text
.
=se
. me w =wc6 u seov u toa,ca o=
- *38 a.NIlovle case eso 3 eo. dew
"*"8"'*
UCENSEE EVENT REPORT (LER)
.aciuv =ame ne suc= ' ama a ai
.= n Shoreham Nuclear Power Station Unit #1 oisloloIo131212 1 lor l0l2 vita RBCLCW Split Due to a low "A" Head Tank Level e ve=, o.,e...
i =,a.. i,
...os, u n i,.
os a eaciuv ee... so e.
mo=v-l one te.a veas "t',;;
',';;,*;,; wo t-ca, vena
'*'"a*=a Soc"' w'" " +
0l610l0t0l I l 0 l2 1l 2 86 Sl6 0l0l7 0l 0 0l 3 1l4 8l6 o,sioio,o,,,
',,,,,,,,,q,-
v=.esi.e.,iseu nioevaev =,toveniouias e=no.ise, i,c.
=4 ni.
5 y
a n...
n n,,,
m. i.,
e ea a as.inne n
no a nosaa..
- ni.i 6.. e,6 0, 0l 0
.o..
.,. a ne se.m.,n n..
m m,.n,
os,wan.
r..
=c,-
masi.num a sweini m t w en nai m eBW't,Het se 93.sH3Het es 99.KRHee. net
-.==
Se aes.H1n.6 80 flesHtHe's 80 73mHtHep 6aegesegg cogf 4Cf een Twie 6ee Hsi
=aws it 48.=o=3 *wb4 8
.aga cocia S 1,6 9,2,9,
,8,3,0,0 Robert W. Grunscien, Operational Co:pliance Engineer i
commuts o=s 6=e e a saen cowo=s=, eaituas eseca.eso nu t=4 ema, ns.
"$w'%'$6
"$'o",'!jj' cawse avstem cowo=t =t
"$*%'$8
"$7".'!!s' o
caves svstew cowo=s='
l i l I i i l i
I i !
l i l I
I i f I l l l
1 1 1 1 ! I
.w.
e.,
eu u. =,a6 as.o., e...evio n..
ege u.o=
~] vs e ti.
e..tetto sve.,sseo= e4 rei y a.o l
l l
awn a e,,.. =......
.,, a.. a. -,.., o e.
O ri February 14.'.
1906 at 0320 a nullt or the Reactor buildiriu Cionnd Loop Cca l i vin Water (RDCLCW) i rit u itu a cc i nor,t c ori f i n u r n t t ori occurred cue to a low low AbCLCW "h"
Hoad l a rip Level.
The c l a rit Waq i ri Onvr at ivria l Cr r.d i t t on L wit h the r iM o nwiten f re G5utdowre for a r. o u t i ra n a rid all roJn t rit o r t ed in tho I
corn.
An Fa u x pmerit O o,> r.a t or (EN wau pl ar i ren tho "G" Cool Pi.. o l Con 11riu Water beat C x t.ho r n r c in not l ov up, when the W'
PiCLEW l
h e a ti t a re level decenanod holow ttie
- .o t n o i n t o for ei tytten nellt.
The low lovel clarm did rot a nre trac t at e a t: d han s t ra:o b r.o n rouaired.
Btatirn proceduen T3.110.01, RDCLCW Gv ;t en Unora t teri, d i c' iet adequatoly athir evm tho r ea u i e ntr+nt u f r.r f t 11 A rtte the hont e s,r h a ri n e r n
.i nd w111 be rWicod to t ric i ud a the rio' e ma r v ut905 *o
') t 'P V o rs t tfM i,t r r' t e r d : ( ! Of th t *; fry (a nt.
U } ar,( P,a fi a q P U'u n t 4 Jab re: ? j f i g.r1 of the ovarit.uid the N7C w..is rmit t f i nd at 17.3/ per 10 C F R 'i.^. 7 J.
003 O 060314 ADO (Q.K 050003pg
)
g PUR mes e.. m.
is
).
ke..m.
wa wo..a
.e mo LICENSEE EVENT REPORT ILER) TEXT CONTINUATION
.peo.s e em.o ss eia.
es.*es eni l
"ga;;:-
2:.::
, p g*c l e le l 3l 2 l 2 Shoreham Nuclear Power Station l' nit #1 0l0 0l 2 or 0l2 01017 816 te ee m., n, On February la, 19ec at NG, a unlit of the Reactor Du11dino Cloned Looo Coolina Water (RDCLCW) inte its accident configuration occurred due to low low R L4CLCW "A"
Head Tank Level.
The olant wan in Operational Condition 5 with the modo twitch in Shutdown for an outate and all rodu inuorted in the cc.re.
An Ec.u t pment Courator (EO) was i nnt roct od by tho Watch Enoinoor t
to olace the "A"
Fuel pool Cooling Water (FPCW) Heat Exchancer in wot layun (the heat egenanger in normally out of servict' throunh
[
the first refueling outaqo).
lho FPCW heat exchancmr take".
nuction from the Reactor buildino Clound Lnoo Cooline Water (RDCLCW) Head Tank.
Takinq <snecial preenut iorm to ulnw1v fill up the heat exchangrer, the CO firnt cloned the vont F a crain valvs-On the heat oxchancer and therhoo the outlet valv' uhut.
Ho then croched opon the inlut valvo (acuron. 1/4 to 1/i; d a turn) until he felt flow throuuh the 1 a no.
H'* then ooeneJ the valvo to cocrouirnately half opon over a ton to fiftenn ra i nu t o curlod.
During thta
- tino, the lusol in the 40CLCW "n ' Head Tardi wau i
decreaning t,o l c w the lovN of the netooints for a
low lovel i
a ', a r n,
- ,u t the alaro did not a nnur,c l a t e.
The invol drorpod tr
{
the Low Lnw Lovel entooint and at OW8 the %CLCW nyt, ten unlit into it; arrident confluuratten
( "W v. i th ).
The nyt t ern tr.olatou into two nuparato, i nd e oe nt% nt 1< oos by a u t eala t s c a l l y c l os i n o t h n header croneconnect valveu on t *1 e tiutti.n and dir>rharne headtra of the NDCLCW Heat Eechannero and pumps on tho "F
s t dn.
I Thn inlot line to the hnnt um:bancer tu a four anch Itna anc the head tank in t><+ t n r; fod t h orair:h a two inch wator lino.
Therefore, i
1 water wn',
heAno taken out of the h"ad t a n te f a t t i., - th n it was bein; realmend.
Onorowtmately t#o minutc%
ofter the HICLCW i
- uplit, the hund t a nt' lovel retorrud to nor a 1
.4 id the
%CL EW ny n t orn wem r o t u r nettj tu i t t.
notr..al conf 1queatton orior tti the event.
l Thorn we no unrety *ar.nir a r a r.c o ta thn event.
Thp RDCLCW e v t. t o r i oonrated an don i r no tt.
Corrators corried out all ronetrud Ac t lu fsM.
No ECC
% V ati t, f s )". wort
- cilalletrt0(*(' Or T Pq t d ) T t/d f G 7" (l ef i
ovont.
Plant Mano t orremt was not.tttod of the uvent and tho NT4 was n e t t t t en t at I?3A onc ! D f60. 7P.
Thore et no out hod to f111 the FTCW neat roachanopr.1 Adentifind in Gt at ion pracocturo GP IJ.110. V l,
RBCLJW Uyrtem C:.er a t ion.
O orocorhire chance h.n boon initintod tn i nc l ud s.
tho mntin; and
{
I I 1 I I n Ej QI IhDSf 8 hkAt
$$ H t h a n U f
- f' *u (o p r 7 V o r i', r DC u f F* Df e"U.
I h t*
O100{
Mc rniger han d i r r, t r t' that a r o,. tJ W hn per f es r re ed of all M itton Pr ocodoret uund for tho s o-n t 4 n t,
fi!Itnt and draintno nf nafotv r o l a t **d o p u l otr.p n t,
t r.. 4 % u c ts.
tout hropor vemt i no, f illin; and dra i n t riq as m hiuvud. In s;. 1 d i t t o r,.
thu hnad t a n t<
l< H l t. v e l n w i t tm o mm 1 m mon _, _ m..
..t see3 a.ee Gee
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000322/LER-1986-001, :on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements |
- on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements
| | | 05000322/LER-1986-002, :on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired |
- on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired
| | | 05000322/LER-1986-004, :on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging |
- on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging
| | | 05000322/LER-1986-005, :on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency |
- on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency
| | | 05000322/LER-1986-007, :on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised |
- on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised
| | | 05000322/LER-1986-008, :on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised |
- on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised
| | | 05000322/LER-1986-009, :on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed |
- on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed
| | | 05000322/LER-1986-011, :on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220 |
- on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220
| | | 05000322/LER-1986-011-02, Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | | | 05000322/LER-1986-012, :on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication |
- on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication
| | | 05000322/LER-1986-013, :on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated |
- on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated
| | | 05000322/LER-1986-015, :on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed |
- on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed
| | | 05000322/LER-1986-016, :on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines |
- on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines
| | | 05000322/LER-1986-018, :on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised |
- on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised
| | | 05000322/LER-1986-019, :on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised |
- on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised
| | | 05000322/LER-1986-020, :on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector |
- on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector
| | | 05000322/LER-1986-021, :on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves |
- on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves
| | | 05000322/LER-1986-022, :on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps |
- on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps
| | | 05000322/LER-1986-023, :on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised |
- on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised
| | | 05000322/LER-1986-024, :on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress |
- on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress
| | | 05000322/LER-1986-025, :on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples |
- on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples
| | | 05000322/LER-1986-026, :on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised |
- on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-027, :on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer |
- on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer
| | | 05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced |
- on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
| | | 05000322/LER-1986-030, :on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists |
- on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-031, :on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities |
- on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities
| | | 05000322/LER-1986-033, :on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve |
- on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve
| | | 05000322/LER-1986-034, :on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down |
- on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000322/LER-1986-035, :on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc |
- on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc
| | | 05000322/LER-1986-036, :on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised |
- on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised
| 10 CFR 50.73(a)(2)(i) | | 05000322/LER-1986-037, :on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished |
- on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished
| 10 CFR 50.73(a)(2)(i) | | 05000322/LER-1986-039, :on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated |
- on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-040, :on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced |
- on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-042, :on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010 |
- on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010
| | | 05000322/LER-1986-044, :on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal |
- on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-045, :on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled |
- on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|