LER-1979-011, /01T-0:on 790804,while Proceeding to Cold Shutdown Condition,Containment Integrity Was Briefly Violated.Caused by Faulty Interlock Allowing Inside Containment Door to Open When Outside Door Was Already Open |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2661979011R01 - NRC Website |
|
text
_..... _ _ _
(7 77)
LICENSEE EVENT REPORT CONTROL BLOCK l
}
l l
l lh PLEASE PRINT OR TYPE ALL REQUIRED INFCRMATION) 1 6
W l Il Pl B l H 1l@l 0 l 0 l -l 0 l 0 l 0 l 0 l 0 l -
0 l 0 l@l 4 l1 l1 l1 1l@l l
l@
o i
7 d 9 UCENSEE CODE 14 tt UCENSE NUMBER 25 26 L8 CENSE TYPE Jo
$ 1 C A T $a CON'T SZRC LLBI I5I I of of 2 e i s l@l 0 l 810 ] 4l 7 l 9 )@l 0 l 811_l 4 l 7 9l@
o 7
8 60 61 DOCK ET NUMBER ed 69 EVENT DATE 74
'S REPORT DATE 80 EVENT OESCRIPTION AND PPOBABLE CONSEQUENCES h At 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />, 8-3-79, while proceeding to a cold shutdown condition I
o 2
with reactor coolant system at 393 psig and 343 degrees, containment I
o 3
[ integrity was briefly violated.
The violation occurred when the inside I o
4
- containment door was opened with the outside door already open.
Con-l o
o 6
f tainment integri ty was quickly reestablished by shutting the inside doorp lTS 15.3.6.A.a requires that containment integrity not be violated unlessl o
7
,the reactor is in a cold shutdown condition.
l o
g 7
8 9 80 SYSTEM
CAUSE
CAUSE C OY P.
VALVE CODE CODE SU3 CODE COMPONENT CODE SUSCODE SUSCODE lS l A @ {@ l B l@ lM E l C l F l U lN l@ l Z l@ l Zl @
O 9
1 4
9 10 11 12 13 18 19 20 SEQUENTI AL OCCURAENCE REPORT REVISION LER RO EVENTvfAA REPOR T NO.
COCE TYPE NO.
@,at,7g l2 '7lQ l-l l0 1l1 l y
10l1l l T_l l-01 u
23 24 26 27 29 29 30 31 JJ A Tl N ON PLANT V TH D HOURS 22 5 8 ff D FOR h B.
SL PP LI E R M ANUF ACTURE R TAKE" gZ l @
lZl@
lZl@
l0l0l0 0l lY @
Y@
Nl@
l P l 2 l 7 l 0j@
lB l 33 J4 35 3#
40 el 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS
]Ordinarilv the inside and outside doors are prevented from being opened l o
,, j,, simultaneously by a mechanical interlock.
In this instance the inter-I lock failed due to a roll pin falling out of a connecting rod in the j
mechanism.
The interlock was repaired and satisfactorily tested along l
- with a qualifying air test of the personnel hatch by 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />,8-4-79 l
7 8 9 80 STA $
% POWER OTHER STA TUS DISCO RY DISCOVERY QESCRtPTION [GJ@ l0 l 0 l 0l@l NA l
W @l NA l
t 5
44 45 46 80 AMOUNT OF ACTIVITY @ l LOCATION OF RELEASE @
RELEASCO OF RELEASE L;j @ l z l@l NA l
NA l
i e
PERSONNEL E XPOSL ES NUMBER TYPE D E SCRIP TION 1010l01@lZl@l J
NA i
T PERSONNEL INJURIES NUM8ER
DESCRIPTION
l 0 l 0l 0l@l J
NA i
4 7
8 1 11 12 i
80 LOSS OF OR D AMAGE TO F ACILITY TYPE D E SC RIPTION NA 7009120 l
IZl@l 3
7 4 3 10 80 PU B L iCI TY N AC USE ONLY ISSUED
DESCRIPTION
lNlbl NA lllIlllIll llI 2
o 7
8 9 to 68 69 60 ;
C*
4I4!277~2011 NAME OF PREPARER PHONE:
~
ATTACHMENT TO LICENSEE EVENT REPORT NO. 79-011/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 At 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />, 08/03/79, while proceeding to a cold shutdown condition with the residual heat removal system lined up to the reactor coolant system (reactor coolant pressure 393 psig, temper-ature 343*F), containment integrity was briefly violated.
The violation occurred as the result of an interlock's failure in the containment personnel hatch operating mechanism which allowed the inside door to be opened with the outside door already open.
Containment integrity was quickly reestablished by shutting the inside door after ambient and in-containment pressures equalized.
Two persons were at the outside containment door at the time of the incident and two by the inner door.
No one was injured in the event although one of the persons standing by the outer door was drawn into the air lock by the inrushing air, and was knocked down in the process.
Ordinarily the inside and outside doors are prevented from
~
being opened simultaneously by a mechanical interlock.
In this instance the interlock failed dae to a roll pin falling out of a connecting rod in the mechanism.
Apparently, the roll pin had loosened from use.
The interlock was repaired and satisfactorily tested along with a qualifying air test of the personnel hatch by 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, 08/04/79.
To prevent recurrence, high strength tape has been strapped around the connecting rod over the roll pin as a temporary measure, pending review of alternatives by the Manager's Supervisory Staff.
e,,
4 q
J
.c
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000301/LER-1979-001-01, /01T-0 on 790219:w/unit off-line & at 10% Steam Flow,A&B Main Steam Stop Valves Failed to Close.Caused by Deposits on Valve Shafts or Hardening of Gland Packing. Valves Were Exercised & Packing Adjusted | /01T-0 on 790219:w/unit off-line & at 10% Steam Flow,A&B Main Steam Stop Valves Failed to Close.Caused by Deposits on Valve Shafts or Hardening of Gland Packing. Valves Were Exercised & Packing Adjusted | | | 05000301/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000266/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000266/LER-1979-001-01, /01T-0 on 790219:inadvertent Radioactive Gaseous Release Occurred While Returning K10B Cryogenic Sys Gas Compressor to Svc.Caused by Operator Failure to Ensure Valve Was Closed.Procedures Restressed | /01T-0 on 790219:inadvertent Radioactive Gaseous Release Occurred While Returning K10B Cryogenic Sys Gas Compressor to Svc.Caused by Operator Failure to Ensure Valve Was Closed.Procedures Restressed | | | 05000301/LER-1979-002-03, /03L-0 on 790227:during Biweekly Test of a Reactor Trip Breaker,Several Seconds Elapsed Following Trip Signal Before Breaker Tripped.Caused by Faulty Reactor Trip Relay,Westinghouse BFD31.Relay Replaced | /03L-0 on 790227:during Biweekly Test of a Reactor Trip Breaker,Several Seconds Elapsed Following Trip Signal Before Breaker Tripped.Caused by Faulty Reactor Trip Relay,Westinghouse BFD31.Relay Replaced | | | 05000301/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000301/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | | | 05000301/LER-1979-006-01, /01T-0 on 790711:during Insp & Repair of Main Feedline,Confirmed That Branch Connection of Auxiliary Feedline Was Not Mfg Per Design Requirements.Branch Connections Replaced by Weldolets | /01T-0 on 790711:during Insp & Repair of Main Feedline,Confirmed That Branch Connection of Auxiliary Feedline Was Not Mfg Per Design Requirements.Branch Connections Replaced by Weldolets | | | 05000301/LER-1979-007, Forwards LER 79-007/01T-0 | Forwards LER 79-007/01T-0 | | | 05000301/LER-1979-007-01, /01T-0:on 790929,main Steam Line B Isolation Valve Failed to Close During 20% Steam Flow,W/Unit Off Line.Caused Not Stated.Packing Was Loosened & Atwood Morrill Reverse Swing Check Valve Closed | /01T-0:on 790929,main Steam Line B Isolation Valve Failed to Close During 20% Steam Flow,W/Unit Off Line.Caused Not Stated.Packing Was Loosened & Atwood Morrill Reverse Swing Check Valve Closed | | | 05000301/LER-1979-008-03, /03L-0:on 791210,charging Pump a Taken Out of Svc Due to Observed Leakage in Discharge Manifold Area.Caused by Valve Seat Failure Possibly Resulting from Normal Fatigue.Valve Seat Replaced | /03L-0:on 791210,charging Pump a Taken Out of Svc Due to Observed Leakage in Discharge Manifold Area.Caused by Valve Seat Failure Possibly Resulting from Normal Fatigue.Valve Seat Replaced | | | 05000266/LER-1979-008, Forwards LER 79-008/01T-0 | Forwards LER 79-008/01T-0 | | | 05000266/LER-1979-008-01, /01T-0 on 790502:remote Possibility Exists for Simultaneous Safety Injection in Both Units,Which Could Result in Emergency Diesel Overloading.Pressurizer Logic & Power Supplies Changed | /01T-0 on 790502:remote Possibility Exists for Simultaneous Safety Injection in Both Units,Which Could Result in Emergency Diesel Overloading.Pressurizer Logic & Power Supplies Changed | | | 05000301/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000266/LER-1979-009, Forwards LER 79-009/01T-0 | Forwards LER 79-009/01T-0 | | | 05000266/LER-1979-009-01, /01T-0 on 790510:during Hydrostatic Test of Fire Water Sys,Compression Fitting Failed.Caused by Broken Flange.Flange Replaced | /01T-0 on 790510:during Hydrostatic Test of Fire Water Sys,Compression Fitting Failed.Caused by Broken Flange.Flange Replaced | | | 05000266/LER-1979-010-01, /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed | /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed | | | 05000266/LER-1979-011, Forwards LER 79-011/01T-0 | Forwards LER 79-011/01T-0 | | | 05000266/LER-1979-011-01, /01T-0:on 790804,while Proceeding to Cold Shutdown Condition,Containment Integrity Was Briefly Violated.Caused by Faulty Interlock Allowing Inside Containment Door to Open When Outside Door Was Already Open | /01T-0:on 790804,while Proceeding to Cold Shutdown Condition,Containment Integrity Was Briefly Violated.Caused by Faulty Interlock Allowing Inside Containment Door to Open When Outside Door Was Already Open | | | 05000266/LER-1979-012-01, /01T-0 on 790805:primary to Secondary Leak Noted in Steam Generator A.Caused by Defective Tubes in Steam Generators a & B.Leaking & Defective Tubes Plugged | /01T-0 on 790805:primary to Secondary Leak Noted in Steam Generator A.Caused by Defective Tubes in Steam Generators a & B.Leaking & Defective Tubes Plugged | | | 05000266/LER-1979-012, Forwards LER 79-012/01T-0 | Forwards LER 79-012/01T-0 | | | 05000266/LER-1979-013-01, /01T-0:on 790830,Unit 1 Taken Off Line for Steam Generator primary-to-secondary Leakage Repair.Leakage Had Risen to 324 Gallons Per Day.Caused by 88% Defect Located Just Below Top of Tubeseheet.Tube Plugged | /01T-0:on 790830,Unit 1 Taken Off Line for Steam Generator primary-to-secondary Leakage Repair.Leakage Had Risen to 324 Gallons Per Day.Caused by 88% Defect Located Just Below Top of Tubeseheet.Tube Plugged | | | 05000266/LER-1979-013, Forwards LER 79-013/01T-0 | Forwards LER 79-013/01T-0 | | | 05000266/LER-1979-014-03, /03L-0:on 790912,charging Pump 1-P2B Found to Have Cylinder Block Crack.Caused by Pressure Spiking During Compression Stroke Following Hydrogen Separation During Suction Stroke.Cracked Block Replaced | /03L-0:on 790912,charging Pump 1-P2B Found to Have Cylinder Block Crack.Caused by Pressure Spiking During Compression Stroke Following Hydrogen Separation During Suction Stroke.Cracked Block Replaced | | | 05000266/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000266/LER-1979-015, Forwards LER 79-015/01T-0 | Forwards LER 79-015/01T-0 | | | 05000266/LER-1979-015-01, /01T-0:on 791002,during Normal Power Operation, Loose Tube Fitting Discovered on Common Line from containment-to-containment Pressure Transmitters.Cause Undetermined.Fitting Tightened | /01T-0:on 791002,during Normal Power Operation, Loose Tube Fitting Discovered on Common Line from containment-to-containment Pressure Transmitters.Cause Undetermined.Fitting Tightened | | | 05000266/LER-1979-016-03, /03L-0:on 791003,emergency Diesel Generator 3D Failed to Start for Monthly Tech Spec Test.Caused by Sticking of Woodward UG8 Dial Control Governor Load Limit Strap in Stop Position.Governor Replaced | /03L-0:on 791003,emergency Diesel Generator 3D Failed to Start for Monthly Tech Spec Test.Caused by Sticking of Woodward UG8 Dial Control Governor Load Limit Strap in Stop Position.Governor Replaced | | | 05000266/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000266/LER-1979-017, Discusses 791105 & 20 Meetings W/Nrc Re Info & Data on Steam Generator Tube Problems,Presented in LER 79-017/01T-0 on 791116.Certificate of Svc | Discusses 791105 & 20 Meetings W/Nrc Re Info & Data on Steam Generator Tube Problems,Presented in LER 79-017/01T-0 on 791116.Certificate of Svc | | | 05000266/LER-1979-017-01, /01T-0:on 791103,testing Revealed 131 Defective Tubes in a & B Steam Generators.Cause Under Investigation. Tubes Welded & Plugged | /01T-0:on 791103,testing Revealed 131 Defective Tubes in a & B Steam Generators.Cause Under Investigation. Tubes Welded & Plugged | | | 05000266/LER-1979-018, Forwards LER 79-018/01T-0 | Forwards LER 79-018/01T-0 | | | 05000266/LER-1979-018-01, /01T-0:on 791102,taping on Unit 2 Containment Motor Leads Did Not Meet Const Specs.Insp Showed Similar Situation W/Unit 2.Cause Not Stated.Unit 2 Motor Leads Retaped by 791109.Unit 1 Will Be Complete Prior to Startup | /01T-0:on 791102,taping on Unit 2 Containment Motor Leads Did Not Meet Const Specs.Insp Showed Similar Situation W/Unit 2.Cause Not Stated.Unit 2 Motor Leads Retaped by 791109.Unit 1 Will Be Complete Prior to Startup | | | 05000266/LER-1979-019-01, /01T-0:on 791107,while Filling Steam Generator a Secondary Side W/Water to Perform secondary-to-primary Leak Test,Dilution of RCS Occured.Caused by Leakage from Open Steam Generator Tube Falling Into Primary Outlet Nozzle | /01T-0:on 791107,while Filling Steam Generator a Secondary Side W/Water to Perform secondary-to-primary Leak Test,Dilution of RCS Occured.Caused by Leakage from Open Steam Generator Tube Falling Into Primary Outlet Nozzle | | | 05000266/LER-1979-019, Forwards LER 79-019/01T-0 | Forwards LER 79-019/01T-0 | | | 05000266/LER-1979-020-01, /01T-0:on 791115,during Refueling Shutdown,Anchor in Steam Generator a Auxiliary Feedwater Line Contained Const Deficiency.Caused by Improper Installation of Three Bolts in Anchor Support Plate.Anchor Permanently Modified | /01T-0:on 791115,during Refueling Shutdown,Anchor in Steam Generator a Auxiliary Feedwater Line Contained Const Deficiency.Caused by Improper Installation of Three Bolts in Anchor Support Plate.Anchor Permanently Modified | | | 05000266/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | | | 05000266/LER-1979-021, Forwards LER 79-021/01T-0 | Forwards LER 79-021/01T-0 | | | 05000266/LER-1979-021-01, /01T-0:on 791211,during Normal Operation, Increasing Steam Generator Primary to Secondary Leakage Noted.Caused by Leaking Tube in Steam Generator B.Plugs Welded & Repaired | /01T-0:on 791211,during Normal Operation, Increasing Steam Generator Primary to Secondary Leakage Noted.Caused by Leaking Tube in Steam Generator B.Plugs Welded & Repaired | | | 05000266/LER-1979-022-01, /01T-0:on 791226,safety Injection Pump B Failed to Start During Operational & Sys Leak Test.Caused by Incomplete Breaker Closure.Breaker Closed & Returned to Svc Following Cold Shutdown | /01T-0:on 791226,safety Injection Pump B Failed to Start During Operational & Sys Leak Test.Caused by Incomplete Breaker Closure.Breaker Closed & Returned to Svc Following Cold Shutdown | | | 05000266/LER-1979-022, Forwards LER 79-022/01T-0 | Forwards LER 79-022/01T-0 | |
|