ML040490440

OAT6

1 HP-5 Fails closed: (C, QATC)

Applicants Actions or Behavior

1. AP/032 (boss of Letdown)

m

8

Verify CC in operation

e

m

Ensure 1HP-120 (RC V O ~ I E

Control) in HAND and closed

Notify chemist RCS Boron sample needed and normal letdown

line is isolated.

Position the standby HPI pump switch to OFF.

Throttle 1HP-31 (WCP Seal Flow Controi) to establish 12-15

gpm SEAL INLET HDR FLOW.

Verify loss of letdown is due to letdown valve or interlock

failure. GO TO Step 4.29

Close 1 HP-6 (Letdown Orifice Stop)

Close 1 HP-7 (Letdown Control)

i-

i HP-1 (lA Letdown Cooler Inlet)

k 1 HP-2 (1 B Letdown Cooler Inlet)

k 1 HP-3 (1 A Letdown Cooler Outlet)

P

1 PIP-4 (1 B Letdown Cooler Outlet)

Verify letdown temperature 6 135°F. Perform RNO

Open 1HP-13 (Purification IX Bypass)

Ensure 1 HP-8 (Purification IX In1et)and 1 HP-9&11 (Spare

Purification BX Inlet & Outlet) closed

Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Ensure 1 HP-5 (Letdown Isolation) is open

GO TO seep 4.1 1

0

Verify 1 HP-5 (Letdown Isolation) closed

E Close 1 HP-6 (Letdown Orifice Stop)

e

Close 1 HP-4 (Letdown Control)

m

Dispatch an operator in continuous communication with Control

Room to manually open 1 HP-5 (LETBBWN ISOLATION)

Note: 1HP-5 failure not known to the crew at this time

8

m

Ensure the following open

m

e

0

e

Note: 1HB-5 will not open from the control room.

Cue: Open 1 HP-5 and inform CR

NUREG-I 021, Draft Revision 9

Page 5 Qf 16

Op-Test No.:

Event Description:

Scenario No.: SPARE

IHP-5 Fails closed: (C, OATC)

Event No.: 4

Page 2 of 2

Time

Position

QATC

Applicant's Actions or Behavior

a

e

a

e

e WHEN letdown temperature

13O"F, THEN ensure

e

WHEN 1 HP-5 (Letdown Isolation) is open, THEN ensure CC

System in operation.

Verify letdown temperature i

135°F. Perform RNO.

Open 1 HP-13 (Purification IX Bypass)

Ensure 1 HP-8 (Purification IX Inlet) and 1 HP-SEkll (Spare

Purification IX inlet & Outlet) are closed

Select LETDOWN Hi TEMP BNTLK BYP switch to BYPASS.

Throttle open 1 HP-7 (Letdown Control) to establish zz 20 ggm.

LETDOWN HI TEMP INTLK BYP switch in NORMAL.

Open 1 HP-6 (Letdown Orifice Stop)

Adjust 1 HP-7 (Letdown Control) to control desired letdown flow.

Re-establish normal makeup through t HP-128.

Note: Normal letdown flow is 78 gpm.

When letdown has been re-established or when directed by the

lead examiner this event is complete. (OATC and BOP swap)

NUREG-1021, Draft Revision 9

Page 6 of 16

Bp-Pest No.:

Scenario No.: SPARE

Event No.: 5

Page 1 of ?

Event Description:

I

Position

OATC

S R 8

That fails HIGH: (E, OATC)

Applicant's Actions or Behavior

Plant response:

a

That recorder =612"F

a

Loop A mot Dixson meter reading goes to 62Q"F

Tave recorder and digital meter increases to -583°F

Loop A Delta T meter increases to ~65°F

Loop A Pave meter increases to 488°F

Statalarm ?SA-ZB-3, WC Hot beg Temp High, alarms

Crew response:

a

The crew should use Plant Transient Response to stabilize the

unit. Reactor Diamond and the FDW Master should be taken to

manual to stabilize the plant.

Depending on when ICS is taken to manual, FDW flow may be

greater than 100%. If this is true, taking ICs to hand will allow Nl

Power to begin to increase to match FBW flow. When this occurs,

the OATC will be required to decrease FDW flows to stop the power

increase.

SRO shsuki refer to APE8 (16s Instrument Failures).

a

When the ICs has been taken to manual and the plant is stable or

when directed by the lead examiner this event is complete.

NUREG-1 021, Draft Revision 9

Page 7 of 16

3p-Test No.:

Scenario No.: SPARE

Event No.: 6

Page 1 of 1

Event Description:

1 Dd Heater Drain Pump oil leak: (C, All)

Time

Position

Applicants Actions or Behavior

When directed by the Lead Examiner an NE0 will inform the

control room that the 1 D1 HDP has a severe oil leak.

Crew Response:

D

I

Refer to OP/l/A/llQ6/02D, (Shutdown of the 1 B1 HDP)

SRO skouBd determine that reducing power to e 87% is required

and direct unit shutdown in accordance with on@ of the following:

P APi29 (Rapid Unit Shutdown)

P OP/I/A/I 10~084

(Operation At Power)

Note: A manual shutdown is required because the ICs is in

manual dwe to the previous Thot failure.

Event is complete when a unit shutdown is directed by the SRO

or when directed by the Lead Examiner.

NUREG-1021. Draft Revision 9

Page 8 of 16

Op-Test No.:

Scenario No.: SPARE

Event No.: 7

Page 1 of 1

Event Description:

OATC

Manual reactor power decrease: (R, OATC)

--

Atmlicants Actions of Behavior

Crew Response:

1. SRO will direct the unit shutdown and continue in the AW29 (Rapid

Unit Shutdown) or OP/l/PJ110~004 (Operation AB Power).

2. O A K will reduce FDW flow with the FBW Masters and insert the

control rods manually to reduce reactor power.

Event is complete when reactor power has been reduced 5% or

when directed by the lead examiner.

NUWEG-1821, Draft Revision 9

Page 9 of 16

I

-

--

-^

Scenario No.: SPARE

Event No.: 8

Page 1 of 2

3p-Test No.:

Event Description:

Time

_I_-

Position

Loss of Main Feedwater: (M, ALL)

Applicants Actions or Behavior

When directed by the Lead Examiner BOTH Main FDW pumps will

trip.

Plant response:

Reactor trip

A MDEFDW Pump will g l ~ t start

B MDEFDW Pump will start

No EFW flow the A SG and level will decrease to = 1 5 XSUR

a

0

Crew response:

SWQ will direct the OATC to perform lrnmediate Manual actions

and the BOP to perform a Symptom Check.

SRQ should transfer to Subsequent Actions of the EOP.

Subsequent Actions will:

Verify all control rods fully inserted.

Verify Main FDW in operation and controlling properly.

> No FDW pumps are operating. Perform RNQ. Ensure Rule

3 (Loss of Main or Emergency FDW) in progress or

complete.

Verify BBVs contrding SG pressure = 1010 psig.

Dispatch an operator with Encl 5.29 (MSWV Locations) to verify

all MSRVs have reseated.

Verify ES is NOT required.

Initiate Encl 5.5 (Pzr and LDST Level Control).

Ensure PCB 20 and PGB 21 open

Ensure Generator Field Breaker and Exciter Field Breaker is

open.

Verify AB and TB Instrument Air pressure 2 90 psig.

Verify ICS/NNl power available.

Verify all 41 6OV switchgear (ITC, lVB, 1TE) energized.

Verify both SGs > 550 psig.

Note: AH steps may not be performed depending on the timing of

the next event.

NUREG-1021, Draft Revision 9

Page 10 of 16

Bp-Test No.:

Scenario No.: SPARE

Event No.: 8

Event Description:

Loss of Main Feedwater: (M, ALL)

Time

Position

OATC

Page 2 of 2

Applicants Actions or Behavior

0

Verify Main FDW operating.

r No FDW pumps operating perform WNO Ensure Rule 3 (Loss

of Main or Emergency FDW) in progress or complete.

0

Ensure SG levels approaching proper setpoint. (Rule 7)

Verify 4 SCMs > 0°F.

Note: There will be not feed to the A SG at this time.

This event is complete when SCM has been verified > 0°F or

when directed by the lead examiner.

NUREG-1021, Draft Revision 9

Page 11 of 16

Op-Pest No.:

Event Description:

Time -

Position

OAT6

Scenario No.: SPARE

Event No.: 9

Page 1 of 3

Loss of Main and Emergency Feedwater, 1 B MDEFDWP trips

(CBP Feed): (M, ALL)

Applicants Actions or Behavior

When directed by the Lead Examiner 1 B MDEFDW pump will trip.

Plant response:

No E W flow to either SGs

RCS temperature and pressure will increase

Crew response:

The SRO should direct the OATC and the BOP to perform a

symptom check.

The OATC should determine no Main or Emergency Feedwater

is feeding the SGs and with SRO concurrence re-start RULE 3

(Loss of Main and Emergency Feedwater).

lAAT NO SGs can be fed with FDW (Main/Emergency),

AND any of the following conditions exists:

RCS pressure reaches 23008 psig OR NBB limit

PZP level reaches 375 [340

acc]

THEN PERFORM Rule 4 (Initiation of HFI Forced Cooling).

a

RULE 3 (Loss of Main and Emergency Feedwater) will:

Ensure any EFDWP operating.

0

RNO step, GO TO Step 4.

Verify Main FDW NOT operating.

Place the following in MANUAL and close:

b 1 FDW-315 (1 A EFDW Control)

i. 1 FDW-316 (1 B EFBW Control)

e

NUREG-1021 Draft Revision 9

Page 12 of 16

Op-Test No.:

Scenario No.: SPARE

Event No.: 9

Page 2 of 3

Event Description:

Time

Position

BATC

Loss of Main and Emergency Feedwater, 1B MDEFDWP trips

(CBP Feed): (M, ALL)

Applicants Actions or Behavior

Verify all the following available:

P ARYCBP

>. TBVs

Disable both Digital Channels 1&2 of AFlS on both Readers A

and B:

P A Header DOG. CH. 1 and 2 OFF

k B Header DIG. CH. 1 and 2 OFF

Place Startup Block valve control switch for 1 FDW-33 (1 A SG)

and 1 FDW-42 (1 B SG) in OPEN:

Position Startup Control valve 10 - 20% open on all available

SGs: 1 FDW-35 OR 1 A SG and 1 FDW-44 on t B SG.

Close the following:

> 1FDW-32 (1A Main FDW Control)

k 1 FDW-41 (1 B Main FBW Control)

I. 1 FDW-31 (1A Main FDW Block)

2. 1 FDW-40 (1 B Main FDW Block)

bower SG pressure in available SGs to = 500 psig.

Control FDW flow to stabilize RCS P/T by throttling the

following as necessary: (CT-10) (CT-11)

k Startup Controi valves

k TBVs

Notify CR SRO that CBP feed is in progress.

Dispatch an operator to perform Encl 5.26 (Manual Start of

BDEFDWP).

NUREG-1 021, Draft Revision 9

Page 13 of 16

Scenario No.: SPARE

Event No.: 9

Page 3 of 3

Event Description:

Loss of Main and Emergency Feedwater, 1 B MDEFDWP trips

(CBP Feed): (M, ALL)

Position

Applicant's Actions or Behavior

SWO should transfer to the "Loss of Heat Transfer" (LOHT) tab

of the EOP.

The LOHT tab will:

e

Ensure Rule 3 (Loss of Main or Emergency FDW) is in

progress or complete.

IAAT core SCM = 0"F,

THEN GO TO Step 4.

lAAT NO SGs can be fed with FDW (Main/Emergency),

AND any of the following conditions exists:

>. RCS pressure reaches 2300 psig OR NBT limit

> Pzr level reaches 375" [340" acc]

WEN GO TO Step 4.

Perform RNO step:

0

o

1 NOTE: 1Al RCP provides the best Pnr spray.

I_

I__

Reduce operating RCPs to one purnp/laop.

WHEN any of the following conditions exists:

k Unit 1 EFDW available

k EFDW aligned from another unit

k Main FDW pump available AND reset

THEN GO TO Step 52

Note: The SRO should wait at this WHEN step until a Feedwater

source is aligned or conditions are met to go into Forced HPI

Cooling.

This event is complete when CBP flow has been established and

the plant is stable or when directed by the lead examiner.

NUWEG-102%

~ Draft Revision 9

Page 14 of 16

Scenario No.: SPARE

Event No.: IO

Page 1 Of 1

Event Description:

I

Position

TDEFDWP returned (CBP feed recovery)

Applicants Actions or Behavior

Note: When directed by the Bead examiner SPQC will call the

control room and inform them that the TDEFDWP has been

repaired and can be used.

The SRO should transfer to Step 52.

Verify MFDW or Unit t EFDW available.

Verify Encl 5.27 (Alternate Methods For Controlling EFBW

Flow) is NOT in progress.

Verify Main FDW pump available and reset. (FDW pumps are

not reset) Perform RNQ

GOTOStep59

Verify one of the following:

&=

Both MDEFDWPs operating

k TDEFDWP operating

0

e

Verify all the following:

k Tcold > 500°F

P TBVs available

Verify Tcold I

547°F.

> Perform WNO step:

Ensure THP setpoint at -885 psig.

GO TO Step 64.

e

Ensure TBVs in AUTO for available SGs.

Initiate feed to available SGs per Rule 7 (SG Feed Control)

lAAT heat transfer is established in any SG,

THEN GO TO Step 77.

Control feeding and steaming of available SGs to maintain SG

level at setpoint and cooldown rate within Tech Spec limits:

(CT-26)

. P

~

M

5 m n v .

6 GnaF 1 V,

hr

This event and the exam is complete when TDEFDWP flow to the

SGs have been established and the plant is stable or when

directed by the lead examiner.

NUREG-1 821, Draft Revision 9

CRlTlCAL TASKS

1

~ CT-18, Establish FW Flow and Feed SGs

2. CT-11, C ~ n t r ~ l

SG pressure to Maintain RC Temperature Constant.

3. CT-26, Restore Feed Po A Bty SG

NUREG-1821, Draft Revision 9

Page 16 of 16

Amendix D

Scenario Outline

Form ES-D-1

Facility: Qcsnee

Scenario No.: 1 fnr

Op-Test No.: -

Examiners:

Operators: Traeey Roland (SRQ-U)

Kevin Csoley (RQ)

Initial Conditions:

0

RCS Boron 108 ppm

50% Reactor Power, (Snap 201)

Turnover:

m

OP/1/A/1102/004

(OPS At Power) End. 3.2 in progress at step 2.17. Holding per

dispatcher request.

SASS is De-energized for I&E troubleshooting

1 B MDEFDW Pump OOS for PMs, expected to be returned to service later this shift.

k TS 3.7.5 Condition A

After turnover, perform the Unit 1 portion of PT/0/N0610/014 (Operability Best of 41 60 V

Breakers)

m

e

"A" RBCLD fails to receive ES signal

il

2 I MPI12f

I I , BOP. SRO

I PZR Level # 1 Fails LOW (TS)

II

7

I

I R. QATC. SRO 1 Manual unit shutdown

NUREG-1021, Draft Revision 9

Page 1 of 17

~-

_-

(N)orrnal, (R)eactivity,

(I)nstrurnent, (C)omponent, (M)ajor

NUREG-1021, Draft Revision 4

Page 2 of 17

-

__

-_--

Form ES-D-2

Appendix

~ Q

_.

__

OperatoFActions

-.

Op-Test No.:

Scenario No.: 1

Event No.: 1

Page 1 of 1

Event Description:

Position

OATC

Operability test of 4160V breakers: (N, BOP)

Applicant's Actions or Behavior

Crew response:

The OATC should perform Step 12.6 of PT/0/,4/8610/O'f7 (Operability Best

of 41 60 V Breakers).

0

Place Unit 1 MFBl AUVOIMAN transfer switch to "MAN".

2. dSA-14/8-1 (EL Normal to SLJ Transfer Bus 1 Automatic

Transfer Block) actuates

Close El, MFB1 STARTUP FDR.

> 1SA-14/A-1 (EL I T Normal Supply Breaker Bus I Open)

actuates

P 1 SA-14A-3 (EL 6T1 4KV SLB Feeder Bus 1 Closed) actuates

Verify N1 MFBl NORMAL FDR opens, and electrical auxiliaries

transfer.

Close Nll MFBl NORMAL FDR.

Verify E l I MFBI STARTUP FDR breaker opens and electrical

auxiliaries transfer.

Place Unit 1 MFB1 AUTO//MAN transfer switch to "AUTO".

Place Unit 1 MFB2 ALBTO/MAN transfer switch to "MAN".

k 1 SA-1WB-2 (EL Normal to SU Transfer Bus 2 Automatic

Transfer Block) actuates

>.

1 SA-1 4/A-2 (EL 1 T Normal Supply Breaker Bus 2 Open)

actuates

'r 1 SA-1418-4 (EL CT1 4KV SCB Feeder Bus 2 Closed) actuates

Verify N21 MFB2 NORMAL FDR breaker opens and electrical

auxrliaries transfer.

o

e

Close E21 MFB2 STARTUP FDR.

0

Close N2i MFB2 NORMAL FDR.

0

Verify E2, MFB2 STARTUP FDR breaker opens and electrical

auxiliaries transfer.

Place Unit 1 MFB2 AUTOIMAN transfer switch to "AUTO".

When Step 12.1 is complete or when directed by the Lead Examiner

this event is completed.

NUREG-1021, Draft Revision 9

Page 3 of 17

Bg-Test No.:

Scenario No.: 1

Event No.: 2

Page 1 of 1

Event Description:

PZR Level # 1 Fails LOW: ( 8 , BOP)

Time

Position

Applicants Actions or Behavior

Plant response:

Statalarms

m

1 SA-2/C-3, RC Pressurizer Level Highlbow

1SA-2/C-4, RC Pressurizer Level Emerg High/bow

Front board (1 UBl ) indications:

PZR Level 1 indicates 0

1 HP-120 (RC Volume Control) throttles open

Makeup flow increases to = 160 gpm.

Crew response:

Refer to ARG

b Check alternate PZR level indications (1 U81 and OAC) and

determine that PZW Bevel 1 has failed !ow.

k Check for proper Makeuplbetdown flows and adjust to restore

proper level.

> Select an alternate PZR level channel on f UBI.

SRO should direct the OATC to take actions to restore normal PZW

level.

SRQ should direct the OATC Bo refer to PV/608/001 (Periodic

Instrument Surveillance) SASS Manual Operation and have the OATC

select an alternate PZR level channel on 1 UBI.

SRO should refer to PS 3.3.8 (PAM Instrumentation) Table 3.3.8-1.

P Two PZR level channels are required. No action required.

When an alternate PZR level channel has been selected and PZR

Bevel is stable or when directed by the lead evaluator this event is

completed.

NUWEG-l82fi, Draft Revision 9

Page 4 of 17

Op-Test No.: __ Scenario No.: 1

Event No.: 3

Page 1 of 1

Event Description:

Time

Position

OATC

OATC

swo

A LPSW pump suction valve closes and standby pump does not

Applicants Actions or Behavior

Plant response:

Statalarms:

Control board indications:

1 SA-Q/A-9, LPSW Header A/B Press Low

LPSWP (A LPSW Pump Suction) indicates closed (also an OAC

alarm)

A LPSW pump amps are cycling

LPSW Header A/B Pressure Low

Crew response:

1. Refer to ARG for 1 SA-9iA-9, LPSW Header A B Press Low

2. Refer to AP/24 (Loss of LPSW)

Ensure LPSW pump suction valves are open.

Note: CPSW-2 (A

LPSW pump suction valve) will indicate closed. The

team may dispatch an NE0 to open LPSW-2. The valve will not be able

to be opened locally.

Verify LPSW pumps are cavitating

k Pump amps erratic

k LPSW header pressure fluctuating

Ensure the Unit 1/2 STANDBY LPSW PUMP AUTO START

CIRCUIT is DISABLED.

Stop the affected pump. Stop A LPSW pump.

Ensure all available (NOT previously cavitating) LPSW pumps

operating. Start C LPSW pump.

Verify normal LPSW System operation is restored.

The SRO should call SPOC to troubleshoot the reason for the

suction valve closing, the Auto Start failure and determine if the K

LPSW pump was damaged due loss of suction.

The SRO should refer to TS:

k TS 3.7.7 (Low Pressure Service Water System) Condition Ar

applies. Restore required LPSW pump to operable status. 72

hours completion time.

. TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition A.

Restore Auto-Start Circuitry to operable. 7 day completion time.

Note: TS 3.3.28 may be addressed as a follow up question.

Event is complete when SRO has referred to TS 3.7.7 or when

directed by the Lead Examiner. (BOP and O A K Swap positions)

NUREG-1821, Draft Revision 9

Page 5 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 4

Page 1 of t

Position

Event Description:

QAPC

SRQ

RC Loop B Flow fails LOW: (I, OATC)

Applicants Actions or Behavior

Plant response:

1. Statalarms:

o

1 SA-2JA-4, WC Loop B Flow bow

1 SA-2JA-5, RC Total ROW LOW

6

e

1 SA-l/A-1, RP Channel A Trip

1SA-11/44, RP Channel A FluxilrnblFlow Trip

2. Control board indications:

o

m

RPS Channel A trips.

RCS Flow meter shows Loop B flow at zero.

5 SI6 FDW Flow instrument shows a reduction in FDW, and the A

S/G FDW Flow indicates increasing flow or off-scale High.

e DELTA Tc meter indicates a large Delta Temp.

Crew response:

0

The crew should stabilize the unit by using the Plant Transient

Response process.

Take the Diamond and BOTH FDW Masters to MANUAL and stabilize

the unit.

The SRO should refer to AP/28, ICs instrument Failures and notify

SPOC to have the instrument repaired.

0

API28, ICS Instrument Failures wilt:

e

k Ensure DIAMOND and BOTH FDW Masters in MANUAL.

P Notify SPQC to select a valid RCS flow input to IC.§ and

investigate and repair the failed WCS flow instrumentation.

. Ensure any associated requirements of PTll/NO6OO/OQ1

(Periodic instrument Surveillance) are met for the failed

instrument.

r WHEN notified by SPQC that a valid RCS flow input has been

restored to IC§, THEN GO TO Encl 5.1 (Placing ICs in AUTO).

Note: Crew may refer to PT16001001 (Periodic Instrument

Surveillance) and TS 3.3.1 (RPS Instrumentation) due to A

RPS

Channel trip and may choose to place A9

RPS to manual Bypass.

Event is complete when the SRO has reached the WHEN step in

APD8 or when directed by the Lead Examiner.

NUREG-1021, Draft Revision 9

Page 6 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 5

Page 1 OB 1

If the reactor trips QII event 4, activate timer to insert A SG Startup

Level failure.

Plant response:

Statatarms:

0

1SA-2/E-8, MS Stm. Gen A Level Low Limit

Control board indications:

0

A SG Startup Levei indicates 0 on the control board and the 086.

A SG XSUR Level indication will indicate greater than 25.

A

SG Main and Startup Control valves will be open even though

the SG level will be above setpoint.

A SG level will continue to increase. XSUR indication should be

used to determine SG level.

1 crew response:

i

OATC

0

The OATC should diagnose the failure of the A SG Startup Level

instruments and inform the SRO.

The SRO should direct the RO to take the A SG Main and Startup

Control valves to manual.

The SWO should direct the RO to close the A SG Main Control valve

and use the A SG Startup Control valve to control A SG level at 2 5

XSUR.

The SWO should notify SPOC to have the instruments repaired.

0

Event is complete when the OATC is controlling Ar

SG level

NUREG-1 021, Draft Revision 9

Page 7 of 17

Bp-Test No.:

Event Description:

Scenario No.: 1

Event No.: 6

Page 1 of 1

BQTH MDEFDWPs Auto-start circuitry inoperable: (C, ALL) (TS)

Time -

Position

Applicants Actions or Behavior

Note: When directed by the lead examiner, call the CR and inform

them that that !&E has determined that the Auto-start circuitry for the

BQTH MDEFDWPs are out of tolerance and technically inoperable.

Parts required for the repair are not expected for 3 days.

Crew response:

The SWO should refer to TS 3.3.14 (Emergency Feedwater Pump

Initiation Circuitry) Condition B and determine that the A

MDEFDWP is inoperable.

Determine TS 3.7.5 (EFW System) Condition C requires restoring

one MDEFDWP pump in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be MODE 3 in an additional 12

hours.

SRQ should determine that at unit shutdown is required and direct unit

shutdown per OPII/NI 18Y804 (Operation At Power) Encl. 3.2, Power

Reduction.

Event is complete when the decision to shutdown has been made or

when directed by the Lead Examiner.

NUREG-1021, Draft Revision 9

Page 8 sf 17

9

Scenario No.: 1

Event No.: 9

Page 1 of 1

Manual unit shutdown: (a, OATC)

Event Description:

Position

O A K

Amkcants Actions or Behavior

Crew response:

Direct unit shutdown per OP/f/A/1 1021004 (Operation At Power) Encl. 3.2,

Power Reduction.

1. Review Limits and Precautions

2. Notify OSM to contact NRC if required.

3. Refer to OW1 106/001 (Turbine Generator) to ensure operating limits

are NOT exceeded during shutdown.

4. Notify System Operations Center (SOCJ or lead reduction.

Note: Due to procedure complete wp to Step 2.17 the crew may not

perform steps 1-4 above.

5. Reduce reactor power in manual by inserting control rods with the

Diamond and controlling FDW flow with the FDW Masters.

6. Stop D HDPs per OP/I/A/1106/002 B (HDP Operation)

Event is complete when reactor power has been reduced 5% or when

directed by the Lead Examiner.

NUREG-1021. Draft Revision 9

Page 9 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 8

Page 1 of 1

Event Description:

I1

Position

OATC

Reactor trip, Main Turbine Fails to trip (Lockout EHC Pumps) (C,

OATC)

~

Applicants Actions or Behavior

Note: The reactor will trip as a result of initiating event 9 (SBLOCA).

Plant response:

Statalarms:

0

Control board indications:

o

1 SA-9/.4-6, RB Reactor Bldg Norm Sump bevel Hlghlkow

1 SA-WB-9, Process Monitor Radiation High

PZR level and RCS pressure will decrease

The reactor will trip OR low RCS pressure.

The Main Turbine should trip but dues not. This will result in a

reduction of steam pressure in both SGs until actions are taken to

trip the turbine. The will result in WCS overcooling until the turbine is

tripped.

Crew response:

1. SRO will direct the OATC to perform IMAs and the BOP to perform a

symptom check and then enter the EOP.

2. O A K will perform Immediate Manual Actions

0

Depress REACTOR TRIP pushbutton

0

Depress turbine TRIP pushbutton.

0

Verify reactor power < 5% FP and decreasing

Verify all turbine stop valves closed

bock out both EHC pumps (CT-18)

Note: The OATC should diagnose that the turbine did not trip and

then perform the R H 8 step which will stop and lock out both EHC

pumps. This will cause the turbine to trip.

Verify RGP seal injection available.

3. BOP will perform a symptom check.

Event is complete when EHC pumps have been tripped or when

directed by the lead examiner.

NUREG-1 021, Draft Revision 3

Page IO of 19

Op-Test No.:

Event Description:

Scenario No.: I

Small Break LOCA: (M, ALL)

Event No.: 9

Page 1 of 5

Time

Position

OATC

Applicants Actions or 5ehavior

Plant response:

Control board indications:

0

ES 1-6 actuate

RCS subcooling margin will indicate 8°F.

Crew response:

1. The OAPC should verify lMAs complete with the SRO and then &e

SRO should direct the OATC to perform a symptom check.

2. The BOP should report symptoms and inform the SWO that the RCS

has saturated and obtain SRO concurrence to perQorrn Rule 2, boss ob

SCM.

o

0

o

0

o

Verify that reactor power is e 1%.

Trip WCPs within 2 min of LOSCM (CT-1)

Notify SRO of RCB status.

Verify 1HP-24/25 (IN1 B BWST Suction) open

Ensure all available HPI pumps operating.

Note: I C HPI pump will not be operating and an attempt should be

made to manually start the 1C HPI pump.

Ensure 1HP-26/27 (IN18 HP Injection) open

Determine HPI flow in the B header is in the unacceptable region ob

Figure 1 and open I HP-409 (1 HP-27 Bypass). (CT-2)

Verify that bPI flow in any header is e 1 OOO gpm.

Verify that TBVs are available.

Disable AFlS in non-actuated channels.

Establish EFDW to the BTSGs to feed to LOSCM setpoint per Rule

7 (SG Feed Control). (CT-10)

Verify both MDEFDWPs operating. (1B MDEFDWP is off)

Ensure TBEFBWP is in PULL TO LOCK. (Not performed due

16 MDEFDWP not operating)

Trip both MFDWPs and close the FDW block valves.

Notify SRO of SG feed status.

Maintain SG pressure e RCS pressure.

Ensure Rules 3 & 8 in progress or complete.

NUWEG-1026, Draft Revision 9

Page 1 1 of 17

Sp-Test No.:

Scenario No.: 1

Event No.: 9

Page 2 OB 5

Event Description:

Small Break LOCA (M, ALL)

Time

__a_.

Position

SRQ

QATC

Applicants Actions or Behavior

3. When reporting symptoms, the BATC should inform the SRO that ES

Channels 1-6 have actuated. The SRO should initiate EOP Encl. 5.1, ES

Actuation per the parallel actions page of Subsequent Actions section or

of the LOSCM Tab. When running Encl. 5.1

I the operator will:

o

Determine which ES channels should have actuated and verify all

Blue Lights and White Lights are lighted for the appropriate

channels.

Note: A RBCU will not receive an ES signal and will remain In HIGH

speed. The operator should diagnose this and place the A RBCU in

LOW speed.

Place HPP in Manual.

Verify any RCP operating. (No RCPs operating)

Verify SCMs > 0°F and proceed to the HPB flow check when he

determines that the RCS has saturated.

The operator should determine HP! flow is adequate per Figure 1.

a

e

Note: 1 HP-409 should have been opened by Rule 2.

Open IBS-1 and 1BS-2

Place LPB pumps in manual control.

At SWO direction secure LPI pumps.

Ensure A and B and 3A and 3B Outside Air Booster Fans are

operating. (CT-27)

IAAT ES Channels 5 & 6 have actuated,

THEN dispatch an operator to establish = 1000 cfm flow in each

PWVS filter train using 1 BW-13 and 1 PW-17 (Controller, Filter

Ensure the following are open:

1 CC-7 and 1 CC-8

1 LPSW-6 and 1 LPSW-15

Ensure open 1CF-1 and 1CF-2 ( N B C f T Outlet)

Verify 1 HP-410 closed.

Dispatch an operator lo perform Encl. 5.2 (Placing RB Hydrogen

Analyzers In Service)

Notify Chemistry to prepare for caustic addition.

The operator must get SRO approval to exit this enclosure.

I N 1 B)

NUWEG-1021, Draft Revision 9

Page 12 of 17

--

Bp-Test No.:

Event Description:

Time

Position

Scenario No.: 1

Small Break LQCA: (M,

ALL)

Event No.: 9

Page 3 of 5

Applicant's Actions or Behavior

4. The SWO should GO TO the LOSCM Tab per the Parallel Actions page

of the EOP Subsequent Actions section. LOSCM Tab will:

e Ensure that Rule 2 is in progress or complete.

Verify that station ASW is not feeding any SG.

Verify that the LOSCM is not caused by excessive heat transfer.

Open 1 AS-40 while closing 1 MS-47.

Verify all the following conditions exist:

"r NO WCPs are operating

"r HPI flow exists in both HPI headers

"r Adequate Total HPI flow per figure 1 (Total Required HPl Flow)

Control steaming and feed rates on all intact SGs to maintain

csoldown rate within Tech Spec limits:

k Tc 2 280°F

5 5 0 W ?h hour

o

0

GO TO Step 75.

Close 1 RC-4 (POW Block)

o

Close the following: (CT-3)

k 1HP-1 ( I A Letdown Cooler inlet)

L 1 HP-2 (1 B Letdown Cooler Inlet)

k 1 RC-3 (Spray Block)

F tGWD-17 (PZR Vent Control)

Note: RCS leak will be isolated when 1 RC-3 is closed.

o

0

Maintain SG pressure .s RCS pressure.

Uerify primary to secondary heat transfer exists.

initiate Encl. 5.16 (SG Tube-to-Shell AT Control)

Verify NO indications of an SGTW.

Verify HPI forced cooling NOT in progress.

Verify CETCs NOT increasing.

Verify primary to secondary heat transfer is NOT excessive.

Verify NO indications of SGTR.

Verify required RCS makeup flow within normal makeup capability.

'r RNO Transfer to LOCA CD tab.

NUREG-1021, Draft Revision 9

Page I3 of 17

Scenario No.: 1

Event No.: 9

1 Event Description:

Small Break LOCA: (M, ALL)

Position

SRQ

Page 4 of 5

Applicants Actions or Behavior

5. GO TO LOCA CD tab.

0

IAAT BWST level 5 19 feet transfer ECCS suctions to the RBES.

Verify ES is actuated.

Ensure ali RBCUs in low speed and opera 1LPSW-18, 1bPSW-21,

1 LPSW-24, and 1 LPSW-565 closed.

Initiate Encl. 5.35, Containment Isolation

Ensure all RB Aux fans are operating

initiate Encl. 5.36 (Equipment Alignment For Phnt Shutdown)

IAAT all of the following conditions exist: (Step 33)

> ALL SCMs 5 0°F:

i RCS pressure v LPI shutoff head

b Required HPI within normal makeup capability

o

0

Note: If step 33 met then go to Event 10.

0

If step 33 NOT met crew will GO TO Step 37 and continue in

LOGA CooEdown tab.

IAAT all of the following conditions exist: (Step 37)

b ALL SCMs > 8°F

2. ES Bypass Permit satisfied

2. RCS pressure controllable

THEN bypass ES as necessary

Disable all AFIS headers NOT actuated by selecting OFF on both

Digital Channels 1 &2 on that header.

0

NlBREG-1(321, Draft Revision 9

Page 14 of 17

Op-Test NO.:

Scenario No.: 1

Event No.: 9

Page 5 of 5

Event Description:

Position

Small Break LOCA: (M, ALL)

Applicants Actions or Behavior

IAAV a sustained re-pressurization of the RCS occurs due to any

of the following:

P Leak isolation

>. Degraded heat transfer due to hot leg voiding

THEM perform Steps 42-48.

Verify at least one SG available.

Verify any bop e 539. (both should be above)

Cycle PORV to maintain RCS pressure.

Ensure appropriate level and feed flow is available to SGs per

RULE 7 (SG Feed Control)

Notify PSC to evaluate starting or bumping WCPs.

Notify Chemistry to sample RCS boron hourly until MODE 5.

Event is complete when RCS SCM is greater than 0°F or when

directed by the Lead Examiner.

NUREG-10211, Draft Revision 9

Page 15 of 17

Op-Best No.:

Scenario No.: 1

Event No.: 18

Page 1 of 1

Event Description:

Position

RCS leak isolated, SCM increases > 0°F

Applicants Actions or Behavior

Plant response:

e

SCM increases > 0°F

0

PZR level increasing

Crew response:

1. Throttle HPB per RULE 6 (HPI) (CT-20)

HPI Forced Cooling not in progress

RX power 5 1 % and Core SCM > 0

0

Note: If SCM increases > 0°F prior to reaching the following lAAT

step the SRO may elect to transfer to Subsequent Actions based on

plant conditions changing.

2. IAAT all of the following conditions exists:

ALL SCMs > 8°F

e

RCS pressure > LPI shutoff head

Required HPl within normal makeup capability

3. Verify primary to secondary heat transfer

4. Verity NO indications of SGTW

5. GO TO Subsequent Actions

Event and exam is complete when the SRO has transferred to

Subsequent Actions or when directed by the Lead Examiner.

NUREG-1025, Draft Revision 9

Page 16 of 17

CRITICAL TASKS

1. CT-1, Trig, All RCPS

2. CT-2, Initiate HPI

3. CT-3, Isolate Possible WCS Leak Paths

4. CT-18, Establish FW Flow and Feed SGs

5. CT-18, Turbine Trip

6. CT-20, WCS Pressure Control To Prevent Exceeding WV P-T Limits And Comply With

PPS Guidance

7. CT-27, Implementation OB Control Room Habitability Guidance

NUREG-1021, Draft Revision 9

Page 17 of 17

_.

-~

Appendix D

Scenario Outline

Form ES-8)-1

Facility: Oconee

Scenario No.: SPARE fnl

Qp-Test No.: -

Examiners:

Operators: Tracey Roland (SRO-U)

Kevin Cooley (RQ)

Initial Conditions:

o

100% Reactor Power, (SNAP 202)

Turnover:

0

AMSACIDSS bypassed for I&E testing

o

LDST pressure is LOW

0

Unit 1 TDEFDWP has been out of service for bearing replacement for about 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

Expect it to be returned to sewice within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Event

Description

PBEWP fails to start

1A CC Pump trips (1B CC Pump fails to auto

II

4

I MPS110

I C. BOP. SRB

I 1HP-5 (Letdown Isolation) Fails closed

1 D1 Heater Drain Pump oil leak

LQSS of Main Feedwater

......

....... .-

.......

..

1- ........ I

.... .- ....... .....-........ A

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

(Njcrma!, (R)eact:vity, (i)nst!umsrit,

(C)ompone?t, (M)ajor

NUWEG-1021~ Draft Revision 9

Page 1 of 16

Form ES-D-2

Appendix D

Operator Actions

-

Qp-Pest No.:

Scenario No.: SPARE

Event No.: 1

Position

Event Description:

(I

OATC

QATC

Pressurize the LDST with H2: (N, BOP)

Page I of 1

Applicants Actions or Behavior

Plant response:

0

1 SA-WD-2 (Approaching bDST Operating Limits) is in alarm

crew response:

1. Refer to AFG

Add hydrogen to establish desired LDST pressure per

OPIl/A/ll Q6/017 (Hydrogen System)

Refer to bBST Pressure vs. bevel enclosure in

OP/Q/A/1108/001 (Curves and General Information.

e

2. Direct the OATC to use OP/I/A/1106/817 (Hydrogen System) Encl.

3.5 (Unit 1 LDST H2 Addition) to add H2 to the LDST.

0

Review Limits and Precautions

Immediately prior to pressurization determine lowest reading of

diverse LDST level indications:

inches.

For existing LBST level determine LDST Pressure allowable

per LDST Pressure vs. Level curve:

psig.

Notify Operator at H2 Cage to pressurize primary hydrogen.

NOTE: Operator s t ~ ~ t c i

be in constant communication with CR to

close 1 H-26 if 1 H-1 fails open.

Direct Operator to open 1 H-26 (LDST Block).

Cycle 1 H-1 fbDST SUPPLY) as required to Pressurize LDST

per LDST Pressure vs bevel curve.

WHEN complete, ensure closed 1 H-1 (LDST SUPPLY).

Note: 1H-1 (LDST SUPPLY) will fail open.

When 1H-1 (LDST SUPPLY) is opened or when directed by the

lead examiner this event is complete.

NUREG-1621

I Draft Revision 9

Page 2 of 16

Op-Test No.:

Event Description:

Time

Position

O A K

Scenario No.: SPARE

Event No.: 2

Page 1 of 1

1 H-t fails OPEN: (C, BOP) (TS)

Applicants Actions or Behavior

Plant response:

1 H-1 (LDSP SUPPLY) will indicate open

LBST pressure will continue to increase

0

Crew Response:

Monitor LDST Pressure and 1 H-3 (LDST SUPPLY) indication

and determine that 1 H-1 (LDST SUPPLY) has failed open.

Direct Operator to close 1 H-26 (LDSP Block).

Ensure LDST pressure within LDST Pressure vs. Level curwe.

0

Note: LDST pressure will NOT be within the LDST Pressure vs.

Level curve.

Refer to ARG for ISA-OZYD-2 (Approaching LDST Operating

Limits) actuates.

Determine that LDST pressure is not within LBST Pressure vs.

Level cuwe and declare BOTH trains of HPI inoperable. Direct

the OATC to take actions to reduce LDST pressure to within

the proper operating region of the LDST Pressure vs. Level

curve.

Vent LDST to GWD per OP/1/A/1104/002 (HPI System).

0

Note: The crew will not have time to vent the LDSP.

SWO should refer to TS 3.5.2 (HPI) and determine that

Condition H is met. The required action is to enter LCO 3.0.3

immediately.

When the SRO has declared BOTH trains of HPI inoperable or

when directed by the lead examiner this event is complete.

NUREG-1 821, Draft Revision 9

Page 3 af 16

3p-$est No.:

Scenario No.: SPARE

Event No.: 3

Page 1 of 1

!vent Description:

Time

Position

OATC

OATC

1A CC Pump trips: (C, OATC)

Applicant's Actions or Behavior

Plant response:

1. Statalarms:

1 SA-S/B-I, CC CRD RETURN FLOW LOW

1 SA-S/C-l, CC COMP COOLING RETURN FLOW LOW

0

1 SA-2/C-1 LETDOWN TEMPERATURE HIGH

2. Control Board indications:

m

1 HP-5 (Letdown Isolation) will close due lo high letdown

temperature

Crew Response:

1. Refer to ARGs

2. Initiate AP/020 (boss of Component Cooling)

0

IAAV both ob the following are lost:

i. CCtoRCPs

k RCP seal injection

THEN perform the following:

i. Trip RX

> Stop all RCPs

P initiate AQ/25 (SSF EOP)

IAAT 2 two CRD stator temperatures 2 48O"F,

THEN trip RX.

0

Open 1 CC-7 and 1 CC-8

o

3. Verify CC TOTAL FLOW > 575 gpm

4. Verify both of the following:

Letdown in service

LETDOWN TEMP I

130°F

5. Step not met. Perform WNO, Initiate AQ/032 (Loss of Letdown)

This event is complete when the Standby CC pump is started or

when directed by the lead examiner.

Verify CC Surge Tank level b 12".

Manualty start the Standby CC Pump

NUREG-1 021, Draft Revision 9

Page 4 of 16

_______I___._

_

I

~

__________-

I

Form ES-D-1

____I___-

___.-._________

Appendix D

Scenario Outline

Facility: Osonee

Scenario No.: 1 fnl

Bp-Test No.:

Examiners:

Operators: Tracey Roland (SRO-U)

Kevin Cooley (RO)

Initial Conditions:

50% Reactor Power, (Snap 201)

RCS Boron 100 gpm

QP/I/Ni fQZ3'804 (OPS At Power) End. 3.2 in progress at step 2.17. Holding per

dispatcher request.

SASS is De-energized for I&E troubleshooting

15 MDEFDW Pump OOS for PMs, expected to be returned to service later this shift.

'i. TS 3.7.5 Condition A

After turnover, perform the Unit 1 portion of PT/Q/N0610/017 (Operability Test of 41 60 V

Breakers)

Turnover:

~

1

0

1

Event

Descriation

!

Pre-Insert

MP1290

I Block AI^ Turbine Trips Except Manual

_-

' HPI pump fails to start

NUREG-1821, Draft Revision 9

Page 1 of 17

_ I _

(N)aamaB,

(W)eactivity, (I)nstrument, (@)omponent, (M)aJQa

NUREG-1021, Draft Revision 9

Page 2 of I?

Appendix D

Operator Actions

Form ES-DP

Bp-Test No.:

Event Description:

Position

OATC

Scenario No.: 1

Event NQ.: 1

Page 1 of 1

Operability test of 41 6OV breakers: (N, BOP)

Applicant's Actions or Behavior

Crew response:

The OATC should perform Step 12.1 of PT/O~NBGl8/017' (Operability Test

of 41 60 V Breakers).

e Place Unit 1 MFB1 AUTB/MAN transfer switch to "MAN".

k 1SA-I4/5-1 (EL Normal to SU Transfer Bus 1 AUtQmatiC

Transfer Block) actuates

Close El1 MFBI STARTUP FDR.

"r lSA-14/A-l (EL 1T Normal Supply Breaker Bus 1 Open)

actuates

k 1 SA-1 4/A-3 (EL CT1 4KV SU Feeder Bus 1 Closed) actuates

Verify Nt , MFBl NORMAL FDR opens, and electrical auxiliaries

transfer.

o

0

Close Ndl MFBI NORMAL FBR.

Verify El, MFBl STARTUP FBR breaker opens and electrical

auxiliaries transfer.

Place Unit I MFBf AUTO/MAN transfer switch to "AUTO".

Place Unit 1 MFB2 AUTO/MAN transfer switch to "MAN".

"r lSA-14/B-2 (EL Normal to SU Transfer Bus 2 Automatic

Transfer Block) actuates

0

Close E21 MFB2 STARTUP FDR.

k 1 SA-1 4/A-2 (EL 18 Normal Supply Breaker Bus 2 Open)

actuates

"r 1 SA-I 4A-4 (EL CTl 4KV SU Feeder Bus 2 Closed) actuates

Verify N21 MFB2 NORMAL. FDW breaker opens and electrical

auxiliaries transfer.

a

Close N21 MFB2 NORMAL FDR.

Verify E2? MFB2 STARTUP FDR breaker opens and electrical

auxiliaries transfer.

Place Unit 1 MFB2 AUTB/MAN transfer switch to "AUTO.

0

When Step 12.1 is complete or when directed by the Lead Examiner

this event is completed.

NUREG-1021, Draft Revision 9

Page 3 ob 17

Qp-Test No.:

Scenario No.: 1

Event No.: 2

Event Description:

Time

Position

Page 1 of 1

PZR bevel ## 1 Fails LOW: (I, BOP)

Amlicants Actions or Behavior

Pfant response:

Statalarms

b

1SA-UC-3, RC Pressurizer Level HigWLow

1SA-UC-4, RC Pressurizer Level Emerg High/bow

Front board (1 UBI) indications:

b

PZW Level I indicates 0

I HP-120 (RC Volume Control) throttles open

b

Makeup flow increases to = 160 gpm.

Crew response:

Refer to ARG

P Check alternate PZR level indications (1 UBI and OWC) and

determine that PZW level 1 has Bailed low.

P Check for proper MakeupiLetdown flows and adjust to restore

proper level.

i. Select an alternate PZR level channel ow 1 UBl .

SRO should direct the OATC to take actions to restore normal PZR

level.

SRO should direct the OATC to refer to PV/600/001 (Periodic

instrument Surveillance) SASS Manual Operation and have the OATC

select an alternate PZR level channel on 1 UBI.

SWO should refer to TS 3.3.8 (PAM Instrumentation) Table 3.3.8-1.

P TWQ PPR level channels are required. No action required.

When an alternate PZR level channel has been selected and PZR

level is stable or when directed by the lead evaluator this event is

completed.

NUREG-1021, Draft Revision 9

Page 4 of 17

. . . . . .

=

Op-Test No.:

Scenario No.: 1

Event No.: 3

Page I of 1

Event Description:

Position

OATC

SRQ

O A K

A LPSW pump suction valve closes and standby pump does not

Applicants Actions or Behavior

Plant response:

Statalarms:

0

1 SA-9/A-9, LPSN Header NE3 Press Low

Control board indications:

e LPSW-2 (A LPSW Pump Suction) indicates closed (also an QAC

alarm)

e A LPSW pump amps are cycling

LPSW Header N B Pressure Low

Crew response:

1. Refer to ARG for 1 SA-918-9, LPSW Header AIB Press Low

2. Refer to AP/24 (Loss of LPSW)

e Ensure LPSW pump suction valves are open.

Note: LPSW-2 (A LPSW pump suction valve) will indicate closed. The

team may dispatch an NE0 to open LPSW-2. The valve will not be able

to be opened locally.

a

Verify LPSW pumps are cavitating

2. Pump amps erratic

i LPSW header pressure fluctuating

Ensure the Unit 1/2 STANDBY LPSW PUMP AUTO START

68WC181T is DISABLED.

Stop the affected pump. Stop A LPSW pump.

Ensure all available (NOT previously cavitating) LPSW pumps

operating. Start C LPSW pump.

Verify normal LPSW System operation is restored.

The SRO should call SPOC to troubieshsot the reason for the

suction valve closing, the Auto Start failure and determine if the A

LPSW pump was damaged due ioss of suction.

e

The SRO should refer to TS:

k TS 3.7.7 (Low Pressure Service Water System) Condition A

applies. Restore required LPSW pump to operable status. 72

hours completion time.

k TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition A.

Restore Auto-Start Circuitry to operable. 7 day completion time.

e

Note: TS 3.3.28 may be addressed as a follow up question.

Event is complete when SRO has referred to TS 3.7.7 or when

directed by the Lead Examiner. (BOP and OATC Swap positions)

NUREG-1021, Draft Revision 9

Page 5 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 4

Page 1 of 1

Event Description:

I

RC Loop B Flow fails LOW: (I, OATC)

H

Position

OATC

SRQ

Applicants Actions or Behavior

Plant response:

1. Statalarms:

0

1 SA-2/A-4, RC LOOP B Flow LOW

e

1 SA-YA-5, RC Total Flow Low

1 SA-l/A-l, RQ Channel A Trip

iSA-l/A-3, RP Channel A FluxllrnbiFlow Trip

2. Control board indications:

e

RPS Channel A trips.

e

RCS Flaw meter shows Loop B flow at zero.

B S/G FBW Flow instrument shows a reduction in FDW, and the A

S/G FDW Flow indicates increasing flow or off-scale High.

DELTA Tc meter indicates a large Delta Temp.

Crew response:

e

The crew should stabilize the unit by using the Plant Transient

Response process.

Take the Diamond and BOTH FDW Masters to MANUAL and stabilize

the unit.

The SRO should refer to AP/28, ICs Instrument Failures and notify

SPQC to have the instrument repaired.

AP/28, ICs Instrument Failures wik

e

> Ensure DIAMOND and BOTH FDW Masters in MANUAL.

lj Notify SPQC to select a valid RCS flow input to BCS and

investigate and repair the failed WCS flow instrumentation.

i Ensure any associated requirements of PT/4/A/Q6OQ/QOI

(Periodic instrument Surveillance) are met for the failed

instrument.

2. WHEN notified by SPQC that a valid RCS flow input has been

restored to ICs, THEN GO TO Encl 5.1 (Placing ICS in AUTO).

Note: Crew may refer to PT/600/001 (Periodic Instrument

Surveillance) and TS 3.3.1 (RPS Instrumentation) due to A RPS

Channel trip and may choose to place A*

RPS to manual Bypass.

Event is complete when the SRO has reached the WHEN step in

APE8 or when directed by the Lead Examiner.

NUREG-1021, Draft Revision 9

Page 6 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 5

Page 1 ot 1

Event Description:

Time

Position

O A K

A

SG Startup Level Fails LOW (I, OATC)

Applicants Actions OF Behavior

If the reactor trips on event 4, activate timer to insert A SG Startup

Level failure.

Plant response:

Statalarms:

0

1 SA-2iE-8, M S Stm. Gen A Level Low Limit

Control board indications:

0

A SG Startup Level indicates 0 on the control board and the QAC.

A SG XSUR Level indication will indicate greater than 25.

A

SG Main and Startup Control valves will be open even though

the SG level will be above setpoint.

A SG level will continue to increase. XSUW indication should be

used to determine SG level.

0

Crew response:

The QAPC should diagnose the failure of the A

SG Startup bevel

instruments and inform the SRO.

The SRO should direct the 80 to take the A SG Main and Startup

Control valves to manual.

The SRQ should direct the RQ to close the A SG Main Control valve

and use the A SG Startup Control valve to control A SG level at 25

XSUW.

The SWO should notify SPOC to have the instruments repaired.

Event is complete when the OATC is controlling A

SG level

manually or when directed by the Lead Examiner.

NUREG-1025, Draft Revision 9

Page 7 of 17

..

Scenario No.: 1

Event No.: 6

Page 1 of 1

Event Description:

BOTH MDEFDWPs Auto-start circuitry inoperable: (C, ALL) (TS)

Time

-

Position

Applicants Actions or Behavior

Note: When directed by the Dead examiner, call the CR and inform

them that that I& has determined that the Auto-start circuitry for the

BQTH MDEFDWPs are out of tolerance and technically inoperable.

ParZs required for the repair are not expected for 3 days.

Crew response:

The SRO should refer to TS 3.3.14 (Emergency Feedwater Pump

initiation Circuitry) Condition W and determine that the A

MDEFDWP is inoperable.

Determine TS 3.7.5 (EFW System) Condition 6 requires restoring

one MBEFDWP pump in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be MODE 3 in an additional 12

hours.

SRO should determine that at unit shutdown is required and direct unit

shutdown per OP/l/N1102/854

(Operation At Power) End. 3.2, Power

Reduction.

Event is complete when the decision to shutdown has been made or

when directed by the Lead Examiner.

NUREG-1021, Draft Revision 9

Page 8 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 7

Event Description:

Manual unit shutdown: (R, OATC)

Time

Position

OATC

Page 1 of 1

Applicants Actions or Behavior

Crew response:

Direct unit shutdown per OPll/A/l102/004

{Operation At Power) End. 3.2,

Bower Reduction.

1. Review Limits and Precautions

2. Notify OSM to contact NRC if required.

3. Refer to OP/1106/081 (Turbine Generator) to ensure operating limits

are NOT exceeded during shutdown.

4. Notify System Operations Center (SOC) or lead reduction.

Note: Due to procedure complete up to Step 2.17 the crew may not

perform steps 1-4 above.

5. Reduce reactor power in manual by inserting control rods with the

Diamond and controlling FDW flow with the FDW Masters.

6. Stop D HDPs per OP/I/A/f 106/002 D (HDP Operation)

Event is complete when reactor power has been reduced 5% or when

directed by the Lead Examiner.

NUREG-1021, Draft Revision 9

Page 9 of 17

Op-Test NO.:

Event Description:

Position

sa0

QATC

Scenario No.: 1

Event No.: 8

Page I of 1

Reactor trip, Main Turbine Fails to trip (Lockout EHC Pumps) (C,

OATC)

Applicants Actions or Behavior

Note: The reactor will trip as a result of initiating event 9 (SBLOCA).

Plant response:

Statalarms:

-

a

Control board indications:

o

ISA-9/A-6, RB Reactor Bldg Norm Sump Level WigWLsw

1 SA-WB-9, Process Monitor Radiation High

PZW level and RCS pressure will decrease

The reactor will trip on low RCS pressure.

The Main Turbine should trip but does not. This will result in a

reduction of steam pressure in both SGs until actions are taken to

trip the turbine. The will result in RCS overmooling until the turbine is

tripped.

Crew response:

1. SRO will direct the O A K to perform IMAs and the BOP lo perform a

symptom check and then enter the EOP.

2. OATC will perform Immediate Manual Actions

o

Depress REACTOR TRIP pushbuttori

0

Depress turbine TRIP pushbutton.

Verify reactor power < 5% FP and decreasing

Verify all turbine stop valves closed

Lock out both EWC pumps (CT-18)

Note: The OATC should diagnose that the turbine did not trip and

then perform the RNO step which will stop and lock out both EHC

pumps. This will cause the turbine to trip.

a

3. BOP will perform a symptom check.

Verify WCP seal injection available.

Event is complete when EHC pumps have been tripped or when

directed by the lead examiner.

NUWEG-1021, Draft Revision 9

Page 10 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 9

Event Description:

P

Time

Position

OATC

Small Break LOCA: (M, ALL)

Page 1 of 5

Applicants Actions or Behavior

Plant response:

Control board indications:

0

E§ 1-6 actuate

RCS subcooling margin will indicate 0°F.

Crew response:

1. The OATC should verify lMAs complete with the SRO and then the

SWO should direct the OATC to perform a symptom check.

2. The BOP should report symptoms and inform the SRO that the RCS

has saturated and obtain SRO concurrence to perform Rule 2, Loss of

SCM.

o

Verify that reactor power is e 1 %.

0

Trip WCPs within 2 min of LBSCM (CT-1)

o

Notify SRO of RCP status.

Verify 1 HP-24/25 (1 A/1 B BWST Suction) open

Ensure all available HPI pumps operating.

Note: I C HPI pump will not be operating and an attempt should be

made to manually start the 1C HPI pump.

Ensure IHP-2W27 (lA/lB HP Injection) open

Determine HPI flow in the B header is in the unacceptable region of

Figure 1 and open 1 HP-409 (1 HP-27 Bypass). (CT-2)

Verify that LPB flow in any header is e 1000 gpm.

Verify that TBVs are available.

Disable AFBS in non-actuated channels.

Establish EFDW to the OTSGs to feed to LQSCM setpoint per Rule

7 (SG Feed Control). (CT-10)

Verity both MDEFDWPs operating. (le MDEFDWP is off)

Ensure PDEFDWP is in PULL PO LOCK. (Not performed due

1 B MDEFDWP not operating)

Trip both MFDWPs and close the FDW block valves.

Notify SRO ob SG feed status.

Maintain SG pressure < RCS pressure.

Ensure Rules 3 & 8 in progress or complete.

Page 1 1 of 37

NUREG-3021, Draft Revision 9

Op-Test No.:

Event Description:

Time

Position

OATC

Scenario No.: 1

Event No.: 9

Page 2 of 5

Small Break LOCA: (M, ALL)

Amlicants Actions or Behavior

3. When reporting symptoms, the OATC should inform the SRO that E§

Channels 1-6 have actuated. The SRO should initiate EOP EncL 5.1, ES

Actuation per the parallel actions page of Subsequent Actions section or

of the LBSCM Tab. When running Encl. 5.1, the operator will:

E Determine which ES channels should have actuated and verify all

Blue Lights and White Lights are lighted for the appropriate

channels.

Note: A RBCU will not receive an ES signal and will remain in HIGH

sped. The operator should diagnose this and place the A RBCU in

LOW speed.

0

Place HPI in Manual.

o

E

Verify any RCP operating. (No RCBs operating)

Verify SCMs > 0°F and proceed to the HPI flow check when he

determines that the RCS has saturated.

The operator should determine #PI flow is adequate per Figure 1.

Note: 1HP-409 should have been opened by Rule 2.

Open 1 BS-1 and 1 BS-2

Place LPI pumps in manual control.

At SWO direction secure LPI pumps.

Ensure A and B and 3A and 3B Outside Air Booster Fans are

operating. (CT-27)

IAAT ES Channels 5 & 6 have actuated,

THEN dispatch an operat0r to establish = 1000 cfm flow in each

PRVS filter train using 1 PR-I3 and 1 PW-17 (Controller, Filter

lA/lB)

Ensure the foliowing are open:

1 CC-7 and 1 CC-8

1 LPSW-6 and 1 LPSW-15

Ensure open 1CF-1 and 1CF-2 (NB CW Outlet)

Verify 1HP-410 closed.

Dispatch an operator to perform End. 5.2 (Placing RB Hydrogen

Analyzers In Service)

Notify Chemistry to prepare for caustic addition.

The operator must get SWO approval to exit this enclosure.

NUREG-1021, Draft Revision 9

Page 12 of 17

Op-Test No.:

Scenario No.: 1

Event No.: 9

Page 3 of 5

Event Description:

Small Break LQCA (M, ALL)

Time

Position

Applicants Actions or Behavior

4. The SRO should GO TO the LOSCM Tab per the ParaBiel Actions page

of the EOP Subsequent Actions section. LOSCM Tab will:

Ensure that Rule 2 is in progress or complete.

Verify that station ASW is not deeding any SG.

Verify that the LOSCM is not caused by excessive heat transfer.

Open 1 AS-40 while closing 4 MS-47.

Verify all the following conditions exist:

k NO RCPs are operating

> HPL flow exists in both HPI headers

k Adequate Total HPI flow per figure 1 (Total Required HPI Flow)

Control steaming and feed rates on all intact SGs to maintain

cooldown rate within Tech Spec limits:

i. Tc 2 280°F

5 50W YZ hour

e

0

GO TO Step 70.

Close 1 RC-4 (POW Block)

Close the following: (CP-3)

k 1HP-I (1A Letdown Cooler Inlet)

k 1 HP-2 (1 3 Letdown Cooler inlet)

> 1 RC-3 (Spray Block)

2. 1GWD-17 (PZR Vent Control)

Note: RCS leak will be isolated when 1 RC-3 is closed.

Maintain SG pressure < RCS pressure.

Verify primary to secondaty heat transfer exists.

initiate Encl. 5.16 (SG Tube-to-Shell AT Control)

Verify NO indications of an SGTW.

Verify HPI forced cooling NOT in progress.

0

Verify CETCs NOT increasing.

D

Verify primary to secondary heat transfer is NOT excessive.

Verify NO indications of SGTW.

Verify required RCS makeup flow within normal makeup capability.

k RNO Transfer to LOCA CD tab.

NUREG-1021, Draft Revision 9

Page 13 of 57

Op-Test No.:

Scenario No.: 1

Event No.: 9

Page 4 of 5

Event Description:

Position

SWQ

Small Break LOCA: (M, ALL)

Applicants Actions or Behavior

5. GO TO LOCA CD tab.

e

e Verify ES is actuated.

IAAT BWSP level 5 19 feet transfer ECCS suctions to the R E S .

Ensure all RBCUs in low speed and open 1 LPSW-IS, 1LPSW-21,

1 LPSW-24, and 1 LPSW-56% closed.

Initiate EncI. 5.35, Containment Isolation

Ensure all WB Aux fans are operating

Initiate Encl. 5.36 (Equipment Alignment For Plant Shutdown)

IAAT all of the following conditions exist: (Step 33)

> ALL SCMs 2 0°F

b RCS pressure 2 LP! shutoff head

i. Required HPI within normal makeup capability

a

e

Note: If step 33 met then go to Event 10.

if step 33 NOT met crew will GO TO Step 37 and continue in

LQCA Cooldown tab.

IAAT all of the following conditions exist: (Step 37)

2. ALL SCMs > 8°F

L+ ES Bypass Permit satisfied

L+ RCS pressure controllable

THEN bypass ES as necessary

Disable all AFlS headers NOT actuated by selecting OFF on both

Digital Channels i&2 on that header.

e

0

NUREG-1 Q21, Draft Revision 9

Page 14 of 17

op-Test No.:

Event Description:

P

Time

P

Position

Scenario No.: 1

Small Break LQCA: (M,

ALL)

Event No.: 9

Page 5 of 5

Applicants Actions or Behavior

IAAT a sustained re-pressurization of the WCS occurs due to any

of the following:

k Leak isolation

k Degraded heat transfer due to hot leg voiding

THEN perform Steps 42-48.

Verify at least one SG available.

Verify any loop < 537. (both should be above)

Cycle POWV to maintain RCS pressure.

Ensure appropriate level and feed flow is available to SGs per

RULE 7 (SG Feed Control)

Notify TSC to evaluate starting or bumping WCPs.

Notify Chemistry to sample RCS boron hourly untiE MODE 5.

Event is complete when RCS SCM is greater than 0°F or when

directed by the Lead Examiner.

NUREG-1021, Draft Revision 9

Page 15 of 17

Op-Test No.:

Event Description:

Time

Position