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
References
Download: ML041410390 (39)

Text

Final Submittal V. C. SUMMER EXAM 50-395/2004-3OI

-

APRIL I 9 23,2004 April 28, 2004 (written) 1s ES-

Facility: Vy. sum me^ Scenario N o . : 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 1000/0reactor p o ~ e r

_I _ __ - I - - -

__ --__-

- P Event Event No. Description

_c_ 5-PRE TDEFW over-smeds on start and will not reset.

PRE .Failure of Turbine to trip.

PRE ATWS Reactor fails to trip

~- ~

L 2

TUR-11 Running EE pump trips. (Must m u a l l y start otber pump)

Selected P-inv fails low 3 Letdown Pressure Control Valve PCV-145 fails ciosed 4 Place excess letdown in service J IT-444 fails High 6 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.

Event 3 PCV-145 fails closed, this will cause a loss of letdown and the RO will have to deal with relief lifting, isolating letdown.

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.

Event 6 A MFP trips. The BOP operator works wih the CRS to perform the immediate actions of AOP 210.3.

Event 7 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.

Event 8 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). Thiswill cause the crew to go to Loss of heat sink / f e d and bleed.

Sc.enarioto be terminated whcn BFW flow is reinitated to a SG or at the discretion of the Lead Examiner.

Page 2 of 18

Scenario 1 Operator . . ,1 Actions

_.... - - ~ 1 ,

BOP 1 Increasing- amps- on AEHC -pump. - Receive alarm XCP-63 1, 1-4.

Operator removeles appropriate ARP, reviews procedure, and hands it to the .....

CRS. A

.......... - , .. ............

CRSiBOP Directs/recommend BEHC p m p . BOP starts e pump and observes normal

. . . . . . ....

CRSIBOP 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-

- ....... ___ .. .

TB A 0 Reports A EHC extre Page 3 of 18

Seenaris 1

.... P-imp Fails Low ..............

........ ~ .... ........

~

......., , ~ . ~....-/ j i-TGi'ii'6perator . . . ~ .....

RQ ik i d s 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 eck if Main Turbine lo

.

.

I Adjust Control Rods until Tavg.'

. . ~ ~ .. . . ..

~. ....

....

....

-- .........

~~~..___ .

ithin one hour, verify the following permissives are dim:

~ 1 3 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.VEISOL

.- . .....

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 .....

___.. 'i ..

7- ___.Actions -. ....... , . .

CRS,RO ~ Ensure the following are open:

11 0 MVT-8100, SEAL. WTR R'lW ISOL.

e P\7T-8153yXS L'I'DN ISOL.

FVT-8154,X S LTDN ISOL.

0

.... _-

..... . . . . -. . . .

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 H C i . 137 if'rhi.~aiarm i.7 rweived.

.- ...... .- - .....

&./R()-  : hlonitor the following to ci?surc flow between 0.2 gpm m d 5.0 I I gpm:

1 0 154A. WCP SL LKOFF HI RANGE.

plant shutdown. & TO W P - 4 , POWER OPERATION

,;j ..

(YOVE I). MA, us excess letdo

........

At least 6 gpm Seal Injection flow Reactor Coolant Pump.

service, THEN Letdown to maintain PZR level at progam level. As neither is in service the CRS .. will be . . directed

. . . . .

~

to the

.......

alternative action.

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 I

. . . . . -CKS , Irtdo;rx mrd R(CP seal injecrronfloii, halarice.

rv -:-

......~ .. . . . . -.

cntv PZR Dresswe i s stable at QR trending to 2235 psip,

~ (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

......-

' [ E n dof 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 isjuiled high j (may have been done initially). Places the M A 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.

... ...

~ EkS ,, Verify the PZR PORVs are closed:

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 . ___

1PZR PWESS MASTERCONTROL 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 f o r 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 I !I performed, RO will close block vulve at this time.

......

"

.i ~ 1-445. PRESS cation is

..

.~

Ensure ROD-CNTRL is In AUTO. R

-.. l _

l ..... ......

psig and 2250 psig. h4uy control ut this time.

... . ........

-___~ se of

...... ___

the channel failure.

ieted in AOP 401.5 untilfuiled turned

~.

e. .. .

Page 8 of 18

Scenario 1

........

........

Operator

....... ......... .... .... Actions ........... .

BOP A MFP trips. Recognizes pump is tripped and performs m e d i a t e actions of AOP 210.3, FEEDWATER PUMP MALFUNCTION. BOP vrerifies at least onefeedwater pump is wining, checks that ajkedwater pump trip did occur, a d checks heremainingfeedwuter pumps for proper response and veriJes

..... peed is increasing - on.both. ~ .. ..

BOP!RO Pulls ARP for XCP 625, 2-1, FWP A/BiC TNP, reviewy procedure md/or hands procedure to CHS. ...........

C.RS FEED WATER PUMP MALF C R S / B o ~ .......____ .....

Verify at least one Feedwater Pump is running. BOP reports B 2nd C MFPs are operating.

-. ... ~ ............ ~ ........ ~ ....... ..

Check if a Feedwater Pump trip occurred. BOP verifies and that ,AMFP

................. ___

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.

-.

.~~

...

...

CRS 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... ....___ .......__

CRS/BOP Verify two Feedwater Pumps and three Feedwater Booster Pumps

~~~ ~

-

are running. BOP verifies and revorts that B and C MFP s are running, and-.that I

r ~ ~ , ~ Bare ru

........... .~ . . . .a. .l l. J

. oIu

_.. __-- Ps . .-.

CRS/BOP CRS directs BOP to commence plant load reduction to 91% as follows:

e Ramp power at directed rate (li/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

..... ......... .......... ..~.-____. .

e RO borates using normal makeup controls to maintain Tavg as jOll0ws.

i e Use control rods andor commence boration as follows:

I 0 Perform a boration per SOP-106 0 Energize B/U htrs for mixing I iI 0 Retum WU system to auto per SOP-106 Ir--

f II I

0 Maintain AFD within limits 0 Maintain

....... rods above

~ ......

WL CRSBOP . Verify the high pressure and low pressure stop valves close on the

. .~ ...........

~ AFFECTED Feedwater Pump (GRAPHIC 310 SCREEN). BOP

.......

-

TR 4 0 i ,; 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

...

CRSSE i / Determine and correct the cause of the Feedwater Pump trip. S F r 1 makes calls to the appropriate mechanical and I&C maintenance 1 1 representutives. . , .....

BOP :I AL.L FRVs will be at 1 be required to take manual wntroi of FRVs ani KRILKXflow to

~

I

...__ ..... ~

.. .~ . . ....

L ....... ............ t ...... ..........

Page 10 of 18

Scenario 1 Reactor Power Reduction .........

..

rimd Operator . . . . . . . . . .__

.. Astiom

~ __.__.__

1-1 -~

CRSBOP 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) e 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

~

...........

CRS!RO Use control rods andor commence boration as follows:

0 Perform a boration per SOP-I 06 0 Encrgkze B/U htrs for mixing 0 W e b M U system to auto per SOP-106 0 Maintain AFD within limits 0 Maintain rods above RL

...

. .____ - _- ................ ___ ....

CRS 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 AtSet 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

. !.

... Switch. Verifyall Reactor Trip and Bypass Breakers are open. As

..

. .

.. ..

... both reactor trip switches will have been tried at this point and

.. ..

.: 1! 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 m a n u d v were unsucre,s,$ul in EOP ill direct the IB 80 to tr@ the reactor Attachment 1. The i l and Bh4SIV:r being in test on K-616 re1a.y on A train, and the K-616 relay has failed on B train, thereby will not trip, and then insert control r0d.v using thejastest manner

............

BOP recognize thejkilure 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 I/ 14 counterclockwise.

..._____ ......... ~

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

.......................

........................

xiWater Isolation / ATWS / Loss of Heat Sink. . . . . . . . . . . . . . . . . . . .

Operator......

....... __ ............. ..... ..... .Actions

... . . . . . . . . . . . . .

Note Manual or Autonlatic Rod Control muy be used Alternative Action Step I , whichever provides the.fustest Control Rod ins

. .

.... ............ _______

ALL Verify Reactor Trip:

e Trip the Reactor using both Reactor Trip Switches.

e Verify all Reactor Trip and Bypass Breakcrs are open.

e Verify all Rod Bottom Lights are lit.

e Reactor Power level is ..... decreasing.

.........- ~. ........... ~

ALL As the ot tripped, the CRS will move to the alternative actionfor step 1. IF the Reactor will NOT trip OR is NOT subcritical, THEN insert C o n t i ~Rods. l 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 R

...

All One member of operating crew directs the IB A 0 to peujorm EOP 13.0. A TTACHMEAVTI , TRIPPING THE REACTOR LOCALLY. ... ......... . . ._~ .... .........

~- -. ~ ~ ~~ ~

CRSiBOP 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 Depress Emerg Trip Sys TRIP.

e Set LOAD LMT SET fully Counterclockwise.

e Place EHC Pumps A and B in PULL TO LK NON-A.

e 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.).

........ _____~. ......___

..

.. ......... .- ....

CRSIBOP 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.

Page 13 of 1X

Scenario 1 Imadverteent Feed Water Isoiation I ATWS / Loss of Heat Sink .........

~

Time ..

Operator ...... . . . ~

Actions

___.~ ......... ~ -...........___

ALL 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, prompts the CRS which........ to read the ulternative actions.

. ....... ~~

........ ~. ...____ ~ ........

CRSWBP 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

..

I BUF operator reports that all valves are

................

..... open. ........

.. ........

-

I Investigation may reveal the presence ofXCP 622, 3-4, ID EFP STP VLVNOT OPEN OIL PRESS LO, indicating the ii XW02865-EF, EF PUMP TCRB MAIX STEAM TWROTTIJ~

j VALVE, is mostprobabk closed. ABLL AO will be dirt.cted to

.-

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 il

--F 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 BMSIVs (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 jI REACTOR TRIPiSAFETY INJECTION ACTUATION ACTIJATION, should be performed to verify. proper _ . SI, sctilaticr., while continu:ng with this procedure.

. - . -.

!

1 CRS BOP Dirccf.rHOP operanlor 10 pcyfonn thc s r i p 1-8 oj'COP 1.0.

...... _______.

.......

1 CRSRO ~i~VerifyCont Valves closed by 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). _

......... .

... ~. ................. ~

CRSIR Verify the Reactor is subcritical:

a. Power Range channels indicate LESS THAN 5%.

b. Intermediate Range channels indicate a negative startup rate. A 0 reports indications, which are a positive responseJor verij%ation that the reactor is subcritical. CRS proceeds to

. .,

step

..

I5 ofEOP

~- 13.0.

. . . ......... ~

-.

~ CRS 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.

.... ........ ...

CRSIRO Check if a scondary heat sink is required:

a Verify RCS pressure is GREATER THAN NON-FAULTED SG pressure.

.

.I

................. ,j 0 verify RCS a h i t~

.....

is GREATER

_...._......

THAN 3500 F......

lock Valves:

..

~ Verify power is available to & l P PZR I o MVG-8000A, RELIEF 445 A ISOL.

e MVG-8000B, RELIEF 444 E ISOL.

___ 1 a MVG-8000Cl. . RELIEF

....... . - 445

' LB ISOL. ..... . -.

I .o

~~ ~

li .

t:-:IL,

.. ..

uen the Block Valve for any PZR PORV that has been isolated due to excessive seat leakage:

MVG-8000A, RELIEF 445 A ISOL.

e MVG-8000B9 RELIEF 444 B HSOL.

.: ,

0 MVG-8000'2. RELIEF 445 I3 ISOL.

iI 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 Operator ... Actions

. , . ~.~ ...

~

........ . .l ._l_ll_. ...

....

....

.... .~ . ~. ..................

Cautioiz I f Wide Range level in any SGYis LESS 1Ha4N15% [2506]

CRS) 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.

CRS/BOP ds to step I 7 to initiate bleedand feed base identijication ofSG WR levels <15% in two or more SGs

... _ _ _ ~ ....... ................. ____ .............

Caution S t q s 14 through 24 must be performed quickly to establish (CRS) RCS heat removal by RCS bleed and feed, to minimize core

...

Critical

_-

.......

CRSIRO

. . . .

Critical CRSRO ,

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.

• LCV-l15B(D), RWST TO CHG PP SUCT.

e Verify COLDMOT LEG RECIRC monitor lights are dim on XCP-6 104.

e Verify SI flow on FI-943, CHG LOOP B CEDIHOT LG FLOW GPM. ....... .

........

CRSIRO . .

CRSIRO Resct Containment Isolation:

• RESET PHASE A - TRAIN A(B) CNTMT ISOL.

RESET PHASE B - TRAIN A(B) CNTMT ISOL.

CRSIBOP

a. NON-ESF L.CKOIJTS.

............

..I____ ......... _-

CRSIRO 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

. . . . .l .i ._. . . .

The RO may requei?that the cooling w t e r be ndjusted to the ressor locally per the attached caution tag.

................... .- ~~~ . ~~ .........

an RCS bleed path:

Open all PZR PORV Block Valves, MVG-8OOOAA(B)(C) e Open all PZR PORVs:

o PGV-445A. PWR RELIEF.

o PCV-445B. PWR =LIEF.

o PCV-444B. PWR RELIEF. -. .....

- - --____ I _

IJRBpressure increases to G k A T E R THAN 12 psig. RE Spray should be verifedper EOP-1.0. REACTOR TRIPBAFETY INJECIION A CTUATION, Step 8, to prevent containment integrity. -

I

. . . ___

.......

Steps 1 through 8 of EOP-1mEACTOR TRIP/SAFETY INJECTION ACTIJATION, while continuin, with this procedure. T k BOP operator hadpreviously completed the fht 8 steps ofEOP 1.0 and verqiicntion that R has

.

not

....

actuated.......is . ail that .i .....antic

..s .........

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.

e Feed flow should be established slowly to prevent

. ________- . .

............

SE reports that electrical maintenance has,fouad the problen and repaired the breaker fo .44DEFWpump.

.... .. ........ .. ~___

Continue to try to establish a secondary heat sink in at least o SG:

0 REFER TO Step 5 for EFW flow.

OR REFER TO Steps 8 through 11 for Feed md Condensate flow.

CRS should direct BOP operator to prepare to start B MDEFWpump and refer to step 5 of this procedure.

Page 17 of 18

Scenario 1 Inadvertent Feed Water Isolation / ATWS I LOSS of Heat Sink... ...

Actions

...... .. .

...____. .... ., .- ..........

Try to establish EFW flow to at least one SG:

e Check Control Room indications for the cause of EFW failure:

e 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 failure to one SG. -....... __ ........ . . . .

The CRS will direct the BOP operator to throttle closed on 541)(3551), MI) EFW TO SG.A.

-- ....-- .. .

The CRS will direct the BOP operutor to start the B MDEFWpump. - .-

... ... ..

I ALL The CRSwill direct the BOP operator to slowlv open FCV 3531 and feed A SG ut 50-100 GPM, vJhilethe RO monitors A loop RCS temperutures. _ _ _ I ___ _ I End...ofscenario 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-21E)) inoperable for maintenance. Severe Thunderstorm 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.

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.

Event 3 A Main Condenser Vacuum pump trips, BOP should start standby vacuum pump and open associated valve.

Event 4 FT 474, selected steamline flow transmitter for A SG fails low, BQP should take manual control and control S/G level.

Event 5 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.

Event G Failure of Pressurizer protection pressure transmitter (Beginning of steam space break).

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! I 0 Dial load limiter fully clockwise

!

0 Increase load set to raise load at %% per minute sin MVARs as required - _~ coordinate

... ....

%power

._I_

ascension.

.......___^___ . .

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

Scenario 2

.- ..... ....... .... A. .Charging

. /SI Pump

... Sheared Shaft...........

..

ERSiRO 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.

~ . , , ____

............

ERSiRO 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.

....... ____ ..

. ~~~

CRSIRO 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

..... .... ...

CRSIRO

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.

.. . .....

.. ... ~ . ~~

CRS!RO 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 I s o l a t i o i V a l v i s s a i n 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 monitorsfor the proper operation of the PZR

~ level control system, then returns to theJinal step of SOP 102, section L.

~ RE-ESTABI~ISEIINC;CHARGING AND I V O W L LETDO W A F T E R ISOU TION AT OPERATTNG CONnlTIONS

..........

~~ ~~

....... ........... .... ~. ...

0 Afier the Letdo matures have st Page 8 of 20

scmario 2

........... .. A Main Condenser. . . . . . . . Vacuum

.... Pump

. . . . . . . Trip

..

~~~ -. ............. , .

Time

..........

Oper .......... ........... ~- ............. ~

~ Receives annunciator XCP 628, 1-1 CVPA operator I notices that the A CVP has tripped and handy the associated ARP to the CRSfor review.

.... .. . .

s, the CRS will direct tlee TB A 0 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.

b. Start XBC-OOOlC, MAIN CVP C.

c. Place XAC-OOOlA, MAIN CVP A, to STOP.

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), M A N 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 overcurrentflag 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-474Steam FIow Transmitter Fails Law . . . . .

..*. ......

Operator

..............

'1,.Actions........__- .................... . .

BOPiRO I T 474fails low. Receive annunciator X'GP 624, 4-MIShlATCH. BOP operator scans MCB indicatinns and notices that

~

i CPIIII steam flow is pegged low. One operator will pull the ARP and

-r--

__I

.... .... .: . P?!!?. .........

CRS Quickly determines that an instrumentfailure has occurred and implements AOP 401.3, STEAM FLOW- FEED WATER FLOW 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,lflowto A SG using

' channel IVindications. benins restoring SCi level to 60% to 65% (if

~

1"

...

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'lowto 475 (both switches io the rightfor A SG)

.~ ...... _ _ _ ~ ~ .

CRSIBOP ESS THAN 950 MW;

.. ..... ..___ .......

CRSIBOP 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 value and trend for A_. SG level.

~

..............-~ i ................................

.........

Page 10 of 20

sceraario 2

~.

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 00psig higher than steam header pressure.

Feed flow is normal for steam flow and power level. BOP reports normal indicationsfor feedpow and stenm.flow.

0 All operating Feedwater Pump speeds and flows are balanced.

. . . .

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~tI.

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 w e rrippod.

- .....

Deteimix and correct the c~ilseof the c h a r d failKc. SI:\rill direct I&C to investigate and develap u troubleshooting plan. No further 401.3 at. . .this

. . . . . . .time.

......

_II. ~

I

.......

d. . .low

. . event . . ~

~~~ ......

- . .

Page IIof 20

Scenario 2

. . . . . . .............. ~ _ _ _ _

...... ......... -.

ceives annunciators XCP 617, 1-1 RCPA-TRIP andXkP61.7, 1-1

- ~~ .

t the crew stop any turbine to set load

............. . . . . .and

... s

.... ..........

TOR COOLAMII'PUMPFROM SER vI(:E: directs place the or Coolant Pump A. The CRS will direct the K O 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

scenario 2

~

...... Pressurizer Steam S e Break - LOCA ........ ............

T he

.....

Operator _. ....

-- . ........... . ........................

CRSiRO A break occur~son the.high side of thefollowing 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 indicatorsfor the crew skould be an increasing pressurizer l e d , a decreasing pressurizer pre.ssure, and an increasing RB pressure. Receive annunciators XCP 614 5-1 and XCP 404 & 607 2-2.

.. ......................... ~. . ~-

All The crew ~

• i evuluate ll the indications and ma.y utilize drawing 302-602 to identijj where the sol~rceqf the break may be, but the CRS will make the ultimately .... decision respond to the an RCS leak.

~. ........ ..____. ...... ~ . ...

CRS CRS enters AOP 101.1 LOSS OF REACTOR COOLANTillBT I...........

_. ................. ~.

ERS.RO PZR will decrease, directing the CRS to the alternativ

...._____ ______ ..... ....... ..........

CRSk0 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.

OR 0 PZR level is approaching 12%.

OR 0 PZR pressure is approaching 1870 psig.

OR e VCT level is approaching 5%.

b. Perfom the following:

1) Trip the Reactor.

2) GO TO EOP-1 .O, REACTOR TRIPBAFETY INJECTION ACTUATION WHEN EOP-1 .O Immediate Actions are complete, THEN actuate SI.

NOTE: CRS should direct Reactor Trip as RCS pressure

.......... approaches ..... .

.

_ I Page I 4 of 20

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 H I P 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.

___. ........ ..... ~ - .........

CRS

....................... ____

.............

_ _ l l l e Trip the Reactor using either Reactor Trip Switch.

e Verify all Reactor Trip and Bypass Breakers are open.

ghts are BOP

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 E X FLD CNTRL.

- .._.___ .........

CRSIB Verify

.

both

.........

ESF buses are energi . ..... .

CKS,RO;BOP Cheek if SI is actuated:

a. Check if either either:

e SI ACT status light is bright on XCP-6107 1-1.

OR Any red first-out SI annunciator is lit on XCP-626 top row.

____ ....... ........ .....

CRS!RQP

,._____ ....... -

Note Thefailure 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, d i e n 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.

.... ...... __ ........ -. . .

CRS!RO Verify R B pressll-e has remaificd LESS ' W A S 12 psig on PK.-9G,.iZU'

scenario 2

... Pressurizer Steam Space Break - LOCA. . . . . .-. ................

Time

.....

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-8Q00B1RELIEF 444 B ISOI,.

• MVG-8000C, RELIEF 445 B ISOL.

d. Verify at least. one . PZR PORV Block Valve is open.

~ .. .

Critical Check if RCPs should be stopped:

a. Check if either of the following criteria is met:

• Annunciator XCF-612 4-2 is lit (PHASE B ISOL).

OK e RCS pressure is LESS THAN I400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM.

1 If anv of the above criteria are met. then stou all RCPs.

I/ N o SG pressure is decreasing in an uncontrolled manner.

........... I _ _ _ _- _

..

CRS/SE levels indicate SG tubes RIJPTURED:

• RM-G19A(B)(C), STMLN H I RNG GAMMA.

RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR.

e RM-L3, STEAM GENERATOR BL.OWDOWN LIQUID MONITOR.

o RM-LIO, SG BLQWDOWN CW DISCHARGE LIQUID MONT

-- ..... ................. ___- ....... ~

~ . . ............ _____ ..

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 ( W C U 1BI2B DRK FI,O HI).

'1

' 1 GO TO EOP-2.0, LOSS OF REACTOR OR SECONDARY Check if RCPs should be stopped:

a. Check if either of the following criteria is met:

a Annunciator XCP-612 4-2 is lit (PHASE B ISOL).

OR 0 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 m d 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 a n uncontrolled manner.

....... ~ ....... ~

~

a. Verify Narrow Range level in INTACT SGs is GREATER THAN 30% [SO%].

I b. Control EFW flow to maintain Narrow Range level in each INTACT 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 131RNG GAMMA.

e WM-A9, CNDSR EXHAUST GAS ATMOS MONITOR.

e WM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR.

e 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:

0 MVG XOOOA, RELIEF 445 A-ISOL.

e MVG 80OOl3,RELIEF 444 B ISOL.

e 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

.~..... Pressurizer . . . . . . . Space Break - LOCA

. . . . . . . .Steam ~

rime Operator Actions

........... .......... ..........

-~ ~. -. ...

&S/RO/BOP 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.

None are running, directing ...... th ____-

..........

R pumps shouldb

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.

.~ ...

-

C

-~ ....... ______

CRSiBOP Check if pressure in all SGs Is stable or increasing. BOP should report

. . . . SG pressures as stable. ....... ..... ...

_ I SiCB 'Check I f D 6 s s A0 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 ...

-. ......

CRS!RO!SE Verify eq

a. Verify power is available for tit least one RHR P u p :

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- 1 1 8. COMPONENT COOLING WATER.

d. Consult with TSC personnel to determine if equipment required for Cold Leg Recirculation is available.

..

Page I 9 of 20

scenario 2 Break - LOCA .....

Time

-. . . . . . .... ..... ~

for evidence o f ECCS leakage:

a. Verify AB radiation levels are normal on:

• RM-A3. M A N PLANT VENT EXH ATMOS MONITOR:

PARTICULATE, IODINE, GAS.

6 RM-A13. PLANT VENT 131 RAXGE.

• RM-AI 1 AB VENT GAS ATMOS MONITOR.

• 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

..... ..........

. _I_.....__...

CRSiROiSE

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