ML20071A433
| ML20071A433 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, 05000000 |
| Issue date: | 04/10/1981 |
| From: | PLG, INC. (FORMERLY PICKARD, LOWE & GARRICK, INC.) |
| To: | |
| Shared Package | |
| ML20071A408 | List: |
| References | |
| FOIA-82-626 PRA-810410-01, NUDOCS 8302240105 | |
| Download: ML20071A433 (66) | |
Text
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INCIAh PO RT PRA Pi:.pi-:,' the anc Garrick, /Inc.
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SEC\\ 12 wt TU 5T 5 TEM k'W s, A.
SUMr'RY 3
A.1 IN'RODUCTION The service water syster (SWS) acts as a heat transport medium, remcvinc heat f r ort the Comp 0aerts that it supDlies, anc transferring this heat te' the Hucser River. Tnis syster is necessary to remove reactor ce:ay. neat unce-LOCA concitiens anc mcs; transient events.
Tnis analysis it carriec out uncer the following cencitions:
Tne systerr is cuar.tified te the first isolatior valve capaLle of e
isc1ating a major component. The Component isolation valves are, ir.
trest cases, inclucec with the components which are isolatec; for exarsle, the cerocner.t cocling heat exchanger isolation valves are inclucec witr. tne corrpor.ert cocling heat exchangers.
e Opereter irteractior with tne SW5'tc correct ceficiencies or to tne syster following f ailure are cor.sicerec for tne mcce recever selecter swittn; anc, after the first hour, for errors in shifting-the syster lineup.
Frier te the ir.itiating event, twe service water purrps were e
su:clyir.g tne nuclear heacer anc twc service water purps were 9
sur:1ying the cer.venticr.a1 heater.
Success cf ine syster.is cefinec as twc service water pum s e
supclying ne nuclear heacer for -2a nours af ter the initiating event, anc one service water pump supolying the conventional heacer for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the initiating event.
A.2 RE SULTS a
Tat,le 1 surmtarizes the results obtained for the service water systerr analysis. Two cases f or electric power are presentec: "Nc Loss of.
Of f site Power" anc " Loss of Off site Power." Three bouncary conditions for each electric power case are analyzec:
" Power at all 480V t,uses";
"Less of power at a single 480V t,us"; anc " Loss of power at twe 480V tuses."
The analysis has revealec the following corrinent contributors to f ailure of tne SWS to supply water to time t a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Mean Cas'e 1 - No Loss-of Offsite Power a
Power at all'aE0V Duses.
Mispesitioned mode selector switch (96.4%)
2.2 x 10-3 e
8302240105 830113 PDR FOIA BLUM82-626 PDR 1
0861A040S81/1
D4.
4 Year.
Less cf po-er at a sincie 480V bus e
'Rencoc failure of-the pumps'selectec 3.9 x 10-3 to supply the nuclear neacer (63%)
e Mispcsitionec mode selector switch (37%)
=2.2 x 10-3 Less of poner at twc 480V buses-e.
-Failure of the pumps selectec to supply 1.0 the nuclear heacer due to insufficient poner.(100%)
e Case 2 - Less-of Offsite Power Pcwer at all 480V Luses o.
Mispcsitioned moce selector switch (93%)
2.2 x 10-3 Loss of power at one 480V bus
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5.3 x 10-3
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e Rancot failure of the pumps selected tc supply the nuclear heacer (69.5%)
o Pispcsitionec moce selecter switcr, (29%)
2.2 x 10-3 Less cf power at tac 480V buses e
Failure cf the punps selectec to supcly 1.0 the nuclear heacer due to insufficient power (100%)
No comparison is mace tc WASF-1400 results as there is no comparable syster analysis in W 55-1400.
S A.3 COND '.'S! 0t.'S
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ine service water system is reccirec te support plant operatien anc will be coerating at the time of the initiating ever.t. For'inis reason, the.
systen is unusual in relation to the plant standby emergency systems.
Failure of this system is dominatec by the human error of mispositioning tne moce selector switch. There is no indication in the-control' room which'Can aic the operator in determining the Correct position for this switch during normal plant operation; and, under the assumptions usec in this analysis, if undetectec, this error leads directly te system failure.
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4 B.
SYSTEF: CES :.::T:0L B.l' SY5'EF FUNCT!OL The SW5 provices water from the Hudson River to various. plant components reccirirg heat remoial for proper operation during normal plant operatien anc during abnormal plant conditions.
Tnis analysis was'performet to determine the frequency of f ailure of the SW5 to supply suffi:ient coolin5 water'io the components recuired curing abncrmal plart operatiers. The componer.ts requiring service water during abncrmal plant concitions are: the three emergency diesel generators (EDGs); the five containment building ventilation fan Cooler recirculation.cr.its (FCOs); and the twc component cooling heat exchangers.
Tne SWS corsists of three groups of-three pumps and two cooling water heacees. One grouc of inree pumps normally supplies esser.tial plar.t se-i:es i ne nuclear header; which, for this analysis, consists of the t
EDGs anc tne cectainmert FCOs. The seconc group cf three pumps supplies
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ronessertial plar.t services (the' conventional heacer) which, for this aralysis, corsists of' the component cooling heat exchangers.- The tnird grou; of pumps, backup service water pumps numbers 37, 38, ano 39, are provicec to sucoly essential plant services in the event of loss of the normal water supcly. The third set of pumps cannot be selectec for automati: starting, are nct corsicered a part of the engineerec safeguarcs system anc, for_these reasons, are excludec from this
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aralysis.
Nuclear :lart services anc ccnvertional plant services car be supplie:
I frem eitner of the first twc groups of pumps. Operator action to manually realign the service water headers is required in order to shift heacer services. The pumps selected to supply the nuclear header are selectec for automatic starting by the control room operator by shifting a moae selector switch.
System failure is'definec as "No or Insufficient Flow from the Service Water Syster" which may be further cefined as failure of two of three service water pumps selected for nuclear. plant service to supply water to'the nuclear services header and failure of one pump selectec for L
conventional plant service to supply water to the conventicnal services I
heacer.
B.2 SYSTEM DI AGRAMS The block diagram, Figure 1, is a schematic repre'sentation of the SWS which cepicts the system success' requirements.
Figure 2, is a system functional diagrem showing the basic system piping ar.rangenents.
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-E.3 SEni E WTEF. SYSTEF 4fC OPEUT10r.
S.3.1 SYSTEF. NOP.m' OPERATI0t.
The SKS consists of nine identical vertical, c entrifugal sump-type purrps ratec at 5,000 gptr at 220 f t. TDh. These pumps supply'two independent supply headers. One header normally provides cooling water for.the plart essertial.loacs (nuclear heacer), the other header provioes cooling-water for the plant nonessential loads (conventional header).
The backup pumps are normally linec up to both service water headers; however,-these pumps are provided for loss of the normal water supply only.
During normal operation,~the essential cooling loads are supplied by'two of the three service water pumps aligned to the nuclear header while the nonessential loacs are supplied by twc of the three service water pumps alignec to the convertional heacer. During plant emergency conditions, ar twc of tne three service water purps on the nuclear header can succ'y all of the cooling water requirements for essential plant ec:. ipr.ent ; any one of the three service water pumps on the conventional heacer can supply all of the cooling loacs for nonessential equipment.
The. service water pumps supplying the essential cooling loads are
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selectec for automatic starting during engineered safeguarcs system (E55) actuatior by means of a mode selector switch in the control roce.
Tris mcce selector switen nas two positions "4, 5, 6,* and "1, 2, 3."
ine "4, 5, 6" pcsition closes contacts in the ESS actuation control v
circi;its anc ocer:s Contacts in tne safety injection re-irculatiCr centrcl circuits for service water cumps 34, 35, anc 36. Tne opccsite cen:itions exist for tne service water pumps controllec ey tne positicn not selectec (for this analysis, pumps 31, 32, anc 33). The "1, 2, 3*
position performs the same functions for service water pumps 31, 32, and 33 that the "4, 5, 6" position performs for pumps 34, 35, anc 36. For the purposes of this' analysis, service water pumps i
34, 35, and 36 are assumed to be selected to supply essential plant l
services.
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The discharge of each service water pump passes through a self-washing, automatic blowdown strainer. These strainers function to remove i
particles >l/8" in diameter from the service water flow stream.
Cleaning and blowdown of the service water discharge strainers is automatic in response to the following signals:
every 2a hours, the strainer is cleaned and blown down for five minutes; and whenever the Ap l
across the strainer aaches 3 psid, the strainer is cleaned and blown I
down until the strainer Ap is reduced to <3 psid. The strainer motors l
receive power from KCs 36A and 36B which are the essential 480V KCs for Indian point 3.
Each service water pump discharges through a check valve and a normally open butterfly valve to its respective service water header. The
,I butterfly valve is used to isolate a service water pump for maintenance, l,
and the check valve is used to prevent back flow thro' ugh an idle service L
water pump.
4 OS61A040281/1 L
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The essential cooling.heacer supplies the following systerrs anc ccrponer.t s :
e Containment Building Fan Cooler Recirculation Units.
f e
e Containment Suiicing Fan Cocier Recirculation Units' Fan Mctor Coeling Coils.
Instrument Air Compressers' Closec Cooling System.
e e
Mair Eciler Feec Pump Lube Oil Coolers.
e Main Turbine Oil Coclers.
e Gere ater Seal Oil Cociers.
e Eme gency Diesel Generatcr Cooling Services.
e Cortrcl Teor Air Conciticring Unit.
The corvertional header supclies the component cocling heat exchangers anc various corventior.al plart loads.
The EDGs and tne cortainment building FCOs have automatic valves which ope-ate ir resperse te a safeguarcs actuation signal. The operation of these valves is ciscussec below:
o Se vi:E water for tne EDGs provices lube cil co' cling anc jacket water cooling. Eacn ciessi generator nas a heacer supply isolation frer both service water supply heacers and an outlet isolation vahe. The outlet from each diesel ccm:ines inte e single outlet heacer and passes to a parallel flow control valve arrangement.
These pneumatically operated valves maintain a total' flow of 1,200 gpm through the EDGs. In the event of a,high dieseT generator jacket water temperature or a safeguards actuation signal, the air l.
to the. flow control valves is' vented from the controller, and the valves go to the full open position. During normal plant power cperation, one of the diesel generator flow control valves throttles l
'open to maintain'a total diesel generator cooline flow of 400 gpm.
e The service water systerr supplies cooling water to the five containment builcing FCUs. This water cools the air in the containment and the fan motors. The inlet and outlet isolation valves for each unit are located outside the containment building and.may be operated during plant abnormal conditions. The outle:
line from each fan motor cooler is combined into a single header anc passes through a flow indicator and temperature indicator. Flow through the fan motor coolers is maintained at 55 spm (total). The outlets from the FCU cooling coils are combined into a cor:rnon outlet he a der.- During normal plant operation, the service water flow from the FCUs is throttled to maintain containment ar5bient j
temperature <1200F. Two parallel bypass valves around the i
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0861A040281/1
temoe-ature control valve are automati: ally opene: in response to a -
j safeguarcs actsation signal. As tnese valves are pneumatically j
i closec, ioss of air or loss of poner to tne associate: solencio valve causes tne bypass valves to open. Tne containment building FCU automatic outlet valves are included with the containment fan cooler system description as failure of the valves to open does not
. result in SW5 failure.
The normal service water pumos are located in a common well o'f the intake structure and tame tneir suction from nis well. The service water well rece.ives river water througn its own debris screen system and from eitner or botn of the circulating. water pump wells. Tne gates on the main circulating supply openings are normally open. Tne backup pumps-are locatec in' tne plant discnarge canal. This location allows the pumps to supply essential plant service in the event of a loss of the normal service water supply.
Tacle 2 lists the required flows for the SWS for various plant conditions. Daring normal operation, two nuclear service water pumps anc two conventional service water pumps are recuired to support power ope-ation. During t0:A con itions, two of tr.e tnree nuclear service.
water pumps are required to start anc run. After the shift from injection to recirculation, two nuclear service water pumps are required to continue running and one conventional service water pump is required to start and run.
.B.3.2 SYSTEM OPERATION DURING EMERGENCY CONDITIONS Four concitions of emergency operation of the SWS are discussed below.
.Tnese conoitions are:
" Unit Trip, No Blackout, No Safety Injection";
c.
" Unit Trip, Bla:<out, ho safety Injection"; " Unit Trip, No Blackout and Saf ety Injection"; and " Unit Trip, Blackout, and Safety Injection."
1.
Unit Trio, No Blackout and No Safety injection. When the Unit trips anc no blaccout or saf ety injection occurs the system will remain in operation as it was before the event, since all power requirements will have transferred from the unit auxiliary transformer to the station auxiliary transformer, and the service water pumps will continue to operate.
2.
Unit Trio, With Blackout and No Safety Injection. When this condition occurs, all service water pumps are tripped.. Electrical power is' reestablished using the EDGs and the essential service l
water neader is automatically reestablished in order to support the
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l EDG cooling requirements. The nonessential service water header is then operator reestablished to support the component cooling heat exchangers since a component cooling pump is automatically started-i I
by this event. By reestablishing these headers all other loads are then supplied with water as necessary.
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i 3.
Unit Trio, No Blackout and Safety Injection. Under this condition, the service water pumps wnicn were running remain running, and an additional pump selecteo by the mode selector switen to supply the b'
essential heater will start.
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-4.
Unit Trio, witn Bla:< oat anc itn Safe:v Iniection. When tnis concition o:cs-s, all service -ater pumps are trippec. Ele:trical
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power is reestaolisned using the EDGs.
Tne ESS safeguares sequence signal inen starts the service water pumps _ selected by the mode selector switen-(rignt-nand safeguards panel)-to-supply the essential neader..
Wnen active safety' injection is completed and the recirculation phase is entered into, two pumps (with outsioe. power or tnree diesels running) or one pump (witn only two of the diesels running) of the nonessential heade will oe started by recirculation phase switenes RS-2 and RS-5.
RS-2 wil1 start one pump; RS-5 will start the other pump if three
. diesels'are running or outside power is available. Assuming pumps 34, 35, and 36 were enoser. for essential loads, essential service pumps 31, 32, and 33 woald be used for tne recirculati.on phase._ Positioning
. switch _RS-2 to "On" would' start. pump 31; if it failed to start, pump 32 woulc ce started; and i_f 32 failed to start,_ pump 33 would oel started.
Switen RS-2 is independent of power available. Positioning switch RS-5 to "On" will cause the following action only if three diesels are run.ing o outside power is availaole: pump 32 will be started; if it is, runting anc pump 31 is not running, pump 31 is started; if pump 31 is running ano pump 32 fails to start, pump 33 is started.
B.4-INSTRUMECAT Or, AND CONTRO.S Tne operator' controls the service water pumps from the control room. In accition to tne mode selector switen wnicn determines the service water pumos selected for automatic starting during the' injection.pnase:of an-ESS actuation, the coerator nas incividual pump breaker control switenes-.
t in tne control room at tne cooling =ater and air panel. Tnere are_~nine swittnes, one for eacn service water pum:.
E3cn crea(er control switen for tne normal service water pumps nas four positions (spring-return-to-Auto):
o Pull Out. The pump is disabled from starting by any automatic-start signal. Witn tne switen in tnis position, the " Safeguards Equipment Locked Open" alarm will be snnunciated in the control room on the-safeguards panel.
{
e Stop. The pump breaker is tripped open.
e Auto. Tne pump will De started for any one of tne following conditions:
If selected for essential service, the pump will start upon-receipt of a safety injection signal or a unit trip with' l:
blackout and no safety injection signal.
If not selected for essential service, the pump will-start when the recirculation phase switches are positioned for the blackout i
and safety injection condition. For the unit trip with blackout condition, operator action is necessary to start a nonessential z.
service water pump.
e Start. The pump will be started.
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0861A040581/1 l.
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wnile tne-pump is' running,lit may be tripped by:
^
Placing tne. control switen to tne'Stop or Pull Out position o
e Overlocc.
- The bac<up service water pump breakers are controlled from.the control room Dy "On-Off" swittnes on.the cooling wattr and air panel. In addition to tne control room breaker control switches, eacn normal pump may be started locally at the 480V switchgear. To start a pump-locally, 4
a " Local / Remote" selector. switch.is positioned to " Local" and the pump is started. Witn the " Local / Remote" selector switch in " Local," the' pump cannot be started automatically, and all control room indication of pump breaker status is lost. This condition is annunciated in the control room.
The controls for the self-cleaning strainers are located at the intake structure or by tne backup pumps, each strainer having its own control panel. Three switches are located on each panel:.a disconnect switch whicn removes all power from the unit; a-three-position (Off-Hand-Auto) concitice. of operation-selector; and a two-pesition (Intermittent-Continuous) moce of operation selector..A " Service Water Strainer'Trosole" alarm is indicateo in tne control room.if straiher Ao >3 psic or if trouole nas occurred to defeat tne normal operation of the strainer motor.
During 'perr. tion, pressure-in the service water headers is monitored and o
j' fan alarm is soundeo in the control room if aonormally high or low.
In adcition,. flow indicators and temperature detectors indicate the:
concition of the components served ty tne SW5.
B.5 TE:HNi: A_ 53ECIFl:AT10NS
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ine piant tecnnical' specifications require three service water pumps on tne designated essential neader and two pumps on-tne designated nonessential and tneir associated piping and-valves oe operable at all times. If, during power operation, these requirements cannot be met witnin twelve hours the operators shall proceed.to.b' ring the reactor to
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the cold shutdown condition utilizing normal operating procedures'. In adcition, the -isolation between the headers shall'be maintaineo'at all times except for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> allowed to shift service water
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header services.
B.6 TESTING AND MalNTENANCE B.6.1 TESTING'AND SURVEILLANCE Periodic testing of the service water pumps is required by ASME i--
Section XI. The required frequency of testing is montnly during normal plant operation. Plant test procedure 3PT-M35 tests all service water pumps monthly. Successful completion of this test requires that the service. water pump under test run-successfully for 15 minutes.
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t Automatic ~ starting of the service water pumps in response to a safety injectior signal is performee every refueling cycle in conjunction witt EDG tests.
In accition to the above tests, plant operating procecures require shifting of running service water pumps weekly.
Menitoring of the SKS is performed routinely by the plant operators to determine system status.
B.6.2 MAINTENANCE Periodic maintenance is performed as required.on.the service water pumps and associated equipmert. Due to the plant technical specification limits on the number of operable service water pumps on the nuclear header, periodic maintenance is not performed on a service water pump that is linee up to this header. Instead, the header services are shifted and the pump is placed out of service for maintenance. The periccic maintenance consists of a range of actions from clear.ing and servicing tne self-clear.ing strainers to pump disassembly and seal replacement.
Basec upcn our review cf plant work permits, the probability of a service water pump being out.of service for maintenance is:
Mear:
1.47 x 10-2 Variance: 3.95 x 10-5 8
U::r the com:letice of pump train maintenance, testing is requirec to cetermine pue; ccerability anc te ensure ccrrect syster lineup. At the ccmoletior' of this testing, the pump is returned to its normal lineup.
E.7 -SUPPORT SYSTEVS
~The system recuired for operation of the SWS is the electric power system. Table 3 identifies the service water pumps-and the electrical power supplies for the pumps.
B.8 OPERATOR INTERACTION WITH THE SERVICE WATER SYSTEM Operat'or action or inaction can affect the operation of the SWS.,As this system is required to support normal plant operation, most operator errors that affect system operation will be annunciated or incicated in the contrcl room within a short period of time after their occurrance.
These actions include shifting pump control to Local (annunciated in the control room), inadvertently securing a running service water pump (alarmed tn the control room), and mispositioni,ng manual valves which control service water flow.to individual components or groups of components.
Because of the reasons stated above and because the SWS is required to be in operation to support plant. operation, these types of human errors do not contribute to the failure of the SWS to start and continue running following an initiating event.
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Tne cperater may affect the automatic startinc of the service water pumps selectec to supply the nuclear services heacer by mispositioning the_roce selector switch in the. control room..This results in the wrong set of sers ice water pumps starting automatically in the event of a safeguarcs. actuation or blackout condition.
If uncorrected, this concitior. results in failure of the EDGs due to overheating. This concition_is indicated imnediately after-ESS actuation by low flow alarrs on the containment-building FCus followed shortly by low flow alarns and high te.cperatures'on the EDGs. This condition is rapidly 4
corrected in the contrcl room by starting the reauired service water
. pumps and securing the misselected service water pumps, and returning the mode selector switch tc the correct position (this allows subsequent restart of the service water pumps selected.to the conventional header during the shift to recirculation).
Fror NUREG/CR-1278*,.the error of omission while using a procedure with check-cff. provisions is 0.001 (.0001 to.005) (Table 20-21). Using the guicance presentec in tne Human Error Rates section of this report, we take tne upoer bounc as the 9Cth percentile value anc the best estimate' as tne mediar'value of a lognormal distributier.. This leads to the fcilowing cistributien for tne errcr of omission when written procedures
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are usec.in ncnpassive tasks:
Mean:
2.20 x 10-3 4
Variance:
1.EE y 10-5 The probability of'not oiscovering this error (Switch position only) fror Tacle 20-25-(Iter 21) cf NUREG/CR-1275 is 0.95 (.9c te.994}.
Agair., usine the guicance presentec in the Human Error Rates s.ection of tris report, we take.the upper bounc-(.994) as the 90th percentile value, anc the best estimate (.98) as the mecian value of a lognormal cistributior. This leacs'tc the following distribution for the probatility of not discovering the mispositioned switch:
Mean:
-9.8C x.10-I-
-Variance:
1.93 x 10-4.'
Combining the error of omission with the probability.of not discovering the error, we obtain the frequency.of occurrence for this mispositionec switch. The mean and variance for this event ~are:
~Mean:
2.16 x 10-3 variance:
1.48 x 10-5 i
Swain, A.D. anc H.E. Guttman.."HancDook of Human Reliabiity Analysis 6
c,.
with Emphasis on Nuclear Power Plant Applications," *NUREG/CR-1278 Draft Report,' April 1980.
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r On cerant the operator will receive immediate incication that syster ope ation'is incorrect (low flow alarms, etc.); however, the operator is also receiving numerous indications and alarms. The operator will probarly pass over the first low flow alarms and miss t,he status of the SWS-until diesel generator temperature alarms occur. At this point, with a less of offsite power, system failure due to loss of electric is imminent and, for this analysis, system failure is assumec tc power occur.
B.9 COMMCf. C AL'5E AtiA.v515 Tne normal service water pumps'are located in a common well of the intake structure. The backup service water pumps are locatec at the discha ge canal. The intake structure is designated as Seismic Class I,-
as is the SwS itself. The breakers for the service water pumps are locatec at the 480V essential switchcear at elevation.15' of the control buticing. The manual valves for aligning the service water supclies to the va*icus com?Cner.ts servec are located in Commer locations through0Ut the plart (i.e., diesel generator valves are locatec tocether, cortainmentbu11dingsupplyvalvesarelocatedtogether).
Ccmm:r. generic compenerts in the SWS are manuf actured by the same manufacturer, are subject to commer. maintenance, test, and operation procedures, anc have common susceptisilities to secondary causes of failure (grit, moisture, vibratien}.
Table 4 presents a listing c.f the core:nents incluced in the SWS analysis anc the susceptibilities to the sarious categ: ries of failure. -Further discussion of the effect of c:r :- casse failures on syster failure is presentec in Sectice D.c of tris analysis.
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-C.-SYST5VMCDELING C.1 EVEh! TREES The to; event for the SWS in the event trees for Indian Point 3 is "ho or Insufficient Flow fron the Service Water System." This is further definec as failure of the purps selected to the nuclear header to start or rur., or f ailure of the pumps selectec tc tne conventional heacer tc start or r'un.
In the everit trees, the SWS appears with the events concerning the containment fan coolers.
C.2 FAU'_T TREES Figure 3 preser.ts the syster f ault tree developed for the Indiar Point 3 SK5. The top event, "Ne or Insufficient Flow (N01F) from Service Water Syster" is definec as no or insufficient flow free service water header nc.1 (nuclear) or ne flow from service water heeder ne. 2
( c or.v e-t s or.a l ). For tne purposes of this analysis, service water pum; nos. 34, 25, and 36 are-alignec to supply the nuclear heacer and pum; 31, 32, ane 33 are alignec to supply the conventional header. The nos.
assucctions use: in ceveleping tne fault tree are presentec below.
Four pum;s were-in operation prior to the initiating event - twc on e
the nuclear services header, anc two on the conventional services heacer.
minimal cutsets which lead directly to the top event of thE fault tree,
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Quantification of the SWS is based upon the reliability block diagrae preserted as figure 1.
The compcnents on these blocks are described in Sectier C of tnis analysis and cefined'as a train for the purposes of this ant'ysis.
In the fcilowing sections, quantification of the nuclear header and,the corventional heecer cortributiens te syster failure are presented separately. The results of the heacer analysis are combined to present the protarility of systen failure.
D.1 SING'_E FAILU.E5 Otsersatien cf Figure i reveals the service water intaie (Elock A) as a sincie centributor to SW5 failure. As this train can fail the nuclear
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anc tne convectional service water headers, this failure is treated as a sir.;'s failure.
This faiiare corsists of failures of the service water intake screer anc ine tw: screer cypass gates. The bypass gates are no-cally open.
Because the bypass gates are normally oper, and must be manually insertec to ticck flow, no crecible failure mechanis was four.c which coulc result in nese gates transferring closec. The probability of cccurrence of water suppiy failure is' assigned a value cf zerc.
Als: incluce: as single failures for the indivicual heacers are Blocks J ar. : r.,
ric. corsist c': hea:er ; icing failures tae neacer cischarge is lati:r valve; an: the hea:e cischarge check vahe. Tnese everts are ciscusseC Dtiow.
1.
Pioe Failures. Table 6 icentifies the system effects of pipe failure for various sections of pipe in-the SWS. Failures in piping which is less than 10 inches in diameter are not presented. The i
table is presentec in two sections; the nuclear header which is cefinec as the header supclied by pumps 34, 35, and 36; anc the conventional heacer which is supplied by pumps 31, 32, an'c 33.
Our mean anc variance for the probability of failure of a single pipe section are:
Mean:
8.60 x 10-10 Variance: 6.00 x 10-I7 Fbr the nuclear heacer, Table 6 identifies ten sections of pipe where rupture will cause immediate failure of the SWS. For the conventional header. Table 6 identifies eight sections of pipe where rupture will cause inmediate failure of the SKS. This results in the following distribution for the probability of piping failure per hour for the nuclear and conventional service, water headers:
16 0861A0a02Bl/l
9 Mear.(nuclear):
8.60 x 10-9 Variance:
4.29 x-10,-15 Mean (consentional): 6.88 x 10-9 Variance:
2.75 x 10-15 Piping f ailures curing plart operation are immediately oetectable and result in either plant shutdowr o'r heacer realignment for repair. ke are interestec in those piping failures which occur after the start of an ir.itiating event. The time period of interest is the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the initiating event. This leads to the following cistributions for failure of the nuclear or conventional service water heacers due to piping failures:
Meer (nuclear.:
2.06 x 10-7 2.47 x 10-12 Variance:
2 Mear (corvertional):
1.65 x 10 '
Variance:
1.5E x 10-12, 2.
Isciatier Valve. Each service water header contains a manual header isolatter valve anc a header check valve. A failure in either of 4
these valves curing plart operation is irtr'ediately cetectatle anc wcu'.c rec. ire plar.t snutccwn_for repair. We are interestec in these fatiures whic occur after initiatice of the system. The mean anc variance for.these events are:
Manual Valve Transfers Closed Mean:
9.15 x 10-8 (per hour)
Variance:
1.01 x 1,0-I4
. Check valve Faiis to Open Mean:
6.91 x 10-5 (on demand)
~
Variance:
1.03 x 10-8 With no loss of offsite ' power, the pumps selected to supply the nuclear header will continue to run and the pumps selected to supply the conventional pumps will trip. The conventional heacer pumps are later started by operator action. With a loss of offsite power, all pumps are initially tripped and subsequently restarted (either putomatically or by operator action).
For the case of no loss of offsite power, we have the following distribution for failure of a header isolation or check valve to time, t = 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Mean:
2.20 x 10-6
. Variance:
5.51 x 10-12 17 0861A040281/1
Kite a less cf cffsite power, or when the pumps are trippec by clar.;
ac-ior., we have the fcilowing distribution for failure of a header isclation or check valve to time, t = 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Mean:
7.13 x 10-5 Variance:
8.93 x 10-9 D.? 00 TELE FAILURES 0.2.1 NUCLEAP HEADER.
Nuclear heacer double contributions to system failure consist of failure of twc of the three pump trains and failure of the two diesel generator outlet flow centrcl valves.
1 Se vice water pum-trair, Block E.
Section C of this analysis press-ts tne comper.erts wtich are includec ir a single pump trair.,
Ta-ie 4 icertifies tne failure rates associatec with these cc pene-is. P-eser.tec belcw is the component failure data for a single pumt train.
Mean Varia,ce Pum; fails (on cemanc) 1.36 x 10-2 1.22 x 10-6 (per hour) 4.6S x 10-5 1.07 x 10-9 Meter fails (witn pum; f ailure)
C Cor.trcl circuit fails (witr pump failure)
Switchgear bus fails Control power te switchgear bus fails Expansion joint ruptures, 8.60 x 10-9 6.00 x 10-15 per hour Discharge strainer plugs Discharge check valve fails, 6.91 x 10-5 1.03 x 10-8 to open, demand Discharge valve transfers 9.15 x 10-8 1.01 x 10-14 closed, per hour Blocks C, D, E, F, and G consist of similar components.
For an operating pump train, the probability of failure per hour is described by the following probability distribution (made up of pump failure to continue running, expansion joint rupture, and discharge valve transferring closed):
Mean:
4.69 x 10-5 c.
Variance:
9.54 x 10-10, U
'5nown for. completeness only, quantified in the electric powe analysis.
" Negligibly small probability of failure.
18 0861A040281/1
~
For a time
= 2a nours, we have the following distribution for failure of an operating pump train:
Mean:
1.13 x 10-3 Variance ~: 5.51 x 10-7 At Incian Point 3, with no loss of offsite power, and a safeguards acts,ation signal, the nonvital electric loaos are.strippec from the 486V switchgear buses. The pumps selected by the mode selector switch to supply the r.uclear heacer will remain operating' while the pumps not selectec (the conventional header pumps) will be stripped. The standby nuclear header pump will be sent a starting sigr.al by the safegt. arcs secuence system. With a loss of offsite power all service water pucps will be strippec from the 480\\ switchgear buses.
When pcwer is available, the pumps selected tc su :ly the ru: lear header will be sent starting sigr.als by the safeg:.aecs secuer.cing syster.
Tne crebability cf failure to start of a previously running service wate peep is cace up of: purp f ailure to start on cerrand; expansion jcin* rupture; check valve failure to open on cemanc; anc
~
discharge valve transferring closec. The expansion joint rupture and the discnarge valve closbre must have occurred while the pure was icie (t < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). The prcbasility of failure en cemanc for the expansion joint anc cischarge valve with t < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> are:
Fea- (ex:ansicr jcint):
E.60 x 10-9 Variance:
6.00 x 10-15 Mean (discharge valve):
9.15 x 10-8 Variance:
1.01 x 10-18 For a single previously. operating pump train, the probability of failure on cemanc is described by the following distribution:
Mean:
1.43 x 10-3 Variance:
1.12 x 10-6, Given a successful start, the service water pump must operate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The total probability of failure (start and operate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) for a single previously operating se'rvice water pump train is now:
Mean:
2.55 x 10-3 Variance:
1.36 x 10-6, v
19 2e 0861A040281/1
O e
r During plaat operation, one service water pump selected'to supply the nuclear heacer will be in standby. Pump f ailure to start on cemanc anc check valve failure to open on cemand remain as previously definec; however, the discnarge valve and the expansior, jeirt contributions to pump train failure on demand must be cevelopec.
Plant procedures recuire shifting of the operating service water pumps weekly. Fa'ilure in either component coulo have occurred at any time curing this period without being detected. The fault detection time for the failures is taken as one half of the test interval (84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />). This results in the following distributions for the probability of failure on demand of an expansion joint and the discharge valve:
Mean (expansion joint): 7.22 x 10-7 Variarce:
3.03 x 10-11 Mear. (discharge valve):
7.69 x 10-6 Variance:
8.03 x 10-11 This results in the following probability of f ailure on cemand for a single standby service water pump train:
Me e r. :
1.44 x 10-3 9
Variarce:
1.11 x 10-6, Giver a successful sta-t, tne pump must continue to operate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which results in the following probability distribution for failure of a stancby service water pump train:
Mean:
2.56 x 10-3 Variance:
1.36 x 10-6, The following expression defines the probability of failure of the nuclear service water header cue to pump train failures:
Opumps = 2[P(OP) x'P(STBY)] + [P(OP)]2 + [P(OP)]2 x P(STEY) where P.( OP )
= Probability of failure of a running (or previously running) pump to t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
P(STBY) = Probability of failure of a standby pump to t = 24. hours.
20 0861A0dO281/1 s
9 kita effs'te peaer available, anc all 4SCr switchgear buses energizec, tne pues train's contributier tc heacer f ailure.for.the pumps selectec to supply the nuclear heacer is described by the fcliewing cistribution:
Me an':
7.59.x 10-6
-variance: 5.50 x 10-11
-k*ith a lost of offsite power, anc all 480V switchgear buses energized,:the pump trair's contributior. tc heaoer failure is-describec by the fCllowing cistribution:
1Mean:
2.10 x 10-5 Variance: 2.48 x 10-10, 2.
Diessi sererater cutlet flow cortrel valves, Blocks H anc J.
Failure cf salves -F V-Il76 anc FCV-Il76A tc oper on derar: or te remain oper for.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> results in f ailure of. all three EDGs. The precarili s cf a single valse not oper.ing en demanc is representec by the fellowing dist.ribution:
Mean:
4.95 x 10 '
Variance: 4.03 x'10-7 9
Fcr t*
valves ir-parallel we :ttair. tne fellowir; cistri:ctice for
.. tne : rcra: 'ity cf syster f ailure:
Mear:
6.27 x IC-7 Variance:
1.54 x IC-II.
D.2.2 CONVENTIONAL HEADER There is no double failure contribution to conventional header failure
~
as only one of three pump trains is required _for system success.
D.3 TRIPLE FAILURES D.3.1 NUCLEAR HEADER There is no triple failure contribution to nuclear header failure.
D.3.2 CONVENTIONAL HEADER The contribution of triple failures to failure of the conventional header consists of failure of all three pump trains.
Upon receipt of a safety injection signal, the pumps 5, elected to supply conventional plant services are stripped from their respective 480V switchgear buses. These pumps are not restarted until the recirculation 21 0861A040281/1
pr.ese of LOCA recevery.
System sut ess requires that a single pump selectec to supply the conventional beacer start and operate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The following expression defines the. probability of failure for the:
service water pump. trains selected to supply the conventional service water header.
Opumps = P(15) [P(OF)2 x P(STBY)) + 3 x P(05) [P(OF))2 where P(OF)
= Probability of failure of a previously running pump to t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from Section D.2.1)
P( STEY)
= Probability of failure of a standby pump to t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from Section D.2.1)
.P(15)
= Prebability of having a standby pump [1-P(05))
P(CS)
= Pretatility cf mair.tenance of a service water pump (from Sectier. B.6.2)
With power available at all 480V switchgear buses (with or without offsite power), the probability of conventional heacer failure due te pump train failure is cescribed by the following distributier:
C Mear:
3.61 x 10-'-
Variance:
1.49 x 10-I3 D.4 ~ TEST ANC MAINTENANCE FAILURES D.a.1 NUCLEAR HEADER Due td the plant technical specifications and the discussion presentpd in.Section B.6 of this report, no test or maintenance failure contribution to system failure is assigned for the nuclear header.
D.4.2 CONVENTIONAL HEADER There is no contribution to system failure due to the testing performed upon the service water pumps selected to supply the conventional header.
The maintenance contribution to system failure is included with the quantification of the conventional pump train's effect on system failure.
D.5 HUKAN INTERACT 10N FAILURES D.5.1 NUCLEAR HEADER C.*
From Section B.8, the operator error of omission an.d nondiscovery of the o
error resulted in'the following distribution for the frequency of occurrence of a mispositioned mode selector switch:
22 0861A040281/1
~
y
.m
Mea *:
2.16 2 10-3 Variance:
1.46 x 10-5, This failure results in failure of the SWS.
D.5.2 CONVENT 10'NAL HEADER As twc service wat'er pumps alignec tc the conventional header are always running to suspect plant operations, no human error contribution is assionec for the conventional header. The human error of failing tc shift ~to recirculation from injection is analy2ed with the recirculatier system description.
D.6 COW Or. CAL'SE FLILU E5 Altncuck there a e many similar components sharing comron locations in the 5 5, a la*cs portier of :ne components are not susceptitle te ecst
- cce cr cacse f ailure mectarises be:ause they perfcrm a passive function (iters suct. as raruel valves, check valves, piping, etc.). Active cococnents of tne system, tne service water pumps, are more likely cancicates for corscr cause failure and are ciscussec below. External eserts such as eartnquakes anc flooding are discussed elsewhere in this reocet.
1 Fire. The normal service water pumps are located at.the screen well
- structure. Tne pumcs are net enciesed anc the fire loacing in the a-ea is icw (as cefinec in'tne "Resie of tne Indian Ocin Statier Fi e crctectier Fregrar' }.
Nc fires are Destulatec in this area inat ccalc cisacle all' service water pumps.
2.
Meisture. The service water pump motors are designed for outdoor service and are protectec by cesign from the effects of moisture.
3.
Grit. Due to the design of the service water pump motors anc the location of the service water pumps, airborne grit is not ! common Cause Candidate.
4 Other Causes. Other common cause susceptibilities, such as manufacturer, test anc maintenance procedures, etc., are possible contributors to commor cause failure of the service water pumps.
However, the plant test program, maintenance program, and technical specifications combine to 1) aid in discovery of pump problems anc,
- 2) limit the effects of common cause failures. No Quantification is performed for these causes of failure.
NOTE: The service. water pump breakers are susceptible to the common cause failure mechanisms of fire, moisture, and grit due to their connon location in the switchgear room. Quantification and discussion of these effects is presented in the event tree analysis c
q.
' as these effects would be felt throughout the plan.t.
23 0861A040281/1
P D.7 Sv5TEF F4 R U.E Failure of=the service water syster is defined as failure of the nuclear heacer or conventional heacer to supply sufficient water to time s
~
t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Ihe frecuenCy of failure for eaCh header is presented separa:Ely below. Tne f ailure frequency for each header is made up of the following contributors:
single event, double event, and triple event randee hardware failures; test and maintenance failures (which are includec with the triple event failures); human errors which result in syster failure; and the commor. cause contribution to system failure.
1.
Nuclear Heacer Failure. The probability of failure of the nuclear heaoer with offsite power.available~is characterized by the following me'ar. anc variance:
Mear:
a singles + acoubles + atriples + atest and maintenance
+ OCperator error + aCoCCon Cause
= 2.17 x 10-3 Variance:
1.41 x 10-5 Tne probatility of f ailure of the nuclear header with a loss of offsite power is characterizec by the following mean anc variance:
Mean:
2.25 x 10-3 g
Variance:
1.41 x 10-5 2.
Conventier.al heacer Failure. Tne prcbability of failure of the conventional heacer with or without offsite power is characterized by the following mean and variance:
Mean:
asin'gles + adoubles + atriples + atest'and maintenance
+ aoperator error + acommon cause + aother
= 7.18 x 10-5 variance: 8.84 x 10-9 3.
System Failure. The frequency of failure of the service water system is mace up of those failures in the two headers which result in header failure. For the case "Offsite Power Available" and under the condition ' Power Available at All 480V Switchgear Buses," we have'the following distribution for the fo.llowing distribution for the frequency of failure of the service water system to time, t = 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Mean:
2.24 x'10-3 Variance:
1.41 x 10-5 24 0861A040281/1
- e' For the case "i.ess-c'~0ffsite Power" and under the condition " Power-Asaflatle at-All 4SOV15mitchgear Buses,".we hav'e t_he'following cistribution for'the frequency-of faiTure of the service water sys tert te-time, t'= 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s
Mean:
2.33 x 10-3 Variance:
1.41'x.10-5.-
g d
o V
k l
~
I i=
?
i 25.
s l-0861A040281/1 i
e.
I i
4 E.
SYSTEF QUANTIFICATION WITn DIFFERING SOUNDARY CONDITIONS FOP' ELECTRIC P0a'EP.
E.1 LOSS OF POWER AT A 5]NGLE BL'S This condition is defined as loss of power to Switchgear buses SA, 6A, or 2A and 3A.
5*itchcear buses 2A and 3A are cefinec as.a single bus for the following. reason:
a single EDG supplies both buses upon a less of offsite powee.
The Icss of power at the various switchgear buses only affects the number of service water pump trains available; all other cor.tributions to system failure remair as stated in Sectior< D of this analysis.
~
For the purpcses of this analysis, an operating (or previously-operating service water pump is assumec to have been powerec from the switchgear bus that is now ur.available. This is a consersative assur.pticr in tr.at it results in a higher probacility cf f ailure for the '
pur; trairs. This assumption-is usec for all loss of power calculaticrs wr.ich fcilow.
1.
Effect or. the nuclear heacer. The following expressien defines the procatility of syster failure due to pump train failures for the pumps selected te supply the nuclear heacer:
Opumps = P(OP) + P(STEY) g where P(0:' ar.c P(ST5v) rerair. as cef.nec in Sectic. :.
Fcr the condition "Offsite Power Available," this results' in the following cistribution for the probability of heacer failure oue to pump train failure:
Mean:
3.69 x 10-3 Variance:
1.88 x 10-6, The probability of failure of the nuclear header, with Offsite power available anc a loss of power at a single 480V switchgear bus is:
Mean:
5.85 x 10-3 Varianc2:
1.58 x 10-5, With a loss of offsite power, the probability,of header failure due to pump train f ailures with a loss of power at a single 480V switchgear bus is:
-Mean:
5.11 x 10-3 e.
C.-
Variance: 2.68 x 10-6 26 0861A040281/1 N
,v-e
which rest,lts in the fellowing distribution for the probability of failure of the nuclear. header with a loss of offsite power and loss of_ power at a single 480V switchgear bus:
'Mean:
7.35 x 10-3 Variance:
1.66 x 10-5 2...Effect on the conventional header.. The following expression cefines the'probatility of heater failure due to pum; train failures for the pumps selectec to supply the conver.tional header:
Cpumps = F(15) [P(OP) x'P(STBY)] + P(05) [P(OP)]
where the terms of the expression remain as defined in Section D.
Inis results ir. the following distributier.'for the probability of-heaCE-failure cue to pump trair. failures:
Me ar.:
4.40 x 10-5 variance:
5.94 x 10-10, The protability of conventional heacer failure with a loss of power at a single 480V switchgear bus (with or without offsite power) is:
~
Mean:
1.15 x 10 4
.e Va-iar.ce:
9.34 x 10-9 3.
Effect on the syster. The prcbability of system f ailure, given a loss of a single 450V switchgear bus and offsite power availatle is; now:
Mean:
5.97 x 10-3 Variance:
1.58 x.10-5, For the " Loss of Offsite Power" case, we have the follo' wing distribution for the probability.of system failure with loss, of a single 480V switchgear bus:
Mean:
7.46 x 10-3 Variance:
1.66 x 10-5, E.2 LOSS OF POWER AT TWO BUSES This condition is defined as loss of power to switchgear buses 5A and 6A, 5A and 2A and 34, or 6A and 2A and 3A. The discussion for buses 2A and 3A remains as presented in Section E.1.
The assumption
('.
concerning which buses are lost is modified as follows: the previously operating service water pumps are assumed to have been powered by the switchgear buses that are now unavailable.
27 1
0861A040281/1
-l
o 1.
Effect or the nuclear heacer. Loss of power to the combinatier.s~of swit'chgear buses icer.tifiec abcve results in failure of the nuclear header due to insufficient flow.
2.
Effect on the conventional header. Coss of power to the conbinations of switchaear buses defined'above leacs to th,e following expressicn for the probability of-pump train f ailures which result in heacer failure, Opumps ='P(IS) x P(STEY) + P(05).
Tr.is results_in the following distributior for the probability'of heacer failure cue to pump train failures:
Mear:
1.72 x 10-2 Variance: 3.27 x 10-5, Tne orcbatility Cf f ailure of the conventional header with a -loss of pcwer at twc 4E2r switchgear buses is:
Me ar.:
1.73 x 10-2' Variance: 3.85x10-5, 3.
Effect.or tre syster.. The procability of syster failure giver loss cf t.o 450V switchsta-buses is i.0 due tc the effect of this concitier. u:er tne nuclear heater pumps.
9 4
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-O 34
TABLE 2 FL0k REOU!REMENTS FOR THE SERVICE WATER SYSTEP'.
Esse-: s' m s:e-sesi;- *1o.
h r.a1 In3e::io-Re:ir:.lau :,
e th.:1:4-ta:
.;n-0:e : son Paese Pnese con:n n,e-: rae :::'e-i!>
2.oss 2.853 10.000 (5 of 5) 6.5:: i2 of 5.
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10.6!!
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Desigt Ilow hormal InjeC ior.
RetirCwletion
'( en.er.ti:nali Eacn (gs,
Operation Phase Phase Liese' 3emerats-40 h:: Recaires hot Re: aire-405 (1 of 3)
Co.::ae.: :oc im; nes: (2) 3.533
.7.000 (2 of 2)
Not te:wi e 3.500 (1 of 2.
In:r.an;ers Strasme 51s.:3.-
(3; 135 200 ho 2e:. ire:
133 Otne ms:elianeoss 4.69*
2,550 1
40 Total 11.253 0
a.342
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Nu.:,e cf line cotaanents coeles.
r y
O I
o626006 til -
35
7 r.
e TAB;.E 3.
ELECTRICAL SUPPLY BUSES FOR
'INDI AN P0lhi 3 SERVICE WATER PUMPS ~
o
. Fur.:. Narbe-480V Bus
'31
.5A 4
- 32-2A' 33 6A 34 5A-
- q 35 3:
36
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e Y
9 TADI.E 4 (continued)-
BASIC EVENT DATA - INDIAN POINT 3 SERVICE WATER SYSTEM Fault I.illure taala 6mewan Cause pala toninent s (vent Description and f ailure tiede frec
==
Cneling M'an 18/ 11 v.u 6.iew e HI lit Mcf. (l)
I ear at inn Sust ept IhlI eI y
$W pun, no. 35 does not start IPM'35-5 1.36 a 10-3 li 1.7/ a In-fi II 1, y does not continue to run 4.611 m 10-5 11 1.u/ a lo 'i see test 1/
$W purp no. 36 dnes not start it'N'36-5 1.36 a 10-3 0
1.77 = 10-fi -
II
- 1. Y does not continue to run
- 4. fill a lit-5 18 1.n/ e t o 'I sec t est, 1/
Inlake structure
5W ownp no. 33 actor does not start / IMOP33-5 run witti punv SW pwap no. 34 notor does not start / IPOP34-5 run with pini SW purp nn. 35 setor does not start / IMP 35-5 run w i t h pimi SW pur, no. 36 inotor does not start / IMOP36-5 run Cont, am/4Roy Sagr with pwap SW pero,po. 31 control circuit f alls ICCP31-r with puay SW pum no. J7 control circuit f alls ICCP3i-l' witti puev SW pwap no. 33 control circuit f alls ICCP33-F
~
with puan SW pu*p no. 34 control circult f alls ICCP34.F w i t 8 puay SW puno no. 35 control circuit f alls 1CCP35-F witn pune SW peep no. 36 control circuit f alls ICCP36-F Espansion joint swis-3-1 ruptures IKJ5W3IL (1.60 a 10-9 si 6.00 m 10-15 see ten:
41 Intane well I, y
=
(spansion jolnt iWN-3 7 ruptures IXJsW37L A.60 m 10-9 41 6.lM a 10 15 see test 41-(l) lieference - Ref ers to itein nundiers in the plant f allure' data ser.1lun of this report.
~
0626A040281/1 if
<~
TAlU 4 (cont iriued)
BASIC EVENT DATA - INDIAN POINT 3 SERVICE WATER SYSTEM
.. - - -. - _ =
Fault f ailure Data Ownnun B.ause Data (vent Description and f ailure Ptede Irce
- Comarnts (neling M?an ll/D Var iance HilR lief. (1) localisen
'Susceptthillir
.. ~.. _
(spanslun joint 5WN.J.3 ruptures IXJ5W32 A.60 x 10-9 11 6.lNI 10-15 see lest 41
~=
i (spanslim jolrt 5WN-3-4 ruptures IX.15W34L 8.60 a 10-9 11
- 6. Ins a 10-15 see ir :
4; (spanglem joint SWN-3-5 ruptures IXJ5H351.
8.60 a 10-9 11 6.ful a 10-l%
see lest 41 (spanslam joint 5WN.3 6 ruptures IAJ5W36t.
8.60 a 10-9 il 6.Bri 10-15 see lest 4/
rheck valve 5WN.1-1 f alls to open ICir$WilQ 6.91 a 10-5 0
1.03 a 10 8 3
Strainer carinsure 1
Check valve SWN-t-2 f alls to open ICV 5W12Q 6.91 m 10-5 U
l.01 x 10 8 t
1 g
Check valve 5WN.1-3 f alls to open ICV 5Wl3Q 6.91 a 10-5 ' U l.Ol a 1 0 - 13 1
Check valve SWN l 4 f alls to open ICV 5W14Q 6.91 a 10-5 o
1.01 a 10 81
)
4
=
a Check valve SWM-l-5 f alls to open ICV 5W15Q 6.91 m 10-5 0
1.03 a 10-fi 3
=
=
Check valve $WN-l.6 f alls to open ICV 5W169 6.91 a 10-5 0
1.01 a 10-a 3
=
Olscharge valve 5WN.2-1 transfers IAV5W21C 9.15 a 10-8 n
g,og, 30 14 see test I
=
c loscil Olscharge valve 5WN-2-2 transf ers.
IAV5W22C 9.15 m 10-8 11 1.01 m In-14 see test I
=
=
closcel Olscharge valve SWN.2-3 transfers TXV5W23C 9.15 m 10-8 3,og a 30 14 gee geng g
closed Olscharge valve SWM-2-4 transfers IXV5W24C 9.15 a 10-8 16 1.01 a 10-14 see test I
a
=
closed Olscharge valve 5WM-2-5 transfers IEW5W25C 9.15 m 10-8 n
g,ol n 30 14 See test 3
i closed Olscharge valve SWN-2 6 transfers TKV5W26C 9.15 a 10-8 H
1.01 m 10-14 see test I
=
c lose.1 (1) Reference - Peters to lless nuediers in the plant f ailure data section sof this rroort.
0626A040281/1 4
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TASLE 6'
. SYSTEM EFFECTS OF PIPE -FAILURE 7 t:e'.*r::::- ~
Di a.
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0625:3a32!!/1 48
1 o -
c 9
-TABLE 6 (continued)
SYSTEM EFFECTS OF PIPE FAILURE P1:a Se:: :a Dia.
. Systea 8ctential for Nw: lea nea:e-(1.: es.
Fait.*e-0: er Systems Inns:
C0"r;5 6.
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INDIAN POINT 3 SERVICE WATER SYSTEM - CAUSE TAllLE e
Nutlear Header Case l Soundary Conlation: Power Lost at two 48(N $witchgear liuses failure D.ita (llourly)
(Demand) fellure Data (t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) component
=
5 Lifed
.fs?an Verlante ts'an War t.ine e Psaan Variant.e
_ _ =.
A. Single Events
- 1. Piping f ailures (10) 8.60 a 10-9 4.?9 a 10-35 System failure 2.06 10-1 2.41 a 10-12
- 2. Header esolation valves 9.15 s 10-8 1.01 a 10-19 System f ailur er 2.20 a 10 6 5,$3 3u.1/
S. Uouhle [ vents
- 1. Puan trains 4 Pimp f alls to start 1.lb a 10-3 1.22 a lu.h
- b. Puap f alls to run 4.68 a 10-5
'l.07 a 10-9
- c. (spansion joint ruptures. 8.60 a 10-9 6.00 a 10-15
- d. Check valve f ails to open 6.91 a 10-5 1.0) a 1018 h
- e. Denharge valve f ails 9.15 a 10 8 1.01 a 10-14 Single train total 4.69 a 10*5 9.54 a 10 10 g,43, 1o.3 3,32, 30 6 2 uf J pum trains
- 2. [DG flow control valve System failure 1.0 0.0
- 4. valve falls 4.9ft a IO-O 4.03 a 10-1 2 of 2 valves System failure 6.21 a 10-1 I,54 a 10-11 C' Human Error
- 1. Hisposit ioneet switch
-System failure 2.16 a 10-3
't.46 a 10 5 D. Comon Cause
- f. Other
- f. steader total System failure 1.0 0.0
- Negliglhly small f ailure probability.
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