from Source Range Channel N31.Caused by Removal of Fuses from Voltage Cut Out Relay | /03L-0:on 800311,while Performing SI-247.605, Reactor Solid State Protection Sys Was Placed in Input Inhibit Mode,Removing High Voltage from Source Range Channel N31.Caused by Removal of Fuses from Voltage Cut Out Relay | | | 05000327/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000327/LER-1980-006-01, /01T-0:on 800314,w/essential Raw Cooling Water Radiation Monitors on Train a Inoperable,Personnel Determined That Limiting Condition of Operation Requires Sampling.Caused by Misinterpretation of Tech Specs | /01T-0:on 800314,w/essential Raw Cooling Water Radiation Monitors on Train a Inoperable,Personnel Determined That Limiting Condition of Operation Requires Sampling.Caused by Misinterpretation of Tech Specs | | | 05000327/LER-1980-006, Forwards LER 80-006/01T-0 | Forwards LER 80-006/01T-0 | | | 05000327/LER-1980-007-01, /01T-0:on 800315,following Initial Core Loading, Found Incorrect (Nonconservative) Valve Operator Weights Used in Seismic Analysis for Component Cooling Water Valves FCV-70-133,134 & 183.Caused by Incorrect Vendor Data | /01T-0:on 800315,following Initial Core Loading, Found Incorrect (Nonconservative) Valve Operator Weights Used in Seismic Analysis for Component Cooling Water Valves FCV-70-133,134 & 183.Caused by Incorrect Vendor Data | | | 05000327/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000327/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000327/LER-1980-008-03, /03L-0:on 800303,cooling Tower Blowdown Effluent Line Flow Monitor O-FR-27-175 Was Declared Inoperable.Flow Monitor Consistently Indicated Higher Flowrate than Actually Existed.Cause Unknown.Different Instrument to Be Instal | /03L-0:on 800303,cooling Tower Blowdown Effluent Line Flow Monitor O-FR-27-175 Was Declared Inoperable.Flow Monitor Consistently Indicated Higher Flowrate than Actually Existed.Cause Unknown.Different Instrument to Be Installed | | | 05000327/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000327/LER-1980-009-03, /03L-0:on 800303,liquid Radwaste Effluent Line Flow Monitor 0-FT-77-42 Consistently Indicated Higher Discharge Flow Rate than Actually Observed.Cause Not Stated.Flow Monitor Modified & Returned to Svc | /03L-0:on 800303,liquid Radwaste Effluent Line Flow Monitor 0-FT-77-42 Consistently Indicated Higher Discharge Flow Rate than Actually Observed.Cause Not Stated.Flow Monitor Modified & Returned to Svc | | | 05000327/LER-1980-010-03, /03L-0:on 800304,gaseous Vent Flow Rate Monitors for Units 1 & 2 Shield Bldgs & Auxiliary Bldg Were Declared Inoperable.Cause Not Stated.Gaseous Flow Rate Monitors to Be Redesigned | /03L-0:on 800304,gaseous Vent Flow Rate Monitors for Units 1 & 2 Shield Bldgs & Auxiliary Bldg Were Declared Inoperable.Cause Not Stated.Gaseous Flow Rate Monitors to Be Redesigned | | | 05000327/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000327/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000327/LER-1980-011-01, /01T-0:on 800314,support Pin Insp at Foreign Plant Revealed Stress Corrosion Cracking in Westinghouse Supplied Pins.Insp Supported Westinghouse Ltr Informing Utils of Potential Hazard.Pins Will Be Replaced | /01T-0:on 800314,support Pin Insp at Foreign Plant Revealed Stress Corrosion Cracking in Westinghouse Supplied Pins.Insp Supported Westinghouse Ltr Informing Utils of Potential Hazard.Pins Will Be Replaced | | | 05000327/LER-1980-012-03, /03L-0:on 800301,during Initial Core Loading,Rhr Flow Secured or Throttled Above Tech Specs.Caused by Intentional Increase to Allow Placement of Fuel Assemblies Near Loop 4 Hot Leg | /03L-0:on 800301,during Initial Core Loading,Rhr Flow Secured or Throttled Above Tech Specs.Caused by Intentional Increase to Allow Placement of Fuel Assemblies Near Loop 4 Hot Leg | | | 05000327/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000327/LER-1980-013-03, /03L-0:on 800302,failed to Analyze Samples from Unit 2 Shield Bldg Exhaust.Caused by Misunderstanding of Surveillance Requirements.Lab Personnel Instructed on Sampling & Analysis Requirements | /03L-0:on 800302,failed to Analyze Samples from Unit 2 Shield Bldg Exhaust.Caused by Misunderstanding of Surveillance Requirements.Lab Personnel Instructed on Sampling & Analysis Requirements | | | 05000327/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000327/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000327/LER-1980-014-03, /03L-0:on 800328,while Performing Check Source Test,Auxiliary Bldg Vent Noble Gas Monitor Had Module Power Problem & Failed in Svc.Caused by Zener Diode IN4740 & Transistor Fmps A13 Shorting Out | /03L-0:on 800328,while Performing Check Source Test,Auxiliary Bldg Vent Noble Gas Monitor Had Module Power Problem & Failed in Svc.Caused by Zener Diode IN4740 & Transistor Fmps A13 Shorting Out | | | 05000327/LER-1980-015-03, /03L-0:on 800305,while in Mode 6 W/Fuel Loading Complete,Pressure Was Only Being Monitored in One Steam Generator & Reactor Pressure Vessel.Caused by Misunderstanding of Surveillance Instruction | /03L-0:on 800305,while in Mode 6 W/Fuel Loading Complete,Pressure Was Only Being Monitored in One Steam Generator & Reactor Pressure Vessel.Caused by Misunderstanding of Surveillance Instruction | | | 05000327/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000327/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000327/LER-1980-016-03, /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary | /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary | | | 05000327/LER-1980-017-03, /03L-0:on 800310,while in Mode 6,turbine Bldg Sump Monitor O-RM-90-212 Alarm Kept Coming In.Monitor Was Declared Inoperable.Caused by Malfunctioning Flow Switch Not Allowing Sufficient Flow Through Monitor | /03L-0:on 800310,while in Mode 6,turbine Bldg Sump Monitor O-RM-90-212 Alarm Kept Coming In.Monitor Was Declared Inoperable.Caused by Malfunctioning Flow Switch Not Allowing Sufficient Flow Through Monitor | | | 05000327/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000327/LER-1980-018-01, /01T-0:on 800326,while in Mode 6 W/All Fuel Loaded,Exposed Cables Inside Containment Between Conduit & Penetrations Not Qualified to re-evaluated post-LOCA Max Dose Levels.Cables Shielded from Exposure to New Dose Level | /01T-0:on 800326,while in Mode 6 W/All Fuel Loaded,Exposed Cables Inside Containment Between Conduit & Penetrations Not Qualified to re-evaluated post-LOCA Max Dose Levels.Cables Shielded from Exposure to New Dose Level | | | 05000327/LER-1980-018, Forwards LER 80-018/01T-0 | Forwards LER 80-018/01T-0 | | | 05000327/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000327/LER-1980-019-01, /01T-0:on 800326,found Possibility of Not Maintaining Control Room Habitability Due to Leakage of Unfiltered Air.Possibly Caused by Isolation Dampers. Corrective Mods Planned | /01T-0:on 800326,found Possibility of Not Maintaining Control Room Habitability Due to Leakage of Unfiltered Air.Possibly Caused by Isolation Dampers. Corrective Mods Planned | | | 05000327/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000327/LER-1980-020-01, /01T-0:on 800404,investigation Revealed That Several vendor-designed Pipe Supports Were Designed Utilizing Manufacturer Std 0.25-inch U-bolt Which Overstressed During Seismic Event.Caused by Design Error | /01T-0:on 800404,investigation Revealed That Several vendor-designed Pipe Supports Were Designed Utilizing Manufacturer Std 0.25-inch U-bolt Which Overstressed During Seismic Event.Caused by Design Error | | | 05000327/LER-1980-021-03, /03L-0:on 800308,while in Mode 6,flow Rates from Auxiliary Bldg Ventilation Sys Flow Rate Monitor Were Not Recorded for Three Shifts.Caused by Misreading of Notation Used in Surveillance Instruction.Temporary Change Issued | /03L-0:on 800308,while in Mode 6,flow Rates from Auxiliary Bldg Ventilation Sys Flow Rate Monitor Were Not Recorded for Three Shifts.Caused by Misreading of Notation Used in Surveillance Instruction.Temporary Change Issued | | | 05000327/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000327/LER-1980-022-03, /03X-2:on 800318,sample Isolation Valves 1-FCV-90-108,109,110,114,115 & 116 Closed,Isolating Radiation Monitors.Caused by Isolation of Nonessential Control Air to Sample Valves.Valves Reopened | /03X-2:on 800318,sample Isolation Valves 1-FCV-90-108,109,110,114,115 & 116 Closed,Isolating Radiation Monitors.Caused by Isolation of Nonessential Control Air to Sample Valves.Valves Reopened | | | 05000327/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000327/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000327/LER-1980-023-03, /03L-0:on 800402,during Surveillance Testing, Diesel Generator 2A-A Feedbreaker Failed to Close.Caused by Power Contacts Being Dirty.Power Contacts Cleaned | /03L-0:on 800402,during Surveillance Testing, Diesel Generator 2A-A Feedbreaker Failed to Close.Caused by Power Contacts Being Dirty.Power Contacts Cleaned | | | 05000327/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000327/LER-1980-024-03, /03L-0:on 800331,flow Switches on Radiation Monitors ORM-90-212 & 122 Found Inoperable.Caused by Small Particulate Matter in Monitored Liquid.Design Change Request Initiated.Weekly Preventive Maint Program Established | /03L-0:on 800331,flow Switches on Radiation Monitors ORM-90-212 & 122 Found Inoperable.Caused by Small Particulate Matter in Monitored Liquid.Design Change Request Initiated.Weekly Preventive Maint Program Established | | | 05000327/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000327/LER-1980-025-03, /03L-0:on 800313 W/Unit 1 in Mode 6,O-RM-90-225 Condensate Demineralizer Effluent Line Was Taken Out of Svc for Maint.Caused by Weak Transistor.Transistor Replaced & Monitor Returned to Svc | /03L-0:on 800313 W/Unit 1 in Mode 6,O-RM-90-225 Condensate Demineralizer Effluent Line Was Taken Out of Svc for Maint.Caused by Weak Transistor.Transistor Replaced & Monitor Returned to Svc | |
|