Similar Documents at Hatch |
|---|
|
LER-1980-008, /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3211980008R03 - NRC Website |
|
text
U.S. NUCLEAR REGULATORY COW%StON NRC F.JRM 366 (7 7'/)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l 6
l0 l1l l G l A l E l I l H l 1 l@l 0 l 0 l-l 0 l010 l 0 l0 l-1010 l@l411 l1 (1 l1 l@l l
l@
LICENSE NUYWEH JS 26 LICENSE TYPE JO ST LAi Sd i
7 8 9 LICEN5EE CODE le 15 Scn%lLl@l 0l5l0l010l3l2l1 )@l 0 l1 l1151810 l@l0 l1 1310 810 l@
con'T 66 63 EVENT DATE le 75 REPORT DATE 83 O
i, 6u 61 OOCKE T NUMBER 1
8 EVENT DESCRIPTION AND PROBABLE CONSEoVENCES h Io 121 l Uuring steady state power coeration of 2344 MWt, secondary containment inteority was I
10131 I momentarily violated w%n plant personnel inadvertently opened the 164' elevation re-l
] actor building and turbine building airlock doors simultaneously.. The doors were l
o 4 Licensed operations personnel verified that the doors had been g
1 o I s 1 I closed immediately.
f o 161 I re-closed and that secondary containment integrity was maintained by at least b inch l
This is a repetitive oc-l 71
- of water vacuum pressure to comply with Tech. Specs 4.7.C.2.
o currence; refer to R0 Report #50-321 '979-086.l 80 0 a i 7
8 9 DE CODE SUBC E COMPONENT CODE SUSCdDE SU E
l Sl Al@ [B_j@ l A l@ l Zi Zl Zl 21 Zl 2 @ [_Zj@ l Z @
g 18 19 20 7
8 9
10 11 12 13 RE\\ r sN OCCU R H E NCE REPORT SEQUENTIAL EVENT YEAR REPORT NO.
CODE TYPE NO.
O17,Rtg 18 l0 l l-l 1010l8l 1/l l 01 3 lLl
[-j l 0l LE R/RO
_2s 22 23 24 2u 21 28 29 30 3r 32 u
TAK N ACT O ON PL NT 1E H HOURS S6 IT D FOR UB.
S P LIER MA FACTURER lFjglFl@
l zig g@
l 0l 0l 0l 0[
lY l@
l Ni@
l Zl@
lZl9l9l9l@
33 34 35 36 31 40 43 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The cresent desian of the airlock in-1 1i 1011 The cause of this event was desian deficiency.
De-1 li ti l I terlock system will not prevent the simultaneous ocenina of both airlock doors.
e sign Chance Reauest 79-409 has been written to revise the oresent airlock inteirlockinal i 2 The electrical desian is comrlete, I
[TTTl I scheme to orevent the recurrence of this event.
(continuedf l
li l4 ) I but imolementation of Design Chance Request 79-409 is awaitina 80 7
8 9 DISCOVERY DESCR PTION ST A
% POWER OTHER STATUS 015 O RY W [_Ej @ l0l9l6l@l-NA l
l A lgl Personnel Observation l
8
'8 i
COOTENT I
ACTivin LOCATION OF RELE ASE
[ TIT) [_Zj @ j_Z_,j@l NA l
l NA l
RELE ASED OF RELE ASE AMOUNT OF ACTIVITY j
PERSONNEt ExPOsOES i
NUMBER TYPE DE SCRIPTION j
[TITl l 010l Ol@[Zj@l NA B0 PERSONN E L INJURIES OEsCRiPTiON@
j NuMsER NA l010lOl@l 80 1 s 7
8 9 11 12 wPio' o=>=o '* " @
l.938 034 1
NA LZj@l go t 9 8 O 07 C
RC UsE ONI Y 7
8 9 10 NA l
lllllllllllllj ISSUE @DE CRIPTION L_Rj l
8u..
2 o 68 69 C. L, Coogin, Supt. Plt. Ena. Serv, pgang W49WM
{
7 8 9 10 NAME OF PREPARER
f Georgia Power Company Plant E. I. Hatch
- 'Baxley, Georgia 31513 Event Description and Probable ConsequencesThere were no effects on public health or safety due to this event.
Cause Description and Corrective Actions
(' cont!ned) delivery of cable, hardware, and electrical parts, and completion of the archit-ectural design.
k o
9 9
9 e
~
4 1938 035
LER 7:
go-??1/1090 n09 Licensee:
Georgin Powe" Company Facility Nane:
Edwi.n I.
Hatch Docket f:
90-??1
Narrative
Report for LER 90 191/1090-009 On 1-19 80, at Oa??
hou-s while steady state one"ation, secondary containnent i n t e cr r i t y
'J a s nonenta"ily viointed when maintenance oe"sonnel inadvertent 1.y coened the 1'h' alevation reacto" building to contaol. huilding nialock doors RhD and 241 simultaneously.
The doo"s aemained opan for less thnn ten seconds as indicated hv the 4t"stion of the ala",
sounded in the cont"o1
" con.
Licensed operations ceasonnel v i. s u a l l y inspected the airlock doors to insure that thev had been properly aeolosed and that secondaav containment integrity was restored.
Licensed oceantions personnel also verifte' that secondaay containme'it intcgaity was rn a i n t a i n e d hv greater than or equal to 1/4 inch water vacuum orestare to comolv with Tech Spacs u.7.C.2, Secondary Containment, Su rve il l a n c e After Integrity Violated.
This type of v i o la t i. o n of seconda"y containment integatty has hacoened numerous times in the nast and
- 5. s caused hv the inadequate design of the present airlock interlock systen.
Althotagh plant personnel have been instructed in the p"opea usage of the a t a l. o c k doors, the o"esent atriock inte" locking scheme does not orovide a rapid enough response to prevent the simultaneous ' opening of two airlock doo"s.
Desico Change Request 70 400 has been written to revise the nresent atriock interlocking scheme,thereby alleviating the recuarence of this event.
This modifiention util assign a orio"ity to one of the doors and the "evised interlocking scheme will be enabled before the first doon is allowed to ooen.
The oroblem co secondaav containment integrity violations at r
the airlocks is inherent to both Hatch Unit 1,
Docket f90 1?1 and Hatch Unit ? Docket f50-366 Desien Change Request 7 n !! n o will he implemented for both Hatch Unit 1 and Hatch Unit ?
a t r i o c k' d o,o r s.
The p"esent ta"get date for conoletion of this
.nodification wi.11 he ielavad several nonths due to the lack o'
necessaay material.s.a n d incompleta a"chitectual r esign.
%\\
21s D
3 1gb 1938 036
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000321/LER-1980-001-01, /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | | | 05000366/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000366/LER-1980-001-03, /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | | | 05000321/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000321/LER-1980-002-03, /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | | | 05000321/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000366/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000366/LER-1980-002-01, /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | | | 05000366/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000366/LER-1980-003-03, /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | | | 05000321/LER-1980-003-03, While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | | | 05000321/LER-1980-003, Forwards Revised LER 80-003/03X-1 | Forwards Revised LER 80-003/03X-1 | | | 05000321/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-004-03, /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | | | 05000366/LER-1980-004-03, /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | | | 05000366/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000321/LER-1980-005-03, /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | | | 05000366/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000366/LER-1980-005-03, /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | | | 05000321/LER-1980-006-03, /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | | | 05000321/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000321/LER-1980-007-03, /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | | | 05000321/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | | | 05000366/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000366/LER-1980-008-03, While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | | | 05000366/LER-1980-008, Forwards LER 80-008/03L-1 | Forwards LER 80-008/03L-1 | | | 05000321/LER-1980-008-03, /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | | | 05000321/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000366/LER-1980-009-03, /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | | | 05000321/LER-1980-009-03, /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replace | /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replaced | | | 05000366/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000321/LER-1980-010-03, /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010-03, /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | | | 05000321/LER-1980-011-03, /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | | | 05000366/LER-1980-011-03, /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | | | 05000321/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000366/LER-1980-012-03, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | | | 05000321/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000366/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000321/LER-1980-012-03, /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | | | 05000321/LER-1980-013, Forwards Updated LER 80-013/03X-1 | Forwards Updated LER 80-013/03X-1 | | | 05000321/LER-1980-013-03, Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | | | 05000366/LER-1980-013-03, /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | | | 05000366/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000366/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000366/LER-1980-014-03, /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | |
|