ML041410390

V. C. Summer April 2004 Exam 50-395/2004-301 Final Scenarios

ML041410390
Person / Time
Site:	Summer
Issue date:	04/28/2004
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation
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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 Feedwater 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 Feedwater System capacity:

FEEDWATER 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 flow. OR CRS should direct 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 MAIN CONDENSER VACUIJM. This step will be unnecessary as main condenser 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 Feedwater 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 ~~ . 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 annunciators 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