ML081370200

educes reactor

ower in accordance with 3-GOI-100-12 and 3-01-6

[1] IF NOT in single loop operation, THEN

ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-

HS-96-15A(158)/LOWER SLOW(MEDIUM) 3-HS-96-17A(178), push-

buttons, to achieve balanced jet pump flows. AND/OR ADJUST

Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-

6A(16B) /LOWER SLOW(MEDIUM) 3-HS-96-18A(18B), pushbuttons, to

achieve balanced jet pump flows.

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the

RECIRC MASTER CONTROL, THEN

ADJUST Recirc Pump speed 3A & 38 using the following push

buttons as required:

RAISE SLOW, 3-HS-96-31

RAISE MEDIUM, 3-HS-96-32

LOWER SLOW, 3-HS-96-33

LOWER MEDIUM, 3-HS-96-34

LOWER FAST, 3-HS-96-35

Peer checks during power reduction

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Event 1b:

POSITION

VOLTAGE REGULATOR TO AUTOMATIC

EXPECTED ACTIONS

VERIFY VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, is in

MAN.

PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-

57-26, to RAISE UNTIL the upper limit is reached (red light

illuminated).

PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 32-HS-

57-26, to LOWER UNTIL the lower limit is reached (green light

illuminated).

ADJUST GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-

57-26, UNTIL GEN TRANSFER VOLTS, 2-EI-57-41, indicates zero.

PLACE VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, in

AUTO.

VERIFY GEN VOLT REGULATOR TRIP TO MAN,

3-EA-57-132 (3-XA-55-8A, window 3) alarms.

RESET GEN VOLT REGULATOR TRIP TO MAN,

3-EA-57-132 (3-XA-55-8A, window 3).

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Event 2:

POSITION

SPURIOUS START OF 3D CORE SPRAY PUMP

EXPECTED ACTIONS

Reports start of 3D Core Spray pump and verifies no valid

automatic start signal.

Directs trip of 3D Core Spray pump

Trips 3D Core Spray pump. Informs SRO that Lockout indicator

for 3D Core Spray Pump is illuminated indicating the pump will

not start automatically if needed.

Consults Tech Spec 3.5.1 determines that 3.5.1.A is a 7 day

Action Statement for 3D Core Spray pump and 3.5.1.D is a 72

hour Action Statement in effect with HPCI and one (1) Low

Pressure ECCSsystem inoperable.

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Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

Announces "Rod Drift" alarm 3-ARP-9-SA window 28

A. DETERMINE which rod is drifting from Full Core Display.

Identifies rod 26-27 as drifting in.

B. F rod driftin

in THEN REFER TO 3-AOI-85-5.

C. IF rod drifting out, THEN REFER TO 3-AOI-85-6.

D. REFER TO Tech Spec Section 3.1.3, 3.10.8.

Recognizes that Rod 26-27 stops moving at Notch 42.

irects actions

er 3-AOI-8S-5

Directs rod be continuously inserted to 00

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NA

Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

3-AOI-85

Immediate Actions

[1] IF multiple rods are drifting into core, THEN

MANUALLY SCRAM Reactor. REFER TO 3-AOI-100-1.

Subsequent Actions

[1] IF the Control Rod travels greater than two notches from its

intended position, THEN INSERT Control Rod to position 00 using

CONTINUOUS IN. (otherwise N/A)

[2] NOTIFY Reactor Engineer.

[3] CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).

[4] ADJUST control rod pattern as directed by Reactor Engineer

and CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).

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Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

[5] IF CRD Cooling Water Header DP is excessive and causing

the control rod drift, THEN ALTERNATELY ADJUST tape setpoint of

CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and position of CRD

DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A, to establish

the following conditions (otherwise N/A):

o CRD CLG WTR HDR DP, 3-PDI-85-18A, of about 20 psid, and

o CRD DRIVE WTR HDR DP, 3-PDI-85-17A, between 250 and 270 psid,

and

o CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, between 40 and 65

gpm.

Directs AUO to check the following per 3-AOI-85-5:

[6] VERIFY scram pilot air header aligned to scram inlet and

outlet valves.

[7] CHECK CRD SCRAM OUTLET VALVE, 3-FCV-085-39B, for

leakage as indicated by the following :

o Scram riser for affected HCU has higher than normal Temperature

o CRD SCRAM OUTLET VALVE , 3-FCV-085-39B, producing flow noise

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Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

[8] CHECK CRD SCRAM INLET VALVE , 3-FCV-085-39A, for

leakage as follows:

[8.1] CHECK insert riser for affected HCU for higher than

normal temperature.

Directs AUO to perform the following;

[8.2] CLOSE CHARGING WATER SOV, 3-SHV-085-588and

OBSERVE CRD ACCUMULATOR NITROGENSIDE

PRESS, 3-PI-085-034,for lowering trend.

Declares accumulator inoperable per Tech Spec 3.1.5.A and

addresses actions (when charging water is isolated)

EXAMINER NOTE: With charging water isolated to the HCU, the

control rod no longer satisfies the OPERABILITY requirement that

the control rod is capable of being scrammed even if the rod is fully

inserted.

After report from AUO thart scram inlet valve is leaking, Directs

scramming of affected rod from panel 9-16 in Aux.lnst. Room

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Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

[9] IF either Scram Inlet or Outlet Valve is found to be leaking,

THEN PERFORM the following to scram the control rod (otherwise

N/A):

[9.1] ESTABLISH communications between Control Room and the

folloWing locations:

o Hydraulic control unit affected, elevation 565, Reactor Building

o Panel 3-9-16 in Auxiliary Instrument Room, elevation 593, Control

Bay

[9.2] VERIFY CLOSED CHARGING WATER SOV, 3-SHV-085-588.

[9.3] INITIATE individual rod scram by actuating selected rod

scram switch on Panel 3-9-16 to its scram (DOWN) position.

[9.4] VERIFY control rod has reached FULL IN on Panel 3-9-5.

[9.5] IF attempting to reseat scram valves, THEN RETURN rod scram

switch for associated control rod to its normal (UP) position at

Panel 3-9-16,.

Have AUO check locally;

[9.6] CHECK solenoid operation of CRD SCRAM INLET and OUTLET

VALVEs 3-FCV-85-39A and 3-FCV-85-39B, (they should function

normally without chatter or abnormal buzzing.)

[9.7] CHECK stem travel indicators on CRD SCRAM INLET and OUTLET

VALVEs 3-FCV-85-39A and 3-FCV-85-39B. IF either scram valve

indicates OPEN, THEN NOTIFY control room.

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Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

[9.8] CHECK blue Scram indicator light on Full Core Display

extinguished.

[9.9] RESET Rod Drift Alarm and CHECK DRIFT indicator light on

Full Core Display extinguished. (N/A if rod is still drifting in)

[9.10] CHECK annunciator CONTROL ROD DRIFT (3-XA-55-5A,

Window 28) reset. (N/A if rod is still drifting in)

Have AUO perform the following;

[9.11] SLOWLY OPEN CHARGING WATER SOY, 3-SHV-085-588.

[9.12] CHECK amber ACCUM indicator light on Full Core Display

extinguished.

[9.13] CHECK red indicating light for associated HCU extinguished on

local Panel 3-28-4(3-25-22).

[9.14] NOTIFY Site Engineering.

[9.15] INITIATE a work order.

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Event 3:

POSITION

CONTROL ROD DRIFT IN

EXPECTED ACTIONS

[10] IF insert directional control valve is suspected of leaking, THEN

ATTEMPT to reseat valve as follows (otherwise N/A):

[10.1] INSERT control rod one notch.

[10.2] NOTIFY Site Engineering.

[10.3] INITIATE a work order.

[11] IF attempts to stop control rod drifting are unsuccessful, THEN

PERFORM the following (otherwise N/A):

[11.1] VERIFY control rod drive is at position 00 or "FULL IN".

[11.2] REMOVE associated HCU from service.

REFER TO 3-01-85 and Tech Spec 3.1.3.

Reports to SRO rod settles to 00 position

Initiates actions to determine CR operability and suggests actions

including maintenance and inspection.

De-selects and re-selects Rod 26-27to clear RBM DOWNSCALE 3-

ARP-9-5A (W 31).

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Event 4:

POSITION

ATC/BOP

RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS

EXPECTED ACTIONS

Recognizes B Recirculation pump trip

irects 3-AOI-68-1 ent

Contacts Rx Engr to place APRM's in SLO mode (If time permits)

[1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN

(Otherwise N/A),

A. SCRAM the Reactor.

[2] IF Region I or II of the Power to Flow Map (Illustration 1) is

entered, THEN (Otherwise N/A)

IMMEDIATELY take actions to INSERT control rods to less than

95.2% loadline. Refer to 0-TI-464, Reactivity Control Plan

Development and Implementation.

[3] RAISE core flow to greater than 45%. Refer to 3-01-68.

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Event 4:

POSITION

RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS

EXPECTED ACTIONS

[4] INSERT control rods to exit regions if not already exited. Refer

to 0-TI-464, Reactivity Control Plan Development and

Implementation.

Inserts rods on emergency shove sheet ~

[5] CLOSE tripped Recirc Pump discharge valve 3-FCV-68-79.

[6] MAINTAIN operating Recirc pump flow less than 46,600 gpm.

Refer to 3-01-68.

Verifies flow on A Recirc pump < 46,600 gpm

[7] [NERlC] WHEN plant conditions allow, THEN, (Otherwise N/A)

MAINTAIN operating jet pump loop flow greater than 41 x 106 Ibm/hr

(3-FI-68-46 or 3-FI-68-48). [GE SIL 517]

Verifies jet pump flow> 41,100 Ibm/hr

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Event 4:

POSITION

ATC/BOP

RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS

EXPECTED ACTIONS

[10] [NERlC] WHEN the Recirc Pump discharge valve has been

closed for at least five minutes (to prevent reverse rotation of the

pump) [GE SIL-517], THEN (N/A if Recirc Pump was isolated in

Step 4.2[8]) OPEN Recirc Pump discharge valve as necessary to

maintain Recirc Loop in thermal equilibrium.

Recognizes power oscillations

Notices failure to Scram~ or anticipates trip and

inserts a manual scram ~

Directs manual reactor scram ~

Inserts manual scram

Places Mode switch in shutdown

Recognizes hydraulic ATWS

Provides scram report

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Event 4:

TIME

POSITION

RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS

EXPECTED ACTIONS

nters EQI-1/C-5 and verifie

Verifies Mode switch to shutdown

ARI initiated

Directs ADS inhibited ~

Inhibits ADS ~

Contacts AUO to perform outside portions of App 1F & 2

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Event 4:

TIME

POSITION

RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS

EXPECTED ACTIONS

1. VERIFY at least one CRD pump in service.

2. IF ..... Reactor Scram or ARI CANNOT be reset,

THEN ..* DISPATCH personnel to CLOSE 3-SHV-085-o586,

CHARGING WATER SOV (RB NE, EI565 ft).

Dispatches AUO to close 3-SHV-85-586.

3. VERIFY REACTOR MODE SWITCH in SHUTDOWN.

4. BYPASS Rod Worth Minimizer.

5. REFER to Attachment 2 and INSERT control rods in the area of

highest power ~

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Event 5:

POSITION

Crew

ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN

EXPECTED ACTIONS

Recognizes 3A Recirc pump trip, if not tripped by ATC Operator

due to ATWS

Recognize and reports

"OG Pretreatment Radiation High"

"OG Annual Release Limit Exceeded"

"Turbine Building High Radiation"

Notifies RadCon, and Chemistry

Evacuates appropriate area of Turb. Bldg.

Directs RPV pressure be maintained 800-1000 psig

Controls RPV pressure between 800-1000 psig with SRVs

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(

Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

Directs Appendix 8A and 8E be performed

Reports SAE 1.2-5

1. PREVENT injection to RPV from the following systems in

any order as required:

a. HPCI

1) IF

HPCI Turbine is NOT at zero speed, THEN

PRESS and HOLD

3-HS-73-18A, HPCI TURBINE TRIP push-button.

2) WHEN ..*.HPCI Turbine is at zero speed, THEN ....PLACE 3-HS-73-

47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK

and

RELEASE 3-HS-73-18A, HPCI TURBINE TRIP push-button.

b. RCIC

1) IF

DIRECTED by SRO to allow RCIC injection, THEN

EXIT step

1.b.

2) PRESS 3-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC

Turbine.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

c. CORE SPRAY

NOTE: Following receipt of an automatic initiation signal, it is NOT

necessary to wait until the pump actually starts before performing the

next step.

Following an initiation signal, PLACE ALL Core Spray pump control

switches in STOP.

d. LPCI SYSTEM I

PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM I pump control

switches in STOP.

BEFORE RPV pressure drops below 450 psig,

1) VERIFY Appendix 16F has been performed, AND

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT

VALVE.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

e. LPCI SYSTEM II

PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM II pump control

switches in STOP.

BEFORE RPV pressure drops below 450 psig,

1) VERIFY Appendix 16G has been performed, AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT

VALVE.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

f. CONDENSATE and FEEDWATER

1) LOWER RFPT 3A(3B)(3C) speed to minimum setting

(approximately 600 rpm) using ANY of the following methods on Panel 3-9-

5:

Using 3-L1C-46-5, REACTOR WATER LEVEL CONTROL PDS, in

MANUAL AND individuaI3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED

CONTROL PDS in AUTO,

Using individuaI3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL

PDS in MANUAL,

Using individuaI3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT

RAISE/LOWER switch in MANUAL GOVERNOR.

2) CLOSE the following valves BEFORE RPV pressure drops below 450

psig:

3-FCV-3-19, RFP 3A DISCHARGE VALVE

3-FCV-3-12, RFP 3B DISCHARGE VALVE

3-FCV-3-5, RFP 3C DISCHARGE VALVE

3-LCV-3-53, RFW START-UP LEVEL CONTROL.

3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the

following push-buttons:

3-HS-3-125A, RFPT 3A TRIP

3-HS-3-151A, RFPT 3B TRIP

3-HS-3-176A, RFPT 3C TRIP.

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Event 5:

POSITION

Crew

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

Monitors suppression pool temperature

8A&8E

After Appendix 1F and 2 complete resets scram and drains SDV

~

1

2. WHEN ... RPS Logic has been defeated, THEN ..* RESET Reactor

Scram.

3. VERIFY OPEN Scram Discharge Volume vent and drain valves.

4. DRAIN SOV UNTIL the following annunciators clear on Panel 3-9-4:

o WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM

(3-XA-55-4A, Window 1)

o EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM

(3-XA-55-4A, Window 29).

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

Continues to insert control rods per Appendix1 D

Maintains water level as directed with RFP I RCIC

Maintains Pressure control using the following appendices:

11D Main Steam line Drains

11F RFPT

11ASRV's

2. VERIFY hotwel! pressure below -7 in. Hg.

3. CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS reset.

b. OPEN the following valves (Panel 3-9-3):

o 3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV

o 3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VLV

o 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER

4. THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO

CONDENSER, as necessary to control cooldown rate.

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Event 6:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN

EXPECTED ACTIONS

2. VERIFY MSIVs open.

3. VERIFY Hotwell Pressure at or below -7 in. Hg.

4. PLACE RFPTs in service as follows:

a. VERIFY the following:

1) At least one condensate pump running.

2) At least one condensate booster pump running.

3) Condensate System aligned to supply suction to RFPs.

b. VERIFY Main Oil Pump running for EACH RFPT to be started .

c. VERIFY CLOSED 3-FCV-3-19(12)(5), RFP 3A(3B)(3C)

DISCHARGE VALVE.

d. DEPRESS 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT

RAISE/LOWER, and VERIFY amber light is

illuminated.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN

EXPECTED ACTIONS

e. DEPRESS 3-HS-3-124A(150A)(175A), RFPT 3A(3B)(3C)

TRIP RESET.

f. PLACE 3-HS-46-112A(138A)(163A), RFPT 3A(3B)(3C)

START/LOCAL ENABLE, in START.

g. CHECK RFPT 3A(3B)(3C) speed increases to approximately 600 rpm.

h. VERIFY OPEN 3-FCV-3-20(13)(6), RFP 3A(3B)(3C) MIN

FLOW VALVE .

i. PLACE 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED

CONT RAISE/LOWER in RAISE to raise RFPT speed,

maintaining discharge pressure less than 1250 psig.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

A

11A1

2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE

MSRVs and CONTROL RPV pressure using other options.

3. OPEN MSRVs using the following sequence to control RPV

pressure as directed by SRO:

a.

1

3-PCV-1-179 MN STM LINE A RELIEF VALVE.

b.

2

3-PCV-1-180 MN STM LINE 0 RELIEF VALVE.

c.

3

3-PCV-1-4 MN STM LINE A RELIEF VALVE.

d.

4

3-PCV-1-31 MN STM LINE C RELIEF VALVE.

e.

5

3-PCV-1-23 MN STM LINE B RELIEF VALVE.

f.

6

3-PCV-1-42 MN STM LINE 0 RELIEF VALVE.

g.

7

3-PCV-1-30 MN STM LINE C RELIEF VALVE.

h.

8

3-PCV-1-19 MN STM LINE B RELIEF VALVE.

i.

9

3-PCV-1-5 MN STM LINE A RELIEF VALVE.

j.

10 3-PCV-1-41 MN STM LINE 0 RELIEF VALVE.

k.

11 3-PCV-1-22 MN STM LINE B RELIEF VALVE.

I.

12 3-PCV-1-18 MN STM LINE B RELIEF VALVE.

m.

13 3-PCV-1-34 MN STM LINE C RELIEF VALVE.

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(Critical Task)

Event 5:

POSITION

Crew

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

When alarms

WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM

(3-XA-55-4A, Window 1)

EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM

(3-XA-55-4A, Window 29).

Are clear, directs 3-85-586 re-opened and after accumulator alarms

are clear, Inserts manual scram

Recognizes some control rod movement, but all control rods not in

Directs reactor reset, drain SDV, and re-scram ~

Directs SLC injection if Torus temperature approaches 110 deg.

ntel'S EQI-2 on Torus wa er leyel

Directs placing H20 2 monitors in service

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV,

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

3. IF ... While executing this procedure to vent the Suppression Chamber,

Suppression Pool water level can not be determined to be below 20 ft, THEN

. PERFORM step 13 to secure the vent path and reenter this procedure if

further venting is required.

4. IF ... While executing this procedure, the desired vent path is lost or can

not be established, THEN . PERFORM step 13 to secure the vent path and

reenter this procedure if further venting is required.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4

OR G-9, is to begin, THEN. BEFORE CAD is initiated, PERFORM Step 13

to secure the vent path.

NOTE: Venting may be accomplished using EITHER:

o3-FIC-84-19, PATH B VENT FLOW CONT, OR

o3-FIC-84-20, PATH A VENT FLOW CONT.

NOTE: Unless the TSC recommends otherwise, venting the Drywell

DIRECTLY should be performed ONLY if the Suppression Chamber can

NOT be vented.

6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR

Suppression Chamber can NOT be vented , OR

SRO orders DIRECT drywell venting,

THEN CONTINUE in this procedure at:

Step 10 to vent the Drywell through 3-FCV-84-19, OR

Step 11 to vent the Drywell through 3-FCV-84-20.

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

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Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT

FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL

BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE

(Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with

setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN

(Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating

approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

HLTS-3-3

Revision 0

Page 40 of 49

XI.

Simulator Event Guide

(

Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

12. ADJUST 3-FIC-84-19, PATH 8 VENT FLOW CONT, or 3-FIC-84-20,

PATH A VENT FLOW CONT, as applicable, to maintain ALL of the

following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

i. IF. . .PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level

Control, is in progress THEN..MAINTAIN release rates below those

specified in Attachment 2.

ii. IF. . .Severe Accident Management Guidelines are being executed, THEN .

.MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF...Venting for ANY other reason than items i or ii above, THEN.

.MAINTAIN release rates below Stack release rate of 1.4 x 107 ~Ci/s

AND 0-S1-4.8.8.1.a.1 release fraction of 1.

Contacts LOG AUO to monitor release rates

(

XI.

HLTS-3-3

Revision 0

Page 41 of49

Simulator Event Guide

Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

Maintains water level as directed to control power

After SDV drained and after accumula~d,scrams

reactor again and verifies all rods in ~

Directs level be restored +2" to +51"

Directs SLC stopped (if injected)

(Critical Task)

Crew

Recognize RM-90-29A Rx Bldg High Radiation (conditional)

Evacuates Reactor Building

radiation and directs ventilation

(

XI.

HLTS-3-3

Revision 0

Page 42 of49

Simulator Event Guide

(

Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN

EXPECTED ACTIONS

1. VERIFY PCIS Reset.

2. PLACE Refuel Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS,

control switch is in OFF.

b. PLACE 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS,

control switch to SLOW A (SLOW B).

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-3A, REFUEL

ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH

A(B) red lights illuminate.

d. VERIFY OPEN the following dampers:

3-FC0-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR

3-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR

3-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR

3-FC0-64-10, REFUEL ZONE EXH INBD ISOL DMPR.

(

XI.

HLTS-3-3

Revision 0

Page 43 of 49

Simulator Event Guide

Event 5:

POSITION

ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN

EXPECTED ACTIONS

3. PLACE Reactor Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS,

control switch is in OFF.

b. PLACE 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS,

control switch in SLOW A ( SLOW B).

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-11A, REACTOR

ZONE FANS AND DAMPERS, control switch

extinguish and two SPLY/EXH A(B) red lights illuminate.

d. VERIFY OPEN the following dampers:

3-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR

3-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR

3-FC0-64-42, REACTOR ZONE EXH INBD ISOL DMPR

3-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMPR.

(

XI.

HLTS-3-3

Revision 0

Page 44 of 49

Simulator Event Guide

Event 5:

POSITION

ATC/BOP

ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN

EXPECTED ACTIONS

Announces MAIN STEAM LINE RADIATION HIGH-HIGH

Annunciator 3-ARP-9-3A window 27 (if received)

A. VERIFY alarm on 3-RM-90-136 thru 137 on Panel 3-9-10.

B. CONFIRM main steam line radiation level on recorder 3-RR-90-135,

Panel 3-9-2.

C. IF alarm is VALID and scram has NOT occurred, THEN PERFORM the

following:

IF core flow is above 60%, THEN

1. LOWER core flow to between 50-60%.

2. MANUALLY SCRAM the Reactor.

3. REFER TO 3-AOI-100-1.

D. IF plant conditions DO NOT require the execution of 3-C-5,

Power/Level Control, THEN VERIFY the MSIV's CLOSED.

E. NOTIFY RADCON.

(

XII.

Crew Critical Tasks (CCT)

1.

Manual scram due to Scram failure of OPRM Trip within one minute.

2.

Prevent ADS actuation.

3.

Controls power by :

Inserting control rods per RC/Q-21 .

Lowering reactor water level per EOI-C-5.

4.

Maintains RPV water level above -180" with rods out

HLTS-3-3

Revision 0

Page 45 of49

SAT/UNSAT

(

HLTS-3-3

Revision 0

Page 46 of 49

XIII.

Scenario Verification Data

EVENT

KIA Number

RO

1. Control Rod Drift

201002A2.02

3.2

3.3

2. APRM Failure

215005A2.03

3.6

3.7

2.1.12

2.9

4.0

3. Recirculation Pump Trip/Power Oscillations/ATWS

295001

3.3

3.4

295025

3.8

3.9

295037

3.9

4.0

(

SCENARIO REVIEW CHECKLIST

SCENARIO NUMBER HLTS-3-3

HLTS-3-3

Revision 0

Page 47 of 49

7

Total malfunctions Inserted; List:

1.

Recirc Trip

2.

Power Oscillations

3.

ATWS

4.

Fuel Failure

5.

Core Spray pump 3D trip

6.

Control Rod Drift

(4-8)

2

Malfunctions That Occur After EOI Entry; List: (1-4)

1)

ATWS

2)

Fuel Failure

2

Abnormal Events; List:

1)

Control Rod Drift

2)

Recirc Trip

Major Transients; List:

1)

ATWS

2)

Fuel Failure

(1-3)

(1-2)

3

EOls used; List:

1)

EOI-1

2)

EOI-2

3)

EOI-3

(1-3)

1

EOI Contingencies Used; List:

1)

C5

(0-3)

75

Run Time (minutes)

35

EOI Run Time (minutes);

50

% of Scenario EOI Run Time

(

4

Crew Critical Tasks

(2-5)

Yes

Technical Specifications Exercised (yes/no)

(

XV.

SHIFT TURNOVER INFORMATION

Equipment out of service/LCOs: HPCI tagged out for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months to repair Auxiliary Oil Pump. Expected

back in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Flow indicator 3-78B out of service, 1M's are looking for a new transm itter. Main

Generator voltage regulator in manual for PMs on Automatic voltage regulator. Spare RBCCW pump in

service to Unit 2.

Operation/Maintenance for the Shift: Reduce power to 95% with recirculation flow due to high river water

temperature. PMs on voltage regUlator complete, return voltage regulator to automatic.

Unusual Cond itions/Problem Areas:

_---!.,;N!..l::o~n~e

_

AppendixD

Scenario Outline

Form ES-D-l

(

Facility: BFN

Scenario Number: HLTS-3-4

Op-Test Number: HLT0610

Examiners:

Operators:

Initial Conditions:

The unit is starting up following a refuel outage. Reactor power is at - 9%. "An RFP is uncoupled for

performance of turbine overspeed testing. Currently at step 5.76.8 of3-GOI-IOO-IA.

Turnover:

The 3A RFP is uncoupled and the suction and discharge valves are tagged for performance of turbine

overspeed. Currently at step 5.76.8 of3-GOI-100-IA and at step 5.6 [18] 00-01-3 for warming 3B

RFP.

Event

Malfunction

Event

Number

Type*

Description

I

none

R-ATC

Crew will continue to pull rods to increase power and start

N-BOP

warming up 2B RFP

R-SRO

2

imf rdl4a

I-ATC

Crew will respond to a RWM failure.

I-SRO

SRO references Tech Specs.

TS-SRO

3

imfrdOla

C-ATC

Crew will respond to a trip of 3A CRD pump.

C-SRO

4

imfsw02a trip

C-BOP

Crew will respond to a RBCCW pump trip

7048FfC

C-SRO

Crew manually closes 70-48 after fails to auto close

5

ior zdihs468a

C-BOP

Crew will respond to feedwater controller malfunction which

imfth235

C-SRO

results in cold water irijection

6

imfth235

M

Crew responds to fuel failure after cold water injection

All

7

imf cu0425

M

Crew responds to a RWCU line break and scrams reactor

ior zdihs691

All

before any area reaches max safe value.

null

(N)ormal,

(R)eactivity, (I)nstrument,

(C)omponent, (M)ajor

Appendix D

Scenario Outline

Form ES-D-l

(

Facility: BFN

Scenario Number: HLTS-3-4

Op-Test Number: HLT0610

Examiners:

Operators:

Initial Conditions:

~A"

'\\

The unit is starting up following a refuel outage. Reactor power is at - )6/0. I RFP is uncoupled for

performance ofturbine overspeed testing. Currently at step 5.76.8 of3-GOI-IOO-IA.

Turnover:

~

The 3Sl RFP is uncoupled and the suction and discharge valves are tagged for performance ofturbine

overspeed. Currently at step 5.76.8 of3-GOI-IOO-IA and at step 5.6.~ of3-01-3 for warming 3B RFP.

t(&i

Event

Malfunction

Event

Number

Type*

Description

1

none

R-ATC

Crew will continue to pull rods to increase power and start

N-BOP

warming up 2B RFP

R-SRO

2

irnfrd14a

I-ATC

Crew will respond to a RWM failure.

I-SRO

SRO references Tech Specs.

TS-SRO

3

irnfrdOla

C-ATC

Crew will respond to a trip of3A CRD pump.

C-SRO

4

irnf sw02a trip

C-BOP

Crew will respond to a RBCCW pump trip

7048FTC

C-SRO

Crew manually closes 70-48 after fails to auto close

5

ior zdihs468a

C-BOP

Crew will respond to feedwater controller malfunction which

irnfth235

C-SRO

results in cold water injection

6

irnfth235

M

Crew responds to fuel failure after cold water injection

All

7

irnf cu0425

M

Crew responds to a RWCU line break and scrams reactor

ior zdihs69 1

All

before any area reaches max safe value.

null

(N)onnal,

(R)eactivity,

(I)nstrument,

(C)omponent,

(M)ajor

AppendixD

Scenario Outline

Form ES-D-l

Facility: BFN

Scenario Nwnber: HLTS-3-4

Op-Test Nwnber: HLT06I0

Examiners:

Operators:

Initial Conditions:

The unit is starting up following a refuel outage. Reactor power is at - 1%. "C" RFP is uncoupled for

performance of turbine overspeed testing. Currently at step 5.76.8 of3-GOI-IOO-IA.

Turnover:

The 3C RFP is uncoupled and the suction and discharge valves are tagged for performance ofturbine

overspeed. Currently at step 5.76.8 of3-GOI-100-lA and at step 5.6.13 of3-0I-3 for warming 3B RFP.

Event

Malfunction

Event

Number

Type*

Description

I

none

R-ATC

Crew will continue to pull rods to increase power and start

N-BOP

warming up 2B RFP

R-SRO

2

irnfrd14a

I-ATC

Crew will respond to a RWM failure.

I-SRO

SRO references Tech Specs.

TS-SRO

3

irnfrdOla

C-ATC

Crew will respond to a trip of3A CRD pump.

C-SRO

4

irnfsw02a trip

C-BOP

Crew will respond to a RBCCW pump trip

7048FTC

C-SRO

Crew manually closes 70-48 after fails to auto close

5

ior zdihs468a

C-BOP

Crew will respond to feedwater controller malfunction which

irnfth235

C-SRO

results in cold water injection

6

irnfth235

M

Crew responds to fuel failure after cold water injection

All

7

irnf cu0425

M

Crew responds to a RWCU line break and scrams reactor

ior zdihs691

All

before any area reaches max safe value.

null

(N)onnal,

(R)eactivity,

(I)nstrument,

(C)omponent, (M)ajor

(

HLTS-3-4

Revision 0

Page 1 of 43

SIMULATOR EVALUATION GUIDE

TITLE

RWM FAILURE, CRD PUMP TRIP, RBCCW PUMP TRIP, FEED

PUMP CONTROL FAILURE, FUEL FAILURE, RWCU LINE

BREAK WITH FAILURE TO ISOLATE, RAPIDLY DEPRESSURIZE

WITH 2 AREAS APPROACHING MAXIMUM SAFE RADIATION

LEVELS

REVISION

o

DATE

January 20, 2008

PROGRAM

BFN Operator Training - HLT

PROVIDE COPY OF 3-GOI-100-1A TO EXAMINEES

CONCURRED

Z-joo-=J

Date

~/d

Date

/-~-t---

/

PREPAREDBy:Q~

~

REVIEWED BY:

i..I2t.J-~

(Operations Training Manager or Designee)

D-RsJ) ~

(Operations Superif1t8i1dent or Designee)

VALIDATION :

l......::.......lf--+-----:>l~-

/

BY

(Operation

0 : Required for Exam Scenarios Only)

(

HLTS-3-4

Revision 0

Page 2 of 43

NUCLEAR TRAINING

REVISION/USAGE LOG

REVISION

DESCRIPTION

DATE

PAGES

REVIEWED BY

NUMBER

OF

AFFECTED

REVISION

0

INITIAL

2/5/2008

All

R.M. Spadoni

(

I.

II.

III.

Program:

Course:

Title:

HLTS-3-4

Revision a

Page 3 of 43

BFN Operator Training

Examination Guide

RWM FAILURE, CRD PUMP TRIP, RBCCW PUMP TRIP,

FEEDPUMP CONTROL FAILURE, FUEL FAILURE, RWCU LINE

BREAK WITH FAILURE TO ISOLATE, RAPIDLY DEPRESSURIZE

WITH 2 AREAS APPROACHING MAXIMUM SAFE RADIATION

LEVELS AND EMERGENCY DEPRESSURIZE AFTER 2 AREAS

REACH MAXIMUM SAFE RADIATION LEVELS

IV.

Length of Scenario: 1 to 1 % hours

V.

Examination Objectives:

A.

Terminal Objective

1.

Perform routine shift turnover, plant assessment and routine shift

operation in accordance with BFN procedures.

2.

Given uncertain or degrading conditions, the operating crew will

use team skills to conduct proper diagnostics and make

conservative operational decisions to remove equipmenUunit from

operation. (SOER 94-1 and SOER 96-01)

3.

Given abnormal conditions, the operating crew will place the unit in

a stabilized condition per normal, annunciator, abnormal, and

emergency procedures.

B.

Enabling Objectives:

1.

The operating crew will start and warm-up "B" RFP In accordance

with 01-6 section 5.7.

2.

The operating crew will recognize and respond to a failure of RWM

in accordance with 3-01-85-5 and Tech. Specs.

3.

The operating crew will recognize and respond to a CRD pump trip

in accordance with 3-AOI-85-3.

HLTS-3-4

Revision 0

Page4 of 43

4.

The operating crew will recognize and respond to a RBCCW pump

trip in accordance with 3-AOI-70-1 .

5.

The operating crew will recognize and respond to Feedpump

control failure in accordance with 3-AOI-3-1.

6.

The operating crew will recognize and respond to a fuel failure in

accordance with ARPs and EOI-3.

7.

The operating crew will recognize and respond to a break in the

RWCU system and rapidly depressurize the RPV.

(

HLTS-3-4

Revision 0

Page 5 of 43

VI.

References: The procedures used in the simulator are controlled copies and are

used in development and performance of simulator scenarios.

Scenarios are validated prior to use, and any procedure differences

will be corrected using the procedure revision level present in the

simulator. Any procedure differences noted during presentation will

be corrected in the same manner. As such, it is expected that the

references listed in this section need only contain the reference

material which is not available in the simulator.

VII.

Training Materials:

(If needed, otherwise disregard)

A.

Calculator

B.

Control Rod Insertion Sheet

C.

Stopwatch

D.

Hold Order I Caution tags

E.

Annunciator window covers

F.

Steam tables

(

HLTS-3-4

Revision 0

Page 6 of 43

VIII.

Console Operator Instructions

A.

Scenario File Summary

1.

File:

bat HLTS3-4

MF/RF/lOR#

Description

a.)

ior zdihs691 null

Fails 69-1 to close

b.)

imf cu04 25

RWCU suction line break

c.)

imf cu06

d.)

bat 7048FTC

fail 70-48 to not auto close

2.

File:

bat HLTS3-4-1

MF/RF/lOR#

Description

a.)

imf rm10g 10005:00

Fails rm14 upscale

b.)

imf rm10e 1000 10:00

Fails rm09 upscale

3.

File:

bat 7048ftc

MF/RF/IOR#

Description

a.)

ior zlohs7048a[2] on

Override red light on

b.)

ior ypovfcv7048 fail-power_now

Fails power to valve

c.)

trg e1=bat 7048-1

Set trigger to 70-48 HS

d.)

Imffw10c

Fail 3C RFP auto trips

4.

File:

bat 7048-1

MF/RF/IOR#

Description

a.)

dor zlohs7048a[2]

Delete Override on red

light

b.)

dor ypovfcv7048

Restore power to valve

5.

File:

bat HLTS3-4-4

MF/RF/lOR#

Description

a.)

imf fw30c (none 0) 60 30 50

Run up and stop 3C RFP

controller in manual

(

VIII.

Console Operator Instructions

B.

Console Operator Manipulations

HLTS-3-4

Revision 0

Page7 of 43

ELAPTIME

Sim. Setup

Sim Setup

After RFP warmed and

When requested by

Examiner

Reset IC 9

Manual

bat7048ftc

F3

DESCRIPTION/ACTION

-9% power, MOC

Place Hold Order Tags on A RFP

suction and discharge valves

Ensure RWM is latched with no Insert

or Withdrawal blocks and comp/prog

lights reset, rod group 39 - 06-47

selected

Verify 3A RFP suct & disch valve lights

extinguished. If not, bat 3arfptag

Set 70-48 to not close on low pressure

and fail 3C RFP auto trips

Fails RWM (imf rd14a)

ROLE PLAY:

If asked, have not performed a startup with RWM

bypassed within last calendar quarter

If requested to verify open 3-1-155 and 3-1-156, report that they

are open

After Tech Specs

addressed for RWM

imf rd01a

Trips 3A CRD Pump.

ROLE PLAY:

When sent to investigate the trip of 3A CRD Pump, report that

the breaker is tripped on over-current.

After the crew starts 38

CRD pump and with Lead

Examiners concurrence:

F8

Trips A R8CCW pump

(imf sw02a)

(

VIII.

Console Operator Instructions (continued)

B.

Console Operator Manipulations

HLTS-3-4

Revisiona

Page 8 of 43

If requested to align spare

RBCCW pump to Unit 3

Wait 3 minutes

If requested to reset local

RWCU panel alarms

After spare RBCCW pump

aligned and RWCU

returned to service

Two (2) Minutes after

Feedpump governor

problem

When directed by examiner

F9

F12

Bat HLTS3-4-4

F6

F7

Aligns spare RBCCW pump to Unit 3

(mrf sw02 align)

mrf an01e reset

Fails RFP governor in raise direction in

manual for 30 sec

fuel failure

(imf th23 5 15:00)

RWCU line break with failure to isolate

(bat HLTS3-4)

ROLE PLAY:

If requested to attempt to close 69-1 locally at the breaker, wait

5 minutes and report it will not close

If requested to check Aux Inst rm, report 835 A&C and 835

B&D reading 90 deg F and fairly steady

After attempts to close 69-1

are made

F10

Causes Rad monitors to reach max

(bat HLTS3-4-1)

Terminate the scenario when the following conditions are satisfied or when requested

by Chief Examiner:

1.

Reactor Water level restored between +2 to +51"

2.

RPV rapidly depressurized

3.

RPV emergency depressurized

(

HLTS-3-4

Revision 0

Page 9 of 43

IX.

Scenario Summary

The plant is at approximately 9% power withdrawing control rods to open

sufficient bypass valves to roll the main turbine. "B" RFP needs to be started

and warmed in preparation for water level control.

During the control rod withdrawal, the RWM will experience a program fault

which will block rod movement. Tech. Specs will be addressed and control rod

withdrawal will continue when a second licensed operator is present to ensure

withdrawal is in accordance with the BPWS.

A CRD pump will trip causing the crew to start the standby CRD pump.

An RBCCW pump will trip causing RWCU to be secured and the spare RBCCW

pump aligned to Unit 3 and the RWCU system returned to service.

The In-service RFP will experience a governor fault causing it to inject cold water

into the RPV causing a power spike and some fuel failure. Later the RWCU

system develops and leak and fails to isolate requiring entry into EOI-3 and

subsequent rapid depressurization due to 2 areas approaching max safe

radiation levels.

(

x.

HLTS-3-4

Revision 0

Page 10 of 43

Information to Evaluators:

A.

Ensure recorders are inking and recording and ICS is active and updating.

B.

Assign Crew Positions based on the required rotation.

1.

2.

3.

C.

Conduct a shift turnover with the Shift Manager and provide the Shift

Manager with a copy of the Shift Turnover.

D.

Direct the shift crew to review the control board and take note of present

conditions, alarms, etc.

E.

Terminate the scenario when the following conditions are satisfied are at

the request of the floor/lead instructor/evaluator.

1.

Reactor water level restored at +2" to +51"

2.

RPV rapidly depressurized

3.

RPV emergency depressurized when 2 areas are above max safe

values.

(

XI.

HLTS-3-4

Revision a

Page 11 of43

Simulator Event Guide

EVENT 1:

Warming up second RFP

TIME

POSITION

EXPECTED ACTIONS

irects warmin

u

B RFP in accordance with 3-01-

Warms up "B" RFP utilizing section 5.6 of 3-01-3.

3-ARP-9-6C window 32

A. VERIFY reactor Feedpump flow on Panel 3-9-6.

B. REFER TO 3-01-3, Section 8.7.

C. IF annunciation is caused by RFW Control System

malfunction, THEN REQUEST assistance from Site

Engineering and IMs.

(

XI.

HLTS-3-4

Revision 0

Page 12 of 43

Simulator Event Guide

EVENT 1:

Warming up second RFP

(

TIME

POSITION

EXPECTED ACTIONS

Place in auto and verify open RFP min flow valve 3-FCV-

3-13

Place 38 start/local enable 3-HS-46-138A in start and

observe RFP accelerates to 600 rpm

Verify no abnormal rubbing or vibration is observed

Raise speed to -1000 rpm using 3-HS-46-9A

Place TG motor 3-HS-3-127A in Auto

Depress 38 trip 3-HS-3-127A and verify HP and LP stop

valves close

Verify TG auto engages or RFP rolling on min flow

Depress 38 trip reset 3-HS-3-150A and verify blue light

extinguishes and HP and LP stop valves open

Place 38 start/local enable 3-HS-46-138A in start and

observe RFPT speed increases to - 600 rpm

HLTS-3-4

Revision 0

Page13of 43

XI: Simulator Event Guide

EVENT 2:

RWM FAILURE

TIME

POSITION

EXPECTED ACTIONS

Announces "RWM ROD BLOCK" 3-XA-55-5B window

35 alarm and refers to ARP.

A. CHECK RWM panel for error.

B. CHECK rod position and COMPARE it with Control Rod

Movement Data Sheet (3-SI-4.3.B.1.a) (3-SR-3.1.3.5(A)).

C. IF RWM becomes inop, THEN REFER TO 3-01-85 and

Tech Spec 3.1, 3.3, Table 3.3.2.1-1.

Directs ATC to bass RWM

er 01-85

Refers to T.S. 3.1 3.3 table 3.3.2.1-1

Contacts Rx Engineer

(

HLTS-3-4

Revision 0

Page 14 of 43

XI: Simulator Event Guide

EVENT 2:

RWM FAILURE

TIME

POSITION

EXPECTED ACTIONS

-01-85 section 8.1

[1] VERIFY the following initial conditions are satisfied:

The Shift Manager/Reactor Engineer has directed the Rod

Worth Minimizer to be bypassed.

A second licensed operator is available to verify control

rod position.

[2] REVIEW all Precautions and Limitations in Section

3.4.

[3] PLACE RWM SWITCH PANEL, 3-XS-85-9025, in

BYPASS.

[4] CHECK the Manual Bypass light is illuminated .

[5] CHECK all other indications on the Rod Worth Minimizer

Operator's Panel are extinguished.

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EVENT 2:

RWM FAILURE

TIME

POSITION

EXPECTED ACTIONS

[6] CHECK the Blue Rod Out Permit light above 3-HS-85-48

is illuminated.

[7] RESET CONTROL ROD WITHDRAWAL BLOCK

annunciator (3-XA-55-5A, Window 7).

Determines T.S. 3.3.2.1 condition C.2.1-1 & 2.2 applies.

Greater than 12 rods withdrawn and 2nd person to verify

compliance with BPWS.

(

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EVENT 3:

CRD PUMP 3A TRIP

(

TIME

POSITION

EXPECTED ACTIONS

Recognize annunciator MOTOR TRIPOUT 3-ARP-9-8c (W

33) is in alarm.

Acknowledges and resets MOTOR TRIPOUT annunciator.

4.1 Immediate Actions

[1]

IF operating CRD PUMP has TRIPPED AND

STANDBY CRD PUMP is AVAILABLE, THEN

(Otherwise N/A)

PERFORM the following at Panel 3-9-5:

[1.1]

PLACE CRD SYSTEM FLOW CONTROL, 3-FIC-

85-11, in MAN at minimum setting .

(

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EVENT 3:

CRD PUMP 3A TRIP

TIME

POSITION

EXPECTED ACTIONS

[1.2]

START associated standby CRD Pump using one of

the following:

CRD PUMP 3B, using 3-HS-85-2A

CRD Pump 3A, using 3-HS-85-1A

[1.3]

ADJUST CRD SYSTEM FLOW CONTROL, 3-FIC-

85-11, to establish the following conditions:

CRD CLG WTR HDR DP, 3-PDI-85-18A,

approximately 20 psid.

CRD SYSTEM FLOW CONTROL, 3-FIC-85-11,

between 40 and 65 gpm.

[1.4]

BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-

85-11, and PLACE in AUTO or BALANCE.

(

XI.

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Simulator Event Guide

EVENT 4:

LOSS OF 3A RBCCW pump

TIME

POSITION

EXPECTED ACTIONS

Responds to loss of RBCCW pump 3A trip and

attempts to restart 3A RBCCW pump and reports it

failed to start.

3-ARP-9-4C window 12

A. VERIFY 3-FCV-70-48 CLOSING/CLOSED.

Reports that the 3-FCV-70-48 sectionalizing valve failed

to close.

B. VERIFY RBCCW pumps A and B in service.

C. VERIFY RBCCW surge tank low level alarm is reset.

D. DISPATCH personnel to check the following:

o RBCCW surge tank level locally.

o RBCCW pumps for proper operation.

C'

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EVENT 4:

LOSS OF 3A RBCCW pump

TIME

POSITION

N/A

EXPECTED ACTIONS

Immediate Actions

[1] IF RBCCW Pump(s) has tripped, THEN: ATTEMPT to

restart tripped pump(s).

[2] IF RBCCW Pump(s) cannot be restarted, THEN:

(Otherwise N/A) SHUT DOWN RWCU System Pumps.

(Reference TRM 3.4.1)

Secures RWCU pumps and reports that the 3-FCV-70-48

sectionalizing valve failed to close.

IF Reactor is at power AND Drywell Cooling cannot be

immediately restored, AND core flow is above 60%,THEN:

(Otherwise N/A):

REDUCE core flow to between 50-60%.

MANUALLY SCRAM the Reactor and PLACE Mode Switch to

SHUTDOWN. REFER TO 3-AOI-100-1.

SHUT DOWN both Recirc Pumps.

o DEPRESS RECIRC DRIVE 3A SHUTDOWN, 3-HS-96-19.

o DEPRESS RECIRC DRIVE 3B SHUTDOWN, 3-HS-96-20.

INITIATE a 90°F/HR cooldown rate. REFER TO 3-AOI-100-

1.

IF any EOI entry condition is met, THEN: (Otherwise N/A)

(

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Simulator Event Guide

EVENT 4:

LOSS OF 3A RBCCW pump

TIME

POSITION

EXPECTED ACTIONS

[3] IF unable to restart a tripped pump, THEN:

Otherwise N/A PLACE Spare RBCCW Pump in service.

REFER TO 3-01-70.

REQUEST Unit 1 to place the spare RBCCW pump in

service to support Unit 3 operation. (REFER TO 1-01-70).

Contacted U1 Operator to place the spare pump in

service to Unit 3.

ack to 3-AOI-70-1

[4] IF RBCCW flow was restored to two pump operation

THEN: (Otherwise N/A)

[4.1] REOPEN RBCCW SECTIONALIZING VLV, 3--HS--70-

48A. After Spare RBCCW pump placed in service,

(conditional, SRO may not direct valve to be opened

after failure to auto close and if so, will NOT place

RWCU in service.)

(

[4.2]

ESTORE the RWCU s stem to 0

iTO 3-01-69J.

(

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EVENT 4:

LOSS OF 3A RBCCW pump

TIME

POSITION

EXPECTED ACTIONS

-01-69 section 5.1 8

RWCU Pump Startup

[1] REVIEW precautions and limitations in Section 3.0.

[2] VERIFY RWCU prestartup requirements in Section 4.0

have been completed.

[3] VERIFY RESET the RWCU Group 3 isolation using PCIS

DIV I RESET, 3-HS-64-16A-S32 and PCIS DIV II RESET, 3-

HS-64-16A-S33 at Panel 3-9-4.

[4] IF a condition exists which could have caused 3-FCV-069-

0094 to isolate, THEN VERIFY OPEN 3-FCV-069-0094,

RWCU SYSTEM APP R FLOW CONTROL VLV, locally. (Unit

3 Rx Bldg, EI 593' R-17 S-Line).

[5] VERIFY RWCU HEAT EXCHANGERS RBCCW FLOW

CONTROL, 3-TIC-069-0010A is in MANUAL, and FULL

OPEN demand is on 3-TCV-70-49. (REFER TO Illustration

5)[BFPER 03-000348-000]

[6] VERIFY CLOSED the following:

o RWCU BLOWDOWN PRESS CONTROL VLV, using 3-HC-

69-15

o RWCU BLOWDOWN TO MAIN CNDR, using 3-HS-69-16A

o RWCU BLOWDOWN TO RADWASTE, using 3-HS-69-17A

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EVENT 4:

LOSS OF 3A RBCCW pump

(

TIME

POSITION

EXPECTED ACTIONS

[7] IF a Caution Order is present on the control room hand

switch for RWCU PUMP 3A(3B) informing operator that 3-

SHV-070-0573A(0573B) is closed, THEN PERFORM the

following:

[7.1] OPEN 3-SHV-070-0573A(0573B), RWCU PUMP A(B)

CLG WTR INLET.

[7.2] REMOVE Caution Order from the control room hand

switch for RWCU PUMP 3A(3B) informing operator that 3-

SHV-070-0573A(0573B) is CLOSED.

[8] NOTIFY chemistry RWCU is being placed in service

and to check the durability monitor.

[9] VERIFY OPEN the following valves:

RWCU INBD SUCT ISOLATION VALVE, 3-FCV-69-1

RWCU OUTBD SUCT ISOLATION VALVE, 3-FCV-69-2

RWCU DEMIN BYPASS VALVE, 3-FCV-69-8

[10] OPEN 3-FCV-069-0012 by one of the two methods

described below.

(

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EVENT 4:

LOSS OF 3A RBCCW pump

(

TIME

POSITION

N/A

EXPECTED ACTIONS

PLACE 3-HS-69-12A in the OPEN position, THEN

RETURN 3-HS-69-12A to the NORM position when

intermediate position (red and green light) is indicated.

PLACE 3-HS-69-12A in the OPEN position, THEN

RETURN 3-HS-69-12A to the NORM position when

FULL OPEN position (red light only) is indicated.

[11] PLACE seal purge in operation to pump(s) to be

placed in service. REFER TO Section 8.2.

[12] START RWCU RECIRC PUMP 3A(3B) using control

switch 3-HS-69-4A(4B)-A, and A RISE flow, using

RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to

prevent low flow trip.

[13] IF two pump operation is desired, THEN START

the second RWCU RECIRC PUMP 3B(3A) using control

switch 3-HS-69-4B(4A)-A, and A RISE flow using RWCU

RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent

low flow trip.

[14] IF the RWCU filter-demineralizers is to be placed

in service, THEN REFER TO Section 6.2.

(all local actions except Operator closing 3-FCV-69-8

valve as AUO rolls demins in service)

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EVENT 4:

LOSS OF 3A RBCCW pump

(

TIME

POSITION

FEEDWATER CONTROLLER FAILURE

EXPECTED ACTIONS

3-ARP-9-4B window 24

A. DISPATCH personnel to local Panel 25-3, to determine

cause of alarm.

B. IF alarm is valid, THEN REFER TO 3-ARP-25-3 for

appropriate operator action.

C. IF this alarm meets the requirements AND the Shift Manager

desires the annunciator to be disabled, THEN REFER TO OPDP-

4.

Coordinates with AUO to roll demins in service

Dispatches personnel to investigate pump loss

May contact Rx Engineer about heat balance

Contacts Chemistry

Reviews TRM LCO 3.4.1 and verify it does not apply

whether RWCU is placed in service or not.

(

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EVENT 5:

TIME

POSITION

FEEDWATER CONTROLLER FAILURE

EXPECTED ACTIONS

Observes period rise by meter or annunciator and

checks for cause of reactivity addition

Ranges IRMs as necessary to prevent a reactor scram

Attempts to take control of A RFP by adjusting 3-HS-46-

8C and reports that "C" RFP cannot be controlled

IF Feedwater Control System has failed, THEN

PERFORM the following:

PLACE individual RFPT Speed Control Raise/Lower

switches in MANUAL GOVERNOR (depressed position

with amber light illuminated).

ADJUST RFP Discharge flows with RFPT Speed Control

Raise/Lower switches as necessary to maintain level.

IF level continues to rise, THEN TRIP a RFP, as

necessary.

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EVENT 5:

(Critical Task)

TIME

POSITION

EXPECTED ACTIONS

Directs t~P and using "B" RFP for RPV level

control ~

Trips "C" RFP by depressing 3-HS3-125C and raises "B"

RFP speed by using 3-HS-46-9B

Opens "B" RFP discharge valve 3-HS-3-12B when "B"

RFP discharge pressure is within 250 Ibs of reactor

pressure.

(

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Simulator Event Guide

EVENT 6:

FUEL FAILURE DUE TO COLD WATER INJECTION

POSITION

EXPECTED ACTIONS

(

Announces "TURBINE BUILDING HIGH RADIATION"

3-ARP-9-3A window 27

DETERMINE area with high radiation level on Panel 3-9-11.

(Alarm on Panel 3-9-11 will automatically reset if radiation

level lowers below setpoint.)

IF the TSC is NOT manned, THEN USE public address system

to evacuate area where high airborne conditions exist.

N/A

IF the TSC is manned, THEN REQUEST the TSC to evacuate

non-essential personnel from affected areas.

NOTIFY RADCON.

MONITOR other parameters providing input to this annunciator

frequently as these parameters will be masked from alarming

while this alarm is sealed in.

(

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Simulator Event Guide

EVENT 6:

FUEL FAILURE DUE TO COLD WATER INJECTION

(

POSITION

N/A

EXPECTED ACTIONS

Announces "RX BLDG HIGH RADIATION" and determines

which area and evacuates that area. North and South RWCU

area.

DETERMINE area with high radiation level on Panel 3-9-11.

(Alarm on Panel 3-9-11 will automatically reset if radiation

level lowers below setpoint.)

IF the alarm is from the HPCI Room while Flow testing is being

performed, THEN REQUEST personnel at the HPCI Quad to

validate conditions

NOTIFY RADCON.

IF the TSC is NOT manned and a "VALID" radiological

condition exists., THEN USE public address system to

evacuate area where high airborne conditions exist

MONITOR other parameters providing input to this

annunciator frequently as these parameters will be masked

from alarming while this alarm is sealed in.

(

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EVENT 6:

FUEL FAILURE DUE TO COLD WATER INJECTION

POSITION

BOP/SRO

EXPECTED ACTIONS

Announces "OFF-GAS ANNUAL RELEASE LIMIT

EXCEEDED" 3-ARP-9-4C window 27

To determine if the Off Gas Annual Release Rate Limit is

exceeded, PERFORM the following :

VERIFY alarm condition on the following:

OFFGAS PRETREATMENT RADIATION recorder, 3-RR-90-157

on Panel 3-9-2

OG PRETREATMENT RAD MON RTMR radiation monitor,

3-RM-90-157 on Panel 3-9-10

CHECK off-gas flow and monitor sample flow normal.

NOTIFY RADCON.

Notifies Chemistry to perform analysis and Radcon

Declares a NOUE on a valid OG pretreatment rad alarm.

(

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EVENT 6:

FUEL FAILURE DUE TO COLD WATER INJECTION

POSITION

N/A

EXPECTED ACTIONS

REQUEST Chemistry perform radiochemical analysis to

determine source.

WITH OPS MGT and Shift Manager's permission, PLACE

charcoal beds in parallel with another unit. REFER TO 3-01-

66.

IF fuel damage is suspected, THEN REFER TO 3-SI-4.6.B.5 (3-

SR-3.4.6.1) for dose equivalent iodine -131 determination.

REFER TO O-SI-4.8.B.1.a.1 and 3-51-4.6.B.6 (3-SR-3.4.6.1-a)

for ODCM compliance and to determine if power level

reduction is required.

IF directed by Shift Manager or Unit Supervisor, THEN

REDUCE reactor power to maintain off-gas radiation within

ODCM limits.

REFER TO EPIP-1.

(

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EVENT?:

RWCU LINE SUCTION BREAK

POSITION

N/A

EXPECTED ACTIONS

Reports on RWCU leak detection alarms 3-ARP-9-3D window

17

IF this alarm is received in conjunction with RWCU ISOL

LOGIC CHANNEL A TEMP HIGH [3-XA-55-5B, window 32]

and RWCU ISOL LOGIC CHANNEL B TEMP HIGH [3-XA-55-

5B, window 33], THEN EXIT this procedure and GO TO 3-

ARP-9-5B. Otherwise,

CHECK RWCU Leak Detection System temperatures on Panel

3-9-21 and Panels 9-83,9-84,9-85 and 9-86 in the auxiliary

instrument room. . The 834 and 835 Temp Loops are also displayed

on ICS under 'HPTURB' for Main Steam Tunnel and 'RWCU' for the

Pipe Trench.

IF high temperature is indicated on TS69-290, E, F, G or H or TIS

69-835A, B, C, or 0, THEN ENTER 3-EOI-3 Flowchart.

CHECK Rx Bldg. RWCU system ARMs, 3-RI-90-13A and 14A on

Panel 3-9-11, and Rx Zone Exhaust Rad Monitor, 3-RR-90-142 on

Panel 3-9-2.

DISPATCH personnel to investigate the affected area.

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EVENT?:

RWCU LINE SUCTION BREAK

POSITION

Crew

EXPECTED ACTIONS

Recognizes that 69-1 failed to isolate and attempts to

manually close

Directs outside personnel to attempt to close 69-1 locally at

the breaker.

Directs Rx Scram before any area temp is above the

maximum safe operating temperature.

Scrams reactor and provides scram report

Directs ATC to

erform actions of 3-AOI-100-1

(

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EVENT 7:

RWCU LINE SUCTION BREAK

POSITION

SRO/BOP

BOP/ATC

EXPECTED ACTIONS

Continue to monitor and trend secondary area temps and radiation

levels

Reports that 2 areas are approaching maximum safe radiation

levels

Directs rapid depressurization ot the RPV using BPVs

Opens all BPVs using the Jack

Coordinate level control during depressurization to prevent flooding

the RPV

Determines that 2 areas are above max safe radiation values

Determine~ncy Depressurization is Required and

entersC2 ~

Directs BOP to open all ADS valves (Critical Task)

(

Opens all ADS valves (Critical Task)

(

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EVENT 7:

RWCU LINE SUCTION BREAK

(

POSITION

EXPECTED ACTIONS

Reports Main Steam Line Radiation High - High

3-ARP-9-3A window 27

A. VERIFY the alarm on 2-RM-90-136and 2-RM-90-137 on

Panel 2-9-10.

B. CONFIRM main steam line radiation level on recorder 2-RR-90-

135, Panel 2-9-2.

C. IF alarm is valid and Reactor Scram has not occurred, THEN

PERFORM the following:

1. IF core flow is above 60% THEN LOWER core flow to between

50-60% ..

2. MANUALLY SCRAM the Reactor.

3. REFER to 2-AOI-100-1 .

D. IF plant conditions DO NOT require execution of 2-C-5, THEN

VERIFY the MSIV's closed.

E. NOTIFY RADCON.

F. VERIFY actions of 2-ARP-9-3A Window 7 have been completed.

G. IF Technical Specification limits are exceeded, THEN

REFER TO EPIP-1.

(

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EVENT 7:

RWCU LINE SUCTION BREAK

POSITION

EXPECTED ACTIONS

3-ARP-9-3A window 7

A. CHECK following radiation recorders:

1. MAIN STEAM LINE RADIATION monitor, 2-RR-90-135 on

Panel 2-9-2.

2. OFFGAS PRETREATMENT RADIATION, 2-RR-90-157 on

Panel 2-9-2.

3. OFFGAS RADIATION, 2-RR-90-160 on Panel 2-9-2.

4. OFFGAS POST-TREATMENT RADIATION, 2-RR-90-265 on

Panel 2-9-2.

5. STACK GAS RADIATION, O-RR-90-147 on Panel 1-9-2.

B. NOTIFY RADCON.

C. [NRC/C) NOTIFY Chemistry to perform radiochemical analysis of

primary coolant. [NCO 940247001]

(

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EVENT 7:

RWCU LINE SUCTION BREAK

POSITION