ML041410390
| ML041410390 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/28/2004 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041410390 (39) | |
See also: IR 05000395/2004301
Text
Final Submittal
V. C. SUMMER EXAM 50-395/2004-3O
I APRIL I9 - 23,2004 April 28, 2004 (written)
1s ES-
Facility:
Vy'. sum me^ Scenario No.:L- Op-lest No.: -1 Initid Conditions:
IC-I61 100% Power BOL. 25 GPD Tube Leak on the "A" SIG. Emergency
Peed SLAVE WXAY TEST Turnover:
Maintain 1000/0 reactor po~er __ --__- _I___ - I--- - Event No. _c_ PRE PRE PRE L 3 4 J 6 TUR-11 2 P Event Description
5- TDEFW over-smeds
on start and will not reset. .Failure of Turbine to trip. ATWS Reactor fails to trip ~- ~ Running EE pump trips. (Must mually start otber pump) Selected P-inv fails low Letdown Pressure Control Valve PCV-145 fails ciosed Place excess letdown in service IT-444 fails High A FW pump trip Ramp unit down to 91% Reactor power . Total Loss of X4ain Feed due to inadvertent
FW isolation. (R)eactivity, (Qnstnunent, (C)omponent, @f)ajor Page 1 of 18
Scenario 1 Synopsis of Scenario.
Pre -event items are to set the simulator
up for a total loss of feed KlWS. Event 1 Select the other EH pump. Direct maintenance
to evaluate the failure of the Pump. Event 2 Selected P-imp fails low interaction
from RO and BOP to take Rods to manual and select out failed chanuel. Could be diagnosed
from either. PCV-145 fails closed, this will cause a loss of letdown and the RO will have to deal with relief lifting, isolating
letdown. Event 3 Event 4 Establish
exccss letdown, Event 5 PT-444 fails high, this will cause the spray valves to open, one PORV to open. The RO will need to close the sprays in manual and close the PORI' prior to a trip parameter
being met. After the valves are closed, and parameters
are stabilized.
The next event can be initiated.
"A" MFP trips. The BOP operator works wih the CRS to perform the immediate
actions of AOP 210.3. RO and BOP coordinate
to reduce load to less than 9IOiO power at 1% per minute. When reactor power is less than 94%, an inadvertent
1;W isolation
will occur, prompting
the CRS to direct a reactor trip as a conservative
decision.
The reactor and turbine does not trip? the TDEFW pump trips on overspeed.
After the *3 MDEFW pump is verified running in EOP-13.0, it will trip on over current. This will put the plant in EOP-13.0 (The reactor trip breakers will be opened locally when S/G levels are less than 45% wide range). 'This will cause the crew to go to Loss of heat sink / fed and bleed. Event 6 Event 7 Event 8 Sc.enario
to be terminated
whcn BFW flow is reinitated
to a SG or at the discretion
of the Lead Examiner.
Page 2 of 18
Scenario 1 .. _.. Actions --~1, Operator . ., 1 BOP 1 Increasing
amps on "A" EHC pump. Receive alarm XCP-63 1, 1-4. .......... - CRSiBOP ...... .... CRSIBOP - ....... TB A0 -- -- Operator removeles
appropriate
ARP, reviews procedure, and hands it to the CRS. "A" Directs/recommend
pump and observes normal ..... .. ............ , "B" EHC pmp. BOP starts e' POWER SYSTEM, section III R. S PUMPS 1. Start the idle EHC pump. 2. Verify the following:
a. Starting amps decay off within 30 seconds. b. The stated pump discharge
pressure is @eater than 1550 psig as indicated
at the EHC unit by HFPM-A OUTPUT PRESSURE or HFPM-B OUTPUT PRESSURE.
c. EHC header pressure is greater than 1550 psig as indicated
by PI-5676, EHC FLUID PRESS PSHG. 3. Place the previously
mnning EHC. pump switch in Aftcr- Stop. This would be performed
only qfter verijkation
that a problem existed, and tk EHC pump in pull- ___ .. . Reports "A" EHC extre Page 3 of 18
Seenaris 1 .... P-imp Fails
Low ..............
........ ~ .... ........ ~ ... i-TGi'ii'6perator
....... ,,~.~. ... - /j ~ ..... RQ i kids step in at maximum rate (72 SPA[). HO receives rrnniinciator . ....... immediate
action per AOP 401.7. TURBINE FIRST STAGE PRESS7JRE
CHz4NiVEL
el: P447, CM RJ -- ..... . .... .........
~~~ I Adjust Control Rods until Tavg.' eck if Main Turbine lo , ..~~... . .. : . - . .... .... ~~~..___ ~. ithin one hour, verify the following
permissives
are dim: . ~13. I S T STG PPZESS. ! desired. Veri@ Reactor power is GREATER THAN 15% (C-5 ...___~ .. ....... ace the failed chan Attachment
1 and documents
on SOP 401, Attachment
1 (FB- 474A, FB-484A, and PB-494A).
BOP operator may verify correct ~. .........
... further actions can he completed
in -. .... Page 4 of 18
Scenario 1 Letdown Pressure Control Valve Fails Closed PVT-81.72, L.TL?NLI.VE
ISOL S will direct the operator to isolate cha .- . ..... 0 Close MVG-8109 0 Close MVG 8108 . ........ 'ch is to Place Excess Letdawn in service. ($an? . ..... .... ... . .... Page 5 of 18
Scenario 1 Letdown Pressure Control Valve Pans Closed .........
..... Actions ,. . ___. -. 'i .. ~ Ensure the following
are open: 11 ....... 7- ___.. CRS,RO 0 MVT-8100, SEAL. WTR R'lW ISOL. e P\7T-8153yXS
L'I'DN ISOL. ........ 0 FVT-8154, XS LTDN ISOL. ..... .... _- Letdown flow: - 0 Slowly throttle open HCV-137, XS LTDN IIX. 0 Maintain temperature
on TI-139, XS LETDOWN HX OLJT TEMP " F, LESS THAN 165 OF. Operator may receive
XCP 603 4-2 when e.xcess letdown is established due to increasing
CCW temperatures.
RO will i make on udjiisrnient
on HCi. 137 if'rhi.~aiarm
i.7 rweived. : hlonitor the following
to ci?surc flow between 0.2 gpm md 5.0 . - ...... .- - ..... , .~ &./R()- II gpm: 1 0 154A. WCP SL LKOFF HI RANGE. plant shutdown.
& TO WP-4, POWER OPERATION
At least 6 gpm Seal Injection
flow Reactor Coolant Pump. Letdown to maintain PZR level at progam level. As neither is
in service the
CRS .. will be ....... directed to the alternative action.
,; j (YOVE I). MA, us excess letdo .. ........ service, THEN ~ ....... Letdown is in service, THEN p control Injection
flow to maintain PZR level at program level. CRS and RO discuss control
of PZR level using excess , Irtdo;rx mrd R(CP seal injecrronfloii, halarice.
..... - ...... ~ .. . . . . -. CKS rv -:- cntv PZR Dresswe is stable at QR trending to 2235 psip, I ~ (2226 psig & 2250 psig). IfPZRyiessure
iislightiJ, high due ~ to increased
PZR level, it may be necessary
to read and discuss alternative action
Control PZR Heaters and Spray as necessary
..... .- '[End of PCV-145 failed closed event Page 6 of 18
Scenario 1 RCS Pressure Cantrot Channel Fails High Actions .............
RO PT-444.fXlng
high:. .. - opening unexpectedly, PCV 444B opening, and/or
one of several alarms, including
XCP 616, 2-5, PZR PCSHI at 2335psig .............
actions of AOP 401.5, PRESSURIZER
PRESSURE.
C.ONTROI, CHANNEL FAILURE. identifies
PCV 444B open with
pressure less than
23OOpsig and closes PCV 444B and ma,y close the associated block valve, MVG 8OOOB. Compares ! PZR pressure channel indications
and ver@s PT-444 is juiled high j (may have been done initially). Places the
MA stations,for
sprczy j valves PCV444C and D in manual and closes both spray valves, i verifiing closed indication
via indicating lights. Places the
pressurizer
master pressure controller
in manual and reduces demand, thereby increasing control
group heater anips to i CEIAh%TEL
FAILURE. ,, Verify the PZR PORVs are closed: .. ... ......... . .... ~ ... ~ EkS e PCV 445A, PWR RELIEF which is to close the associated block valve within one hour (to I sati& the ... T.7 action). ~ .. . . .... .__- -. ... . PCV-4442.
PZR SPRAY. PCV-444D, PZR SPRAY. Page 7 of 18
Scenario 1 RCS Pressure Control Channel. Fails High ..............
Actions . ___ 1 PZR PWESS MASTER C O N T R O L in M ressiire controller
is in manual and mps are muximum. ..... . , . s and Spray Valves I KCS pressure between 2220 psig and 2256) psig. RO may request ~ to piace M/A stutions for sprajl valves PCV444C und D buck in I AUTO, us their control will come
directly.from
the pressurizer
/I /I master t requir .. I/ Within one hour: close MVG-8000B.
RELIEF 444 B ISOL. Zfnot performed, RO will close block vulve at this time. " ...... I !I . i ~ 1-445. PRESS cation is .. .~ Ensure ROD-CNTRL
is In AUTO. R ....._ll..-
...... ... psig and 2250 psig. h4uy control ut this time.
... .... ........ se of the channel failure. turned -___~ ...... ___ ieted in AOP 401.5 untilfuiled
e. .. . ~. Page 8 of 18
Scenario 1 ........ ................
Operator BOP ....... ..... BOP!RO C.RS CRS/Bo~ CRS . CRS/BOP ...........
CRS/BOP .. .... Actions .... ..........
.........
'A" MFP trips. Recognizes
pump is tripped and performs mediate actions of AOP 210.3, FEEDWATER
PUMP MALFUNCTION.
BOP vrerifies at least one feedwater
pump is wining, checks that ajkedwater
pump trip did occur, ad checks 'he remaining
feedwuter
pumps for proper response and
veriJes peed is increasing
-. on both. ~ .. .. Pulls ARP for XCP 625, 2-1, FWP A/BiC TNP, reviewy procedure
md/or hands procedure to
CHS. Verify at least one Feedwater
Pump is running. BOP reports "B " ...........
FEED WATER PUMP MALF ..... .......____
2nd "C" MFPs are operating.
Check if a Feedwater
Pump trip occurred.
BOP verifies and -. ... ~ ............
~ ........ ~ ....... .. ..........
.... ..........
.................
___ -.__ that ',A" MFP has . ____I __I Check the operating
Punip(s) speed control for proper response by verifymg Feedwater
Pump(s) speed is increasing.
BOP verifies and reports that both
"B " r4nd "C" MFP speeds are
increasitzg
and response is proper. .~ ~ ... -. ... REFER TO the table below to determine
the Reactor Power limit based on avtiilable
System capacity:
PUMPS REACTOR POWER AVAILABLE
LIMIT 2 MFW PCMPS 3 BOOSTER PUMPS 91% ___.. ...___......___I...
.... ___ ....... __ Verify two Feedwater
Pumps and three Feedwater
Booster Pumps are running. BOP verifies and revorts that "B " and "C"' MFP 's - ~~~ ~ I ... ......... - are running, and that allJour~~,~BP's
are ru - _..I__-- .~ CRS directs BOP to commence plant load reduction
to 91 '% as follows: e Ramp power at directed rate (l"i/min, in 100 mw increments)
Use dec load rate circuit 0 Take turbine off load limiter 0 Energize dec load rate circuit 0 Select desired rate (I %) 0 Decrease load set by 100 mw Maintain MVARs as required ~ coordinate
with dispatcher
Page 9 of 18
Scenario 1 I I I f r-- ....... - i L ....... .........
..........
..... ..~.-____. . e RO borates using normal makeup
controls to maintain
Tavg as jOll0ws. i e Use control rods andor commence boration as follows: 0 Perform a boration per SOP-106 0 Energize B/U htrs for mixing i I 0 Retum WU system to auto per SOP-106 I 0 Maintain AFD within limits I .~ I 0 Maintain rods above WL ~ AFFECTED Feedwater
Pump (GRAPHIC 310 SCREEN). BOP ....... ~ ...... . ...........
CRSBOP . Verify the high pressure and low pressure stop valves close on the ,; Turning Gear: Check if the Feedwater
Pump Turbine is stopped I and ensure the Feedwater
Pump Turning Gear is engaged and I running. Directed operutotfs)
verifi. that "A " MFP has stopped TR 40 ... CRSSE i/ Determine
and correct the cause of the Feedwater
Pump trip. SFr 1 makes calls to the appropriate
mechanical
and I&C maintenance
1 1 representutives.
- I AL.L FRV's will be at .. , ..... BOP I 1 be required to take manual wntroi of FRV's ani KRILKX flow to ~ .... ~ .. . ~.. ...__ ..... ...... ..........
............
t Page 10 of 18
Scenario 1 .........
Reactor Power Reduction
rimd .... .. .. Operator ~ __.__.__ CRSBOP ~ CRS!RO CRS ___ - Astiom ............
__ -~ 1-1 Continue power reduction
at 1% per minute to less than 91% power as follows: e Ramp power at directed rate (l%,"lin, in 100 mw increments)
Use dec load rate circuit 0 Take turbine off load limiter 0 Energize dec load rate circuit 0 Select desired rate (1 %) 0 Decrease load set by 100 mw e ...........
Use control rods and'or commence boration as follows: 0 Perform a boration per SOP-I 06 0 Encrgkze B/U htrs for mixing 0 Web MU system to auto per SOP-106 0 Maintain AFD within limits 0 Maintain rods above R'L .____ - _- ................
___ .... Depending
upon the ti the crew may rea reactor
power less than 9l%prior to the initiation
ojthe next event, which
necessitates
going to set load on the turbine. If this occurs, it is expected that the BOP operator will depress the increase button i the turbine controlpanel
until the "'At Set Load" light is illuminated.
End of 5-10 %power reductio&
...........
..... ~. .~ ........ ~ Page 11 of 18
Scenario 1 Inadvertent
Peed Water Isolathn / ATWS / Loss of Heat Sink .... roximate4y
94% Reactor power, a - . ............
s.mmual Reactor trip. RO attempts to trip the Reactor
jhom the backup trip switch, which is also
I 1 ACTUATION
.. :; ! ... .. .. ... :: 1 .. .. .. .. .. ... .: ! .: ! .. .. , ., ! Switch. Verify all Reactor Trip and ' Bypass Breakers are open. As both reactor trip switches will
have been tried at this point and neither reactor trip breaker has
opened* the CRS is directed to the alternative action:
IF the Reactor will NOT trip using both Reactor Trip Switches, OR is NOT subcritical, THEN GO TO EOP-13.0, RESPONSE TO ABNORMAL NUCLEAR POWER ____ .. ~ ........ ...... ...........
~. .~ .........
if Attempts to trip the Reactor
manudv were unsucre,s,$ul
in EOP ill direct the
IB 80 to tr@ the reactor being in test on K-616 re1a.y on "A" Attachment
1. The 'il "and "B"h4SIV:r
train, and the K-616 relay has
failed on "B" train, thereby will not trip, and then insert control
r0d.v using the jastest manner ............
BOP recognize the
jkilure of reactor trip, and then move on to the
second immediate operator action, attempting
to verzfi turbine i generator trip. Noticing the turbine has not tripped and the stop I valves do not have a closed indication, he will manually depress
I the turbine trip switch, place both EHCpumps in pull-to-lock, und ! I 14 counterclockwise.
..._____ .........
~ I/ I o locallv triD the ,- ........ .... ~ ennt 2. ___ Begins monitoring
EOP 12.0, CRITICAL SAFETY
FUXCTIOXS, the SPDS display on the IPCS continzlously
per the I<OP ~~ ... Page 12 of 18
Scenario 1 ........ .- .. Inadvertent
.......................
........................
Operator ...... Note ....... __ .. .... ALL ~. ALL All :xi Water Isolation
/ ATWS / Loss of Heat Sink ....................
~- CRSiBOP .........
.- ........ CRSIBOP Page 13 of 1X ........ .... ..... .... Actions .............
..... . Manual or Autonlatic Rod Control
muy be used Alternative
Action Step I, whichever
provides the.fustest Control Rod ins
Verify Reactor Trip: ............
_______ e e e e Trip the Reactor using both Reactor Trip Switches.
Verify all Reactor Trip and Bypass Breakcrs are open. Verify all Rod Bottom Lights are lit. Reactor Power level is decreasing.
As the alternative
actionfor
step 1. IF the Reactor will NOT trip OR is NOT subcritical, THEN insert
Conti~l Rods. Ho may insert rods in manual until there
is adeqziate
Tavg/Tref
deviation
to permit insertion
at greater than 48 SPM. Trip the Reactor per ATTACHMENT
1 One member
of operating crew directs the
IB A0 to peujorm EOP 13.0. A TTACHMEAVT
I, TRIPPING THE REACTOR ...........
..... ~ ot tripped, the CRS will move
to the R ... ..........................
LOCALLY. Verify Turbine/Generator
Trip: Verify all Turbine STM STOP -. ~ ..... ~ .........
~~ ... _~ .... ~ .........
VLVs are closed. BOP operator reports that all
stop vulws are not closed, and may report completion
of actions or verifi steps a7 read by CRS, as follows:
Perfom the following
until all VLVs are closed. Turbine STM STOP OR MS Isolation
and MS Isolation
Bypass Valves are closed: 1) Trip the Turbine: e e e e Depress Emerg Trip Sys TRIP. Set LOAD LMT SET fully Counterclockwise.
Place EHC Pumps A and B in PULL TO LK NON- A. Trip the Main Turbine per ATTACHMENT
2, TRIPPING THE MAIN TIJRBINE LOCALLY. 2) Close all MS Isolation
and Bypass Valves: e MS Isolation, PVM-2801A(B)(C).
e MS Isolation
Bypass, PVM-286YA(B)(C.).
.. Ensure Generator
Trip (after 30 second delay): Ensure the GEN BKR is open, the GEN FIELD BKR is open, and trip the EXC FED CNTRL. _____~ . .... ...... ___
Scenario 1 Imadverteent
Feed Water Isoiation
I ATWS / Loss of Heat Sink .........
Time ~ Operator ALL .. . ....... CRSWBP Actions ... ...... ~ ___.~ .........
~ - ...........
___ Ensure EFW Pumps are running: * Ensure bofh MD EFW Pumps are running. Verify the TD EFW Pump is running if necessary
to maintain SG levels. IIUP operator notes thut the
TIlEFlVpinnp
is not running, which prompts the CRS to read the ulternative
actions. StarttheTD
EFWPump: I. Ensure at least one of the following
is open: ...____ ~ ........ ........ ~. ........ ~~ o MVG-2802A, MS LOOP B TO TD EFP. OR MVG-2802B;
MS LOOP C TO TD EFP. 2. Open PVG-2030, STM SPLY TO TD EFP TRN A@). i I BUF operator reports that
all valves are
..... open. ........ I Investigation
may reveal the presence
ofXCP 622, 3-4, I'D EFP STP VLVNOT OPEN OIL PRESS LO, indicating
the VALVE, is mostprobabk
closed. ABLL AO will be dirt.cted
to .. ........ ........ ~. .. ................
'I -' XW02865-EF, EF PUMP TC'RB MAIX STEAM TWROTTIJ~
i i j ..... . ....... 1 investigate . .- c 0 Initiate em *the RCS: Ensure at least one Charging Pump is running. RO reports that both the
"A " and ....... ___- - It will he noted that there
is now a redpath onheat sink by the SE, at which time the board operators will note
the toss of the "B" MDEFW pump. Other than direction
by muintenance
and building ouerators
to investigate, no other action
is performed as
EUP .. --F il 13.0 remains the highestpriori
\. enfy PZR pressure'&
LESS THAN 2335 psig. RO reports ___ nd ojPZR pressure.
qf SI actuation, booth operator
w8iN remove the ..... ........ .... j closure signals
on "A" and "B" MSIV's (I&C cume out of test i' when they heard
the relay actuations
in the relay room), as i well as locally
open the "A" and "B" RTHS. SiG WR level j shouldshrink
down to -10% following
completion
of these -. ...........
....... SI flow on FI-943, GPM. RO reportsflow
rate. Page 14 of 18
Scenario I Inadvertent
Feed Water Isolation
I ATWS I Loss of Heat Sink ... 'I .............
.............
~ If an SI signal exisg"or occurs, Steps I through 8 of EOP-1.0 j REACTOR TRIPiSAFETY
INJECTION
ACTUATION
I ACTIJATION, should be performed
to verify proper SI, ._ . . -. sctilaticr., while continu:ng with this
procedure.
Dirccf.r HOP operanlor
10 pcyfonn thc srip 1-8 oj'COP 1.0. . - ! 1 CRS BOP ...... _______. ....... 1 CRSRO ~i~VerifyCont
Valves closed by .........
.... CRSIR . ., -. ~ CRS .... ........ CRSIRO verifying
the following
SAFETY INJECTION
monitor lights are dim: XCP-6103 3-4 (POST ACCID HR EXH 6057 & 6067). XCP-6104 2-1 (POST ACCID HR EXH 6056!6066).
~ _ ~. .................
Verify the Reactor is subcritical:
a. Power Range channels indicate LESS THAN 5%. b. Intermediate
Range channels indicate a negative startup rate. A0 reports indications, which
are a positive responseJor
verij%ation
that the reactor is subcritical.
CRS proceeds to step I5 ofEOP 13.0. RETURN TO the Procedure
and S briefwill occur, and
the SE will report thut a redpath exists on heat sink^ The CRS will transition to
EOP 15.0 RESPOIVSE'
OF SECONDARY
IIEAT SINK. Check if a scondary heat sink is required:
.. ~- ... .........
~ ... a Verify RCS pressure is GREATER THAN NON- FAULTED SG pressure. , j ~ Verify power is available
to &l PZR P I o MVG-8000A, RELIEF 445 A ISOL. MVG-8000B, RELIEF 444 E ISOL. 0 verify RCS ahit is GREATER THAN 3500 F ...... .. ~__ .......... . .................
..... lock Valves: .I e li :t :- : : I L , . .. .. .: , iI ___ 1 a MVG-8000Cl
.. ....... RELIEF .-'L 445 B ~~ ISOL. ~ ..... . -. I .o uen the Block Valve for any PZR PORV that has been isolated due to excessive
seat leakage: e MVG-8000A, RELIEF 445 A ISOL. MVG-8000B9
RELIEF 444 B HSOL. 0 MVG-8000'2.
RELIEF 445 I3 ISOL. None have been
closed due to excessive leakage, but MVG Page 15 of18
Scenario I Inadvertent
Feed Water Isolation
/ ATWS / Loss of Heat Sink ... .~.. Time . , . ~.~ ~ ... ... Critical ....... _- Critical ............
..I____ ..............
Operator Cautioiz ....... CRS) ................
CRS/BOP Caution (CRS) CRSIRO .... CRSRO ........ CRSIRO CRSIRO CRSIBOP .........
CRSIRO ... ... .~ . ~. Actions ....... .l_l_ll_....
............
..................
If Wide Range level in any SGY is LESS 1Ha4N 15% [2506] OR PZR uressure is GREATER THAN 2335 psiz due 10 loss of - - ..~ secondary
heat sink, Steps I7 through 24 should be imntedi&ly
............................
initiated&
bleed andfeed ...............................
cooling. ds to step I7 to initiate bleedand feed base identijication
ofSG WR levels <15% in two or more SGs .................
____ .............
___~ ....... Stqs 14 through 24 must be performed
quickly to establish
RCS heat removal by RCS bleed and feed, to minimize core , a. Ensure at least one Charging Pump is running. b. Ensure all the following
are open: * MVG-8801A(R), HI HEAD TO COLD LEG NJ. * e e LCV-l15B(D), RWST TO CHG PP SUCT. Verify COLDMOT LEG RECIRC monitor lights are dim on XCP-6 104. Verify SI flow on FI-943, CHG LOOP B CEDIHOT LG FLOW GPM. ....... . . . Resct Containment
Isolation:
- RESET PHASE A - TRAIN A(B) CNTMT ISOL. RESET PHASE B - TRAIN A(B) CNTMT ISOL. a. NON-ESF L.CKOIJTS.
_- e Start one Instrument
Air Compressor
and place the other in Standby. Open PVA-2659, INST AIR TO E3 AIR SERV. e &en PVT-2660. AIR SPLY TO RB. .. Page 16 of 18
Scenario 1 ....... ... Actions li_. The RO may requei?that
the cooling wter be ndjusted to the ~~ ressor locally per the attached caution
tag. ...................
.- ~~~ . .........
an RCS bleed path: e Open all PZR PORVs: Open all PZR PORV Block Valves, MVG- 8OOOAA(B)(C)
o PGV-445A.
PWR RELIEF. o PCV-444B.
PWR RELIEF. o PCV-445B.
PWR =LIEF. -. ..... ----____I_
IJ'RB pressure increases
to GkATER THAN 12 psig. RE Spray should
be verifedper
EOP-1.0. REACTOR TRIPBAFETY
INJECIION
A CTUA TION, Step 8, to prevent
....... ... ___ containment integrity. -I Steps 1 through 8 of EOP-1mEACTOR
TRIP/SAFETY
INJECTION
ACTIJATION, while continuin, with this procedure.
Tk BOP operator hadpreviously completed the
fht 8 steps ofEOP 1.0 and verqiicntion
that R ................. has not actuated is ail that is antic ........ . .... Maintain RCS heat removal: Maintain SI flow. e Maintain at least two PZR PORVs open. .. ___ ~- Check if RB Spray should be stopped: e Check if any Rl3 Spray Pumps are running. None are at this point, which directs the CRS to the altwnatii
action. If RCS That is stable OR decreasing, feed flow shoulc be established
slowly to only one SG until Wide Rang level indication
increases.
Feed flow should be established
slowly to prevent .~ - ~. __- ___.., .. e ............
.. ________-
.........
SE reports that electrical maintenance
has,fouad
the problen and repaired the breaker fo Continue to try to establish
a secondary
heat sink in at least o SG: ~___ " .44DEFWpump.
.. .... .. ........ 0 REFER TO Step 5 for EFW flow. REFER TO Steps 8 through 11 for Feed md Condensate
BOP operator to prepare
to start "B MDEFWpump
and refer to step 5 of this procedure.
Page 1'7 of 18
Scenario 1 Inadvertent
Feed Water Isolation
/ ATWS I L O SS of Heat Sink... ... ..... I ALL Actions .- .......... , .. ...... ...____. . .... . Try to establish
EFW flow to at least one SG: e e Check Control Room indications
for the cause of EFW failure: Verify no EFW annunciators
are lit. Several are, and appropriate
ARP 's will have
ulreudjj been rejerenced.
Verify CST level is GREATER THAN 5 ft. Ensure power is available
to both MY) EFW Pumps. Power is on& avuiluble
to "B " MDEFWpump.
Electrical
maintenance
reports the hreuker trip problem has beenjbuiad
..... unci corrected.
~, e EFWvulves
should NOT he opened to SGs with Wide
Runge level LESS THAN 15% [2596J. If Wide Range level in all SGs is LESS THAK 15Yo [as%]. EFW valves should be open to only one SG, until RCS temperatures
are decreasing, to limit any The CRS will direct the BOP operator to throttle closed on The CRS will direct
the BOP operutor to start the "B" * failure to one SG. .... - ....... __ ........ 541)(3551), MI) EFW TO SG .. A .. . -- .... -- ... - .- .. MDEFWpump.
The CRS' will direct
the BOP operator to slowlv open FCV 3531 and feed A" SG ut 50-100 GPM, vJhile the RO monitors " "A" loop RCS temperutures.
End ofscenario
___I__I __ I ...............
...................
... -<m Page 18 of 18
Scenario 2 Appendix D Scenario Outline
Form ES-B-1 Facility:
V. C. Summer Scenario
No.: 2 Op-Test No.: 2 Examiners: Operators:
Initial Conditions:
IC-162 25% Power
MOL. 25 GPD Tube Leak on the
" A" S/G. Emeraencv Feed Water Pump
'8' (XPP-21 E)) inoperable
for maintenance.
watch in effect. RMA 9 80s Turnover: Ramp
unit up to 50% power per G6P-4A (POWER OPERATION
-MODE 1 ASCENDING)
startina at stes 3.1 1. Severe Thunderstorm
amp unit toward 50% power. After desired increase initiate
Space Break 5Ogpm to 600gpm ramped in over Page 1 of 20
Scenario 2 Synopsis of Scenario.
Desire is to be at 25% power on the FRV's, and to continue to ramp unit towards 40%. Event 1 Ramp up towards 40% power. (Reactivity
for RQ) Event 2 A charging pump has sheared shaft.
RO should isolate letdown, rack
in the C charging pump
on A train, start the C charging
pump, then reestablish
letdown per AQP 102.2. A Main Condenser
Vacuum pump trips, BOP should start standby vacuum pump
and open associated valve.
FT 474, selected steamline
flow transmitter
for A SG fails low, BQP should take manual control and control
S/G level. A RCP trips (does not cause a reactor
trip <38% power). BO takes action
to control RCS pressure due
to loss of a spray valve.
Must be in mode 3 within one hour. Failure of Pressurizer protection pressure transmitter (Beginning
of steam space
break). Event 3 Event 4 Event 5 Event G When steam space break gets large enough Crew should
SI. Phase A will not actuate (can
be performed
manually, but valves 81498,2660, and 7501 do not reposition
and backup valves used for verification).
Scenario to be terminated
at the entry
to post LOCA cooldown and depressurization or
at the discretion
of the Lead Examiner.
Page 2 of 20
Scenario 2 Power Ascension
540% ...... alt dilution as follows: 0 Perform an ait dilution per SOP-106 I' 0 Energize BAJ htrs for mixing 0 Return MKJ system to auto per SOP-106 0 Maintain AFD within limits I 0 Maintain rods above WL .... ! -.- e Coordinate
with RQ and Use inc load rate circuit ! i 0 Take turbine off load limiter ! I 0 0 Dial load limiter fully clockwise
Increase load set to raise load at %% per minute i ! sin MVARs as required - coordinate
... _~ .... %power ascension.
._I_ ....... ___^___ . . Page 3 of 20
Scenario 2 'Af Charging /SI Pump Sheared Shaft ~~~~~~~. .- ...............
___ ___. .........
.- .. .... .... ~ ....... .__ .lo amps) and alarnt ....... __ ....... __~ .- ..... ___ ....... __ ~. ....... __ Enters AOP 102 m FI-l22A, CHG FLOW GPM, between 30 gpm and 115 @m. e Pump amps between 30 amps and 50 amps. PI-121, CHG PRESS PSIG, between 2650 psi@; and 2850 psig. Both flow and discharge
pressure indicate zero, and amps indicates
-10, -. ... ... ...... .- ... Page 4 of 20
. ... ..... ....... .- ..... ERSiRO ~ .,, ERSiRO CRSIRO ..... CRSIRO .. ... CRS!RO . Scenario 2 'A' ... Charging /SI Pump ... Sheared Shaft ...........
.. .... IF Charging P&p has tripped or flow is abnormal, THEN perform the ~~ ~~ following:
a) Ensure the Charging Pump is secured. b) Close all Letdown Isolation
Valves: 1) PVT-8149A(B)(C), LTDN ORIF1C.E A(B)(C) ISOL. 2) PVT-8152, LTDN LINE ISOL. 3) LCV-459, LTDK LME ISQL. 4) LCV-460, LTDX LINE ISQL. C) Close FCV-122, CKG FLOW. d) Verify CCW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), THERM BARR FLOW GPM. RML-I trouhle alarm when Letdown flow is isolated.
RO reportsflow indicates normal.
e) Display Dedicated
Display ZZRCPBRG on lhe IPCS to monitor KCP temperatures.
SE and/or BOP operator may he directed to monitor
RCP temperatures
f) Contact Electrical
and Mechanical
Maintenance
to investigate.
............
____ Verify Charging System valve lineup: IF Charging Pump wction is aligned to the VCT, THEN ensure both LCV I15C(E), VCT OUTLET SOL, are open. Both are open. Ensure the following
valves are open: ~~~ ___ ....... ____ .. 1) MVG-8106, CHG PP 2) MVT-8109A(B)(C), CXIG PP A(B)(C). 3) MVG-8130A(B), L.P A SUCT TO CHG PP C. 4) MVG-8131A(B), LP B SLJCT TO CBG PP C. 5) MVG-8132A(B), CIIG PI' C TO LP A DISCH. Q LP B DISCH 1) Ensure MVG-8107, CHG LINE ISOL, is open. 2.) Ensure MVG-8108, CHG LINE ISOL, is open. Both are open 3) Ensure FCV-122, CHG FLOW, is in MAX and CLOSE. ROplaces E%V 122 in manual and
minimum demand 4) Ensure one ofthe following
valves is open: .... ... PVT-8146, NORM CHG TO RCS LF B. OR FVT-8147, ALT CHG TO RCS LP A. RO reports available
charging path. Verify VCT level is GREATER THAN 20%. .. .. ~ .. . ~~ ..... Page 5 of 20
Scenario 2 . _____ ...... ....._____
... .. time that the C chargimgpump, A train has been racked ia. The ABLL Letdown in service. REFER TO SOP-102, CHEMICAL AND VOLUhE CONTROL SYSTEM. RO opeits SOP 102 to section I,. RE- ESTABLISHING
CHARGING AND NORMAL LETDOWN AFTER .... . . - . . -. ....... , in VCT. ROplaces the ...... --. . __ .........
~ .. it. LCV-459, LTDN LINE ISOL. ....... Page 6 of 20
scenario 2 n Orifice IsolatioiValvissain
th 0 PRESS LTB FLOW, in AUTO per Section 111. RO twits tu SOP 102, section E, a. PZR LEVEL MASTER CONTROL. .....................
__ .... ___ .. b. FCV-122, CHG FLOW. RO Adiust FCV-122. CKG FLOW, in MAN to establish
PressurizeFLvel
at -. ........ - ~ ...... ~ !I or near programmed
level. RO FCV-122, CHG FLOW, control as follows: Determine
the correct PZR LEVEL MASTER CONTROL setpoint by dividing the current Charging flow by 1.5. Ifthe RO selects 85 gpm as a nominal value fur chargingJow, then the setpoint will be 57%. Ifthe MASTER CONTROL to this ~ maintain Pressurizer
level at or near programed
level. A$er munituring
I for any unexpected change
in FCV 122 demand/position, the RO will place the PZR MASTER CONTROL in ACJTO. ...... . ... .... Page 7 of 20
scenario 2 ..........
........ %%en Pressurizer
level is at or near pro ..................
..............
_I- Charging flow is maintaining
actual Pressurizer
level at or near the programmed
setpoint.
RO monitors for the proper operation
of the PZR ~ level control system, then returns to theJinal step of SOP 102, section L. ~ RE-ESTABI~ISEIINC;
CHARGING AND IVOWL LETDO WAFTER ISOU TION AT OPERATTNG
CONnlTIONS
~~ ~~ ....... ...........
.... ~. ..........
... 0 Afier the Letdo matures have st Page 8 of 20
...........
Time ..........
.... . scmario 2 'A' Main Condenser
Vacuum Pump Trip ,. ............
.........
-. ~~~ .............
.. ..........
...........
~- .............
~ Oper ~ Receives annunciator
XCP 628, 1-1 CVPA I notices that
the A CVP has tripped and
handy the associated
ARP to the operator .. .. CRSfor review. s, the CRS will direct
tlee TB A0 rprobable cause, starting
ut the breaker. ....... . .~ I_- ... ~ ..........
CRSiBOP If Main Vacuum Pump A tripped, perform the following:
a. Open MVB-l02A, VAC PP C TO CNDSR A. c. Place XAC-OOOlA, MAIN CVP A, to STOP. b. Start XBC-OOOlC, MAIN CVP C. BOP operator aligns C CYP to A condenser, starts the pump, and then places the switch.for
A CVP in stop, once directed
and/or concurred with
.. ...... ;~ ................
__ by the CRS. Verify vacuum is stable on PI-3006(3016), MAN A(B) PRESS INCHES If necessary, start the following
ucr SOP-206: .__ .........
...........
~~~ ...... . a. XAC-OOO~A, AUX CGP A. b. XAC-O002B, AIJX CVP B. Vacuum will
be stable and this will not
be necessary.
Refer to AOP-206.1, DECREASING
VACUIJM. This step will
be unnecessary
vaceium will be normal and stable. Investigate
the cause ofthe vacuum pump trip and correct as soon as possible.
The TEA0 will have reported
an overcurrent
flag on the breaker at the IB switchgear. Electrical maintenance
will be called to investigate
and a tagout will be requested
to be prepared for .~ .... ..... ___~~_ ~ .......... . . ~ ....... ....... ........ ... . ....... . Page 9 of 20
Scenario 2 ..... .*.... ...... FT-474 Steam FIow Transmitter
Fails Law .. Operator '1 Actions BOPiRO ..............
,. ....... .__- ....................
IT 474fails low. Receive annunciator
X'GP 624, 4- MIShlA TCH. BOP operator scans MCB indicatinns
and notices that ~ CPIIII steam flow is pegged low. One operator will pull the ARP and i .... .... ..: . P?!!?. .........
Quickly determines
that an instrument
failure has occurred and -r-- implements
AOP 401.3, STEAM FLOW- FEED WATER FLOW __I CRS BOP Performs immediate
operator actions ofAOP 401.3, determining
that the failed channel is the controlling
channel, selects both SF and FF for A SG to channel IV (the operable channel), yerifjt turbine load is less than 950 MWe, verifjt only one SG is affected, takes manual ~ control ofFCV 478 @necessary), increases
FWr,lflow
to A SG using ' channel IVindications.
benins restoring
SCi level to 60% to 65% (if 1" ... .~ CRSIBOP CRSIBOP Place FW CONTROL CHANNEL SEE Switch to the operable channel. 0 Place STEAM CONTROL CI-IAhXEL
SEL Switch to the operable channel. BOP selects FWj'low to 477 and S~eamj'low
to 475 (both switches io the rightfor A SG) ESS THAN 950 MW; ...... ___~~. .. ..... ..___ ....... Verify only one SG is AFFECTED.
BOP reports that A is the only __ ........ flow to the AFFECTED SG. BOP is a&ustingFCV478
to provide a flow than steamflow
on A SG, ifslow in selecting
~ ..............
................................
i value and trend for A SG level. -~ .........
_. Page 10 of 20
sceraario
2 ~. .... .. ..... - _II. ~ ....... ET-174 Steam Flow Transmitter
Fails Low Che:k. if Feedwater
Pump speed control is operating
properly:
... .. ....... ....... 0 Feedwater
Header pressure is GREATER THAN Main Steam Header PK~SSUR. BOP reports that
feed header pressure is approximately
I 00 psig higher than steam header
pressure.
Feed flow is normal for steam flow and power level. BOP reports normal indications
for feedpow and stenm.flow.
All operating
Pump speeds and flows are balanced.
0 ___. BOP reports all speeds andflows are balanced.
... ....... .. ........ Verify Narrow Range level in all SGs A SG level may still
be below the normal range. The
CRS nzq~ or may not move to the alternative action, at his discretion.
!f he does, thep? the actions
will be asfollows:
Adjust the Feedwater
Flow Control Valve as necessary
to restore feed flow to the AFFECTED SC;{s). WHEN all SG levels are restored to bctween 55% and 65%. THEN CONTINUE WITH Step 7. Restore the AFFECTED SG control systems to normal: ..______ ....................
....... ~ ___ * Place the Feeclwater
Flow Control Valve in AUTO. Place the Feedwater
Pump Speed Control System in AUTO. REFER TO SDP-210. FEEDWATER
SYSTEM. me1 protection
bis ..........
__~ tripped condition:
a. Identify the associated
bistables
for the failed channel. REFER TO Att:ichnitx~t
I. b. Record the following
for each associated
bistable on SOP-401. REACTOR PROTECTION
AKD CONTROL SYSTEM, Attachment
I: 0 Instrument
e Associated
Bistable 0 Bistable Location e STPps c. Notify the I&C Department
to place the identified
bistables
in trip. SE willfill out the bistable trip sheet and the
BOP operator will verifi the sheet, as well as locate the applicuble
bistabk status lighfs on the MCB. The Bop operator will work with die Z&C technicians
to ensure .. the correct bista!des
we rrippod. Deteimix and correct the c~ilse of the chard failKc. SI:' \rill direct I&C to investigate
and develap u troubleshooting
plan. No further ................
401.3 at this time.
I ...... .. ~ - ..... d low event ~~~ .. Page I I of 20
Scenario 2 ...... ..............
~____ ...... .........
.- ceives annunciators
XCP 61 7, 1-1 RCPA-TRIP
andXkP61.7, 1-1 - ~~ . t the crew stop any .............
........ turbine to set load and s .... ..........
TOR COOLAMII'PUMP
FROM SER vI(:E: directs place the or Coolant Pump A. The CRS will direct the KO to place PCV a. PVT-478, SG A FWF. b. FCV-3321, LOOP AMAIN FW BYP. , Page 12 of 20
Scenario 2 ..................................
Use dec load rate circuit 0 Take turbine off load limiter 0 Energize dec load rate circuit 0 Select desired rate (li2% per min) 0 Decrease load set by 100 mw ..........
0 Perform a boration per SOP-106 0 Energize B/U htrs for mixing 0 Return Mill system to auto per SOP-106 0 Maintain AFD within limits ..... .. ,. Page 13 of 20
...... ~ The ..... .. ~. ...........
I_. ..........
_I Operator CRSiRO -- . All ........ ..____. CRS .................
ERS.RO ...._____
CRSk0 scenario 2 Pressurizer
Steam S e Break - LOCA A break occur~s on the. high side of the following
trunsmitters, resulting
in a PZR steam space
break: PZR I, VL ILT440 (faiuils high) and PZR PESSprotection
IPT456 (fails low). There
will be a high volume of annunciators at this
point, but the kqv indicators
for the crew skould be an increasing
pressurizer
led, a decreasing
pressurizer
pre.ssure, and an increasing
RB pressure. Receive annunciators
XCP 614 5-1 and XCP 404 & 607 2-2. The crew ~*ill evuluate the indications
and ma.y utilize drawing 302-602 to identijj where the
sol~rce qf the break may be, but
the CRS will ultimately
make the decision respond
to the an RCS leak. CRS enters AOP 101.1 LOSS OF REACTOR COOLANTillBT
........ ............
_. ........... . .... ........................
.........................
~. . ~- ...... ~ .... . ... ~. PZR will decrease, directing
the CRS to the alternativ
Check if SI is required:
a. Check if any of the following
criteria arc met: ______ ..... ....... ..........
e PZR level is decreasing
with Charging maximized
and Letdown minimized.
PZR level is approaching
12%. PZR pressure is approaching
1870 psig. VCT level is approaching
5%. OR OR OR 0 0 e b. Perfom the following:
1) Trip the Reactor. ACTUATION
WHEN EOP-1 .O Immediate
Actions are complete, THEN actuate SI. 2) GO TO EOP-1 .O, REACTOR TRIPBAFETY
INJECTION
NOTE: CRS should direct Reactor Trip as RCS pressure approaches
..... .. Page I4 of 20
__ ___. ........ CRS BOP CRSIB CKS,RO;BOP
____ ....... CRS!RQP Note ,._____ CRS!RO scenario 2 Pressurizer
Steam Space Break - LQCA ... ....... ~ .~ .................
............ . ... ens observed PZR level initial[v decrease, then increase
at some point while minimizing
Letdowin.
Ultimately, the criteria to SI bused on PZR pressure approaching
1870psig will be reached and the
CRS will direct a Reactor
trip, transition
to HIP I. 0, complete immediate
operator actions, then actuate
SI (ifnot alreudy azctomaticullv
actuated).
Automatic
SI actuation will
depend on when the crew decides
to initiate a manual reactor trip.
..... ~ - .........
.......................
.............
____ __lll e e Trip the Reactor using either Reactor Trip Switch. Verify all Reactor Trip and Bypass Breakers are open. ghts are a. Verify all Turbine STM STOP VLVs are closed. b. Ensure Generator
Trip (afier 30 second delay): 1) Ensure the GEN BKR is open. 2) Ensure the GEN FIELD RKR is open. c. Trip the EX FLD CNTRL. Verify both ESF buses are energi Cheek if SI is actuated:
a. Check if either either: - . ._.___ ......... . ......... . ..... . e SI ACT status light is bright on XCP-6107 1-1. Any red first-out SI annunciator
is lit on XCP-626 top row. OR ........ ..... ....... - The failure of Phase A eo as he walks down the board,following
the sufety injection.
or it should
he caught us the BOP operator isperSorming
EOP 1.0, attachment
3. The actions will
be the same.fir either operator, dien discovered:
Actuate Phase MContainment
Ventilation
Isolation
by placing either CS SG02A(R)9
........ TRAIN A & B, Switch .... to ACTUATE. ____.. .. ~ .. Announce plant coditions
ow: the page system. Verify RB pressll-e
has remaificd
LESS 'WAS 12 psig on PK.-9G,.iZU'
.... ...... __ ........ - ...
... Time ..... Critical ..... -- scenario 2 Pressurizer
Steam Space Break - LOCA ....... - ................
ck RCS tanpaahre:
With any RCP running, RCS Tavg is stable ......................
........................
.- - 'I at OR trending to 557 'IF. PORVs and Spray Valves: a. PZR PORVs are closed. b. PZR Spray Valves are closed. c. Verify power is available
to at least one PZR PORV Block Valve: o MVG-XOOOA1
RELIEF 445 A ISOL. e MVG-8Q00B1
RELIEF 444 B ISOI,. * MVG-8000C, RELIEF 445 B ISOL. d. Verify at least one PZR PORV Block Valve
is open. Check if RCPs should be stopped: a. Check if either of the following
criteria is met: ~ .. .. . * e Annunciator
XCF-612 4-2 is lit (PHASE B ISOL). RCS pressure is LESS THAN I400 psig AND SI flow is indicated
on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. OK 1 If anv of the above criteria are met. then stou all RCPs. ...........
CRS/SE .................
I/ No SG pressure is decreasing
in an uncontrolled
manner. I____-_ ... levels indicate SG tubes RIJPTURED:
- RM-G19A(B)(C), STMLN HI RNG GAMMA. e RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR. RM-L3, STEAM GENERATOR
BL.OWDOWN
LIQUID MONITOR. RM-LIO, SG BLQWDOWN CW DISCHARGE
LIQUID MONT o ....... ............
~ _____ .. ~ .. ___- Page 16 of 20
scenario 2 .... .... ....... ace Break - LQCA - - ............
a. RE3 radiation
levels are normal on: 0 * RM-G7, CNTMT HI RNG GAMMA. RM-GlR, CNTMT HI KNG GAMMA. b. RB Sump levels are normal. c. RB pressure is LESS THAN 1.5 psig. d. The following
are NOT lit: * XCP-606 2-2 (RBCU lM2A DRN FLO HI). ! 0 XCP-607 2-2 (WCU 1BI2B DRK FI,O HI). '1 GO TO EOP-2.0, LOSS OF REACTOR OR SECONDARY
'1 Check if RCPs should be stopped: a. Check if either of the following
criteria is met: a 0 Annunciator
XCP-612 4-2 is lit (PHASE B ISOL). OR RCS pressure is LESS THAN 1400 psig and SI flaw is indicated
on FI-943. CHG LOOP B CLDIHOT LG FLOW GPM. b. Stop ALL RCPs While the criteria for securing RCP's may not be net at the time this step is read, this is a continuous
actiun step md the critwiajor
being less than 14OOpsig with SIJow indicated
on FI 943 will be met early in EOP 2.0. Verify no SG is FAULTED: ..... - ....... ~ ..... .~ .... ..........
NO SG pressure is decrezsing
in an uncontrolled
manner. ....... ~ ....... ~ ~ a. Verify Narrow Range level in INTACT SGs is GREATER THAN b. Control EFW flow to maintain Narrow Range level in each INTACT 30% [SO%]. I .. SG between 40% Reset both ..... .- Reset Containment
Isolation:
- RESET PHASE A - TRAPN A(B) CNTMT ISOL. RESET PHASE B - TRAIN __~ A(B) .__ CNTMT .... ... ISOL. . .~. : Page 17 of 20
scenario 2 Pressurizer
Steam Space Break - . ...____. ~ ............... . .~ .........
Ti if Secondary
radiation
levels are normal: a. Check radiation
levels normal on: * RM-G19A(B)IC), STMLN 131 RNG GAMMA. e e WM-A9, CNDSR EXHAUST GAS ATMOS MONITOR. WM-L3, STEAM GENERATOR
BLOWDOWN LIQUID MONITOR. RM-LlO, SG BLOWDONN CW DISCHARGE
LIQUID MONITOR. b. Place SVX-939XA(B)(C).
SG A(B)(C:) SMPL ISOL, in AUTO. c. Notify Chcanistry
to sample all SG secondary
sides and screen samples for abnormal activity using a frisker. Check PZR PORVs and Block Valves: a. Veri6 power is available
to the PZR PQRV Block Valves: e ~ ............
~ ........ 0 MVG XOOOA, RELIEF 445 A-ISOL. e e MVG 80OOl3, RELIEF 444 B ISOL. MVS-8OOOC, RELIEF 445 E ISOL. b. Verifv all PZR PORVs are closed I , ._ : c. Veri3 a: least one PZR PORV Block Valve
is oper.. . __ ~ ...... . __ .... ' CRS BOP Place both ESF LOADMG SEO A(R) RESETS to: i a. NON-ESF EMOUTS. b. AUTO-START BLOCKS. ....... a. Start one Instrument
Air Compressor
and place the ether in Standbj RB AIR SERV. 1 c. Open PVT-2660,'AW
SPLY TO RE. ....... ___ ........ Page 7 8 of 20
Scenario 2 .~ ..... rime -~ ~. ..........
.~ .. _I -. ...... .. Operator &S/RO/BOP
... - C CRSiBOP -~ .. SiCB A0 CRS!RO!SE
............... Pressurizer Steam
Space Break - LOCA ~ ..........
... ...........
-. ..........
Actions Check if SI flow should be reduced: a. RCS subcooling
on TI-499A(B), A(B) TEMP OF is GREATER THAN 30°F. Subcooling should
be 30°F. ...... ..... . ... ...........
Check if RB Spray should be stopped: Check if any RR Spray Pumps are running. th R pumps shouldb ____- None are running, directing
...... a. Check if any RHR Pump is running in the Si Mode. b. Check RCS pressure:
I) RCS pressure is GREATER THAN 250 psig 2) RCS pressure is stable or increasing.
c. Stop any RHR Pump which is mnning in the SI Mode and place in St'mdby. ....... ______ Check if pressure in all SGs Is stable or increasing.
BOP should report SG pressures
as stable. 'Check IfD6ss a. Veri67 both ESF buses are energized
by offsite power. b. Stop any unloaded DG. REFER TO SOP-306. EMERGE.KCY
DIESEL GENEMTOR.
The CRS will di Verify eq a. Verify power is available
for tit least one RHR Pup: ..... ....... ... ... 1) PUMP A. 2) PUMP B. b. Open both MW4503A(B)
CC TO RHR HX A@). c. Shift the CCW Train to fast speed in the Active Loop. REFER TO SOP- d. Consult with TSC personnel
to determine
if equipment
required for Cold Leg Recirculation
is available.
11 8. COMPONENT
COOLING WATER. Page I9 of 20
Time -. ..... ..... ..... .... .. scenario 2 Break - LOCA ..... .... ..... ~ for evidence of ECCS leakage: a. Verify AB radiation
levels are normal on: * RM-A3. MAN PLANT VENT EXH ATMOS MONITOR: PARTICULATE, IODINE, GAS. 6 * RM-A13. PLANT VENT 131 RAXGE. RM-AI 1 AB VENT GAS ATMOS MONITOR. ..........
... ._I_.....__
CRSiROiSE
- Local area monitors.
b. Verify annunciator
XCP-631 6-1 is NOT lit (AB SMP LVL. HI). c. Verify annunciators
XCP-606 3-4 and XCP-607 3-4 are NOT lit (LD b. Notify Chemistry
to sample the following:
- RCS: ~~ . ...... 0 ~AO . heck if RCS cooldown and dearessurization
is required RCS pressure is GREATER THAN 250 psig. b. GO TO EOP-2.1. POST-LOCA COOLOOWN A?JD Page 20 of 20