text
,
COOPER NLACLE AR $T ATION
"^ "
Nebraska Public Power District CNSS923542 February.'10, 1992 U.S. Nuclear Regulatory Commission Document Control Desk-l; Washington, D.C.
20555
Dear Sir:
Cooper Nuclear Station-Licensee Event Report 92 001, Revision 0, is being forwarded as an attachment to this letter, Sincerely, e
sv
. M..Meacham ivision Manager off Nuclear Operations Cooper Nuclear Station JMM/bjs Attachment-cc:
R; D. Martin G. R. Horn R; E.:Wilbur V. L.: Wolstenholm D. A. Whitman-INPO Records Center-
'NRC Resident inspector R.-'J.-Singer CNS Training CNS Quality Assurance t
.... e, ( v s.
1 Q U-Le.A. '
g)
I e9202140209 920,210-r
s c.
,,%Bf v = m tan n autaroa,rOMMin.O.,
AFPROYt D OWS 8:0 atte416e LICENSEE EVENT REPORT (LER)
,ACetiu =AME m con s i avMet a m raat m Cooper Nuclear Station o l6 l 0 l0 lo l2 l 9l8 i lorl nj 3
" " ' " ' Group 3 liigh Flow Isolation While Shif ting fleactor Water Cleanup Pumps As A Ilesult Of An Insufficiently Throttled Yalve EvthT DAT$ ($1 4t h WuM.E n (Si REPORT Datt IF)
OTHth f ACILITitt 4WyOtVID tel MOk1HI DAT ttAM VtAM
* N '4 7f[gj MOhTH DAY TLAR D ACiUT V h AMES DOC ltI NVMDE Mill n
0 15101010 1 I l 0l 1 1l1 9
2 9l2 0l0l1 0l 0 0l2 1l0 9l 2 o isio io, o, i i
~
tHee at, Oar.. v.Mitit a Pua vA=, to rHL movinMt=n o, i. c. i rew
.,.A,,.u. + n n i
N n
,w p easwmHi g
w,si.,c, Hot
,3,,,,,
so ni.im w. wmm tttu.i i i 0i 0 m.
n-.,.
,....i o.,
g=,y,,.g.,g
. mmu
>. mmh,
..,,i.,mi H A,
M 4061sHith.I 6018ial(thel 60.73.H2H.thMB)
H 4066.H1H.1 60 79taH31Dul M,34.HtHal 4SCthllt CONTACT 904 THit 48 A uti NAME 18ttPHOht NUM04M Amt A CODE John it. Myers 41012 812 l 51-13 l811 l 1 COMPttit 04E teht 8On 4 ACH COMPONtat 8:Altunt OtschistD IN TH19 AGPORT 1931 gjf "fn$ pnp tae (Av84 BVITEM CDM*0htNT
"([gf
}"g hemN D
CAust lysitu COM*0NthT l
l i I I I l I
f I i 1 1 I l
I l l i l I i
l l i i l i SUPP4tMikTAL AIPORT ikPGCitO (til MONTH DAV VtAM SUO M'S$'ON
~] vta ru,....
n,serro svewmO= ca res T] r.o l
l l
tu t n &C e <m,,,...
.,....,,...+ <s
,v,..,u.m.., n e i on January 11, 1992, with the plant in normal power operation, the B Reactor Water Clean Up (RWCU) pump was started to transfer operation from the A to the B RWCU i
pump.
Shortly after starting the pump, the licensed operatar observed the RWCU high flow alarm, and then the closure of the RWCU Primary Containment isolation valves and actuation of the Primary Containment Group 3 indication lights. The RWCU Filter /Demineralizers had been previously removed from service, and the bypass valve,_RWCU MOV H074, was throttled to maintain normal pump discharge pressure.
The isolation resulted from insufficient throttling of the RWCU MOV M074 valve.
This allowed the combined flow from both pumps to exceed the setpoint of the high flow isolation switch. With the Filter /Demineralizers isolated, system flow indication is not available in the Control Room. The system operating procedure will be revised to direct the use of local flow indications when shifting pumps with the Filter /Demineralizers isolated.
f l-t 1.".'il*"" "'
pge vi.oes.awwasivw s avans m.,
LICENSEE EVENT REPORT (LER)
E's',,'!,'l#2' M)",g,",*a"j',,,ff'l*J.','N"w'u's i
TEXT CONTINUATlON
!W",,'",L* ';F'Rif,raf'ai',""*/l,l,f ',".' E,Mi'A i
c'1 fpa n
( t0 l' O 60 6
P APL wo, he Of WANA04 Mt N1 Assu suoGt,, W A.M640 TON. (sc 19h03 M8MI F 86d8'O IH 4eceLt t Wusie tM Las LIN NUM88AiW PAG 8 Gl
[
0'.7, '."
*J ".O Cooper Nuclear Statinn 0 l6 l0 l0 l0 l 2 l 9l 8 9l 2 0l0l1 0l 0 0l 2 0F 0 l3 itxtsa.-.
. o w
,n*cr m u nn i
A.
Event Descrintion On January 11, 1992, with the plant in normal power operation, the B 4
Reactor Water Clean Up (RWCU) pump was started to transfer operation from the A to the B RWCU pump to perform post maintenanco testin5 of the i
B pump.
Shortly after starting the pump, the licensed operator observed the RWCU high flow alarm, and then the closure of the Primary Containment RWCU isolation valves and actuation of the Primary l
Containment Group 3 indication lights. The RWCU Filter /Demineralizers i
had been previously removed from service, and the bypass valve, RWCU MOV.M074, was throttled to maintain normal pump discharge pressure.
t B.-
Plant itAtua.
The plant was in normal power operation at approximately 100 percent power, with the Reactor at 1000 psig.
The RWCU Filter /Demineralizers were removed from service, and the bypass valve, RWCU MOV M074 throttled open.
The A RWCU pump was in operation.
C.
Basis for Renort I
Unplanned actuation of the Primary Containment Group 3 1 solation, an Engineered Safety Feature (ESP), reportable in accordance with 10CFR50.73(a)(2)(iv).
D.
Ganig Procedures less than adequate. The isolation resulted from insufficient throttling of the RWCU MOV M074 valvo.
This allowed the combined flow from both pumps to exceed the setpoint of the isolation switch.
The cause of the insufficient throttling of the RWCU MOV M074 valve is the lack of Control Room flow indication when the Filter /Demineralizers are removed from service. Valvo position was set using the available pump discharge pressure indication.
E,
Safety significance
The RWCU high-flow isolation serves to protect against the consequences of significant leakage from the RWCU system. The automatic closure of the RWCU inlet isolation valves upon actuation of the high flow isolation protects the core by preventing continued inventory losses through a break.
In this event, an RWCU break had not occurred.
Consequently. actuation of the Croup 3 isolation was not required for core protection. Upon sensing a high flow signal, the isolation occurred as' designed.
hMC F.rse 3s44 4649i
.r-,
..m..
.~-,-.m._,
.- ~., -, -
g.
u.~ ucas=Usavi,4was
,,,,,,,,,,,,,,,,y,,
...ae..m LICENSEE EVENT REPORT (LER)
!!,'!",?.'!,%fJ'?!;! l', ;' "o"',',!!'*),'s,'"j MA' !!?."dC TEXT CONTINUATlON
%1"A"?'n';!'.'"LZi &E"f'.* 1!,10'l# s',".' "'Ri fA i.'.?"!','TJJ?","an.u't",t,./;;;=?tMTR t#?.'i Of WAhAC.t MLNI AND lsGi f. n A6HINCs1UN, DC #0h03 P ACILily em444 6II LKacttt NuutIn Igl L 4 h luuliett M 461 9A04 (31 weIn sN Cooper Nuclear Station 0 l6 l0 l0 l0 l 2 l 9l 8 9l 2 0l0ji 01 0 013 Of 0 l3 nn su o.=, e.~ n w, em-w nec m seu omn F.
Safety Implications The effect of a high flow isolation at other plant conditions would not be significantly different.
In the event of an isolation with the RWCU pumps operating, the pumps automatically trip.
Removal of the RWCU System from operdtion has minimal safety implications.
s G.
Corrective Action
The Group 3 isolation was reset, and the B pump placed into operation.
The system operating procedure will be revised to direct the une of local flow indications when shifting pumps with the Filter /
Demineralizers isolated.
H.
Eigilar Events None - previous high flow actuations of the Group 3 isolation circuitry have been caused by flashing of the hot fluid at the pump suction during plant cooldown or as a result of volds within system components.
The corrective actions for these events is not applicable to this occurrence, eve r sesA uso
,,. -. -. - _. -. - ~. -.,. - - -...,
,. ~,,
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000298/LER-1992-001, :on 920111,both Pumps Exceeded Setpoints of High Flow Isolation Switch.Caused by Insufficient Throttling of Valve.Group 3 Isolation Was Reset & B Pump Placed Into Operation |
- on 920111,both Pumps Exceeded Setpoints of High Flow Isolation Switch.Caused by Insufficient Throttling of Valve.Group 3 Isolation Was Reset & B Pump Placed Into Operation
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000298/LER-1992-002, :on 920203 & 4,reactor Vessel Water Setpoint Inaccuracy Resulted from Reference Leg Temp Effects That Had Not Been Correctly Addressed.Setpoint Calculations Were Performed |
- on 920203 & 4,reactor Vessel Water Setpoint Inaccuracy Resulted from Reference Leg Temp Effects That Had Not Been Correctly Addressed.Setpoint Calculations Were Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1992-003, Provides Supplemental Info on Rev 0 to LER 92-003 Re Degradation in safety-related Battery Cells,Per NRC Info Notice 89-017.Existing Monitoring of Battery Cells Provides Ample Advanced Notification of Need to Replace Cells | Provides Supplemental Info on Rev 0 to LER 92-003 Re Degradation in safety-related Battery Cells,Per NRC Info Notice 89-017.Existing Monitoring of Battery Cells Provides Ample Advanced Notification of Need to Replace Cells | | | 05000298/LER-1992-004, :on 920210,Group 3 Isolation Occurred on High Reactor Water Cleanup Temp.Caused by Failure to Maintain Interim Corrective Actions.Operating Procedures Revised & Isolation Was Reset |
- on 920210,Group 3 Isolation Occurred on High Reactor Water Cleanup Temp.Caused by Failure to Maintain Interim Corrective Actions.Operating Procedures Revised & Isolation Was Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000298/LER-1992-005, :on 920325,RCIC Sys Declared Inoperable Due to Evidence of Water in Turbine Casing.Caused by Malfunctioning Turbine Exhaust Line Steam Trap.Steam Trap Removed & Cleaned & Internals Installed |
- on 920325,RCIC Sys Declared Inoperable Due to Evidence of Water in Turbine Casing.Caused by Malfunctioning Turbine Exhaust Line Steam Trap.Steam Trap Removed & Cleaned & Internals Installed
| | | 05000298/LER-1992-006, :on 920407,250-volt Battery Charger 1B Input Breaker Tripped.On 920408,250-volt Battery Charger 1A Tripped.Charger 1A Trip Due to Inadequate Preventive Maint. Relay K-3 Replaced & Calibr |
- on 920407,250-volt Battery Charger 1B Input Breaker Tripped.On 920408,250-volt Battery Charger 1A Tripped.Charger 1A Trip Due to Inadequate Preventive Maint. Relay K-3 Replaced & Calibr
| 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1992-007, :on 920420,Shutdown Cooling Isolation Valves Automatically Closed.Caused by Void Formation & Collapse in RHR Lines.Pressure in Vessel Was Increased & Isolation Valve Opened |
- on 920420,Shutdown Cooling Isolation Valves Automatically Closed.Caused by Void Formation & Collapse in RHR Lines.Pressure in Vessel Was Increased & Isolation Valve Opened
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000298/LER-1992-008, :on 920611,HPCI Sys Determined Inoperable When Pump Suction Valve from Torus Would Not Stroke Properly. Caused by Worn Bronze Stem Nut Internal Diameter Threads. Nut Replaced,Operator Reinstalled & Settings Adjusted |
- on 920611,HPCI Sys Determined Inoperable When Pump Suction Valve from Torus Would Not Stroke Properly. Caused by Worn Bronze Stem Nut Internal Diameter Threads. Nut Replaced,Operator Reinstalled & Settings Adjusted
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000298/LER-1992-008-01, :on 920611,HPCI Sys Discovered Inoperable Due to Stem Nut Wear of Mov.Worn Stem Nut Replaced.Independent Failure Evaluation of Stripped Stem Nut Being Performed.W/ |
- on 920611,HPCI Sys Discovered Inoperable Due to Stem Nut Wear of Mov.Worn Stem Nut Replaced.Independent Failure Evaluation of Stripped Stem Nut Being Performed.W/
| | | 05000298/LER-1992-009, :on 920611,noncompliance w/10CFR50 App R, Failure of Post Fire Safe Shutdown Equipment Discovered. Caused by Inadequate Alternate Shutdown (ASD) Design Criteria.Asd Procedures Revised |
- on 920611,noncompliance w/10CFR50 App R, Failure of Post Fire Safe Shutdown Equipment Discovered. Caused by Inadequate Alternate Shutdown (ASD) Design Criteria.Asd Procedures Revised
| 10 CFR 50.73(a)(2) | | 05000298/LER-1992-010, :on 920621,during Performance of Surveillance Procedure CR HVAC Emergency Bypass Inlet Valve Failed to Actuate Correctly.Caused by Failure of Pneumatic Relay in Control Circuit.Temporary Mod Installed |
- on 920621,during Performance of Surveillance Procedure CR HVAC Emergency Bypass Inlet Valve Failed to Actuate Correctly.Caused by Failure of Pneumatic Relay in Control Circuit.Temporary Mod Installed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000298/LER-1992-011, :on 920625,two Installations of Thermo-Lag 330 Fire Barrier Matl,Used to Provide 1 H Protection,Identified Per Review of NRC Bulletin 92-001.Caused by Inadequate Qualification Testing.Restoration Underway |
- on 920625,two Installations of Thermo-Lag 330 Fire Barrier Matl,Used to Provide 1 H Protection,Identified Per Review of NRC Bulletin 92-001.Caused by Inadequate Qualification Testing.Restoration Underway
| | | 05000298/LER-1992-012, :on 920715,RCIC Sys Declared Inoperable Due to Intrusion Into Motor Operator.Caused by Packing Leak & Defective Conduit Shield.Mov Motor Replaced.Conduit Will Be Replaced During 1993 Refuleing Outage |
- on 920715,RCIC Sys Declared Inoperable Due to Intrusion Into Motor Operator.Caused by Packing Leak & Defective Conduit Shield.Mov Motor Replaced.Conduit Will Be Replaced During 1993 Refuleing Outage
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000298/LER-1992-013, :on 920730,error Discovered in Limiting Single Failure Assumption for ECCS Performance Analysis.Analysis in 1976 Contained Erroneous Evaluation of Eccs.Plant Mods Will Be Made to Restore Validity of Previous Assumptions |
- on 920730,error Discovered in Limiting Single Failure Assumption for ECCS Performance Analysis.Analysis in 1976 Contained Erroneous Evaluation of Eccs.Plant Mods Will Be Made to Restore Validity of Previous Assumptions
| 10 CFR 50.73(a)(2)(i) | | 05000298/LER-1992-014, :on 920731,HPCI Sys Declared Inoperable Due to Severe Oil Leak from Diaphragm Area of Mechanical/Hydraulic Overspeed Trip Auto Reset Control Assembly.Valve Assembly Replaced & HPCI Sys Tested Satisfactorily & Returned to Svc |
- on 920731,HPCI Sys Declared Inoperable Due to Severe Oil Leak from Diaphragm Area of Mechanical/Hydraulic Overspeed Trip Auto Reset Control Assembly.Valve Assembly Replaced & HPCI Sys Tested Satisfactorily & Returned to Svc
| | | 05000298/LER-1992-015, :on 920911,RV Level Fell Below Low Level Setpoint Initiating Group 2,3 & 6 Isolations.Caused by Procedures Governing Normal Shutdown of Plant.Procedure Changes & Training Will Be Provided |
- on 920911,RV Level Fell Below Low Level Setpoint Initiating Group 2,3 & 6 Isolations.Caused by Procedures Governing Normal Shutdown of Plant.Procedure Changes & Training Will Be Provided
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000298/LER-1992-016, :on 921001,identified Inadequate Isolation of DG 2 Differential Protection.Caused by Failure of Alternate Shutdown Design Review.Issued Change to Procedure for Operation of DG 2 from DG Room |
- on 921001,identified Inadequate Isolation of DG 2 Differential Protection.Caused by Failure of Alternate Shutdown Design Review.Issued Change to Procedure for Operation of DG 2 from DG Room
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1992-017, :on 921209,HPCI-MOV-MO058 Automatically Opened,Resulting in Closure of Pump Suction Valve from Emergency Condensate Storage Tank.Caused by Procedural Deficiency.Valves Realigned & Event Reviewed |
- on 921209,HPCI-MOV-MO058 Automatically Opened,Resulting in Closure of Pump Suction Valve from Emergency Condensate Storage Tank.Caused by Procedural Deficiency.Valves Realigned & Event Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000298/LER-1992-018, :on 921217,HPCI,RCIC & SLC Sys Declared Inoperable Due to Missed Insps of Pump Suction Piping.Caused by Lack of Scheduling Info for Class 3 Piping.Addl Enhancement Will Be Implemented for Program |
- on 921217,HPCI,RCIC & SLC Sys Declared Inoperable Due to Missed Insps of Pump Suction Piping.Caused by Lack of Scheduling Info for Class 3 Piping.Addl Enhancement Will Be Implemented for Program
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1992-019, Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo | Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo | | | 05000298/LER-1992-019-01, :on 921230,design Deficiency W/Ac Electrical Sys Confirmed When Single Nonaccident Event Could Result in Common Mode Failure of Both Dgs.Permanent Electrical Jumper Installed in Each Breaker Trip Circuit |
- on 921230,design Deficiency W/Ac Electrical Sys Confirmed When Single Nonaccident Event Could Result in Common Mode Failure of Both Dgs.Permanent Electrical Jumper Installed in Each Breaker Trip Circuit
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000298/LER-1992-020, :on 920130,containment Level Instruments Were Removed & re-installed Without Being Declared Inoperable. Caused by Personnel Failure to Follow Procedures.Operators Retrained |
- on 920130,containment Level Instruments Were Removed & re-installed Without Being Declared Inoperable. Caused by Personnel Failure to Follow Procedures.Operators Retrained
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) |
|