ML101650168

301 Final Simulator Scenarios ES-D-1, ES-D-2 (Section 10)

ML101650168
Person / Time
Site:	Turkey Point
Issue date:	03/28/2010
From:	NRC/RGN-II
To:
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Download: ML101650168 (65)

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Appendix 0D Scenario Outline ES-D-1 Form ES-0-1 Facility: Turkey Point Scenario No.: 1 1 Op Test No.: 2007-301 Examiners: Candidates: US RO BOP Initial Conditions: Mode 1, 75% Power, MOL, Awaiting permission from plant management to increase power back to 100%. 3-GOP-301 in use complete through step 5.96 for return to 100% power following a turbine valve test.

Turnover: Equipment OOS: 3B EDG EDO due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 11 & 9 in 4 hrs); B AFW Pump due to bearing failure (OOS 4 hrs; ETR 24 hrs; both trains verified operable);

3B CSP due to failed 1ST - low discharge pressure (OOS 12 hr; ETR 36 hr) 3-OSP-019.3. Steps 7.1.1 & 7.1.2 Perform 3C ICWP isolation valve cycling test per step 7.1.3 of 3-0SP-019.3.

for 3A and 3B ICWP are not scheduled for this shift.

Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being 3-ONOP-071 .2, Attachment 1. The current sample, just completed indicates no taken per 3-0NOP-071.2, significant change in leak rate. MOV-3-1403 remains open at management direction due to small size and stability of tube leak rate.

Event Type*

Event Type* Event Description No.

1 1 (N) SRO/BOP 3C ICWP discharge isolation valve cycling test per 3-0SP-019.3 3-OSP-019.3 step 7.1.3.

2 (I) RO Power range NI channel N-44 upper detector fails high. The crew responds TFN1P4AH TFN1P4AH=T ~ T per 3-0NOP-059.8.

TSI SRO (TS,I) 3 See event 4a PT-3-1604 fails low. The crew responds per 3-ARP-097.CR for annunciator TFS1ML3L TFS1ML3LT ~ T below D-7/4.

0-7/4.

4 (C) BOP 3-ONOP-004.4. TS are Loss of 3C 4kV bus. The crew responds per 3-0NOP-004.4.

TFE2Z52S ~ T

=

evaluated for loss of the A SSGFWP.

(C TS) SRO (C,

4a (R) SRO/RO Automatic runback fails due to PT-3-1604 PT-3-1 604 failure and requires manual action BOP*

(I)l BOP*

to reduce power < 60 % to avoid reactor trip on s!gslg 10-10 b-b level. The crew 3-ONOP-089.

responds per 3-0NOP-089.

TVFACN3 ~ 0.1 01 5 =

(M) ALL (M)ALL Once reactor power stabilized < 60% power, a 3C SG feed break occurs TFVV98M ~T

= T inside containment. A manual reactor trip is required before any SG SO level (C) RO/SRO TCF1009M=F TCF1D09M ~ F drops < 10% since the automatic reactor trip is failed. 3-EOP-E-0 is TFL2XASE=T TFL2XASE ~ T performed. The MOV-3-1409 breaker trips & FCV-3-498 fails to close leaving TFL2XBSE=T TFL2XBSE ~ T an uncontrolled feed path to 3C SGSO if 3A SGFP started.

6 (M) ALL (M)ALL C AFWP trips on overspeed prematurely at 6300 RPM (from setup). The trip TAFXSRPC

~

can not be reset. B AFWP is OOS. A AFWP starts, but runs out of steam 6300.0 - pressure from the 3C feed line fault. Efforts to realign A AFWP to train 2 TCF5MTC~T TCF5MTC=T steam are prevented by AFSS-3-007 stuck closed. SSGFW can not be used due to loss of 3C 4kV bus and a dead battery on B SSGFWP. The crew transitions to 3-EOP-FR-H.1 when AFW flow < 345 gpm and is eventually SOs << 32% narrow range with required to initiate feed & bleed since all SGs adverse containment conditions.

(R)eactivity, (I)nstrument, (N)ormal, (R)eactlvlty, (l)nstrument, (C)omponent, (M)aJor (M)ajor

• • - BOP action to either manually close CV-3-2011

- CV-3-201 1 in event 3 or manually reduce load in event 4a due to automatic turbine runback failure satisfies the BOP PT-3-1604 instrument failure manipulation.

1 1

TP-2007-301 Scenario #1 #1 Event Event Description 2007-301 Scenario #1 Point 2007-301 Turkey Point Event 11 - 3C ICWP discharge isolation Event - isolation valve cycling test per 3-0SP-019.3 3-DSP-Ui 9.3 step 7.1.3 7.1 .3 Event 2 - Power range NI channel N-44 upper detector fails high. The crew responds per 3-ONOP-059.8.

PT-3-1 604 fails low. The crew responds per 3-ARP-097.CR for annunciator 0-7/4.

Event 3 - PT-3-1604

- D-7/4.

Event 4 - Loss of 3C Event - 30 4kV bus. The crew responds per 3-0NOP-004.4.

3-ONOP-004.4. TS are evaluated for loss of the A SSGFWP.

Event 4a - Automatic runback fails due to PT

- PT-3-1 604 failure and requires manual action to 1604 reduce power << 60 % to avoid reactor trip on slg b-b level. The crew responds per 3-0NOP-s/g 10-10 3-ONOP-089.

Dnce reactor power stabilized < 60% power, a 3C SG feed break occurs inside Event 5 - Once containment. A manual reactor trip is required before any SG level drops < 10% since the automatic reactor trip is failed. 3-EOP-E-0 is performed. The MOV-3-1409 MOV-3-1 409 breaker trips & FCV-FCV 3-498 fails to close leaving an uncontrolled feed path to 3C 30 SG if 3A SGFP started.

Event 6 - C AFWP trips on overspeed prematurely at 6300 RPM (from setup). The trip can not be reset. B AFWP is OOS.DOS. A AFWP starts, but runs out of steam pressure from the 3C 30 feed line fault. Efforts to realign A AFWP to train 2 steam are prevented by AFSS-3-007 stuck closed.

SSGFW can not be used due to loss of 3C 4kV bus and a dead battery on B SSGFWP. The 3-EDP-FR-H.1 when AFW flow <

crew transitions to 3-EOP-FR-H.1 < 345 gpm and is eventually required to initiate feed & bleed since all SGs < 32% narrow range with adverse containment conditions.

2

TP-2007-301 Scenario TP-2007-301 Scenario #1

1. 1 Event Event Description Description Scenario XXIII NRC 11 Simulator Operating Simulator Operating Instructions Instructions Setup IC-16 (75% MOL)

SRO_XXIII_NRC_1 .Isn Open & execute lesson file SRO_XXIII_NRC_1.lsn Place simulator in run Trigger lesson steps:

SETUP - AUTO REACTOR TRIP FAIL (actuates TFL2XASE == T, TFL2XBSE == T, TFL2XASE == FF when IML2CRXT & TFL2XBSE = F when IML2CRXT)

IML2CRXT IML2CRXT)

SETUP - 3B EDG OOS (actuates TA05LRSB

- TAQ5LRSB == OFF 0FF (0) & TA05B20P TAQ5B2OP == RACKOUT (3))

SETUP - B AFWP OOS (actuates TAFK244 == 0.0, TAFK002

- TAFKOO2 == 0.0, TAFF01 TAFFO1 B == 0.0, TCF5MTB == T)

SETUP GPD LEAK (actuates TVHHSGA == 0.0000013)

- 3A SG 2 GPO SETUP - 3B CSP OOS (actuates TAM1 DPOB == RACKOUT (3) & TCM1 D41 M == FALSE)

SETUP - C AFWP OVERSPEED TRIP (actuates TAFXSRPC =6300.0, TCF5MTC == Twhen

- T when F50SlAFC F5OSIAFC EQ 6290)

EO Start 3A ICWP and stop 3B ICWP. (Leave 3A & 3C ICWP running). Start train A chilled water and secure train B chilled water (CR HVAC panel).

Acknowledge annunciators F-9/2 F-912 & F-9/5 F-915 (3B EDG) and place simulator in freeze.

Place clearance info tags on 3B EDG normal start switch, B AFWP T&T T&T valve control switch & 3B CSP control switch.

Remove AFW train 2 orange tag from B AFWP tachometer just below ann. panel X.

Provide shift turnover checklists, blank 3-0SP-019.3 3-OSP-O1 9.3 and 3-0NOP-071.2 3-ONOP-071 .2 open to Att 1.

Select 3A QSPDS to page 211 (SAT) and 3B QSPDS to page 212 (RVL). Set ERDADS on VPA to Tavg/Tref (TAV) and at the RCO desk to ENVRN (ED3).

Fill in blender & shutdown boron addition placards at console blender station. Data for each IC may be found in the ECC & Shutdown Guidelines Book in the simulator I/F.

Event 11 - 3C ICWP discharge isolation valve test Initiated from shift turnover immediately after shift turnover.

The crew will start 3B38 ICWP && stop 3C3C ICWP per 3-OP-019 3-0P-019 section 5.3, 5.3, then NSO begins performing 3-OSP-O 19.3 step 7.1.3.

3-0SP-019.3 Respond as NSO if directed directed to perform pre-start checks for 3B ICWP ICWP & & post-shutdown checks for 3C ICWP.

ICWP. Report all checks satisfactory.

Step 7.1.3.1 7.1.3.1 - Done

- Done by securing 3C ICWP.

ICWP.

Step 7.1.3.2 7.1.3.2 - Call

- Call as NSO NSO and request RO log 3C ICWP log 3C ICWP inoperable.

inoperable.

3

TP-2007-301 Scenario TP-2007-301 Scenario #1 Event Event Description Description Step 7.1.3.3 Step 7.1.3.3-- Trigger lessonlesson step EVENT EVENT 11 - REMOVE

- REMOVE 3AD05 CLOSE CLOSE CKT CKT FUSES FUSES (actuates TFK2G05A (actuates TFK2GO5A == T) T)

Step 7.1.3.4 - Trigger lesson

- lesson step EVENT EVENT 11 - CLOSE 3-50-332 (actuates

- TAKB332 =

(actuates TAKB332 = 0.0 on 60 0.0 on 60 sec ramp), then trigger lesson step EVENT 1 1 - OPEN 3-50-332 (actuates

- (actuates TAKB332 == 1.0 on 60 1.0 on sec ramp).

sec ramp).

Step 7.1.3.5 - Trigger lesson step EVENT 11 - INSTALL 3AD05 CLOSE CKT FUSES TFK2GO5A == F).

(actuates TFK2G05A F).

Step 7.1.3.6 - NSO field verification of lights on 3AD05.

Step 7.1.3.7 - Respond as NSO when directed to do 3C ICWP pre-start checks. Report pump ready for start. Respond as NSO when directed to do post-start checks and report pump post-start checks satisfactory.

Step 7.1.3.9 - Respond as NSO when directed to perform post-shutdown checks on ICWP just shutdown. Report pump shutdown checks satisfactory.

Event 2 - PRNI N-44 upper detetctor fails high 3-OSP-01 93 step 7.1.3 complete, trigger lesson step EVENT 2 - PRNI N-44 Once 3-0SP-019.3 -

UPPER DET FAILS HIGH (actuates TFN1 TFN1P4AH=T).

P4AH = T).

This actuates annunciators 8-2/2, B-2/2, 6/1, 6/3, 6/4, 9/2 The crew responds per 3-0NOP-059.83-ONOP-059.8 and takes PRNI N-44 out of service per steps thru5.1.1.7.

5.1.1.1 thru 5.1.1.7.

Step 5.5.1.1.1 B-8/4.

1. 1. 1 actuates 8-8/4.

Step 5.5.1.1.2 B-6/3.

1. 1.2 clears 8-6/3.

Step 5.5.1.1.3 B-2/2.

1. 1.3 clears 8-2/2.

Step 5.1.1.6 clears 8-6/4. B-6/4.

5.1.1 .7.a - Respond as AOM/I&C Step 5.1.1.7.a - AOM/l&C ifit asked whether or not to pull instrument fuses.

Reply that fuses should be pulled. All annunciators clear except 8-6/1, B-6/1, 6/5 & 8/4.

Step 5.1.1.8 - Respond as WCC/I&C when called regarding N-44 failure.

Step 5.1.1.9 - Respond as Rx Eng/STA when directed to perform 3-0SP-059.1

- 3-OSP-059.1 O(QPTR) 0(QPTR)

Step 5.1.1.10 - Not applicable.

Step 5.1.1.11 - Respond as WCC if directed to generate ECO for tripped bistables.

Event 3 - PT-3-1

- PT-3-1604 604 fails low After PRNI N-44 taken out of service, trigger lesson step EVENT 3 - PT-3-1 - PT-3-1604 604 FAILS LOW (actuates TFS1 ML3L == T).

PT 1604 failure causes CV-3-201 PT-3-1604 CV-3-20111 to automatically open. The crew responds per 3-ARP-097.CR for annunciator D-7/4. 0-7/4.

Respond as NSO NSO if directed directed to verify CV-3-1 Schema~

900 closed. Click on Schema*

CV 1900 FEEDWATER FEEDWATER HEATlNGHlGHHEATING~HIGH PRESS PRESS FW HEATERS & & RHTR & & HTR HTR DRAIN TANKS~report CV-3-1900 TANKSreport CV-3-1 900 position (see far right side of mimic).

mimic).

Crew should determine SGFP suction pressure pressure> > 260 psig with 2 HOPs running so fast load reduction is not required.

44

TP-2007-301 Scenario TP-2007-301 Scenario #1

1. 1 Event Event Description Description Event 4 - Loss Event - Loss of of 3C 3C 4kV bus bus The plant The plant is stabilized following is stabilized following CV-3-2011 CV-3-2011 failure failure open, open, trigger trigger lesson lesson step step EVENT EVENT 4 - LOSS OF 3C 4KV BUS 4 - LOSS OF 3C 4KV BUS (actuates TFE2Z52S == T).

(actuates TFE2Z52S T).

This causes a loss of This of 38 SGFP.

SGFP. TheThe crew crew may may taketake the the 38 3B SGFP SGFP control control switch switch to to STOP which STOP which ordinarily ordinarily would would open open the the breaker breaker and initiate automatic turbine runback.

runback.

Since the PT-3-1604 Since the PT 1604 failure failure in event 3 also defeats the automatic loss of of SGFP SGFP turbine turbine runback, the 80P runback, must manually run back load and the BOP must the RO drive rods to reduce power

<60%

< 3-ONOP-089. The 60% per 3-0NOP-089. The crew should also respondrespond per 3-0NOP-004.4 3-ONOP-004.4 due to loss of the 3C 4kV bus. TS TS are evaluated for for the loss of the A SSGFWP.

If the reactor is tripped in response to this event, then proceed directly to Event 5.

Respond if called as NSO to investigate 3C 4kV bus. After 1-3 min, mm, report that the lockout relay has actuated and the bus enclosure smells of overheated insulation. If directed to reset 3C 4kV bus lockout relay, report that the lockout will not reset.

Respond if called as WCC/Electrical to investigate 3C 4kV bus lockout. Do not fix this malfunction before the end of the scenario.

Respond if called as System & & Duty Call Supervisor per O-ADM-115.

Respond if called as SM to review O-ADM-011O-ADM-O1 1 regarding need for an ERT.

Respond if called as Chemistry about RCS sampling following a a>> 15% power change.

Respond as NSO if directed to cross-tie E E MCCs per 3-0P-007 3-OP-007 sect 7.1. No further action required during this scenario.

Event 5 - 3C SG main feed line failures After the plant is stabilized <60% < 60% power, at lead examiner direction, trigger lesson step EVENT 55 - 3C FW LINE FAIL (actuates TVFACN3 ==0.1, TFVV98M =T && TCF1

- DO9M == F). A TCF1D09M main feed break occurs on 3C feed line inside containment. A manual reactor trip is required before any SG level drops < 10% since the automatic reactor trip is failed. 3-EOP-E-O is performed. The MOV EOP-E-0 MOV-3-14091409 breaker trips && FCV-3-498 fails to close. This creates a feed path to the faulted 3C SG should feed be restored.

55

TP-2007-301 Scenario TP-2007-301 Scenario #1 #1 Event Event Description Description Events Events 66 - Loss Loss of AFW AFW II HeatHeat sink sink Entered upon Entered upon completion completion of of 3-EOP-E-O 3-EOP-E-0 stepssteps 1-4.

1-4.

CC AFWP AFWP trips on overspeed trips on overspeed prematurely prematurely at at 6300 6300 RPM RPM (from (from setup).

setup). The The trip trip can can not not be be reset. BB AFWP is ~OS.

reset. QOS. A AFWP starts, but runs out of of steam pressure fromfrom the the feed feed fault on 3C feed line fault feed line. Efforts to realign realign A AFWP to to train 22 steam is prevented by by AFSS-3-007 being stuck stuck closed. SSGFW SSGFW can not be used due to to a dead battery on on B SSGFWP (A SSGFWP SSGFWP not (A SSGFWP not available available due due toto loss of 3C loss of 3C 4kV 4kV bus).

bus). The The crew crew transitions transitions to to 3-EOP-FR-H. 11 when AFW flow < 345 gpm and is eventually required to initiate feed &

bleed since SG levels are <<32% 32% narrow range with adverse containment conditions.

IfIf asked as NSO to locally reset C AFWP overspeed trip (3-0NOP-07S (3-ONOP-075 Attachment 4),

respond that the C AFWP overspeed trip can not be reset.

If asked as NSO to align train 2 steam to the A AFWP by opening AFSS-3-007, report that AFSS-3-007 will not open. Request mechanical maintenance assistance.

Respond as WCC/Mechanical Maintenance if asked to troubleshoot/fix C AFWP mechanical trip and AFSS-3-007.

Respond as NSO if asked to locally close MOV-3-1409 or 3-20-333. Delay local closure of these valves until after feed & & bleed initiated then trigger lesson step EVENT 6 - -

LOCALLY CLOSE MOV-3-1409 MOV-3-1 409 (actuates TFFVV09C TFFVVO9C = = T) and report when complete.

3A SGFP should not be started since an uncontrollable feed path exists to 3C SG. With level < <[33%]

[33%J wide range, feed flow must be limited to 100 gpm to the faulted SG (3-EOP-FR-H. 11 step 4 caution 2).

Respond as NSO when directed to place PAHMS in service on unit 3. After 8-12 minutes, trigger lesson step EVENT 6 - PLACE U3 PAHMS IN SERVICE (actuates TAC2VO2A TAC2V02A = 1.0, TAC2V02B = 1.0,

= 1.0, 1.0, TAAAV21 == 1.0, 1.0, TAAAV22 == 1.0 1.0 & TACA005 ==0.0). Report when complete.

66

Appendix D Operator Actions Form ES-D-2 No.: 2007-301 Op-Test No.: No.: _1_

Scenario No.: 1 No.: 11 Event No.: Page _1_

Page j_ of _1_

j_

Event

Description:

30 ICWP discharge isolation valve cycling test per 3-0SP-019.3 3C 3-OSP-01 9.3 step 7.1.3.

Time Position Time ~===it=io=n=9================A=P=P=li=c=a=nt='s=A=C=t=io=n=s=o=r=B=e=h=a=v=io=r===============91 Applicants Actions or Behavior US Directs BOP to have NSO cycle 3C ICWP discharge isolation valve, 3-3-OSP-01 9.3, section 7.1.

50-332 per 3-0SP-019.3, Directs BOP start 3B ICWP & sid s/d 3C ICWP per 3-0P-019 3-OP-01 9 section 5.3.

BOP 3-OSP-019.3, section 7.1 & 3-0P-019, Obtains copies of 3-0SP-019.3, 3-OP-019, section 5.3.

Performs actions as follows:

1. Starts 3B ICWP & stops 3C 3-OP-Ol 9 section 5.3 30 ICWP per 3-0P-019

a. Verifies NSO understands ICWPs 10W Ps to be started/stopped

b. Directs NSO verify oil in 3B ICWP sightglass & 3B ICWP discharge valve open

c. Starts 3B ICWP & checks VPA ammeter> zero

d. Directs NSO locally check 3B ICWP visible packing leakoff

e. 30 ICWP & checks VPA ammeter Stops 3C =

= zero

f. Directs NSO locally do post-stop check

2. Has RO record 3C 30 ICWP as inoperable.

3. 7.1 .3.6 Directs NSO perform steps 7.1 .3.3 thru 7.1.3.6 NOTE: NSO has sign signoff off procedure copy in field and will perform steps 7.1.3.3 thru 7.1.3.6 and will notify BOP when these steps are done.

4. 3C ICWP per 3-OP-Ol Starts 30 3-0P-019 9 section 5.3 to verify operability.

a. Verifies NSO understands ICWPs lOW Ps to be started/stopped

b. Directs NSO verify oil in 30 3C ICWP sightglass & 30 3C ICWP discharge valve open

c. 3C ICWP & checks VPA ammeter> zero Starts 30

d. Directs NSO locally check 30 3C ICWP visible packing leakoff 5.

5. Has RO record 30 3C ICWP as back in service.

6. Since this is the last ICWP discharge valve to be cycled, stops 3C ICWP per 3-OP-Ol 3B or 30 3-0P-019 9 section 5.3.

a. Stops 3B or 3C ICWP & checks VPA ammeter == zero

b. Directs NSO locally do post-stop check RO Records 30 3C ICWP OOS and return to service when advised by BOP.

11

D Appendix D Operator Actions Operator Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: _2_

2 Page 1 of ~

Page_1_of Event

Description:

Power range NI channel N-44 upper detector fails high. The crew 3-ONOP-059.8.

responds per 3-0NOP-059.8.

Time Position RO J Applicants Actions or Behavior Applicant's Recognizes I/ reports PRNI channel N-44 upper detector failed high.

• G-511,, 5/2 annunciator B-2/2, 6/1, 6/3, 6/4, 9/2 & G-5/1

• . N-44 power range channel indication on console fails high

• . N-44 axial flux indication on console fails high

• . N-44 upper detector indication on NIS racks fails high 3-ONOP-059.8:

Performs immediate actions of 3-0NOP-059.8:

• . Takes rod motion control selector switch to MAN (to stop automatic continuous inward rod motion)

US 3-ONOP-059.8 Directs response per 3-0NOP-059.8 RO/

ROI 3-ONOP-059.8 as directed by US:

Performs subsequent actions of 3-0NOP-059.8 BOP 1. Places dropped rod mode switch for N-44 in BYPASS.

2. Places right rod stop bypass switch to bypass N-44.

3. Transfers upper section comparator defeat switch to N-44.

4. Transfers lower section comparator defeat switch to N-44.

5. Transfers right power mismatch bypass switch to bypass N-44.

6. Transfers comparator channel defeat switch to N-44.

7. Pulls instrument power fuses from N-44 drawer B B US Evaluates impact per TS 3.3.1. Table 3.3-1 functional units 2 &1 &177 apply.

Actions 22 (6hr) & & 7 (1 hr) both in effect.

Conducts crew brief regarding effects of N-44 failure Directs manual rod withdrawal or turbine load reduction to restore Tavg within 3°F of Tref as needed per 3-ONOP-028 3-0NOP-028 RO Manually Manually withdraws control rods as as directed US to restore Tavg directed by US within 3°F 3°F of Tref as as needed needed per 3-ONOP-028.

3-0NOP-028.

22

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: _1_

j Event No.:

Event No.: 22 Page 2 of PageLofL .

Event

Description:

Event

Description:

Power range NI Power range NI channel N-44 uQQer channel N-44 upper detector detector fails fails high.

high. The The crew crew resQonds per responds Qer 3-0NOP-059.8.

3-ONOP-059.8.

Time Position Applicants Actions or Behavior Applicant's BOP turbine load as directed by US to restore Manually reduces turbine restore Tavg within 3°F of Tref as needed 3°F needed perper 3-0NOP-028.

3-ONOP-028.

US I&C

1. Directs notification of I&e

2. Directs STA monitor QPTR per 3-0SP-059.10 3-OSP-059.10 (reactor power approx. 75%)

approx.75%)

WCC generate clearance for tripped bistables

3. Directs wee 33

Appendix D D Operator Actions Form ES-D-2 Op-Test No.: 2007-30 1 2007-301 Scenario No.: _1_ 1 Event No.: ~ 3 Page j_

_1_ of _1_

j_

Event

Description:

PT-3-1 604 fails low. The crew responds per 3-ARP-097.CR for PT-3-1604 annunciator D-7/4.

Time Position Applicants Actions or Behavior Applicant's BOP Acknowledges alarm D-7/4.

Perform actions of 3-ARP-097.CR for annunciator D-7/4.

1. CV-3-201 1 open and PT-3-1604 Recognizes/reports CV-3-2011 PT-3-1 604 failed.

2. Determines no other automatic actions have occurred.

3. Determines reactor power increased due to CV-3-2011 CV-3-201 1 failure but still <

< 100%

4. Determines SGFP suction pressure>

pressure > 260 psig.

5. When directed by US, closes CV-3-2011.

CV-3-201 1.

CV-3-201 1 closure may be delayed pending plant NOTE: CV-3-2011 stabilization and conduct of pre-brief to address potential for secondary plant transient caused by valve closure.

6. CV-3-1 900 closed.

Directs NSO verify CV-3-1900

7. Determines 2 HDPs running as required since turbine load>

450 MWe RO RD Reads 3-ARP-097.CR for annunciator D-7/4 Observes decrease in Tavg & increase in reactor power due to CV-3-2011 failure US CV-3-201 1 once it has been determined that Considers closure of CV-3-2011 SGFP suction pressure> 260 psig (see NOTE above)

PT-3-1 604 failure (e.g, no turbine runback on Determines effects of PT-3-1604 loss of SGFP).

PT-3-1 604 failure.

Conducts crew brief regarding effects of PT-3-1604 Directs WCC have I&C l&C investigate / fix PT-3-1604 PT-3-1 604 failure.

If QPTR directed in event 2, then allows power> 75%

4

Appendix D Appendix D Operator Actions Operator Actions Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _1_

j_ Event No.:

Event 4/4a No.: 4/4a Page _1_

Page of ~2 1 of Event

Description:

Loss of 3C 4kV bus. 3B SGFP is lost. Automatic runback fails due to PT-3-1 604 failure and requires manual action to reduce power <

PT-3-1604 < 60 %

to avoid reactor trip on S/9 b-b level. The crew responds per 3-0NOP-s/q 10-10 3-ONOP-3-ONOP-004.4. TS are evaluated for loss of the A SSG 089 and 3-0NOP-004.4. FW P.

SSGFWP.

Time Position Applicants Actions or Behavior Applicant's BOP Recognizes/reports loss of 3B SGFP

• . Annunciator D-6/2 (B SGFP low flow)

• . 0-5/1 thru 5/3 (SG steam>

Annunciators C-5/1 steam > feed flow)

• . Annunciators D-6/1 thru 6/3 (SG level deviations)

• 3B SGFP breaker open indication with ammeter = = 0

• . Indicated feedwater flow < < steam flow for all SGs

• . Slowly dropping level in all SGs Notices absence of runback and takes 3B SGFP control switch to trip. Recognizes/reports failure of turbine to runback.

US 3-ONOP-089 Directs performance of immediate actions per 3-0NOP-089 including manual turbine runback to < < 60% turbine load or as needed to reduce steam flow < available feedwater flow.

Verifies automatic actions per 3-0NOP-089:

3-ONOP-089:

BOP

1. Manually reduces turbine load

2. Performs fast load reduction to << 60% turbine load or as needed to reduce steam flow << available feedwater flow.

3. Verifies condenser steam dumps open as necessary based on Tavg-Tref mismatch.

4. Verifies main FW regulating valves throttle as necessary to return SG level to program (60%).

RO Verifies automatic actions per 3-ONOP-089:

3-0NOP-089:

1.

1. Verifies auto rod insertion insertion in in response to turbine load load reduction to reduce Tavg/Tref mismatch mismatch

2. Verifies PZR PZR level level && pressure control:

a.

a. Charging pump speed changes to maintain maintain PZR PZR level level b.

b. PZR heaters /1 normal PZR heaters normal spray function as needed needed to maintain maintain PZR PZR pressure pressure approx 2235 psig 55

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: j_1 Event No.:

Event No.: 4/4a 414a Page -L of -.f.2 Page Event

Description:

Loss of 3C30 4kV bus. 3B SGFP is lost. Automatic runback fails due to PT-3-1604 failure and reguires PT-3-1 604 requires manual action to reduce (2ower power << 60 %

trip on s/g to avoid reactor tri(2 s/q 10-10 b-b level. The crew res(2onds responds (2er per 3-0NOP-3-ONOP-3-ONOP-004.4. TS are evaluated for loss of the A SSGFWP.

089 and 3-0NOP-004.4.

Time e Position Applicants Actions or Behavior Applicant's US Directs subsequent actions per 3-0NOP-089.

3-ONOP-089.

NOTE: Slow RO/BOP action to manually insert control rods and/or reduce turbine load may result in the need for a manual reactor trip. If this occurs proceed to Event 5.

BOP Performs remainder of subsequent actions per 3-0NOP-089. 3-ONOP-089.

1. Verifies SG levels and pressures stabilized

2. Verifies steam dumps closed.

3. Marks control room charts with date/time/cause of runback RO Performs remainder of subsequent actions per 3-0NOP-089. 3-ONOP-089.

1. Verifies Tavg matches Tref

2. Verifies PZR level & pressure stabilized.

3. Marks control room charts with date/time/cause of runback BOP Determines loss of 3B SGFP due to loss of 3C 30 4kV bus US 3-ONOP-004.4 Directs actions per 3-0NOP-004.4 BOP 3-ONOP-004.4:

Performs actions as directed by US per 3-0NOP-004.4:

1.

1. Stabilizes plant following manual turbine runback

2. Determines 3A & 3B 4kV buses both energized

3. Determines 30 3C 4kV bus lockout tripped NOTE: Attempts made to reset lockout will be unsuccessful.

4. Directs FS/NSO locally investigate 3C 4kV bus US Directs WCC have Electrical maint. investigate 30 3C 4kV bus lockout.

Determines no further actions per 3-ONOP-004.4 3-0NOP-004.4 can be performed until 3C 4kV bus until 30 bus lockout lockout reset.

Directs Directs SM SM to review 0-ADM-01 0-ADM-0111 to see ifif ERT ERT should should be activated.

activated.

Directs Directs System & & DOS DCS 0-ADM-1 0-ADM-115 15 notification notification about runback.

Directs Directs Chemistry Chemistry notification notification to sample sample RCS (15% power power change)

Determines TS TS 3.7.1 .6 Action a.

3.7.1.6 (30 days)

a. (30 days) applies for A SSGFWP SSGFWP (if time permits this evaluation).

Conducts crew briefbrief regarding effects effects of of loss loss of 3C 4kV of 30 4kV bus.

bus.

66

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.: 11 Scenario No.: Event No.:

Event No.: l Page _1_

Page 1 ofof --+/--

Event

Description:

Event

Description:

Once reactor 120wer Once reactor power stabilized stabilized << 60%

60% 120wer, power, aa 3C 30 SGSG feed feed break break occurs inside occurs containment. A inside containment. A manual manual reactor reactor tril2 trip is is reguired required before before any any SG level drol2s SG level drops << 10%

10% since the automatic since the automatic reactor reactor tril2 trip is is failed.

failed. 3-EOP-3-EOP-E-0 is E-O performed. The is l2erformed. The MOV-3-1409 MOV-3-1 409 breaker breaker tril2s trips && FCV-3-498 FCV-3-498 fails fails to to close leavinq an close leaving an uncontrolled uncontrolled feedfeed l2ath to 3C path to 3C SGSG ifif 3A 3A SGFP SGFP started.

started.

[ Time Position BOP Recognizes and reports Recognizes Applicants Actions or Behavior Applicant's reports dropping dropping 3C30 SG levels and SG levels and feedwater flows BOP

• . Annunciators C-5/1 0-5/1 thru 5/3 steam > feed flow) 5/3 (SG steam>

• . Annunciators D-6/1 thru 6/3 (SG level deviations)

• . Indicated feedwater flow < steam flow for all SGs Indicated

• . Slowly dropping level in all SGs Recommends manual rx trip before any SG level drops < 10% NR.

US Determines a loss of FW flow is occurring and directs RO to Critical manually trip the reactor before any SG level drops < < 10% NR.

Directs crew perform 3-EOP-E-0 immediate actions & foldout page.

RO Performs immediate actions of 3-EOP-E-0:

1. Verifies reactor trip

• . Rod bottom lights on & RPls at zero

• . Ax trip & bypass bkrs open Rx

• • Neutron flux decreasing

2. Determines SI eventually actuates on SG pressure IXP>1 LlP> 10000 psi BOP Performs immediate actions of 3-EOP-E-0:

1.

1. Verifies turbine tripped

.* Turbine stop valves closed

.* Closes MSR main steam stop MOVs

.* Mid & East GCBs open

2. Verifies power power toto emergency 4kV 4kV buses 3.

3. Determines both 3A & 3B 4kV buses energized

& 3B energized with 3D 3D 4kV 4kV bus energized from 3B 3B 4kV 4kV bus RO RO Trips RCPs Trips RCPs ifif subcooling subcooling << 25[65]°F 25[65]OF per per 3-EOP-E-0 3-EOP-E-0 foldoutfoldout page.

page.

77

Appendix 0D Appendix Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _1_ 1 Event No.:

Event No.: _5_5 Page ~ of Page of -A-Event

Description:

Event

Description:

Once reactor Once reactor power power stabilized stabilized < 60% 60% power, power, aa 3C 30 SGSG feed breakbreak occurs inside occurs inside containment. A manual manual reactor reactor trip is is required required before before any level drops SG level drops < 10%

10% since since the the automatic automatic reactor reactor trip trip is is failed. 3-EOP-3-EOP-E-0 is E-O performed. MOV-3-1 409 breaker performed. The MOV-3-1409 breaker trips & & FCV-3-498 FCV-3-498 fails to close leaving close an uncontrolled leavinci an uncontrolled feed feed path path to to 3C 3C SG SG ifif 3A 3A SGFP SGFP started.

started.

Time j Position Applicants Actions or Behavior Applicant's BOP Performs 3-EOP-E-0 foldout page actions when directed by US

1. Isolates AFW to 3C 30 (faulted) SG

2. Opens ADVs on 3A & 3B SG to stabilize RCS hot leg temp.

US Directs BOP verify prompt actions per 3-EOP-E-0 Attachment 3.

Directs RO continue performance of 3-EOP-E-0 subsequent actions.

BOP Verifies prompt actions per 3-EOP-E-0 Attachment 3:

1. Determines 3A, 3B, 3C, 30, 3D & 3H 480V LCs LOs energized

2. Determines status of MSIVs (still open) and closes them if any MS isolation signal actuated (should not be).

3. Verifies FW isolation:

a. Places 3A SGFP control switch in STOP

b. Determines FCV-3-498 not closed. Attempts unsuccessfully to close valve using controller. Determines other 2 main FW regulating valves closed.

c. Determines all main FW regulating bypass valves closed.

d. Closes MOV-3-1 MOV-3-1407 407 & 1408.

1408. Determines MOV-3-1 MOV-3-1409 409 has no power. Directs NSO to locally close valve.

e. Determines A SSGFWP not available & BB SSGFWP off. off.

4.

4. Verifies at least 22 lOW at least ICWPs Ps running, POV-3-4882 POV-3-4882 & & 4883 4883 closed with ICW ICW headers tied together.

5. Verifies 33 CCWHXs CCWHXs in service, 3A & & 3B CCWPs running, COW CCW headers tied together & & MOV-3-626 open. open.

6.

6. Determines Determines 22 ECCsECCs & & all all 33 EOFs ECFs running.

7.

7. Determines Determines all all 44 HHSIPs HHSIPs & & 22 RHRPs RHRPs running 8.

8. Determines Determines ROS RCS pressure> 1600 1600 psig (no HHSI psig (no HHSI flow) 9.

9. Determines Determines bothboth U3 U3 HHSIPs running && shuts HHSIPs running shuts down down bothboth U4U4 HHSIPs HHSIPs 88

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: _5_5 Page ~

Page of -L 3 of Event

Description:

Event

Description:

Once reactor Once reactor power stabilized << 60%

power stabilized 60% power, power, aa 3C3C SGSG feed feed break break occurs inside occurs inside containment.

containment. A manual manual reactor reactor trip trip is is required required before before any any SG level drops < 10%

SG level 10% since since the automatic automatic reactor reactor trip is is failed. 3-EOP-3-EOP-E-0 is E-O is performed.

performed. The MOV-3-1409 MOV-3-1 409 breakerbreaker trips & & FCV-3-498 FCV-3-498 fails to close leaving leaving an uncontrolled feed path to 3C SG ifif 3A 3A SGFP started.

Time Position Position Applicants Actions or Behavior Applicant's Behavior BOP Continues promptprompt action verification per 3-EOP-E-0 Attachment 3:

10. Determines all containment isolation phase A valves closed.

1 1. Determines all SI valves in proper injection alignment 11.

12. Resets SI & containment isolation phase A.

13. If RCPs running, opens MOV-3-1417 & 1418 then resets/starts all available NCCs.

14. Determines containment pressure remained < < 20 psig.

15. Determines containment ventilation isolated and control room ventilation in proper emergency recirculation alignment.

16. Directs NSO place PAHMS in service per 3-0P-094. 3-OP-094.

17. Verifies 3A & both U4 EDGs running (3B EDG is OOS).

18. Determines 3A, 3B & 3D 4kV buses still energized.

19. Notifies US that prompt action verification complete.

RO Performs subsequent actions of 3-EOP-E-O as directed:

1. Determines no AFWPs will be running.

a. A AFWP slowly losing steam supply as 3C SG depressurizes through the FW break into containment.

b. BAFWPOOS BAFWPOOS

c. C C AFWP started, increased speed but then mechanically tripped. Directs Directs NSO NSO investigate investigate C C AFWP AFWP and and attempt to reset trip (3-ONOP-075 (3-0NOP-075 Att. 4 may may be used for guidance).

be used

2. Determines AFW valve alignment proper 3.

3. Recognizes/reports Recognizes/reports SGs SGs levels levels & decreasing AFW flow

& decreasing 4.

4. Determines Determines RCP RCP thermal thermal barrier alarms alarms off.

off.

5.

5. Determines Determines RCS RCS temp temp dropping dropping due due to to feed break.

break. Limits Limits AFW AFW flow flow to to 345 gpm ifif directed

345 gpm directed toto reduce reduce cooldown.

cooldown.

6.

6. Determines Determines PZR PZR PORVs, PORVs, normal normal spray, spray, aux aux spray spray & & excess excess letdown isolation valves letdown isolation valves closed.

closed.

7.

7. Stops RCPs ifif running Stops RCPs running & & trip trip criteria criteria met met 99

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: 11 Event No.: _5_

Event No.: Page --+/-- of Page of --+/--

...4..

Event

Description:

Event

Description:

Once reactor Qower Once reactor power stabilized stabilized << 60%

60% Qower, power, aa 3C30 SGSG feed breakbreak occurs inside inside containment. A manual manual reactor reactor triQ trip is is reguired required before before any any level droQs SG level drops << 10%

10% since the automatic automatic reactor reactor triQtrip is is failed. 3-EOP-3-EQP-E-0 is E-O is Qerformed.

performed. The The MOV-3-1409 MOV-3-1 409 breaker breaker triQs trips & & FCV-3-498 FCV-3-498 failsfails toto close leavinq an close leaving uncontrolled feed Qath an uncontrolled path to to 3C 3C SGSG ifif 3A 3A SGFP SGFP started.

started.

Time Position Position Applicants Actions or Behavior Applicant's Behavior RO Completes performing subsequent actions of 3-EOP-E-O by determining 3C SG faulted.

US 1. If all SG levels < < 6[32]% and AFW flow < < 345 gpm at 3-EOP-E-O step 8, directs transition to 3-EOP-FR-H.1.

2. Determines 3C SG faulted

3. Directs STA monitor CSFSTs (red path on Heat Sink CSF)

4. Directs transition to 3-EOP-FR.H.1 10 10

Appendix DD Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 Scenario No.:

Scenario No.: _1_

1 Event No.:

Event No.: _6_

6 Page 1 of ~2 Page_1_of Event

Description:

C AFWP triQs trips on oversQeed overspeed Qrematurely prematurely at 6300 RPM (from setuQ}. setup). The trip can not be reset. B AFWP is OOS. A AFWP starts triQ starts,l but runs out of pressure from the 3C feed line fault. Efforts to realign A AFWP to steam Qressure prevented by AFSS-3-007 stuck closed. SSGFW can train 2 steam are Qrevented not be used due to loss of 3C 4kV bus and a dead battery bafferv on B SSGFWP. The crew transitions to 3-EOP-FR-H.1 when AFW flow << 345 gpm and is eventually reguired gQm required to initiate feed & & bleed since all SGs <<

32% narrow range with adverse containment conditions.

I Time Position US

} Applicants Actions or Behavior Applicant's 3-EOP-FR-H.1, Directs response per 3-EOP-FR-H.1.

Performs actions per 3-EOP-FR-H.1 as directed by US:

RCO 1. Determines RCS pressure> intact SG pressure

2. Determines RCS Tavg >350°F BOP Performs actions per 3-EOP-FR-H.1 as directed by US:

1. Per step 2 Caution, informs US that all SG narrow range level << 32%

US Since all narrow range SG levels < < 32%, directs immediate transition to steps 11-19 of 3-EOP-FR-H.1.

Critical Directs initiation of feed & bleed per steps 11-19 of 3-EOP-FR-H.1.

RO Performs actions of 3-EOP-FR-H.1 as directed by US:

1.

1. Determines SI & & containment isolation phase A already initiated Critical 2. Stops all running RCPs

3. Determines 2 HHSIPs running & & SI valves in proper injection alignment

4. Determines PORV block MOVs open and energized Critical 5. Opens both 5 both PORVs PORVs for adequate RCS bleed path. path.

6. Determines CV-3-2803 CV-3-2803 open (IA to containment) 7.

7. Determines SI & containment isolation phase A SI & A already already reset.

8.

8. Determines both both unit unit 33 HHSIPs HHSIPs running & & both unit unit 44 HHSIPs HHSIPs already already stopped stopped and and inin standby.

standby.

11 11

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.: _ 1_

Scenario No.: 1 No.: _66_

Event No.:

Event Page~of~

Page 2 of 2 Event

Description:

Event

Description:

CC AFWP tri(2s trips on on overs(2eed overspeed (2rematurely prematurely at at 6300 RPM (from 6300 RPM (from setu(2}.

setup).

The tri(2 trip can not not be be reset.

reset. B B AFWP is is OOS.

OOS. A A AFWP starts, starts, but but runs runs out of steam out steam (2ressure pressure from the the 3C line fault. Efforts 3C feed line Efforts to to realign realign A AFWP to train 22 steam are (2revented AFWP prevented by by AFSS-3-007 stuck closed.

SSGFW SSG FW can can not not be used due be used due to to loss loss of of 3C 3C 4kV 4kV bus bus and and aa dead dead battery on B SSGFWP. The crew transitions to 3-EOP-FR-H.1 when AFW flow

<<345 qpm and is eventually reguired 345 g(2m required to initiate feed & & bleed since all SGs <<32% narrow range with adverse containment conditions 32% narrow conditions..

Time ,ro.

,~ Position Applicants Actions or Behavior Applicant's BOP Performs actions of 3-EOP-FR-H.1 as directed by US:

11 . Reverifies SI &

. & phase A equipment actuated using 3-EOP-E-0 Attachment 3 (performed with same results as in event 5).

2. Determines status of placing PAHMS in service (directed NSO to do this in event 5). Completes PAHMS alignment in control room 3-OP-094 if NSO reports field actions complete.

per 3-0P-094 US Determines RCS heat removal adequate.

TERMINATING Scenario terminated when feed & & bleed alignment complete (3-CUE EOP-FR-H.1 step 22).

12 12

Appendix D Scenario Outline Form ES-D-1 Facility: Turkey Point Scenario No.:

Scenario 2 Op Test No.: 2007-301 2007-301 Examiners:

Examiners: Candidates:

Candidates: US US RD RO BOP Initial Conditions: Mode 1, 50% Power, MOL. MDL. Power on hold at 50% following inadvertent trip of 3B SGFP while investigation in progress.

Turnover: Equipment OOS:

DOS: 3B 33 EDGEDO due to failed fuel pump (OOS (DOS 2 days; next 0-OSP-023.3 Att 11 & 9 in 4 Pump due to bearing failure (OOS hrs); B AFW Pump (DOS 4 hrs; ETR 24 hrs; both trains verified operable);

3B CSP due to failed 1ST 1ST - low discharge pressure (OOS

- (DOS 12 hr; ETR 36 hr)

Need to swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 3-OP-005 section 7.4 after shift turnover to support possible emergent maintenance on 3A CCW pump (vibration increase last shift).

Known tube leak in 3A S/G SIG (2 gpd) - unchanged for last week. Chemistry samples are being 3-ONOP-071 .2, Attachment 1. The current sample, just completed indicates no taken per 3-0NOP-071.2, significant change in leak rate. MOV-3-1403 remains open at management direction due to small size and stability of tube leak rate.

Event Type*

Event Type' Event Description No.

11 SROIBOP (N) SRO/BOP Swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-0053-OP-005 section 7.4.

2 (I) BOP First stage impulse pressure channel PT-3-446 fails low. The crew responds TFS1MABL=T (TS I) SRO (TS,I) 3-ONOP-028 to stop inward rod movement by taking rod control to per 3-0NOP-028 3-ONOP-049.1.

manual and then 3-0NOP-049.1.

3 (C) ALL 1 2OVAC power panel 3P09 normal inverter fails. The auto swap to the CVT 120VAC TFE6XO6F =

TFE6X06F = T TCE6DHC=T 3-ONOP-003.9.

also fails leaving 3P09 deenergized. The crew responds per 3-0NOP-003.9.

TCE6DI1C =T 3-ONOP-003.9 Attachment 1.

nverter per 3-0NOP-003.9 3P09 is swapped over to the spare inverter 4 TFCMM2A4 = T TFCMM2A4=T (C) ALL The 3A steam generator tube leak grows to 2 gpm. R-3-19R-3-1 9 fails to respond.

TvHHSGA=

TVHHSGA=

(TS) SRO The crew responds per 3-0NOP-071.2 3-ONOP-071 .2 0.002 4a (R) ALL (R)ALL A fast load reduction from 50% power is initiated and performed per 3-ONOP-3-0NOP-071.2 5 TVHHSGA= (M) ALL The 3A steam generator tube leak grows from 2 gpm into a rupture. The

° 0.4 (C) SRO/BOP reactor is tripped and 3-EOP-E-0 performed. MOV-3-1433 fails to close TFSvv3SC=T TFSVV33C=T requiring manual isolation of MSIVs.

6 (C) ALL When transition is made from 3-EOP-E-0 to 3-EDP-E-3, 3-EOP-E-3, the startup transformer locks out. 3A EDG starts but the output breaker does not TFQ5A2OA=T TFQ5A20A=T automatically close, and 3-EOP-ECA-0.0 is entered. 3A EDG EDO output breaker TAQ5LRSB=T TAQ5LRSB=T is manually closed and the crew transitions back to :3-EOP-E-3.

3-EOP-E-3. Only 3A & 3D TFP1S38ST TFP1S38S = T 4kV bus are now available from 3A EDG. 3-EOP-E-3 3-EOP-E-:3 is performed to cooldown cool down and depressurize the RCS to stop primary-secondary leak flow.

(N)ormal, (R)eactivity, (R)eactlvlty, (l)nstrument, (I)nstrument, (C)omponent, (M)ajor (M)aJor 11

TP-2007-301 Scenario TP-2007-301 Scenario #2#2 Event Event Description Description Turkey Point Turkey Point 2007-301 2007-301 Scenario Scenario #2#2 Event 11 - Swap Event - Swap 3D 3D 4kV 4kV bus bus power power supply supply to to 3A 3A 4kV 4kV bus bus per per 3-0P-005 3-OP-005 section section 7.4.

7.4.

Event 22 - First Event - First stage stage impulse impulse pressure pressure channel channel PT-3-446 PT-3-446 fails fails low.

low. The The crew crew responds responds per per 3-3-

ONOP-028 to ONOP-028 to stop stop inward inward rod rod movement movement by taking rod by taking rod control control to manual and to manual and then then 3-0NOP-3-ONOP-049.1.

049.1.

Event 33 - 120VAC Event - 1 2OVAC power power panel panel 3P09 normal inverter 3P09 normal inverter fails.

fails. The The autoauto swap swap toto the the CVT CVT also also fails fails leaving leaving 3P09 deenergized. The crew responds responds perper 3-0NOP-003.9.

3-ONOP-003.9. 3P09 3P09 isis swapped swapped over to the the spare inverter spare inverter per per 3-0NOP-003.9 3-ONOP-003.9 Attachment Attachment 1. 1.

Event 4 - The 3A steam generator tube leak grows to 2 gpm. R-3-19 Event - R-3-1 9 fails to respond. The crew 3-ONOP-071 .2.

responds per 3-0NOP-071.2.

Event 4a - A fast load reduction from 50% power is initiated and performed per 3-0NOP-071.2.

3-ONOP-071 .2.

Event 5 - The 3A steam generator tube leak grows from 2 gpm into a rupture. The reactor is MOV-3-1 433 fails to close requiring manual isolation of tripped and 3-EOP-E-0 performed. MOV-3-1433 MSIVs.

Event 6 - When transition is made from 3-EOP-E-0 to 3-EOP-E-3, the startup transformer locks out. 3A EDG starts but the output breaker does not automatically close, and 3-EOP-ECA-0.0 is entered. 3A EDG output breaker is manually closed and the crew transitions back to 3-EOP-E-

3. Only 3A & 3D 4kV bus are now available from 3A EDG. 3-EOP-E-3 is performed to cooldown and depressurize the RCS to stop primary-secondary leak flow.

22

TP-2007-301 Scenario TP-2007-301 Scenario #2

1. 2 Event Event Description Description Scenario XXIII NRC 2 Simulator Operating Simulator Operating Instructions Instructions Setup Setup IC-2 (50% MOL)

Open & execute lesson file SRO_XXIII_NRC_2.lsn Place simulator in run.

Trigger lesson steps:

SETUP - 3B EDG OOS

- TAQ5LRSB =

005 (actuates TA05LRSB TAQ5B2OP =

= OFF (0) & TA05B20P = RACKOUT (3))

SETUP - B AFWP OOS (actuates TAFK244 == 0.0, TAFK002

- TAFKOO2 = TAFFO1 B =

= 0.0, TAFF01 = 0.0, TCF5MTB == T)

SETUP - 3A SG 2 GPD LEAK (actuates TVHHSGA =

- = 0.0000013)

SETUP - 3B CSP OOS (actuates TAM1DPOB = RACKOUT (3)

(actuatesTAMlDPOB=RACKOUT & TCM1D41M = FALSE)

(3)&TCM1D41M=

SETUP - 3P09 AUTO SWAP TO CVT FAIL (actuates TFE6X06F

- TFE6XO6F = = T)

R-3-1 9 FAIL AS IS (actuates TFCMM2A4 == T)

SETUP - R-3-19 MOV-3-l 433 FAIL AS IS (actuates TFSVV33C == T)

SETUP - MOV-3-1433 SETUP - 3A EDG BKR AUTO CLOSE FAIL (actuates TF05A20A

- TFQ5A2OA = = T then =

= F when IM05A20C)

IMQ5A2OC) st 1

Select channel III as the 1st stage turbine impulse pressure controlling channel on VPA.

Start train A chilled water and secure train B chilled water (CR HVAC panel).

Close CV-3-200B and stop 3C 30 charging pump. Leave CV-3-200A open and 3A charging pump running.

Acknowledge any alarms (B-2/2, B-2/3, D-6/2 D-612 & E-2/5 normal for 50% power; F-9/2 & F-9/5 due to 3B EDG OOS) and place simulator in freeze.

Place clearance info tags on 3B EDG normal start switch, B B AFWP T&T T&T valve control switch & 3B CSP control switch.

Remove AFW train 2 orange tag from BB AFWP tachometer just below ann. panel X.

Provide shift turnover checklists, a blank copy of 3-OP-005 3-0P-005 section 7.4 and 3-ONOP- 3-0NOP-071.2 AttAU 1.

1.

Select 3A QSPDS to page 211 (SAT) and 3B QSPDS to page 212 (RVL). Set ERDADS on VPA to Tavg/Tref TavglTref (TAV) and at the RCO desk to ENVRN (ED3).

Fill in blender && shutdown boron addition placards at console blender station. Data for each IC IC may be found in the ECC & Shutdown Guidelines Book in the simulator I/F.

& Shutdown I/F.

33

TP-2007-301 Scenario TP-2007-301 Scenario #2 #2 Event Event Description Description Event 11 - Swap Event - Swap 3D 3D 4kV bus bus to 3A 3A 4kV bus bus Initiated by Initiated crew per by crew per shift turnover using shift turnover using 3-0P-005 3-OP-005 sect 7.4.

sect 7.4.

Crew must Crew start 3A must start 3A ICWP ICWP and and secure secure 3C ICWP per 30 ICWP per 3-0P-019.

3-OP-019.

Respond ifif directed as NSO Respond NSO to perform pre-start pre-start and post-start checks for 3A ICWP ICWP and post-shutdown checks for 3C ICWP. ICWP. Report all all checks satisfactory.

Respond ifif directed to locally verify voltage on 3D 4kV bus. Click on Schema~MAIN SchemaMAIN POWER DISTRIBUTION~4KV DISTRIBUTION*4KV & 480V AC~3D AC3D 4KV BUS~Report BUSReport voltage indicated on 3D bus mimic.

Respond if directed as NSO to perform pre-start checks for 3C ICWP ICWP and post-shutdown checks for 3C ICWP. Report all conditions normal.

Event 2 - PT-3-446 (channel III

- Ill 11 sst t

stage impulse pressure) fails low Following transfer of 3D 4kV bus to 3A 4kV bus, trigger lesson step EVENT 2 - PT- -

3-446 FAI FAILSLS LOW (actuates TFS1 TFS1MABL=T).

MABL = T).

3-ONOP-028 and take rod control to manual to stop inward rod Crew will respond per 3-0NOP-028 movement. Then the crew will respond to the instrument failure per 3-0NOP-049. 3-ONOP-049. 1.

Respond if directed as NSO to reset AMSAC trouble. After 1-3 min, mm, trigger lesson step EVENT 2 - BYPASS AMSAC POWER 1

- 1 (actuate TCL4P1 BA == T then TCL4P1 BB = T after 30 sec and TCL4RST == T after an additional 30 sec). Resets annunciator 0-716. 0-7/6. Report when complete.

Respond if directed as WCC to initiate PWO and notify I&C. l&C. Also respond as WCC if directed to generate a clearance for bistables tripped for PT-3-446 failure.

C-813 alarms when PT-3-446 fails.

Annunciator 0-8/3 Annunciators 0-6/1, C-611, 6/2 613 alarm until ch v 612 & 6/3 IV 1 lsst stage impulse pressure selected for control.

Annunciators C-7/1, 7/2, 713 C-711, 712, 7/3 alarm a/arm due to tripping bistables.

bistab/es.

44

TP-2007-301 TP-2007-301 Scenario Scenario #2 #2 Event Event Description Description Event 33 - Loss Event - Loss of of 3P09 3P09 After crew After crew brief brief forfor PT-3-446 PT-3-446 failure, failure, at at lead lead examiner examiner direction, direction, trigger trigger lessonlesson stepstep EVENT 33 - LOSS EVENT - LOSS OF OF 3D 3D INV INVI3PO9 13P09 (actuates (actuates TCE6DI1 TCE6DI1 CC == T).T).

This deenergizes This deenergizes 3D 3D inverter.

inverter. Since Since thethe auto auto transfer transfer to to CVT CVT was was failed failed at at setup, setup, 120V 120V vital instrument vital instrument panelpanel 3P09 3P09 is is deenergized.

deenergized. The The crew crew responds responds per 3-0NOP-003.9 3-ONOP-003.9 and and reenergizes 3P09 reenergizes 3P09 from from the the OS DS inverter.

inverter.

Respond as FS/NSO Respond FS/NSO when directed to check out 3P09 & 3D inverter. inverter. After 1-3 1-3 min, mm, report 3P09 deenergized with no other unusual conditions and 3D inverter inverter DC DC input input breaker CB CB11 tripped.

Respond as WCC if directed to have Electrical Electrical check out 3P09 for reenergization. reenergization. After mm, report 3P09 okay to reenergize from DS inverter.

8-12 min, When directed as FS/NSO to reenergize 3P09 from DS inverter, wait 1-3 min mm then trigger the following lesson steps per 3-0NOP-003.9 3-ONOP-003.9 Atl. Att. 1:

Step 11:: EVENT 3 - OPEN 3D INVERTER CB6 (actuates TCEDI4C == F)

Step 2a: EVENT 3 - OPEN ALL 3P09 BREAKERS (actuates TCE6217S == T)

Step 2b: EVENT 3 - OPEN ALL 3P24 BREAKERS (actuates TCC2DLM3 == F, TCC2DLM == F, TCM2DX3M = F, TCC2DLE = = F, TCC2DPE = = F, TCF1DA3M = = F, TCK72407 = = F, TCCMP248 = =

TCN14O9M=F, TCN1410M=F&TCN1411M=F)

F, TCN1409M=F, TCN141OM=F&TCN1411M=F)

Step 5a: EVENT 3 - 3P09A SWITCH TO ALTERNATE (actuates TAE6X34 == ALTERNATE)

Step 6: Call as NSO & request RO take both groups of PZR backup heaters to OFF.

Step 7: EVENT 3 3-CLOSE

- CLOSE 3P09 MAIN/13/02 (actuates TCE6DS4C TCE6DS4C=T, TCF1DA2M=T

= T, TCF1DA2M =T after 5 sec & TCH19O2M TCH1902M = = T after 10 sec)

Step 8: EVENT 3 - CLOSE OTHER 3P09 BREAKERS (actuates TCE6DP2C == T, TCE6DP3C = T after 5 sec, TCE6DP4C == T after 10 10 sec, TCM2D95M = T after 15 15 sec, TCE6DP5C == T after 20 sec, TCE6DP6C = T after 25 sec, TCE6DP7C == T after 30 sec, TCCMDRE == T after 35 sec, TCE6DP8C == T after 40 sec, TCN1 TCN1911911 MM== T after 45 sec, TCN1TCN1912M 91 2M

T after 50 sec, TCCMDRE3

= = T after 55 sec, TCB2M915 == T after 60 sec, TCE6D58C = T after 65 sec, TCD2MCCL == T after 65 after 70 70 sec, TCE6DP9C == T after sec, TCE6DP9C after 75 75 sec, TCM2D9TM TCM2D9TM == T after after 80 80 sec sec & &

TCE6D56C == T after after 85 85 sec) sec)

Step 9: EVENT 3 - CLOSE 3P24 BREAKERS (actuates TCC2DLM3

- TCC2DLM3 == F, F, TCC2DLM == FF after 55 sec, TCM2DX3M == FF after 10 10 sec, TCC2DLE TCC2DLE == FF after 15 15 sec, sec, TCC2DPE == FF after 20 20 sec, sec, TCF1 DA3M DA3M = FF after after 25 25 sec, TCK72407 TCK72407 == FF after after 30 30 sec, TCCMP248 TCCMP248 == FF afterafter 35 35 sec, sec, TCN14O9M TCN1409M == FF after after 40 sec, TCN141OM 40 sec, TCN1410M == FF after after 45 45 sec sec && TCN141 TCN14111 M M == FF after 50 50 sec) sec)

Step 10:

10: EVENT 33 - 3Y07B

- 3Y07B SWITCH TO BACKUP DS DS INVERTER (actuates (actuates TAE6X24 TAE6X24 ==

ALTERNATE)

ALTERNATE)

Step 12:

12: Call Call as NSONSO and and report Att.1 complete.

Respond as as NSO NSO ifif directed directed to depress depress and and hold hold relay LC459X LC459X to allow allow restoration of of letdown letdown and and PZR PZR pressure/level pressure/level control.

control. After After 1-31-3 mm,min, trigger trigger lesson lesson step EVENT 33 -

step EVENT -

PRESS PRESS I HOLD HOLD LC459CX LC459CX (actuates (actuates TCH2459C TCH2459C == T). T). When When directed directed to to release release LC459CX, LC459CX, trigger trigger lesson lesson step step EVENT EVENT 33 - RELEASE

- RELEASE LC459CX LC459CX (actuates (actuates TCH2459C TCH2459C == F). If crew F). If crew doesdoes not not allow allow NSO NSO to to release release LC459CX LC459CX by by end end of of this this event, event, callcall to to remind remind them.them.

Annunciator Annunciator F- 1/2 remains F-112 remains in due to in due to failure failure of of 3D 3D inverter.

inverter. Annunciator Annunciator B-7/1 8-711 willwill remain remain on on until until PRNI PRNI N-44N-44 rodrod stop stop bypass bypass switch switch is is taken taken to to reset.

reset.

55

TP-2007-301 Scenario TP-2007-301 Scenario #2 #2 Event Event Description Description Event 414a Event 414a - 3A- 3A SGSG 22 gpm gpm tubetube leak leak Once the Once the process process of of 3P09 3P09 restoration restoration has has begun begun (crew(crew briefbrief complete),

complete), trigger trigger lesson step lesson EVENT 44 - 3A step EVENT - 3A SGSG 2GPM 2GPM TUBE TUBE LEAK LEAK (actuates (actuates TVHHSGA TVHHSGA == 0.002) 0.002)

Crew should Crew should see see R-3-1S R 15 & SJAE SPING

& SJAE SPING readings readings increase increase and and respond respond per 3-0NOP-3-ONOP-071.2. Ann. H-1/4 071.2. H- 1/4 alarms alarms soonsoon after after leak leak rate rate increase.

increase. R-3-19 R 19 failure failure entered entered at at setup setup means actions means actions triggeredtriggered by by R-3-19 R 19 high high radrad alarm alarm must must be be performed manually manually locally.

locally.

The crew The crew should should initiate initiate downpower downpower per 3-0NOP-071.2 3-ONOP-071 .2 to to remove remove thethe unit unit from from service.

service.

Respond as NSO Respond NSO ifit asked to check unit unit 3 condenser air inleakage. Report 0 scfm.

Respond as Chemistry when directed to sample SGs Respond SG5 and MS MS lines per 0-NCAP-1 0-NCAP-104. 04.

After 15-20 min, mm, identify elevated activity in the 3A SG.

Respond as HP when directed to perform rad readings on MS & & blowdown lines. After mm, report radiation slightly> background on 3A MS line. HP may also be 10-15 min, directed to survey Turbine Deck around SJAE effluent & & rope off contaminated areas.

If directed as FS/NSO to deenergize MOV MOV-3-1403 1403 by opening bkr 4001-28, 4D01-28, after 1-3 mm, trigger lesson step EVENT 6 - DEENERGIZE MOV-3-1403 min, - MOV-3-1 403 (actuates TCF5MB28 == F).

Report when complete. If directed to verify MOV-3-1403 MOV-3-1 403 closed, after 1-3 min, mm, report that this is the case.

Respond as NSO when directed to realign aux steam to Unit 4 per 3-0NOP-071.2 3-ONOP-071 .2 Att.

3. After 2-4 min,mm, trigger lesson step EVENT 4- 4 - ALIGN AUX STEAM FROM U4 (actuates TAFFO75 = 0.0, TAFF02 TAFF075 TAFFO2 = TAFFOO7 =

= 1.0 after 60 sec & TAFF007 = 0.0 after 120 sec). Report when complete.

Annunciator D-4/6 0-4/6 will alarm during this process.

Respond as NSO when directed to locally check CV-3-1500 & & bypass valve 3-20-014.

After 1-3 1-3 mm, min, report both valves closed.

Respond as System when notified that Unit 3 is to be removed from service.

Respond as SM when notified to refer to 0-EPIP-20101 0-EPIP-201 01 & & 0-ADM-115.

0-ADM-115.

Event 55 - 3A SGTR I Reactor trip /I Safety injection

- injection At evaluator evaluator direction after after 5-10%

5-10% powerpower reduction (before (before reaching 25% 25% power),

trigger lesson lesson step step EVENT EVENT 55 - 3A - 3A SGSG TUBETUBE RUPTURE RUPTURE (actuates (actuates TVHHSGA TVHHSGA == 0.4).

0.4).

The crew should should recognize the increase in tube leakage to> to > charging pump capacity.

Per 3-ONOP-071 3-0NOP-071.2, .2, the the crew crew should should triptrip the the reactor and and enter enter 3-EOP-E-0.

3-EOP-E-0. MSR MSR mainmain steam stop MOV steam stop MOV-3-1433 1433 failure to to close close requires manual manual closureclosure ofof all all MSIVs.

MSIVs. PZRPZR level level << 12%

12% requires manual manual safety safety injection.

injection.

Respond Respond as as NSO NSO when when directed directed toto place place U3 U3 PAHMS PAHMS in in service.

service. After After 8-12 8-12 minutes, minutes, trigger trigger lesson lesson stepstep EVENT EVENT 5- 5 - PLACE PLACE U3 U3 PAHMS PAHMS IN IN SERVICE SERVICE (actuates (actuates TAc2VO2A=

TAC2V02A = 1.0, 1.0, TAC2VO2B TAC2V02B == 1.0, 1.0, TAAAV21 TAAAV21 == 1.0,1.0, TAAAV22 TAAAV22 == 1.0 1.0 && TACAOO5 TACA005 == 0.0). Report when 0.0). Report when complete.

complete.

66

Scenario #2 Event Description TP-2007-301 Scenario Event 6 - Loss of offsite power I 3A EDG auto start fails Immediately after entry into 3-EOP-E-3, trigger lesson step EVENT 6 - U3 SUT -

LOCKOUT!I LOOP (actuates TFP1 LOCKOUT TFP1S38S S38S == T)

A spurious lockout on the unit 3 SUT combined with 3A EOG EDG output breaker auto close failure (from setup) and 38 3B EOGEDG OOS (also from setup) causes a momentary momentaiy loss of all AC power. 3-EOP-ECA-O.O is entered and the 3A EOG EDG output breaker is manually closed after which the crew returns to 3-EOP-E-3 to complete response to the SGTR.

Respond as NSO if directed to check the condition of the 3A EOG. EDG. After 1-3 min, mm, report EDG running unloaded, otherwise nothing unusual. If asked to monitor 3A EOG 3A EOG EDG after manual output breaker closure, report EOG EDG running satisfactorily.

System/SAC if asked about U3 SUT lockout. Report that personnel are Respond as System/SAO being dispatched to check out the transformer (switchyard still available).

Respond as U4 RO when directed to perform 3-EOP-E-0 Att 11 to align U4 HHSIPs to U3 RWST. After 1-3 min, mm, trigger lesson step EVENT 6 - ALIGN U4 HHSIP TO U3 RWST (actuates TAMH1V41 == 1.0, TAMH1V46 == 1.0 after 11 min mm delay, TAMH1V37 TAMH1 V37 = mm delay,

= 0.0 after 2 min TAMH4856 = mm delay). Report when complete.

= 0.0 after 3 min Respond as NSO when directed to locally verify MOV-3-1417 & & 1418 closed (in the U3 Pipe & Valve Room). After 1-3 min, mm, trigger lesson step EVENT 6 - CLOSE MOV -

1417 & 1418 (actuates TFKV417C TFKV41 7C = TFKV41 8C =

= T & TFKV418C = T after 1 mm delay). Report when complete.

1 min Respond as NSO when directed to locally close LCV-3-115C. LCV-3-1 1 5C. After 1-3 min, mm, trigger lesson step EVENT 6 - LOCALLY CLOSE LCV-3-11SC

- LCV-3-1 1 5C (actuatesTFBVC62=T).

(actuates TFBVC62 = T). Report when complete.

If directed as FS/NSO to deenergize MOV-3-1403 by opening bkr 4001-28 4D01-28 (may be previously done in event 4a), after 1-3 min, mm, trigger lesson step EVENT 6 - -

MOV-3-1 403 (actuates TCF5MB28 = F). Report when complete. If directed to DEENERGIZE MOV-3-1403 verify MOV-3-1 MOV-3-1403 403 closed, after 1-3 mm, min, report that this is the case.

If directed to align auxiliary steam supply from U4, either report that this is already done min, trigger lesson step EVENT 4-or after 2-4 mm, 4 - ALIGN AUX STEAM FROM U4 (actuates TAFF075 = 0.0, TAFFO2 TAFFO75 TAFF02 = = 1.0 1.0 after 60 sec & TAFFOO7 TAFF007 = 120 sec). Report when complete.

= 0.0 after 120 D-4/6 will alarm during this process.

Annunciator 0-4/6 If asked as NSQNSO to locally verify MOV-3-1 MOV-3-1425425 closed, after 1-3 1-3 mm, min, report that this is the case.

The crew may tiy try to reenergize 3B 38 4kV bus using 3-ONOP-004.3.

3-0NOP-004.3. Since 3B 38 EDG EOG is OOS and the U3 SUT is locked out, such attempts will be unsuccessful.

77

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 2007-30 1 No.: 2007-301 Scenario No.: 2 Event No.: _1_1 Page _1_

Page 1 of _1_

j_

Event

Description:

Swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 3-OP-005 section 7.4.

Time Position Applicants Actions or Behavior Applicant's US Directs BOP to transfer 3D 4kV bus supply from 3B 4kV bus to 3A 4kV 3-OP-005 section 7.4.

bus per 3-0P-005 Directs BOP start 3A ICWP & s/d 3C ICWP per 3-0P-019

& sId 3-OP-019 section 5.3.

BOP 3-OP-005, section 7.4 &

Obtains copies of 3-0P-005, & 3-0P-019, 3-OP-Ol 9, section 5.3.

Performs actions as follows:

1. Starts 3A ICWP & 30 ICWP per 3-0P-019

& stops 3C 3-OP-Ol 9 section 5.3

a. Verifies NSO understands ICWPs to be started/stopped

b. Directs NSO verify oil in 3A ICWP sightglass & & 3A ICWP discharge valve open

c. Starts 3A ICWP & & checks for amperage on VPA ammeter

d. Directs NSO locally check 3A ICWP visible packing leakoff

e. Stops 3C ICWP & & checks zero amperage on VPA ammeter

f. Directs NSO locally do post-stop check

2. Opens 3AB3AB19 19 and then 3AD06 NOTE: 3C CCWP & 3C ICWP are DOS QOS while 3D 4kV bus is deenergized TS 3.7.2 - 7 day action statement &

- & TS 3.7.3 - 30 day action statement.

3. 3ADO1 and then 3AA Closes 3AD01 3AA1177

4. Directs NSO to locally check 3D 4kV bus voltage 3744-4576 volts on cubicle 3AD08.

5. 3C ICWP per 3-OP-Ol Starts 30 3-0P-019 9 section 5.3 to verify operability.

a. Verifies NSO understands ICWPs to be started/stopped

b. Directs NSO verify oil in 30 3C ICWP sightglass & 3C ICWP

& 30 discharge valve open

c. Starts 3C ICWP & & checks for amperage on VPA ammeter

d. Directs NSO locally check 3C ICWP visible packing leakoff

6. As directed at turnover, stops 303C ICWP per 3-OP-Ol 3-0P-0199 sect. 5.3.

a. Stops 30 3C ICWP & & checks zero amperage on VPA ammeter

b. Directs NSO locally do post-stop check RD RO Assists BOP as directed by US.

11

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ 2 Event No.:

Event No.: _2_

2 Page 1 of ~

Page_1_of 2 Event

Description:

Event

Description:

First stage First stage imQulse impulse Qressure pressure channel channel PT-3-446 PT-3-446 fails fails low.

low. The The crew crew responds Qer resQonds per 3-0NOP-028 3-ONOP-028 to stop inward to stoQ inward rod rod movement movement by by taking taking rod rod control to control to manual manual and and then then 3-0NOP-049.1.

3-ONOP-049.1.

~

Time Position Applicants Actions or Behavior Applicant's BOP Recognizes/reports ch III Recognizes/reports Ill first stage impulse pressure PT-3-446 failed low.

low.

• • C-611, 6/2, 6/3 (due to change in annunciators C-6/1, in SG level program setpoint from 60% to 50%)

• . C-7/1, 7/2, 7/3 steam line hi flow & C-8/3 stm dump due to failure

• • P1-3-446 indication on VPA fails low PI-3-446

• • Control rods inserting in automatic RO Recognizes/reports control rods inserting in automatic When PT PT-3-446 446 failure recognized, performs immediate action of 3-ONOP-028 for continuous insertion of an RCC control bank: Places rod control in MANUAL and verifies rods stop moving.

US 3-ONOP-028 Directs response per 3-0NOP-028 RO Performs subsequent actions of 3-0NOP-028 3-ONOP-028 as directed by US:

1. If directed, withdraws control rods to restore Tavg =

= Tref

2. Determines rods above RIL from VPA recorder (or PCB section VII figure 3).

3. Determines PRNI N-44 did not fail Sst 1t

4. After PT-3-447 selected for 1 stage pressure control, places rods back in auto 5.

5. Determines TM-408 median Tavg selector not failed BOP Performs subsequent actions of 3-ONOP-028 3-0NOP-028 as directed by US:

1.

1. IfIf directed, directed, reduces turbine load load to restore Tavg ==Tref 2.

2. Selects Selects Channel Select First Channel Select First Stage Stage Control Control to ch ch IV IV (PT-3-447)

(PT-3-447)

US US Directs Directs WCC notify l&C I&C of PT-3-446 PT-3-446 failure.

Directs Directs response per 3-ONOP-049.

3-0NOP-049.11 22

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 2007-301 Scenario No.: 2 Event No.:

Event 2 Page~ofL Page 2 of 2 Event

Description:

First stage impulse pressure channel PT-3-446 fails low. The crew 3-ONOP-028 to stop inward rod movement by taking rod responds per 3-0NOP-028 3-ONOP-049.1.

control to manual and then 3-0NOP-049.1.

Time Position Applicants Actions or Behavior Applicant's BOP Performs actions of 3-0NOP-049.1 3-ONOP-049.1 as directed by US:

1. Determine PT-3-446 failed by comparison to PT-3-447, PT-3-1604 PT-3-1 604 and expected value based on turbine load.

St 1

2. Verifies PT 447 selected for 1 PT-3-447 st stage impulse pressure control

3. Verifies PT-3-447 reading normally US Evaluates impact per TS:

3.3.1. Table 3.3-1 functional unit 17b applies. Actions 6 (6hr) & 7 (lhr)

(1 hr) in effect.

3.3.2. Table 3.3-2 functional units 1iff & 4d. Action 15 (6hr) applies.

Conducts crew brief regarding effects of PT-3-446 failure and of tripping 3-ONOP-049.i Attachment 4 bistables as directed in 3-0NOP-049.1 BOP Continues performing actions of 3-0NOP-049.1 3-ONOP-049.i as directed by US:

Obtains keys, opens door to and trips following bistables in protection channel III, Ill, rack 16:

• . BS-3-446-i (Turbine power >10% input to P-7)

BS-3-446-1

• . BS-3-446-2 (70% turb load limit runback permissive)

.* BS-3-474 (SG A hi steam flow)

.* BS-3-484 (SG B B hi steam flow)

.* BS-3-494 (SG C hi steam flow)

Closes protection rack door when done.

Places Steam Dump to Condenser Mode switch in MANUAL RO Monitors bistable status lights and annunciator panels for expected indications while bistables being tripped.

US 1.

1. Directs NSO bypass power 11 on AMSAC per Attachment 5

2. Directs notification of l&C I&C

3. Directs WCC generate clearance for tripped bistables 3

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 2007-30 1 2007-301 No.: ~

Scenario No.: 2 Event No.: ~ 3 Page 1 of ~

Page_1_of Event

Description:

1 2OVAC Qower 120VAC power Qanel panel 3P09 normal inverter fails. The auto swaQswap to the CVT also fails leaving 3P09 deenergized. The crew resQonds responds Qer per 3-ONOP-003.9. 3P09 is swaQQed swapped over to the sQare spare inverter Qer per 3-ONOP-003.9 Attachment 1.

Time Position Applicants Actions or Behavior Applicant's BOP Recognizes 1 I reports loss of 3P09 120VAC 1 2OVAC vital inst bus

• . Annunciator F-1/2

• • Loss of all ch IV instrumentation (yellow labels)

• . Loss of controller for B SG FRV RO Recognizes 1 / reports loss of 3P09 120VAC 1 2OVAC vital inst bus

• . Annunciators B-6/5 & B-7/1

• . Loss of all ch IV instrumentation (yellow labels)

• . Loss of controllers for PZR pressure, level & spray valves

• . Letdown isolation Determines a reactor trip has not occurred US 3-ONOP-003.9 Directs performance of 3-0NOP-003.9 Determines unit operating in mode 1 1 Directs FS/NSO to restore power to 3P09 per Attachment 1 1 & RO restore PZR pressure and level control per Attachment 4.

RO Performs actions of 3-ONOP-003.9 3-0NOP-003.9 as directed by US:

1.

1. Places rods in MANUAL

2. Reduces charging flow to minimum reqd req'd for seal injection using a charging pump in manual speed control

3. Determines PORVs closed

4. Maintains Tavg, rx power, PZR pressure & PZR level in normal control bands BOP Performs actions of 3-ONOP-003.9 3-0NOP-003.9 as directed by US:

1.

1. Determines steam dump to condenser mode already in MAN

2. Determines 3B SG in auto lockup, lockup. Increases 3B SG blowdown flow as necessary to control 3B SG level.

3. Maintains SG levels levels in normal control band 4

Appendix DD Operator Actions Operator Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ Event No.:

Event No.: ~

3 2 of ~

Page ..£of Page Event

Description:

12OVAC power panel 3P09 normal inverter fails. The auto swap to the 120VAC CVT also fails leaving 3P09 deenergized. The crew responds per 3-ONOP-003.9. 3P09 is swapped over to the spare inverter per 3-ONOP-003.9 Attachment 1. 1.

[ Time Position Applicants Actions or Behavior Applicant's 3-ONOP-003.9 Attachment 4 when directed by US:

RO Performs 3-0NOP-003.9

1. Determines PORVs closed

2. Directs FS/NSO go to rack 46 & press/hold in relay LC459CX

3. Manually operate PZR heaters to return pressure to normal.

4. Restores letdown

a. Determines B CCW header flow normal.

b. Determines letdown orifice isolation valves closed

c. Opens CV-3-204 then opens LCV-3-460

d. PCV-3-1 Manually controls PCV 45 to control letdown pressure 145

e. Opens letdown orifice isolation valve(s) for desired flow US Briefs crew on effects of loss of 3P09 using Enclosure 1.

3.8.3.1 .j applies. Action c. (2hr to reenergize; Evaluates TS impact: 3.8.3.1.j 24 hr to reenergize from inverter).

BOP Coordinates with FS/NSO to restore 3P09 per 3-0NOP-003.9 3-ONOP-003.9 Aft Att 1.

1.

1. Informs FS/NSO that DS inverter not currently in use

2. When informed that 3P09 about to be reenergized, turns off both groups of PZR backup heaters

3. Observes components reenergizing as 3P09/3P24 breakers closed in

4. Relays notification from FS/NSO that all 3P09/3P24 breakers closed in NOTE: Auto/Manual Auto/Manual controllers should not be returned to AUTO AUTO until vital power completely restored. When power is restored to an Auto/Manual station, the AUTO light will turn on for approx. 15 15 sec after which the MANUAL light turns on indicating that manual control is now available.

55

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: 22 Event Event No.:

No.: ~ j Page 3 of -23 Page~of Event

Description:

Event

Description:

1 20VAC 120V power Qanel AC Qower panel 3P09 3P09 normal normal inverter inverter fails.

fails. The The auto auto swaQ swap to to the the CVT also CVT fails leaving also fails 3P09 deenergized.

leaving 3P09 deenergized. TheThe crew crew resQonds responds Qerper 3-3-

ONOP-003.9. 3P09 ONOP-003.9. 3P09 isis swaQQed swapped over over to to the spare inverter the sQare inverter Qer per 3-3-

ONOP-003.9 Attachment ONOP-003.9 Attachment 1. 1.

Time lime [ Position Applicants Actions or Behavior Applicant's RO RO Restores auto controls Restores controls on Encl End 11 as as 3P09 breakers breakers are are closed closed in:

in:

1. Restores auto PZR pressure control per Att 4 section 2

a. Directs NSO release LC459CX Directs

b. Restore charging pumps, PZR heaters & spray valves to auto control

2. Determines annunciators indicate correctly for plant conditions

3. Returns rods to auto once PRNI N-44 reenergized BOP Restores auto controls on Encl1 End 1 as 3P09 breakers are closed in:

1. Returns 3B SG level control to automatic

a. Manually control FCV-3-488 to return SG level to 60+/-5%

and match feed flow = = steam flow

b. Places 3B SG level control in auto

2. Places steam dump to condenser mode selector to RESET and then to AUTO

3. Determines annunciators indicate correctly for plant conditions 66

Appendix D D Operator Actions Operator Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: 22 Event No.: 4 EventNo.:~ Page _1_

Page 1 of -.L Event

Description:

The 3A steam generator tube leak grows to 2 gpm. R-3-19 R-3-1 9 fails to 3-ONOP-071 .2..

respond. The crew responds per 3-0NOP-071.2 Time lillie Position Applicants Actions or Behavior Applicant's BOP Recognizes/reports increase in 3A SG tube leak rate

• . Annunciator H-1/4 (PRMS hi radiation)

• . R-3-1 5 SJAE effluent PRMS rising/alarming R-3-1S

• SJAE SPING RAD-3-6417 rising/alarming (see ERDADS)

NOTE: R-3-19 is failed as is RO Recognizes/reports increase in 3A SG tube leak rate

• . Annunciator H-1/4 (PRMS hi radiation)

• Slight increase in charging flow to maintain PZR level

• Charging/letdown flow mismatch increases to 2 gpm (see ERDADS)

US 3-ONOP-071 .2 Directs performance of 3-0NOP-071.2 BOP 3-ONOP-071 .2 as directed by US:

Performs actions of 3-0NOP-071.2 1..

1 R-3-1 5 validity Checks R-3-1S

a. R-3-15 ALARM SETPOINT Checks readout on alarming R-3-1S;:::

b. Checks channel operability:

1)

1) Depresses and holds FAIL/TEST FAIUTEST pushbutton on alarming R-3-15.

R-3-1S.

2) Checks readout == 288K OR 289K

3) Releases FAIL/TEST FAIUTEST pushbutton

c. Observes CAUTION prior to Step 6 AND go to Step 6

2. If R-3-1 R-3-19 9 failure recognized, may close FCV-3-6278A1B/C FCV-3-6278A/B/C &

LCV-3-6265B LCV-3-626SB as directed by US.

RO Performs Performs actions of 3-ONOP-071 3-0NOP-071.2 .2 as directed directed by US:

US:

1.

1. Determines Determines PZR PZR level level - STABLE STABLE and can be maintained that way since since charging can keep up up with 22 gpm gpm tube leak leak 77

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 2007-30 1 2007-301 Scenario No.: No.: ~ 2 No.: ..1...

Event No.: 4 Page 2 of L2 Page-.£.of Event

Description:

The 3A steam generator tube leak grows to 2 gpm. R-3-19 R-3-i 9 fails to respond. The crew responds per 3-0NOP-071.2.

3-ONOP-071 .2.

Time Position Applicants Actions or Behavior Applicant's US Directs Shift Engineer Approximate Tube Leakage Using 3-0SP- 3-OSP-041 .1, RCS LEAK RATE CALCULATION 041.1, NOTE: SJAE SPING ACTIVITY vs SG TUBE LEAKAGE & R-3-15 ACTIVITY vs SG TUBE LEAKAGE curves in the Plant Curve Book Book*

not applicable since leak> 150 gpd Identifies leaking S/G: SIG:

a. Monitors the following for S/G SIG tube leak indications:

• Unexplained increase in any S/G SIG level

• . High radiation detected on a S/G SIG sample, main steam line, AFW steam supply line (if running) or S/GSIG Blowdown line

• Unexplained difference between steam and feed flow

• . R-.15, R-19, Increasing radiation levels indicated on R-15, SPING, AND DAM-1 DAM-i BOP Continues performing actions of 3-0NOP-071.2 3-ONOP-07i .2 as directed by US:

b. Directs Health Physics to perform the following:

• . Monitor radiation levels on Main Steam Lines, AFW steam supply line (if running) & S/G Blowdown lines

. Monitor airborne activity at Steam Jet Air Ejectors

c. Directs Nuclear Chemistry to perform the following:

• Perform 0-NCAP-1 04, PRIMARY TO SECONDARY LEAK RATE CALCULATION

.* Increase S/G SIG sampling frequency as determined by Nuclear Chemistry

. DAM-i and SJAE SPING readings Monitor DAM-1 Determines SIG S/G Tube Leakage Leakage>> T.S. Limits - TS 3.4.6.2.c action

b. applicable (4 hrs to fix or HSBY next 66 hr & CSD following 30 hr)

US Determines need to be in Mode 33 within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> (more restrictive than applicable TS action statement).

Goes to Step 10. 10.

88

Appendix DD Appendix Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 4a Page ~1_ of Page of L Event

Description:

Event

Description:

A fast load A fast load reduction reduction from from 50%

50% power power isis initiated initiated and and performed performed per per 3-3-

ONOP-071 .2.

ONOP-071.2.

Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior US US Performs the following prior Performs prior to commencing load load reduction:

reduction:

a. Notifies System Dispatcher Notifies Dispatcher about load load reduction reduction b.

b. Briefs Control Briefs Control Room Room personnel personnel using using Foldout Foldout Page Page

1) Specifies sids/d rate (e.g.,

(e.g.,1155 MW MW/mmImin for 11 hr to sid) s/d)

2) Unit to be taken off line

3) 30 slg 3C s/g leaking at 2 gpm

4) Actions required after unit off-line

5) Using control rods & boration

c. Uses page boost to notify plant personnel of load reduction Notifies SM to review the following procedures AND make any required notifications:

• . 0-EPIP-20101, 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR

. 0-ADM-1 0-ADM-115, 15, NOTIFICATION OF PLANT EVENTS

. Verify NRC Resident notified of Fast Load Reduction and S/G SIG Tube Leakage UNUSUAL UN USUAL EVENT per O-EPIP-20101,0-EPIP-201 01, End Encl 1, 1, Cat 22 Item A.2 now applicable.

Initiates boration per 3-ONOP-071 3-0NOP-071.2: .2:

a. Establishes desired boration rate using

a. using normal boration flowpath 1)

1) Places Places Reactor MakeupMakeup Selector Selector Switch Switch toto BORATE BORATE RO RO 2)

2) Places Places RCSRCS Makeup Makeup Control Control Switch Switch to to START START 3)

3) Sets Sets FC-3-1 FC-3-113A1 3A potentiometer potentiometer to 8.0 or to 8.0 or as as directed directed b.

b. Sets Sets Boric Boric Acid Acid Totalizer Totalizer to to desired desired amount amount of of Boric Boric Acid Acid to to be be added added as as directed directed by by USUS Determines Determines amountamount of of Boric Boric Acid Acid for for desired desired power power reduction reduction US US NOTE:

NOTE: For For s/d sid from from 50%

50% MOL, MOL, upup to to 425 425 gal gal boric boric acid acid required required 99

Appendix D Operator Actions Form ES-D-2 No.:

Op-Test No.: 2007-301 No.: 2 Scenario No.: Event No.: 4a Page ~ of L Event

Description:

A fast load reduction from 50% power is initiated and performed per 3-ONOP-071 .2.

ONOP-071.2.

Time Position Applicants Actions or Behavior Applicant's Reduces plant load at a rate determined by SM as follows:

a. Reduces turbine load (BOP) while manually inserting rods (RO) to lower Tavg (Tavg not> Tref by more than 5°F)

BOP/RO

b. (RO)>

Monitors Control Rod Position (RO) > RIL (Ann. B-8/1 & 2)

NOTE: For sid s/d from 50% MOL, rods should remain> RIL RO RD NOTE: Actions performed depend on point when SGrR SGTR inserted 3-ONOP-071 .2 When directed per 3-0NOP-071.2

1. Checks PZR level following program. If not increases charging flow and/or places an additional letdown orifice in service

2. Determines NRHX CCW flow already increased (from setup)

3. Verifies load reduction rate & auto rod control maintaining Tavg-Tavg T ref per expected value as discussed in crew brief Tret

4. Energizes PZR backup heaters.

5. Places station service loads on U3 SUT

6. Closes blowdown isolation valve for leaking (3A) SG

7. Ensures aux steam supplied from U4, then directs NSO locally open SLWU-3-001 and close 3-10-0073-1 0-007

8. Determines turbine load < <400MW 400MW & verifies non-running SGFP recirc valve control switch in closed/auto

9. Verifies both HDPs stopped < <300 300 MWe

10. Stops 1 condensatepurnp<275MWe 1 condensate pump < 275 MWe

11. Opens SGFP recirc valves on running SGFP < <200 200 MWe

12. Opens turbine drain valves < 150 MWe

13. When directed by US (required boration complete or load decreased to 25% power), secures boration:

a. Places rx rn/u m/u selector switch in AUTO

b. Sets FC-3-1 1 3A potentiometer to directed value FC-3-113A

c. Places RCS rn/u m/u control switch to START

14. After 3A SG identified as leaking, per FOP, directs NSO to deenergize & close MOV-3-1 403 (isolates 3A SG AFWSS)

MOV-3-1403 10 10

Appendix D D Operator Actions Operator Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ 2 Event No.:

Event No.: l 5 Page _1_

Page of -23 1 of Event

Description:

The 3A steam generator tube leak grows from 2 g~m gpm into a ru~ture.

rupture. The tripped and 3-EOP-E-O reactor is tri~~ed 3-EOP-E-0 ~erformed.

performed. MOV-3-1433 MOV-3-1 433 fails to close requiring manual isolation of MSIVs.

reguiring Time Position Applicants Actions or Behavior Applicant's RO Recognizes / reports falling PZR levels and rising charging flows US Determines an increase in SG tube leak rate is occurring and directs response per 3-0NOP-071.2 3-ONOP-071 .2 Foldout Page item 11 b RO 3-ONOP-071 .2 to dropping PZR level:

Responds per 3-0NOP-071.2 rd

1. Starts 33 charging pump and establishes maximum flow rate

2. Isolates letdown flow

3. Determines PZR level still dropping

4. Recommends reactor trip due to inability to maintain PZR level US 3-ONOP-071 .2 due Directs RO to manually trip the reactor per 3-0NOP-071.2 to inability to maintain PZR level.

Directs crew perform immediate actions of 3-EOP-E-0.

RO Performs immediate actions of 3-EOP-E-0:

1. Verifies reactor trip

• . RPIs at zero Rod bottom lights on & RPls

.* Rx trip & bypass bkrs open

.* Neutron flux decreasing

2. Actuates SI & phase A due PZR level not maintained <12%

BOP Performs immediate actions of 3-EOP-E-0:

3-EOP-E-O:

1.

1. Verifies turbine tripped

. Turbine stop valves closed

.

• Attempts closing MSR MSR main steam stop MOVs.

MOVs.

Recognizes MOV-3-1 & closes MSIVs 433 failed to close &

MOV-3-1433 MSIVs

.

• Mid Mid & East East GCBs GCBs open 2.

2. Verifies power power to emergency 4kV buses buses

.

• Determines Determines both both 3A 3A & 3B 3B 4kV 4kV buses energized energized

.* Determines 3D 3D 4kV bus bus energized energized from 3B 3B 4kV 4kV bus bus 11 11

Appendix D D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 Scenario No.:

Scenario No.: 2 Event No.:

Event No.: _5_

5 Page ~

Page of -23 2 of Event

Description:

Event

Description:

The 3A The 3A steam generator generator tube leakleak grows grows from 22 gpm gpm into into aa rupture.

rupture.

The reactor The reactor isis tripped and and 3-EOP-E-0 performed.

performed. MOV-3-1433 MOV-3-1 433 fails to close requiring close requiring manual manual isolation isolation of MSIVs.

MSIVs.

I~

Time Position Applicants Actions or Behavior Applicant's Behavior US US Directs BOPSOP verify prompt actions per 3-EOP-E-0 Attachment 3.

Directs RO continue with performance of 3-EOP-E-0 subsequent actions.

BOP Verifies prompt actions per 3-EOP-E-0 Attachment 3:

1. Determines 3A, 3B, 3C, 30, 3D & 3H 480V LCs energized

2. Determines MSIVs all closed

3. Verifies FW isolation:

a. Places running SGFP switch in STOP.

b. Determines all main FW regulating & bypass valves closed.

c. Closes FW isolation valves.

d. Determines both SSGFWPs off.

4. Verifies 3A & 3B ICWPs running, POV-3-4882 & 4883 closed with ICW lOW headers tied together.

5. Verifies 3 COWCCWHXs HXs in service, 3A & 3B CCWPs running, COW CCW headers tied together & MOV-3-626 open.

6. Determines 2 ECCs & all 3 ECFs running.

7. Determines all 4 HHSIPs & 2 RHRPs running

8. Checks for HHSI flow if RCS pressure << 1600 1600 psig 9.

9. Determines both both U3U3 HHSIPs HHSIPs running & & stops both both U4U4 HHSIPs HHSIPs

10. Determines all containment isolation phase A valves closed.

10.

11.

11. Determines all SI valves in proper injection alignment 12.

12. Resets Resets SI & containment SI & containment isolation isolation phase phase A.A.

13.

13. IfIf RCPs running, opens RCPs running, opens MOV-3-1417 & 1418 then

& 1418 then resets/starts resets/starts all available NCCs.

all NCCs.

14.

14. Determines Determines containment containment pressure pressure remained remained <20

< 20 psig.

psig.

15.

15. Determines Determines containment containment ventilation ventilation isolated isolated and and control control room room ventilation ventilation in in proper proper emergency emergency recirculation recirculation alignment.

alignment.

12 12

Appendix 0D Appendix Operator Operator Actions Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: 22 Event No.:

Event No.: _5_5 Page ~

Page of ~3 3 of Event

Description:

Event

Description:

The 3A The 3A steam steam generator generator tube tube leak leak grows grows from from 22 gpm gpm into into aa rupture.

rupture.

The reactor The reactor is is tripped tripped and and 3-EOP-E-0 3-EOP-E-0 performed.

performed. MOV MOV-3-1-3-1433 433 fails fails to to close requiring close requiring manual isolation manual isolation of of MSIVs.

MSIVs.

Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior BOP BOP Continues prompt action verification per per 3-EOP-E-0 Attachment 3:

16. Directs NSO place PAHMS PAHMS in service per 3-0P-094.

3-OP-094.

17. Verifies 3A &

17. both U4

& both EDGs running U4 EDGs running (3B (3B EDG EDG is is OOS).

OOS).

18. Determines 3A, 3B & 3D 4kV buses still energized.

19. Notifies US that prompt action verification complete.

RO Performs foldout page actions of 3-EOP-E-0 as directed:

1. Trips RCPs if RCS subcooling < < 25°F with HHSIP running and SI flowpath verified Critical 2. Identifies 3A SG level increasing in an uncontrolled manner >6% and isolates all FW flow to 3A SG Performs subsequent actions of 3-EOP-E-0 as directed

1. Determines 2 AFWPs (A & C) running.

2. Determines AFW valve alignment proper

3. Determines at least 3A SG level> level > 6%. Controls AFW flow to intact SGs (3B & 3C) to maintain levels 15-50%

4. Determines annunciators A-1 /1,1/2 & 1/3 all off.

A-1/1,1/2

5. Determines Tc stable.

6. Determines PORVs, normal spray, aux spray & excess letdown isolation valves closed

7. Trips RCPs if RCS subcooling << 25°F with HHSIP running and SI flowpath verified

8. Determines no SGs depressurized or depressurizing

9. Determines SG tube ruptured (R-3-15 alarm & & 3A SG level)

US US Based on SG tube rupture:

1.

1. Directs STA monitor CSFSTs STA monitor

2. Directs Directs transition to 3-EOP-E-3.

13 13

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: 22 No.: _6_

Event No.:

Event 6 Page 1 of ~

Page_1_of _4_

Event

Description:

Event

Description:

When transition When transition is is made made from from 3-EOP-E-0 3-EOP-E-0 to to 3-EOP-E-3, 3-EOP-E-3, the the startul2 startup transformer locks transformer locks out. 3A 3A EDG EDG starts starts but but the outl2ut output breaker breaker does does not not automatically close, and 3-EOP-ECA-0.0 is automatically is entered. 3A EDG EDG outl2ut output breaker is breaker is manually manually closed closed and and the the crew crew transitions transitions back back to to 3-EOP-E-3.

3-EOP-E-3.

Only 3A Only 3A & & 3D 3D 4kV 4kV bus bus are are now available from now available from 3A 3A EDG.

EDG. 3-EOP-E-3 is 3-EOP-E-3 is performed l2erformed to cooldown depressurize the RCS to stol2 and del2ressurize stop I2rimary-primary secondary leak flow.

ime Position Applicants Actions or Behavior Applicant's BOP Recognizes/reports LOOP causing loss of all AC power:

• • 3A 4kV bus deenergized. 3A EDG did not start start..

• • 3B 4kV bus deenergized. 3B EDG OOS 005..

US Determines loss of all AC power exists and directs performance of 3-EOP-ECA-O.O beginning with step 3

1. Determines reactor & turbine already tripped per 3-EOP-E-0

2. Determines RCS Tavg >350°F RCO Performs actions per 3-EOP-ECA-0.0 as directed by US:

1. Determines PORVs closed, letdown & excess letdown isolated

2. Determines SI reset BOP Performs actions per 3-EOP-ECA-0.0 as directed by US:

1.

1. Determines 2 AFWPs running

2. Increases AFW flow to 345 gpm to intact SGs

3. Verifies 4kV bus stripping using Attachments 11 & & 2.

4. Determines 3A & 3B 4kV buses both deenergized with lockout lockout relays reset 5.

5. Determines 3A 3A EDG EDG lockout lockout reset & & 3B EDG EDG OOS OOS

6. Determines Determines 3A EDG running, 3A 4kV bus stripped & & SI reset Critical 7.

7. Manually closes Manually 3AA20 and closes 3AA20 and energizes energizes 3A 3A 4kV 4kV bus bus BOP BOP Determines Determines 3D 3D 4kV bus energized 4kV bus energized from 3A 3A 4kV 4kV bus bus 14 14

D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: _2_

2 Event No.:

Event No.: _6_6 Page L2 of Page of --A-4 Event

Description:

Event

Description:

When transition is When is made made from from 3-EOP-E-0 3-EOP-E-0 to to 3-EOP-E-3 3-EOP-E-3,1 the the startuQ startup transformer locks out. 3A EDG starts but the outQut output breaker does not close,I and 3-EOP-ECA-0.0 is entered. 3A EDG outQut automatically close output breaker is manually closed and the crew transitions back to 3-EOP-E-3.

Only 3A & 3D 4kV bus are now available from 3A EDG. 3-EOP-E-3 is performed to cooldown and deQressurize Qerformed depressurize the RCS to stoQstop Qrimarv-primary-secondary leak flow.

Time Position Applicants Actions or Behavior Applicant's RCO/BOP Restarts ECCS loads on 3A EDG as directed by US:

• . Energizes 3A, 3C & 3H 480V LC

• . 3A & either U4 HHSIP, 3A RHRP

• . 3A & 3C CCWPs, 3A & 3C ICWPs

• . 3B&3CECCs,3B&3CECFs 3B & 3C ECCs, 3B & 3C ECFs US Directs monitoring of CSFs for implementation.

Directs transition to and performance of 3-EOP-E-3.

3-ONOP-004.3 since there is no source of Defers performance of 3-0NOP-004.3 power and stopping pri-sec leak is higher priority Determines from 3-0NOP-071.2 3-ONOP-071 .2 (event 4) that 3A SG is ruptured.

RO Performs actions of 3-EOP-E-3 as directed by US:

1. Determines RCPs not running

2. Verifies SI reset BOP Performs actions of 3-EOP-E-3 as directed by US:

11 . Adjusts 3A SG steam dump to atmosphere setpoint to 1060

. 1060 psig and determines CV-3-1 CV-3-1606606 closed

2. Verifies AMSAC reset.

3. Determines AFWSS train 11 from 3C SG & train 2 from 3B SG Critical 4. Closes MOV-3-1 MOV-3-1403403 then directs NSO open breaker 4D01-28 and verify MOV-3-1 MOV-3-1403403 closed (may already already be done done per event 4 using using 3-ONOP-071 3-0NOP-071.2 .2 FOP FOP guidance) 5.

5. Determines CV-3-6275A CV-3-6275A closed

6. Verifies aux

6. aux steam supplied from U4 U4 directed directed per 3-ONOP-071 3-0NOP-071.2 .2 7.

7. Determines 3A 3A MSIV MSIV & & MOV-3-1 427/1426/1425 already MOV-3-1427/1426/1425 already closed 8.

8. Determines 3A SG level 3A SG level>> 6%

6% and and FWFW flow to 3A SG isolated 3A SG isolated 15 15

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: 22 No.: _6_

Event No.:

Event 6 Page ~

Page 3 ofof -- Event

Description:

Event

Description:

When transition When transition is is made made from from 3-EOP-E-0 3-EOP-E-0 to to 3-EOP,.E-3, 3-EOP-E-3, thethe startuQ startup transformer locks transformer locks out.

out. 3A 3A EDG EDG starts starts but but the the outQut output breaker breaker does does not not automatically close, automatically close, and and 3-EOP-ECA-0.0 3-EOP-ECA-0.0 is is entered.

entered. 3A 3A EDG EDG outQut output breaker is breaker is manually manually closed closed and the crew and the crew transitions transitions back back toto 3-EOP-E-3.

3-EOP-E-3.

Only 3A & 3D 4kV bus Only 3A & 3D 4kV bus are now are available from now available from 3A3A EDG.

EDG. 3-EOP-E-3 3-EOP-E-3 is is performed to cooldown Qerformed cooldown and deQressurize depressurize the RCS RCS to stoQ stop Qrimarv-primary-secondary leak flow.

Time Position Position Applicants Actions or Behavior Applicant's Behavior BOP Continues performing actions of 3-EOP-E-3 as directed by US:

9. Determines 3A MSIV & AFWSS isolated

10. Determines 3A SG pressure> 500 psig 10.

US Determines required CET temperature for cooldown based on 3A SG pressure per 3-EOP-E-3 step 11 1 la a table.

BOP Fully opens 3B & 3C steam dumps to atmosphere.

Critical BOP Continues performance of 3-EOP-E-3 actions as directed by US.

1. Controls AFW flow to intact SGs to maintain NR level 15-50%

2. Determines CV-3-2803 open & IA pressure> pressure > 95 psig RD RO Continues performance of 3-EOP-E-3 actions as directed by US:

1. Determines power to one PORV block MOV MDV available, PORVs closed & both PORV block MOVs open

2. Verifies SI & phase A reset (phase B B not actuated)

3. Determines RCS pressurepressure> > 250 psig & stops 3A RHRP

4. Starts 3A or 30 3C charging pump, stops RCS makeup, takes running charging pump speed to maximum & adjusts HCV-3-121 for proper seal injection flow.

5. Opens LCV-3-1 LCV-3-115B 1 5B & directs NSO locally close MOV-3-1 MOV-3-115C 1 5C

6. Informs USUS when CET temperature << value from step 1111 aa table

7. Determines Determines RCS CET subcooling >> 50°F BOP Continues Continues performance performance of of 3-EOP-E-3 3-EOP-E-3 actions as directed by by US:

US:

1. Closes 3B 1 . Closes 3B & & 3C 3C SG SG steam dump to atmosphere steam dump atmosphere when when CET CET temperature temperature << value value from from step step ha 11 a table table 2.

2. Determines Determines 3A SG pressure 3A SO pressure stable/increasing.

stable/increasing.

16 16

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.: _ 2_

Scenario No.: 2 No.: _66_

Event No.:

Event Page ~

Page 4 of ---+/--

of 4 Event

Description:

Event

Description:

When transition When transition is is made made from from 3-EOP-E-O 3-EOP-E-0 to to 3-EOP-E-3, 3-EOP-E-3, thethe startuQ startup transformer locks transformer locks out.

out. 3A 3A EDG starts but EDG starts but the the outQut output breaker breaker does does not not automatically close, automatically close, and and 3-EOP-ECA-0.0 3-EOP-ECA-0.0 is entered. 3A is entered. 3A EDG EDG outQut output breaker is breaker manually closed is manually closed and the crew and the crew transitions transitions back back toto 3-EOP-E-3.

3-EOP-E-3.

Only 3A Only 3A & 3D 4kV

& 3D 4kV bus bus are are now available from now available from 3A EDG. 3-EOP-E-3 is 3A EDG. 3-EOP-E-3 is performed to cooldown and deQressurize Qerformed depressurize the RCSRCS to stoQ stop Qrimarv-primary-secondary leak flow.

I~

Time Position Position Applicants Actions or Behavior Applicant's Behavior RO Continues performance of 3-EOP-E-3 actions as directed by US:

1. Determines RCS CET subcooling > 50°F US Depressurizes RCS to stop primary-secondary leak per 3-EOP-E-3

1. Determines normal spray not available Critical 2. Directs use of one PZR PORV to depressurize the RCS

3. Directs SI termination when criteria met RO Continues performance of 3-EOP-E-3 actions as directed by US:

1. Opens one PORV. Closes PORV when RCS pressure < < SG pressure with PZR level> 17% OR PZR level> 71 level >71%  % OR RCS CET subcooling <30°F.

2. Determines RCS pressure increasing

3. Determines SI termination criteria met.

4. Stops 3A & U4 HHSIPs.

TERMHATION TERMINATION SI terminated after stopping primary-secondary leak.

CUE 17 17

Appendix 0D Appendix Scenario Outline Scenario Outline Form ES-O-1 Form ES-D-1 Facility:

Facility: Turkey Point Turkey Point Scenario No.:

Scenario No.: 33 Op Test Op Test No.:

No.: 2007-301 2007-301 Examiners:

Examiners: candidates:

Candidates: US US RO RO BOP BOP Initial Conditions:

Initial Mode 1, 1, 75% Power, MOL, Awaiting permission from plant plant management management to increase increase power back back 100%. 3-GOP-301 in to 100%. in use use complete through step 5.96 for return return to 100%

100% power power following a turbine valve test.

Turnover: Equipment OOS: 3B EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 11 & 9 in Equipment in 4 hrs); B B AFW Pump due to bearing bearing failure (OOS (OOS 4 hrs; ETR ETR 24 hrs; both trains verified operable);

3B CSP due to failed 1ST - low discharge pressure (OOS 12

- 12 hr; ETR 36 hr)

Perform monthly surveillance on 3A ECC per 3-0SP-055.1 3-OSP-055.1 section 7.1 immediately after shift turnover. 1ST and remote valve position verification not required.

Known tube leak in 3A S/G SIG (2 gpd) - unchanged for last week. Chemistry samples are being 3-ONOP-071 .2, Attachment 1. The current sample, just completed indicates no taken per 3-0NOP-071.2, significant change in leak rate. MOV-3-1403 remains open at management direction due to small size and stability of tube leak rate.

Event Type*

Event Type* Event Description No.

1 1 (N) BOP 3A ECC monthly surveillance performed per 3-0SP-055.1 3-OSP-055.1 section 7.1. 3A TFKV9O5A TFKV905A ~ T ECC inlet valve CV-3-2905 fails to open and 3A ECC is declared ~OS. OOS.

(N,TS) SRO 2 (I) SRO/RO TM-3-408C (Tavg input to rod control) fails high. Crew responds per 3-TFL1TSCH TFL1T8CH ~

= T ONOP-028 and takes rods to manual to stop continuous inward rod movement.

3 (C) RO/BOP Loss of 3H 480V LC. Also takes 3C charging pump, 3B ECC, 3B ECF & 3D TFE3D37A=T TFE3D37A~ T NCC OOS.

~OS. Requires starting another charging pump or securing the in (C,TS)TS\ SRO TFE3D38T=T TFE3D38T ~ T service 60 gpm orifice. The crew responds per 3-ARP-097.CR for annunciators F-9/6,F-9!6, A-5/4, 1-9/3 or 1-9/4.

-9/4.

4 TAKPXA1=10.0 TAKPXA1~10.0 (C) SRO/BOP 3A1 3A 1 Intake screen high Llp. 3-ONOP-Ol 1. 3A

p. Crew responds per 3-0NOP-011. 3A11 CWP is TAKPXA2 =~ 4.0 4.0 secured.

4a (R) ALL 3A2 Intake screen high £xp. Llp. Fast load reduction per 3-ONOP-100 3-0NOP-100 to 60% for TAKPXA2=1.0 TAKPXA2~1.0 the purpose of securing 3A2 CWP. Manual rod control must be used due to rod control Tavg failure.

5 TAHUVBSB=22 TAHUVBSB~22 (M) ALL 3B RCP high vibration. The crew responds per 3-ONOP-041.1. 3-0NOP-041.1. Once TAHUVBMB=6 vibration reaches the trip setpointsetpoint, the crew manually trips the reactor and TAHUVBMB~ 6 .

immediate actions of 3-EOP-E-0 are performed.

6 (M) ALL When 3B RCP is tripped, 3B 4kV bus is lost and a large break LOCA occurs.

TFE2Z51S=T TFE2Z51S ~ T (contd (cont'd from An automatic SI occurs but train A sequencer fails. Train A ECCS equipment event 5) must be manually started. The crew completes 3-EOP-E-0 and transitions to TVHHCLB =~ 00.11 TFQ634AF=T (C)ALL (C) ALL applicable FRPs followed by3-EOP-E-1.

by 3-EOP-E-1.

TFQ634AF ~ T 6a 6a Once CSFSTs Once CSFSTs are are monitored monitored for implementation, implementation, ifif containment containment pressure pressure isis still still above above 20 psig, the 20 psig, the crew crew immediately immediately transitions transitions to 3-EOP-FR-Z.1 ifif nono higher higher red red or orange path or orange path exists.

exists.

6b 6b (C)

(C) SRO/RO SRO/RO 3-EOP-E-1 3-EOP-E-1 is is entered entered after after which which 3A3A RHRP RHRP trips.

trips. Since Since neither neither RHRP RHRP isis TFM1D3AT TFM1D3AT =~ TT running, running, transition is is made made to to 3-EOP-ECA-1 3-EOP-ECA-1.1. .1. Measures Measures are are taken to to minimize minimize the the loss loss of of RWST RWST inventory.

inventory.

(N)ormal, (R)eactivity, (N)ormal, (R)eactlvlty, (l)nstrument, (I)nstrument, (C)omponent, (M)ajor (M)aJor 11

TP-2007-301 Scenario TP-2007-301 Scenario #3 Event Description

1. 3 Event Description Turkey Point Turkey Point 2007-301 2007-301 Scenario Scenario #3#3 Event 11 - 3A Event - 3A ECC ECC monthly monthly surveillance surveillance performed performed perper 3-0SP-055.1 3-OSP-055.1 section section 7.1.

7.1. 3A 3A ECC ECC inlet inlet valve valve CV-3-2905 fails to open and open and 3A3A ECC is declared ECC is declared OOS.

OOS.

Event 2 - TM-3-408C (Tavg Event - (Tavg input input to rod rod control) fails high.

high. Crew Crew responds responds perper 3-0NOP-028 3-ONOP-028 and and takes rods takes rods to to manual manual to to stop continuous inward stop continuous inward rod rod movement.

movement.

Event 3 - Loss of 3H 480V LC. Also takes 3C charging pump, 38 ECC, 38 3B ECC, 3B ECF ECF & 3D NCC OOS. Requires starting another charging pump or securing the in service 60 gpm orifice. The crew responds crew responds per per 3-ARP-097.CR for annunciators F-9/6, F-9/6, A-5/4, 1-9/3 1-9/3 or 1-9/4.

1-9/4.

Event 4 - 3A

- 3A11 intake screen high b.p.tsp. Crew responds per 3-0NOP-011.

3-ONOP-Ol 1. 3A 3A11 CWP is secured.

Event 4a - 3A2 intake screen high b.p.

- p. Fast load reduction per 3-0NOP-1 3-ONOP-1 00 to 60% for the purpose of securing 3A2 CWP. Manual rod control must be used due to rod control Tavg failure.

Event 5 - 38

- 3B RCP high vibration. The crew responds per 3-0NOP-041.1.

3-ONOP-041 .1. Once vibration reaches either shaft or motor trip setpoint, the crew manually trips the reactor and immediate actions of 3-EOP-E-0 are performed.

Event 6 - When 38

- 3B RCP is tripped, 38 3B 4kV bus is lost and a large break LOCA occurs. An automatic SI occurs but train A sequencer fails. Train A ECCS equipment must be manually started. The crew completes 3-EOP-E-0 and transitions to applicable FRPs followed by 3-EOP-E-1.

Event 6a - Once CSFSTs are monitored for implementation, if containment pressure is still above 20 psig, the crew immediately transitions to 3-EOP-FR-Z.1 if no higher red or orange path exists.

Event 6b EOP-E-1 is entered after which 3A RHRP trips. Since neither RHRP is running, transition is made to 3-EOP-ECA-1 3-EOP-ECA-1.1 .1.. Measures are taken to minimize the loss of RWST inventory.

22

TP-2007-301 Scenario TP-2007-301 Scenario #3#3 Event Event Description Description Scenario XXIII NRC NRC 3 Simulator Operating Simulator Operating Instructions Instructions Setup IC-16 (75% MOL)

IC-16 MOL)

Open and execute lesson file SRO_XXIILNRC_3.lsn Open SRO_XXIII_NRC_3.lsn Place simulator in run Trigger lesson steps:

SETUP - 3B EDG

- EDO OOS (actuates TAQ5LRSB =

(actuates TAQ5LRSB OFF &

= OFF & TAQ5B20P = RACKOUT)

= RACKOUT)

SETUP - B AFWP OOS (actuates TAFK244 =

- TAFK0O2 =

0.0, TAFK002 = 0.0, TAFF01B

= 0.0, TCF5MTB = = T)

SETUP - 3A SG 2 GPD LEAK (actuates TVHHSGA

- TVHHSGA=0.0000013)

= 0.0000013)

SETUP - 3B CSP OOS (actuates TAM1DPOB

- TAM1 DPOB = TCM1 D41 M =

= RACKOUT (3) & TCM1D41 = FALSE (0))

SETUP - TRAIN A SEQUENCER FAIL (actuates TFQ634AF =

- = T)

Acknowledge annunciators F-9/2 & 9/5 (3B EDG OOS). 005). Start train A chilled water and secure train B chilled water (CR HVAC panel). Place simulator in freeze.

Place clearance info tags on 3B EDG normal start switch, B AFWP T& T&T T valve control switch & 3B CSP control switch.

Remove AFW train 2 orange tag from B B AFWP tachometer just below ann. panel X.

Provide shift turnover checklists, 3-0NOP-071.2 3-ONOP-071 .2 Att 11 and a copy of 3-0SP-055.1 3-OSP-055.1 section 7.1 & Attachment 11 filled out thru step 7.1.5. 3-0SP-055.1 3-OSP-055.1 is being performed without quarterly 1ST or remote position verification required.

Select 3A QSPDS to page 211 (SAT) and 3B QSPDS to page 212 (RVL). Set ERDADS on VPA to Tavg/Tref (TAV) and at the RCO desk to ENVRN (ED3).

Fill in blender & shutdown boron addition placards at console blender station. Data for each IC may be found in the ECC & & Shutdown Guidelines Book in the simulator I/F.

Event 11 - 3A ECC OSP failure Initiated Initiated at crew direction direction based on shift shift turnover beginning beginning at step step 7.1.6.

Immediately after CV-3-2905 CV-3-2905 closes in in response taking taking 3A ECC ECC to STOP, trigger lesson step EVENT 11 - 3A ECC INLET FAIL AS IS (actuates TFKV9O5A

- TFKV905A == T). The crew performs 3-OSP-055.

3-0SP-OSS. 11 sect. 7.1 to test 3A ECC EGG beginning at step 7.1.6. 7.1.6. Quarterly 1ST 1ST and and remote position position verification are are not not required. Inlet valve CV-3-2905 GV-3-290S fails to open.

open. 3A 3A ECC EGG is stopped stopped andand declared OQS.

OOS.

Respond Respond as NSO for steps as NSO steps 7.1.14 7.1.14 & 7.1.15. Indicate

& 7.1.15. Indicate that that he has portable he has portable ammeter in in hand.

hand. When directed to When directed to measure measure 3A 3A ECC ECC fan current current atat 3B MCC (bkr 3B MCC (bkr 30650),

30650), report 22 22 amps amps indicated.

indicated.

33

TP-2007-301 Scenario #3 Event Description Respond as NSO if asked to locally check Train A ECC CCW flow on FI-3-1472. After 1-3 minutes, report that flow indicates zero.

Respond as WCC when directed to have Mechanical maintenance investigate failure of CV-3-2905 to open.

Respond as WCC if directed to take 3A ECC breaker 30650 to OFF and place it under clearance. After 8-12 min,mm, trigger lesson step EVENT 1 1 - 3A ECC BKR TO OFF (actuates TCC1 DM0 =

TCC1DMG = F)

Event 2 - TM-3-408C Tavg input to rod control fails high Once 3A ECC stopped and declared OOS, trigger lesson step EVENT 2 - TM -

408C FAILS HIGH (actuates TFL TELl1T8CH T8CH = = T).

This fails falls Tavg input to rod control high causing maximum speed control rod insertion.

The operators respond per 3-0NOP-028 3-ONOP-028 and take rod control to manual to stop inward rod movement. This failure does not fail fall median Tavg for other control purposes. Tavg-Tavg Tref recorder TR-3-408 continues to function.

Respond as WCC when directed to have I&C l&C investigate failure of rod control.

Respond as WCC if directed to generate a caution tag to be hung on the rod control selector switch Event 3 - Loss of 3H 480V LC After TM-3-408C failure brief, trigger lesson step EVENT 3 - LOSS OF 3H LC- (actuates TFE3D37A =

T, then TFE3D38T

= T after a 5 sec delay).

This causes a loss of 3H 480V LG LC and along with it 3G 3C charging pump, 38 3B EGG, 38 3B 3D NCC.

ECF & 3DNGG.

EGF&

The crew responds per 3-ARP-097.GR 3-ARP-097. CR for annunciators F-9/6, 1-9/3, 1-9/4 or A-5/4 and 3-ONOP-04 1.6.

may enter 3-0NOP-041. 6.

Since 3G30 charging pump was running, crew either starts 38 3B charging pump or closes CV-3-200B.

GV-3-2008.

Failure also puts plant in a 1hr lhr shutdown plant action statement per TS 3.6.2.2.b since only 11 EGG ECC is left operable.

Respond if directed to check out 3H 480V LC. After 1-3 min, mm, report bkr 35001 feeder from 3D 480V LC tripped open with scorch marks and a burnt insulation smell. 35007 doesn't doesnt appear to have closed in (still open). Report no evidence of fire.

Respond as WCC when directed to have electrical check into the loss of 3H LC. After 8-12 min, mm, call as WCC and relay recommendation from Electrical maintenance that 3H 480V LC remain deenergized until further evaluation of the LC can be performed.

4

TP-2007-301 Scenario #3 Event Description Respond as NSO if directed to do pre-start & & post-start checks on 3B charging pump.

Report all conditions normal.

Respond as NSO if directed to locally control CCW to NRHX flow to maintain letdown temperature. Click on Schema~COMMON Schema.COMMON SERVICES~COMPONENT SERVlCESCOMPONENT COOLlNG~ COOLlNG 834TAKA834 BYP AROUND TCV-144~adjust valve 834~TAKA834 TCV-144---adjust value as desired and INSERT.

Respond as WCC/Mechanical if asked about status of 3A ECC since plant is now in 11 hr shutdown action statement. Report mechanics are investigating the CV-3-2905 failure.

414a - 3A1/3A2 intake screen clogging II Fast load reduction Event 4/4a Upon completion of TM-3-408C crew brief, trigger lesson step EVENT 4 - 3A1/3A2 -

INTAKE CLOGGING (actuates TAKPXA1 = = 10.0 & TAKPXA2 == 4.0).

The crew responds per 3-0NOP-0 3-ONOP-Ol11. 1. First 3A 11 CWP is secured per 3-0NOP-0 3-ONOP-Ol11.1.

When directed as NSO to check screen wash pump basket strainer Llp, Ap, click on Schema*COMMON SERVICES--+INTAKE Schema--+COMMON SERVlCESlNTAKE AREA & WASH.report strainer

& SCREEN WASH--+report Aps in lower right corner of intake area &

Llp's & screen wash system mimic. Value reported should be < < 10 psid.

When directed as NSO to report status of unit 3 traveling screens, report that they are operating in high gear, are rotating. Specific data such as waterfall height, screen Llp Lp and screen wash pressure can be determined from the intake area & screen wash system mimic accessed earlier.

CCW!TPCW flows and basket strainer Llp's ICW to CCW/TPCW 1ps can be determined by clicking on Schema--+COMMON SERVICES*INTAKE Schema÷COMMON SERVICES--+INTAKE COOLlNG--+report COOLING*report requested parameters shown on the ICW system mimic.

If directed, notify BOP when waterfall height in the 3A1 3A1 intake well reaches 2.5 feet as determined by subtracting 3A13A 1 intake well level from indicated intake level as shown on the intake area & & screen wash system mimic.

Respond if called as FSJWCC FS/wCC regarding issuance of an ECO and manual cleaning of on 3A11 traveling screen. To take 3A1 3A 3A 1 traveling screen out of service, trigger lesson step EVENT 4 3A1 TRAVELING SCREEN OOS FOR CLEANING (actuates TCKPD24M == F). To return 3A1 traveling screen to service, trigger lesson step EVENT 4 - 3A1 TRAVELING SCREEN RETURN TO SERVICE (actuates TCKPD24M == T).

Immediately after 3A1 CWP secured, trigger lesson step EVENT 4 - 3A2 - INTAKE 3A21NTAKE REDUCED CLOGGING (actuates TAKPXA2 = 2.0). 2.0).

The crew reduces power per 3-ONOP-100 3-0NOP-1 00 from 75% to <60% for the purpose of securing 3A2 CWP.

55

TP-2007-301 Scenario TP-2007-301 Scenario #3 #3 Event Event Description Description In view In view ofof the the slowly slowly increasing increasing Llp p on on 3A2 traveling screen, 3A2 traveling screen, crewcrew should should electelect to to perform aa fast perform fast load load reduction reduction per per 3-0NOP-1 3-ONOP-1 00. 00. AtAt lead lead examiner examiner direction, direction, prompt prompt this this decision ifif necessary decision necessary by by calling calling asas SMSM andand asking for status status to helphelp crew understand understand problem is problem is not not going away. away. Additionally, call call as NSONSO at intake intake structure and report report debris still coming down intake intake canal collecting collecting mostly mostly around around the canal banks. banks.

Respond as Respond as NSO ifif directed to close 3-30-002 3-30-002 & & 3-30-004 3-30-004 to allowallow stopping stopping the 3A2 3A2 CWP. After 1-3 1-3 min, mm, trigger lesson step EVENT 4 - CLOSE 3-30-002/004 - 3-30-002 I 004 (actuates (actuates TAFBOO2 == 0.0 TAFB002 0.0 then TAFBOO4 == 0.0 then TAFB004 0.0 30 30 sec later.) Report when complete.

sec later.)

Respond as NSO if directed to listen for seal well solenoid valve closure.

Event 5 - 38 - 3B RCP high vibration I Reactor trip After a 5-10% power change, trigger lesson step EVENT 5 - 3B RCP HIGH -

VIBRATION (actuates TAHUVBSB == 22.0 on 5 min mm ramp & TAHUVBMB = mm ramp).

= 6.0 on 5 min The crew responds per 3-0NOP-041. 3-ONOP-041. 1. Once motor & shaft vibration reach the trip setpoint, the crew manually trips the reactor and immediate actions of 3-EOP-E-O are performed.

Respond if notified as system engineer of increasing vibration on 38 3B RCP motor &

shaft.

Event 6 - Large break LOCA I Loss of emergency coolant recirculation Tripping 3B RCP auto triggers lesson step EVENT 6- 6 - LARGE BREAK LOCA (actuates TVHHCLB =0.1 =O. 1 when H2OLO9G)

H20L09G) and EVENT 6 6-- 3B 4KV BUS LOCKOUT (actuates TFE2Z51S = T when H20L09G)

= Twhen H20L09G).

The crew performs 3-EOP-E-O and must manually start train A ECCS EGGS loads due to failure of 3A sequencer entered at setup. 3A 4kV bus remains on offsite power.

Respond as NSO when directed to locally close MOV-3-1407. After 4-6 mm, min, trigger lesson step EVENT 66 - CLOSE MOV-3-1

- MOV-3-1407 407 (actuates TFVVO7C TFVV07C == F). Report when complete.

Respond as NSD NSO if directed to locally locally open MOV-3-843B.

MOV-3-8438. After 1-3 1-3 mm.,

min., trigger lesson step EVENT 6 - OPEN MOV-3-843B (actuates TFMVVO2O

- TFMVV020 ==T). Report when complete.

Respond as as U4U4 RD RO when directed directed to to perform perform 3-EOP-E-0 3-EOP-E-0 Att AU 11 toto align align U4U4 HHSIPs HHSIPs to to U3 RWST.

U3 RWST. After 1-3 1-3 mm, min, trigger lessonlesson stepstep EVENT EVENT 66 - ALIGN U4

- U4 HHSIP HHSIP TO TO U3U3 RWST (actuates RWST TAMH1 V41 == 1.0, (actuates TAMH1V41 TAMH1 V46 == 1.0 1.0, TAMH1V46 1.0 after after 11 mm min delay, TAMH1V37 == 0.0 delay, TAMH1V37 0.0 after after 22 mm min delay, delay, TAMH4856 TAMH4856 == 0.00.0 after after 33 mmn delay). Report min delay). Report whenwhen complete.

complete.

Respond Respond as NSO when as NSO when directed directed to locally verify to locally verify phase phase A valves valves MOV-3-1417, MOV-3-1417, 1418, 1418, 1425 1425 & & 381 closed (all 381 closed of which (all of which areare in in the the U3U3 Pipe Pipe & & Valve Room). After Valve Room). After 1-31-3 mm,min, 66

TP-2007-301 Scenario TP-2007-301 Scenario #3 Event Event Description Description lesson step EVENT trigger lesson EVENT 6 - CLOSE PHASE

- PHASE A ISOL ISOL V ALVES (actuates VALVES TFKV417C == T, (actuates TFKV417C T, TFKV418C == TT after TFKV418C after 11 min mm delay, delay, TFBV60 TFBV6O == TT after after 22 min mm delay delay && TFSWVM5B TFSWVM5B = TT after after 33 min delay). Report mm delay). Report when complete.

Respond as NSO when directs to locally verify phase B valves MOV-3-626, 716B & & 730 closed(aII of which are in the U3 Pipe & Valve Room). After 1-3 min, closed(all mm, trigger lesson step EVENT 6 - CLOSE PHASE B ISOL VALVES (actuates TFKV626C == T, TFKV16BC == T after 11 min mm delay & TFKV730C = =T mm delay). Report when complete.

T after 2 min Respond as NSO NSQ when directed to place PAHMS in service on unit 3. After 8-12 minutes, trigger lesson step EVENT 6 - PLACE U3 PAHMS IN SERVICE (actuates TAC2VO2A =

TAC2V02A 1.0, TAC2V02B

1.0, = 1.0 TACAOO5

1.0 & TACA005 = 0.0). Report when complete.

Transition is made from 3-EOP-E-O 3-EOP-E-0 to 3-EOP-FR-P. 11 which is quickly exited due to the presence of low head SI flow in response to the LBLOCA.

Event 6a - Respond to High Containment Pressure Once CSFSTs are monitored for implementation, if containment pressure is still above 20 psig, the crew immediately transitions to 3-EOP-FR-Z. 3-EOP-FR-Z 11 if no higher red or orange path exists.

Respond as NSO if directed to check CSP suction & & discharge valves open. After 1-3 mm., report that 3A CSP suction &

min., & discharge valves are open while 3B CSP suction & &

discharge valves are closed and under an ECO.

Event 6b - Respond to LBLOCA with no emergency coolant recirc The crew transitions to 3-EOP-E-1 and then to 3-EOP-ECA-1. 1 1 after it is determined that neither RHRP is available to support cold leg recirculation After 3-EOP-E-1 is entered, trigger lesson step EVENT 6b - 3A RHRP TRIP (actuates -

TFM1 D3AT == T). Respond as NSO when directed to investigate loss of 3A RHRP. After 1-3 TFM1D3AT 1-3 mm.,

min., report back motor very hot especially at bottom of motor casing (tailed (failed bearing).

Respond as Chemistry when directed to sample SGs for activity & check DAM-i DAM-1 and as HP when directed to perform radiation readings on main steam lines. After 10-15 10-15 mm.

min.

report no signs of activity or radiation levels above background.

Respond as NSO when directed to locally close 3-297A1B/C. 3-297AlBIC. After 1-3 1-3 mm, min, trigger lesson step EVENT 6b - LOCALLY CLOSE 3-297A1B1C

- 3-297 AlBIC (actuates TAHN97A ==0.0, 0.0, TAHN97B ==

0.0 0.0 11 mm.

min. later later &

& TAHN97C TAHN97C == 0.0 0.0 22 mm.

min. later.).

later.).

77

TP-2007-301 Scenario TP-2007-301 Scenario #3 Event Description

1. 3 Event Description Respond as Respond as NSO NSO whenwhen directed directed to to locally locally close close LCV-3-115C.

LCV-3-1 1 5C. After After 1-3 1-3 min, trigger mm, trigger lesson step EVENT 6b LOCALLY lesson step EVENT 6b - LOCALLY CLOSE LCV-3-115C

- CLOSE LCV-3-1 1 5C (actuates (actuates TFBVC62 TFBVC62 = T).T). Report Report when complete.

when complete.

Respond as Respond as U4U4 RORD when when directed directed to to start start one one train train of of chilled chilled water water for for computer computer roomroom cooling.

cooling.

Respond as Respond as U4U4 RO when directed RD when directed to to shutdown shutdown U4 U4 EDGs.

EDGs. Respond Respond as as NSO NSO whenwhen directed to directed to complete complete shutdown shutdown of of 3A, 3A, 4A 4A && 4B4B EDGs EDG5 perper 3/4-0P-023.

314-OP-023.

Respond as Respond as NSO NSO when directed to verify 3-356 3-356 closed, then open open 3-365A 3-365A && B. B. After 1-3 1-3 mm., trigger min., trigger lesson lesson step step EVENT EVENT 6b 6b - ALIGN

- ALIGN CVCSCVCS M/UM/U TOTO RWST RWST (actuates (actuates TABM365B TABM365B= =

1.0).

1.0). Report when complete.

Respond as NSO Respond NSO when asked to verify MOV-3-350 MDV-3-350 closed.

closed. After 1-3 1-3 min.,

mm., report report valve closed.

Respond as NSO when directed to locally open MOV-3-1417 & & 1418. After 1-3 min, mm, trigger lesson step EVENT 6b - OPEN CCW TO NCCs (actuates TFKV417C == F, TFKV418C == F, TFKV417O =

TFKV4170 TFKV418O =

= T after 5 sec delay & TFKV4180 = T after 65 sec delay). Report when complete.

Respond as NSO when directed to locally throttle discharge of the running HHSIP (most likely 3A using valve 888B). Click on Schema~SAFETY Schema.*SAFETY SYSTEM~SAFETY SYSTEMSAFETY PROCclick on 888 valve for running HHSIP~TAMH888B(C INJECTION PROC~click HHSIPTAMH888B(C or D) 888B(C or D) VALVE PORT AREA~adjust AREAadjust value consistent with ordered flow rate from 3-EDP-ECA-1 .1 Figure 11 then INSERT. Repeat as necessary to achieve desired flow as 3-EOP-ECA-1.1 shown at F943 on SAFETY INJECTION PROC system mimic.

88

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-30 1 Scenario No.: ~

Scenario No.: Event No.:

Event No.: 11 Page Page _1_1 of of _1_

1 Event

Description:

Event

Description:

3A EGG 3A monthly surveillance ECC monthly surveillance performed performed perper 3-0SP-055.1 3-OSP-055.1 section section 7.1.

7.1.

3A EGG 3A inlet valve GV-3-2905 ECC inlet CV-3-2905 failsfails to open and and 3A 3A EGG ECC is is declared 005.

OOS.

Time Position US US

[ Obtains SM permission Applicants Actions or Behavior Applicant's permission and directs BOP BOP to perform perform 3A EGG ECC monthly monthly 3-OSP-055.1 section 7.1 beginning at step 7.1.6.

operability test per 3-0SP-055.1 BOP 3-OSP-055.1 section 7.1. Performs actions as follows Obtains copy of 3-0SP-055.1 7.1 .6:

beginning at step 7.1.6:

11.. Places 3A EGG ECC switch to STOP

2. Determines GV-3-2905, CV-3-2905, GV-3-2814 CV-3-2814 & GV-3-2908 CV-3-2908 all closed.

3. Determines steps 7.1.10, 11 & 13 n/a since 1ST & remote position verification not required.

4. Starts 3A EGGECC & records start time on Att. An. 11

5. Directs NSO perform steps 7.1.14 & 15 to measure current

6. CV-3-2905 did not open Recognizes & reports GV-3-2905

7. Stops 3A EGG ECC fan & records time on Att.1 NOTE: May leave switch in STOP rather than return to AUTO since 3A ECC QOS EGG CV-3-2905 failed closed OOS with GV-3-2905

8. CV-3-2814 open & GV-3-2908 Determines GV-3-2814 CV-3-2908 closed

9. Determines CCW GGW flow on Fl-3-1 470 is zero & records on An.

FI-3-1470 Att. 11 10.

10. Notifies US 3A ECC EGG failed test due to CV-3-2905 GV-3-2905 failure to open US Notifies SM 3A ECC EGG DOS OOS Directs WCC WGG havehave Mechanical investigate/fix investigate/fix CV-3-2905.

GV-3-2905.

Determines Determines TS 3.6.2.2 3.6.2.2 action a.a. applies (72 (72 hr) hr)

May directs WCC WGG place 3A ECC EGG under ECO EGO 11

Appendix D D Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.: 2007-301 Scenario No.: ~ 3 Event No.: _2_ 2 Page _1_1 of _1_

j_

Event

Description:

TM-3-408C (Tavg (Tavci input to rod control) fails high. Crew responds per 3-ONOP-028 and takes rods to manual to stop continuous inward rod movement.

Time Position Applicants Actions or Behavior Applicant's AC RO Recognizes/reports control rods inserting in automatic Performs immediate action of 3-0NOP-028 3-ONOP-028 for continuous insertion of an RCC control bank: Places rod control in MANUAL and verifies rods stop moving.

US 3-ONOP-028 Directs response per 3-0NOP-028 AC RO 3-ONOP-028 as directed by US:

Performs subsequent actions of 3-0NOP-028

1. If directed, withdraws control rods to restore Tavg =

= Tref

2. Determines rods above RIL from VPA recorder (or PCB section VII figure 3).

3. Determines PRNI N-44 did not fail

4. Tl-3-41 2D, 422D & 432D not failed Determines RCS Tavg TI-3-412D, BOP 3-ONOP-028 as directed by US:

Performs subsequent actions of 3-0NOP-028

1. If directed, reduces turbine load to restore Tavg =

= Tref

2. Determines PT-3-446 & 447 did not fail US Directs WCC notify I&C l&C of rod control failure.

Directs WCC hang caution tag on rod control selector to leave switch in MANUAL NOTE: Rods stay in MANUAL for rest of scenario.

3-ONOP-049.1 if TM-3-408 failure Performs applicable actions of 3-0NOP-049.1 suspected

1. Determines RCS Tavg TI-3-41 2D, 422D & 432D not failed TI-3-412D,

2. Determines no control switches require transfer

3. Evaluates no impact per TS

4. Determines no bistable switches require tripping per AU Att 4, no AMSAC-related channels failed and PT-3-446/447 PT 446/447 did not fail

5. Conducts crew brief regarding effects of rod control failure 22

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ 3 Event No.: _ 3_

Event No.: 3 Page Page _1_1 ofof _11_

Event

Description:

Event

Description:

Loss of Loss of 3H 480V LC.

3H 4S0V LC. Also Also takes takes 3C charging [2um[2l 3C charging pump, 3B 3B ECC ECC,l 3B3B ECF ECF

& 3D NCC

& 3D NCC OOS.

OOS. Reguires Requires starting starting another another charging charging [2um[2 or securing pump or securing the in in service 60 g[2m qpm orifice. The crew res[2onds responds [2er per 3-ARP-097.CR F-916,1 A-S/4l for annunciators F-9/6 1-913 or 1-9/4.

A-5/4, 1-9/3 1-9/4.

Time Position Position BOP J Applicants Actions or Applicant's or Behavior Recognizes/reports annunciator F-9/6, X-2/6 & X-S/1.

Behavior X-511.

]

Recognizes/reports both 3H 4S0V 480V LC feeder breakers open indicating loss of power to that LC.

RO Recognizes/reports annunciator 1-9/3, 1-9/4, J-7/1 & J-S/1 J-8/1 (later A-S/4)

A-5/4)

Directs actions from 3-ARP-097.CR for annunciator F-9/6 Recognizes/reports loss of 3C charging pump, 3B ECC, 3B ECF, 3D NCC and 3D 4S0V 480V MCC.

BOP Performs actions per 3-ARP-097.CR for annunciator F-9/6

1. Determines 3H 4S0V 480V LC auto bus transfer failed

2. Determines 3C 30 & 3D 4S0V480V LC both energized US Directs WCC have Electrical investigate loss of 3H 480V 4S0V LC BOP 3-ONOP-041 .6 entry from 3-ARP-097.CR for annunciator A-9/3 Directs 3-0NOP-041.6 US Directs response per 3-ONOP-041 3-0NOP-041 .6 RD RO Performs actions per 3-ONOP-041 3-0NOP-041.6 .6 as directed by US: ,

1.

1. Starts standby (3B) charging pump US Evaluates TS 3.8.3.1 3.S.3.1.a.a or b as applicable (c from U4 point of view)

On U3 - Action a. applies (8

- (S hr)

On U4 - Table 3.8-2

- 3.S-2 72 hr action since 4A2/4B2 battery chargers not not required by by 3.8.2.1 3.S.2.1.c .c or or dd Evaluates Evaluates TS 3.6.2.2.b requiring plant hr shutdown since only plant 11 hr only 11 ECC ECC left operable Evaluates Evaluates TS 3.6.3 requires 7 day TS 3.6.3 day action to restore 3B 3B ECF ECF Conducts crew Conducts crew brief regarding effects brief regarding effects ofof loss loss of of 3H 3H 480V 4S0V LCLC & 3D 480V

& 3D 4S0V MOO MCC and and requirement requirement to commence action to commence action toto shutdown shutdown plant.

plant.

33

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ 3 Event No.: .+/-.

Event No.: 4 Page Page _1_ 1 of of _11 Event

Description:

Event

Description:

3A11 Intake 3A Intake screen screen high p. Crew high Llp. Crew responds responds per per 3-0NOP-011.

3-ONOP-Ol 1. 3A 3A11 CWP is CWP secured.

is secured.

Time Position Position Applicants Actions or Behavior Applicant's BOP/RO BOP/RO Recognizes/reports rising Recognizes/reports tp on 3A rising Llp 3A11 CWP CWP Reports annunciator 1-3/3 Reports 1-3/3 when itit alarms us US 3-ONOP-Ol 1 Directs performance of 3-0NOP-011 BOP 3-ONOP-Ol 1 as directed by US:

Performs actions of 3-0NOP-011

1. Verifies 2 screen wash pumps running

2. Directs NSO monitor & report screen wash pump basket strainers Llp Isp

3. Directs NSO verify all traveling screens rotating in high gear

4. Directs NSO to monitor & report presence of traveling screen waterfall, debris carryover, screen wash water pressure (> 60 psig) and nozzle spray over entire screen NOTE: If a waterfall is reported or 3A 1 1 traveling screen iJ.pLp pegged high, crew should skip ICW/CCW & & ICW/TPCW checks and go to step 7 to check for conditions to stop a CWP. May secure a CWP if associated indicated screen iJ.p Lp pegged high.

5. N50s report:

Directs NSOs

a. lOW ICW flows to CCWHXs & basket strainer Isps Llp's

b. lOW ICW flows to TPCWHXs & basket strainer Isps Llp's US Determines 3A1 3A 1 traveling screen Isp Llp still well above normal Loops between steps 11 & 7 until 3A1 3A 1 traveling screen waterfall height reported reported> > 2.5 ft When 3A1 3A 1 traveling screen waterfall reported reported> > 2.5 ft, directs shutdown of 3A1 CWP BOP BOP Continues Continues performing performing actions of 3-ONOP-Ol 3-0NOP-0111 as as directed directed by US:

US:

6.

6. Stops Stops 3A1 CWPCWP when directeddirected by US US inin response to report of waterfall waterfall> > 2.5 2.5 ft 7.

7. Determines Determines ICWPICWP secured secured inin 3A1 3A1 intake intake well well US US Directs FS/wCC coordinate Directs FS/WCC coordinate performance performance of of Att.

AU. 11 to to clean clean 3A1 3A 1 intake intake well.

well. Notifies Notifies plant plant management.

management.

44

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ 3 No.: ~

Event No.:

Event 4a Page Page _11 of..L of Event

Description:

Event

Description:

3A2 intake 3A2 intake screen screen highhicih Llp. Fast load Lip. Fast load reduction reduction per per 3-0NOP-100 3-ONOP-100 to to 60% for 60% for the the purpose purpose of securinQ 3A2 of securing 3A2 CWP.

CWP. Manual Manual rod rod control control must must be used be used due due toto rod rod control Tavq failure.

control Tavg failure.

I~

Time Position Position Applicants Actions or Behavior Applicant's BOP BOP Recognizes I reports Recognizes reports rising rising 3A2 3A2 traveling screen Llp Lip US Determines that conditions will soon require securing 3A2 CWP and directs performance of a fast load reduction per 3-0NOP-1 3-ONOP-1 00 nd to <60% to allow shutdown of the 22 CWP.

Contacts FS/wCCFSIWCC and determines 3A 3A11 intake well cleaning not complete so 3A1 CWP can not be started.

Conducts crew brief per 3-0NOP-100 3-ONOP-1 00 Attachment 3:

• . Provides reason (2 gpm tube leak requiring plant sid) sld)

• . Target power level = = offline

• . Specifies load reduction rate

• . Specifies boration amount & rate

• . Covers plant control parameters & contingency actions

• . Covers E-O E-0 transition criteria

• . Reviews req'dreqd actions from 3-0NOP-071.2 3-ONOP-071 .2

• Solicits crew questions & input Ensures load dispatcher notified of load decrease.

RO When directed, initiates boration per 3-ONOP-1 3-0NOP-1 00:

1.

1. Sets BA Totalizer to amount directed

2. Sets FC-3-1 FC-3-113A 1 3A pot setting == 8.0

3. Places Rx MIUM/U Selector Switch to BORATE

4. Places Rx MIU Control Switch to START BOP BOP When directed directed per 3-ONOP-1 3-0NOP-100: 00:

1.

1. Notifies Notifies load load dispatcher of of load load reduction when directed directed by US US 2.

2. Makes Makes plant plant page page announcement announcement regarding load load reduction 55

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: ~ 3 Event Event No.:

No.: 4a 4a Page 2 of ~2 Page£of Event

Description:

Event

Description:

3A2 intake 3A2 screen high intake screen high ~!2.

p. Fast Fast load load reduction reduction !2er per 3-0NOP-1 3-ONOP-1 00 00 to to 60% for 60% for the the !2ur!20se purpose of of securing securing 3A2 3A2 CWP.

CWP. Manual Manual rodrod control control must must be used due to rod rod control Tavg failure.

Time Position Position RO Applicants Actions or Behavior Applicant's Behavior When directed, continues fast load reduction per 3-0NOP-100:

]

3-ONOP-100:

1. Checks for T avg reduction from boration Tavg

2. FC-3-1 1 3A for BA flow rate as directed Sets FC-3-113A BOP Reduces turbine load per 3-0NOP-100 3-ONOP-1 00 at rate directed by US.

RO When directed, continues fast load reduction per 3-0NOP-100: 3-ONOP-1 00:

1. Manually inserts rods in response to turbine load reduction.

NOTE: Rods < < RIL not expected at this power level US 3-ONOP-100, Per 3-0NOP-1 00, notifies SM to review O-EPI P-201 01 &

0-EPIP-20101 & O-ADM-0-ADM-1115 15 and ensure required notifications made RO When directed per 3-ONOP-1 3-0NOP-1 00

1. Checks PZR level following program. If not increases charging flow and/or places an additional letdown orifice in service

2. Determines NRHX CCW flow already increased (from setup)

3. Verifies load reduction rate & & manual rod control maintaining Tavg-Tret per expected value as discussed in crew brief TavgTret

4. Energizes PZR backup heaters.

5. Determines turbine load << 570MW & & verifies non-running SGFP recirc valve open

6. When directed by US US ( (;::: 60% power), secures boration:

a. Places rx rn/u

a. m/u selector switch in AUTO

b. Sets FC-3-1 FC-3-113A 1 3A potentiometer to directeddirected value

c. Places Places RCS rn/u m/u control switchswitch to START 7.

7. Stops one Stops one HDP HDP whenwhen << 45OMWe 450MWe US US Determines Determines that transferring station that transferring service loads station service loads toto SUT SUT and and aligning aux aligning aux steam steam to to unit unit 44 notnot required required due due to to stabilization stabilization of of reactor reactor power power at at 50-60%.

50-60%.

66

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.: ~

Scenario No.: 3 Event No.:

Event No.: l 5 Page Page _1_

j_ ofof _1 j

Event

Description:

Event

Description:

3B RCP 3B high vibration. The crew resl20nds RCP high responds l2er per 3-0NOP-041.1.

3-ONOP-041 .1. OnceOnce reaches either vibration reaches either shaft shaft or motor tril2 or motor trip set12oint2 setpoint, the crew crew manually manually trips the tril2s reactor and the reactor immediate actions and immediate actions of of 3-EOP-E-0 3-EOP-E-0 are are l2erformed.

performed.

Time Position Position Applicants Actions or Behavior Applicant's RD RO Recognizes I/ reports annunciator F-1/1 Recognizes F-ill alarming Determines rising shaft & motor vibration on 3B RCP US 3-ONOP-041 I foldout page Directs response per 3-0NOP-041.1 Directs RO to manually trip the reactor per 3-0NOP-041.1 3-ONOP-041 .1 due RCP motor vibration>

to Rep vibration > 5 mils or shaft vibration>

vibration > 20 mils.

RO 3-ONOP-041 .1 foldout page actions as directed by US:

Performs 3-0NOP-041.1

1. Reporls when either motor vibration>

Reports vibration > 5 mils or shaft vibration > 20 mils vibration>

2. Trips the reactor when directed US Directs crew perform immediate actions of 3-EOP-E-0.

RD RO Performs immediate actions of 3-EOP-E-0:

1.

1. Verifies reactor trip

• . boffom lights on & RPls Rod bottom RPIs at zero

• • Rx trip & bypass bkrs open

.

• Neutron flux decreasing

2. Actuates SI & & phase A if PZR level not maintained <12%

BOP BOP Performs immediate actions of 3-EOP-E-0:

1.

1. Verifies turbine tripped

.

• Turbine stop valves closed

.* Closes MSR main steam stop MSR main stop MOVs.

MOVs.

.* Mid Mid && East GCBs open East GCBs open 2.

2. Verifies power to Verifies power to emergency emergency 4kV4kV buses buses

• • Determines Determines bothboth 3A 3A && 3B 3B 4kV 4kV buses buses energized energized

• • Determines Determines 3D 4kV bus 3D 4kV bus energized energized from 3B 4kV from 3B 4kV bus bus 7

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _3_3 Event No.:

Event No.: _6_

6 Page Page _1 of ~

1 of Event

Description:

Event

Description:

When 3B RCP RCP isis tripped, 3B 4kV busbus isis lost lost and and a large larqe break break LOCA LOCA automatic SI occurs but occurs. An automatic but train A sequencer fails. Train A ECCS ECCS must be equipment must be manually manually started. The crew crew completes 3-EOP-E-0 3-EOP-E-0 and transitions to applicable FRPsFRPs followed by by 3-EOP-E-1.

I~Time Position rosltion j s Actions or Behavior T

Applicant Applicant's RO Secures 3B RCP Recognizes / reports rapidly falling RCS pressure and automatic SI NOTE: RO may manually actuate SI & phase A in response to train A sequencer failure.

BOP Recognizes /I reports loss of 3B 4kV bus with 3B EDG OOS.

US Directs BOP restore 3D 4kV bus per step 3c RNO then verify prompt actions per 3-EOP-E-O Attachment 3.

Directs RO continue performing 3-EOP-E-0 subsequent actions.

BOP Restores 3D 4kV bus per 3-EOP-E-O step 3c RNO:

1. Determines no lockout on 3D 4kV bus

2. Verifies 3C CCWP & 3C ICWP breakers open

3. Opens 3AB19 & 3AD06

4. 3AD01 & 3AA17 Closes 3ADO1 Verifies prompt actions per 3-EOP-E-O Attachment 3:

1.

1. Determines only 3A & 30 3C 480V LOs LCs energized

2. Determines MSIVs all closed (on hi-hi containment pressure) 3.

3. Verifies FW isolation:

isolation:

a. Places both SGFP switches in STOP.

b. Determines all main FW regulating & & bypass bypass valves closed.

c.

c. Closes Closes FWFW isolation isolation valves MOV-3-1 MOV-3-1408408 && 1409.

1409. Directs Directs NSO locally close NSO locally close MOV-3-1 MOV-3-1407. 407.

d. Determines both

d. Determines both SSGFWPs SSGFWPs off. off.

Critical Critical 4.

4. Determines Determines no no ICWP ICWP running and and starts starts 3A 3A & 3C ICWP

& 3C ICWP 5.

5. Determines Determines POV-3-4882 POV-3-4882 & & 4883 4883 closed closed with with ICW ICW headers headers tied tied together.

together.

88

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _3_ 3 Event No.:

Event No.: _6_ 6 Page ..L Page 2 ofof -L3 Event

Description:

Event

Description:

When 3B When 3B RCP RCP isis tripped, tripped, 3B 3B 4kV 4kV bus bus isis lost lost and and aa large larqe break break LOCA LOCA occurs. An automatic SI occurs. An automatic Sl occursoccurs butbut train train A A sequencer sequencer fails.

fails. Train Train AA ECCS equipment ECCS equipment mustmust be be manually manually started.

started. The The crewcrew completes completes 3- 3-EOP-E-0 and EOP-E-O transitions to and transitions to applicable applicable FRPs FRPs followed followed by by 3-EOP-E-1.

3-EOP-E-1.

Time Position Applicants Actions or Behavior Applicant's BOP Continues prompt Continues prompt action action verification per per 3-EOP-E-O 3-EOP-E-O Att. 3: 3:

Critical 6. Determines only 3A CCWP running and starts 3C CCWP.

7. Verifies 3 CCWHXs in service, CCW headers tied together &

MOV-3-626 open (no power).

8. Determines no ECC or ECF running. Starts 3C ECC & 3C 30 nd ECF. No power available to start a 22 ECC or ECF.

NOTE: May start 3A HHSIP but not required at this point.

9. Determines only the U4 HHSIPs & no RHRPs running. Starts 3A RHRP.

10. Determines adequate HHSI flow present, but no RHR flow present even though RCS pressure < <250[650J 250[650] psig.

11. Starts 3A HHSIP. Shuts down either unit 4 HHSIP. Directs U4 RO realign U4 HHSIP suction to U3 RWST per Att. 1.

12. Determines not all containment isolation phase A valves closed. Directs NSO to locally verify phase A valves MOV 1417,1418,1425 & &381 381 closed

13. Determines train A Sl

13. SI valves in proper injection alignment 14.

14. Resets SI Sl & containment isolation phase A. Determines containment isolation phase B actuated. Resets phase B when containment pressure << 20 psig.

15.

15. Determines no RCPs running (should have been tripped by by RO due to inadequate RCS subcooling)

16. Determines containment pressure

16. pressure> > 20 psig.

Critical

a. Manually Manua"y starts 3A CSP. Determines Determines MOV-3-880A open.

b. Directs Directs NSO to locally verify phase B B valves MOV-3-626, MOV-3-626, 71 6B &

716B 730 closed

& 730

c. Verifies all RCPs stopped stopped

17. Determines containment ventilation

17. ventilation isolated isolated andand verifies verifies control control room ventilation room ventilation in in proper proper emergency emergency recirculation recirculation alignment.

alignment.

99

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _3_3 Event No.:

Event No.: _6_

6 Page ~ of Page of ~ 3 Event

Description:

Event

Description:

When 3B 38 RCP RCP isis tripped, tripped, 3B 3B 4kV busbus isis lost lost and and a large large break break LOCA LOCA An automatic SI occurs. An SI occurs butbut train A sequencer sequencer fails. Train Train A ECCS equipment ECCS equipment mustmust be manually started.

be manually started. The crew crew completes completes 3 EOP-E-0 and transitions to applicable FRPs EOP-E-O FRPs followed by by 3-EOP-E-1.

Time Position Applicants Actions or Behavior Applicant's Behavior BOP Continues prompt action verification per 3-EOP-E-0 Attachment 3:

18. Directs NSO place PAHMS in service per 3-0P-094. 3-OP-094.

19. Verifies 3A & both U4 EDGs running (3B (38 EDG is O~S).

OOS).

20. Determines 3A & 3D 4kV buses still energized.

21. Notifies US that prompt action verification complete.

RO Performs foldout page actions of 3-EOP-E-0 as directed:

1. Determines containment conditions adverse (> (>180°F) 180°F)

2. Trips RCPs since RCS subcooling < 25[65]°F with U4 HHSIPs

< 25[65]OF running and SI flowpath verified Performs subsequent actions of 3-EOP-E-O as directed

1. Determines 2 AFWPs (A & C) running.

2. Determines AFW valve alignment proper except that MOV 1404 did not open.

3. Determines SG levels << 6[32]%. Controls AFW flow> 345 gpm until level level> > 6[32]% then maintains levels 15-50%. 15-50%.

4. Determines annunciators A-1/2 and/or 1/3 1/3 on. If RCP seal return temps all << 235°F, verifies SI reset then starts 3A charging pump at minimum speed and adjusts HCV-3-121 for seal injection proper seal injection flow

5. Determines Determines Tc Tc trend. IfIf decreasing, reduces AFW flow to ~ 345 gpm until anyany SG level level> > 6[32]%.

6[32]%.

6.

6. Determines Determines PORVs, normal spray, spray, aux aux spray & & excess excess letdown letdown isolation isolation valves closed closed 7.

7. Verifies RCPs tripped (tripped RCPs tripped (tripped earlier on foldout earlier on foldout page) page) 8.

8. Determines Determines no SGs depressurized no SGs depressurized or or depressurizing 9.

9. Determines Determines no no SG SG tube tube ruptures ruptures 10.

10. Determines Determines RCS ReS notnot intact; containment radiation, intact; containment radiation, pressure pressure & & sump sump level level all all not not normal.

normal.

10 10

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: _3_

3 Event No.:

Event No.: --.fuL 6a Page Page _1_

j_ ofof -L Event

Description:

Event

Description:

Once CSFSTs Once CSFSTs are are monitored monitored for im(2lementation implementation,l ifif containment pressure is (2ressure is still still above above 20 20 (2si9 psig,1 the crew crew immediately immediately transitions to 3- 3-EOP-FR-Z.1 ifif no EOP-FR-Z.1 higher red no higher red or or orange orange (2ath path exists.

exists.

I~

Time Position r"U;:'I .* Applicants Actions or Behavior Applicant's Directs monitoring Directs monitoring of CSFs for implementation.

US If any RCS cold leg temperature drops below 320°F (orange) or 290°F (red) transitions to and directs response per 3-EOP-FR-P.1 Performs actions per 3-EOP-FR-P.1 as directed by US:

RO 1. Determines RCS pressure < 250[650} psig with> 1000 gpm RHR

< 250[650]

flow (indication of LBLOCA)

Transitions out of 3-EOP-FR-P.1 (due to LBLOCA indication) us US If containment pressure> 20 psig, CSFSTs are being monitored for implementation and no higher red or orange path exists, transitions to and directs response per 3-EOP-FR-Z.1 RO Performs actions of 3-EOP-FR-Z.1 as directed by US:

1. Determines all RCPs secured.

2. Stops any running NCCs

3. Determines containment isolation phases A & & BB already verified

4. Determines containment ventilation isolated and verifies control room ventilation in proper emergency recirculation alignment.

US Determines no RHRP available. If 3-EOP-ECA-13-EOP-ECA-1.1 .1 entered, determines number of CSPs required from 3-EOP-ECA-13-EOP-ECA-1.1 .1 and skips to step 9.

RD RO Continues performing performing 3-EOP-FR-Z.1 actions as directed directed by US:US:

1.

1. Determines RWST level> level> 155000 155000 gal gal && MOV-3-864A/B MOV-3-864A1B open

2. Determines 3A CSP running & & 3B CSP DOSOOS 3.

3. Determines MOV-3-880A open & & MOV-3-880B closed!

closed/

deenergized deenergized underunder ECO ECO 4.

4. Determines Determines 33 CCWHXCCWHX in service &&22 CCWP in service CCWP running (3A && 3C) running (3A 3C) 5.

5. Determines Determines only only 3C ECC running (no 3C ECC (no power power to other other two) with associated bypass, bypass, inlet inlet && outlet outlet open.

open.

6. Determines

6. Determines only 3C ECF only 3C ECF running running (no (no power power to other two) to other two) 11 11

Appendix DD Appendix Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _3_3 Event No.:

Event No.: ~ 6a Page Lof-L Page 2 of 2 Event

Description:

Event

Description:

Once Once CSFSTs CSFSTs are are monitored monitored forfor iml2lementation, implementation, ifif containment containment pressure is I2ressure is still still above above 20 20 I2si9, psig, the the crew crew immediately immediately transitions transitions to to 3-3-

EOP-FR-Z.1 ifif no EOP-FR-Z.1 no higher higher red red or or orange orange l2ath path exists.

exists.

Time Position Position Applicants Actions Applicant's Actions or Behavior Behavior BOP BOP Periorms actions Performs actions ofof 3-EOP-FR-Z.1 3-EOP-FR-Z.1 as as directed directed by by US:

US:

1.

1. Directs NSO verify CSP suction & discharge valves open.

2. Determines MSIVs closed

3. Determines no SGs faulted US Directs return to procedure and step in effect 12 12

Appendix D Appendix D Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: _3_3 Event No.: ~

Event No.: 6b Page 1 of ~

Page_1_of .

Event

Description:

Event

Description:

3-EOP-E-1 is 3-EOP-E-1 is entered entered after after which which 3A3A RHRP RHRP trips.

trips. Since Since neither neither RHRP RHRP isis running, transition is running, made to 3-EOP-ECA-1.1.

is made 3-EOP-ECA-1 .1. Measures Measures are taken to are taken to minimize the loss minimize loss of RWST inventory.

inventory.

Time Position Applicants Actions or Behavior Applicant's US Directs transition to and performance of 3-EOP-E-1.

Directs 3-ONOP-004.3 is optional since there is no NOTE: Performance of 3-0NOP-004.3 source of power and EOP actions are higher priority.

Conducts crew brief.

RO Performs actions of 3-EOP-E-1 as directed by US:

1. Determines RCPs not running

2. Determines power to one PORV block MOV available, PORVs closed & both PORV block MOVs open

3. Verifies SI reset

4. Determines only 3A charging pump has power available and pump is running at minimum speed for seal injection.

5. Places RCS makeup control switch to stop

6. Establishes maximum flow using 3A charging pump

7. Opens LCV-3-1 LCV-3-115B1 5B & directs NSO locally close MOV-3-i MOV-3-115C.

1 5C.

BOP 3-EOP-E-i as directed by US:

Performs actions of 3-EOP-E-1

11. Determines SGs not faulted.

2. Controls AFW flow> 345 gpm until level >> 6{32]% 6[32]% then maintains levels 15-50%.

15-50%.

3. Directs Chemistry sample SGs for activity & check DAM-i DAM-1

4. Directs Directs HP HP take radiation readings on main steam lines

5. Verifies containment isolation

5. isolation phase A & B B reset.

6. Verifies CV-3-2803 open & & IA IA pressure> 95 psig US US Determines Determines SI can not SI can be terminated (inadequate subcooling, RCS not be RCS pressure pressure && PZR PZR level) level) 13 13

Appendix DD Appendix Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-30 1 2007-301 Scenario No.:

Scenario No.: _3_3 Event No.: ~

Event No.: 6b PageLof~

Page 2 of 3 Event

Description:

Event

Description:

3-EOP-E-1 is 3-EOP-E-1 is entered entered after after which which 3A RHRP trips.

3A RHRP trips. Since Since neither neither RHRP RHRP isis runninc, transition running, transition is made to is made to 3-EOP-ECA-1.1.

3-EOP-ECA-1 .1. Measures Measures areare taken taken to to minimize the minimize the loss loss of of RWST RWST inventory.

inventory.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior RO RO Continues performing Continues performing 3-EOP-E-1 3-EOP-E-1 actions actions as as directed directed by by US.

US.

1.

1. Determines 3A Determines 3A CSP CSP should should continue continue running running since since containment containment temperature> 122°F.122°F.

2.

2. Determines RCS Determines RCS pressure pressure << 250[650]

250{650] psig.

psig. Recognizes/reports Recognizes/reports RHRP tripped with RHR 3A RHRP RHR flow << 1000 1000 gpm

3. Determines RCS pressure stable/decreasing stable/decreasing BOP Continues performing 3-EOP-E-1 actions as directed by US:

1. Determines SG pressures stable

2. Determines 3A 4kV bus on offsite power & 3B 4kV bus deenergized deenergizec

3. Directs U4 RO verify one computer room chiller running

4. Stops 3A EDG. Directs NSO complete shutdown per 3-OP-023.

Directs U4 RO stop U4 EDGs and have them placed in standby.

us US Determines no RHRP available. Directs transition to 3-EOP-ECA-1.1 3-EOP-ECA-1.1 Conducts EOP transition crew brief RO Performs actions of 3-EOP-ECA 3-EOP-ECA-1.1 -1 .1 as directed by US:

1.

1. Determines Determines RWST level level> > 60000 gallons

2. Determines cold leg recirc capability not not available Critical 3. Aligns makeup

3. makeup to U3 RWST to U3 RWST a.

a. Determines Determines CVCSCVCS makeup makeup stopped stopped b.

b. Directs NSO verify Directs NSO verify 3-356 3-356 closed, closed, then then open open 3-365A 3-365A & &B B c.

c. Places Places FCV-3-113A FCV-3-113A in in AUTO, AUTO, FCV-3-114A FCV-3-114A in in OPEN, OPEN, FCV FCV-3-113B 3-113B & & 114B 114B inin CLOSE CLOSE d.

d. Determines Determines MOV-3-350 MOV-3-350 closed.

closed.

e.

e. Places Places FCV-3-1 FCV-3-113A13A & 14A controllers

& 1114A controllers in in MANUAL MANUAL f.1. Places Places RCS RCS makeup makeup selector selector switch switch to to BORATE BORATE g.

g. Sets BA Sets BA totalizer totalizer to to maximum maximum and and starts starts makeup makeup h.

h. Adjusts Adjusts PW PW & BA flow

& BA flow for for max max flow flow atat 1.5:1 1.5:1 blend blend 14 14

Appendix DD Appendix Operator Actions Operator Actions Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 2007-301 2007-301 Scenario No.:

Scenario No.: _3_ 3 Event No.:

Event No.: -.illL 6b Page~of Page 3 of -L j

Event

Description:

Event

Description:

3-EOP-E-1 isis entered 3-EOP-E-1 entered after after which which 3A 3A RHRP RHRP triQs.

trips. Since Since neither neither RHRP RHRP isis running, transition made to running z transition isis made to 3-EOP-ECA-1.1.

3-EOP-ECA-1 .1. Measures Measures are are taken taken to to minimize the minimize the loss loss of of RWST RWST inventory.

inventory.

[ Time Time Position Position BOP Perform actions actions of Applicants Actions Applicant's of 3-EOP-ECA-1.1 Actions or 3-EOP-ECA-1 .1 as or Behavior Behavior BOP Perform as directed directed by by US.

US.

1.

1. Controls AFW Controls AFW flow>

flow> 345345 gpm until level>

gpm until level > 6[32]%

6{32]% then then maintains maintains levels 15-50%.

levels 15-50%.

uS US Determines RCS Determines RCS cool cooldown rate has down rate has exceeded 11 OO°F/hr 00°F/hr and no no additional forced cooldown requiredrequired RO 3-EOP-ECA-1 .1 actions as directed by US:

Continues performing 3-EOP-ECA-1.1

1. Determines only 11 ECC running & available.

a. Determines phase A reset

b. Directs NSO open MOV-3-1417 & 1418

c. Resets & starts 2 available NCCs

2. Directs U4 RO verify at least 1 1 computer room chiller running US Determines CSP suction aligned to RWST. Directs running CSP secured if containment pressure < 14 14 psig.

RO Continues performing 3-EOP-ECA 3-EOP-ECA-1.1 -1.1 actions as directed by US: US:

1.

1. Determines 2 HHSIPs running (3A & one U4 U4 pump)

2. Verifies SI SI reset Critical Critical 3. Stops

3. Stops 11 HHSIP HHSIP

4. Determines

4. Determines RCS RCS pressure pressure << 250{650]

250[650] psig, psig, RHR flow flow << 1000 1000 gpm gpm and no and no RHRPs RHRPs available available

5. Determines

5. Determines no no recirc sump suction recirc sump suction lines lines open.

open. Closes Closes MOV MOV 862A 862A (no(no power power toto 862B) 862B)

US US 1.

1. Determines Determines RCS RCS subcooling subcooling inadequate inadequate for for RCP RCP start start && SI SI termi nation.

termination.

Critical Critical 2. Determines

2. Determines minimum minimum SI SI flow flow per per Figure Figure 1. 1. Directs Directs NSO NSO throttle throttle running running HHSIP HHSIP discharge discharge to to achieve achieve minimum minimum SI SI flow flow TERMINATING Scenario TERMINATING Scenario is is complete complete whenwhen HHSI HHSI flow flow is is reduced reduced to to minimum.

minimum.

CUE CUE 15 15