Text

Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 951204-08
	ML20129E704
Person / Time
Site:	Fort Calhoun
Issue date:	12/29/1995
From:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9610280142
	Download: ML20129E704 (504)
	v • d • e

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Exam Outline Contents

1. FCS 50-285, Exam Schedule (1 page)

2. Count Matrix for RO Written Exam (1 page)

3. Count Matrix for SRO Written Exam (1 page)

4. Overall exam matrix and K/A listings for written RO exam. (7 pages)

5. Overall exam matrix and K/A listings for written SRO exam. (7 pages)

6. RO Administrative Topics Outline (1 page)

7. SRO Administrative Topics Outline (1 page)

8. RO Individual Walk-through Test Outline (1 page)

9. SRO(I) Individual Walk-through Test Outline (1 page)

10. SRO(U) Individual Walk-through Test Outline (1 page)

11. Simulator Scenario Events (2 pages)

12. Copy of signed Security Agreement (2 pages) l 4

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9610280142 951229 PDR V

ADOCK 05000285 pg k !

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7 ff/hlY O.RAF7 FCS 12/95 PILOT INITIAL SRO/RO WRITTEN EXAM i

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SRO ANSWER KEY (1) A (26) B (51) B (76) D (2) D (27) A (52) D (77) C (3) B (28) C (53) C (78) C (4) C (29) B (54) C (79) D (5) A (30) B (55) C (80) D (6) C (31) D (56) C (81) C (7) C (32) B (57) C (82) D (8) D (33) D (58) C (83) C (9) B (34) A (59) D (84) B (10) C (35) C (60) A (85) D (11) C (36) B (61) C (86) C (12) A (37) C (62) A (87) A (13) B (38) B (63) B (88) C (14) D (39) D (64) D (89) D (15) D (40) C (65) A (90) A (16) A (41) C (66) D (91) D (17) C (42) B (67) C (92) D (18) D (43) D (68) C (93) C (19) C (44) B (69) A (94) B (20) B (45) C (70) D (95) C (21) D (46) B (71) D (96) A (22) C (47) B (72) A (97) D (23) B (48) D (73) C (98) A ,

(24) D (49) B (74) B (99) D l (25) A (50) A (75) B (100) A i

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4 RO ANSWER KEY (1) A (26) B (51) B (76) C (2) D (27) A (52) D (77) C (3) B (28) C (53) C (78) A (4) C (29) B (54) C (79) D (5) A (30) B (55) C (80) C (6) C (31) D (56) C (81) D (7? C (32) B (57) C (82) D (8) D (33) D (58) C (83) B (9) B (34) A (59) D (84) D ,

(10) C (35) C (60) A (85) A I (11) C (36) B (61) C (86) B i (12) A (37) C (62) A (87) D I (13) B (38) B (63) B (88) C l (14) D (39) 9 (64) D (89) B l (15) D (40) e (65) A (90) B l (16) A (41) C (66) D (91) A '

(17) C (42) B (67) C (92) C (18) D (43) D (68) C (93) D (19) C (44) B (69) A (94) A (20) B (45) C (70) D (95) A l (21) D (46) B (71) D (96) A l (22) C (47) B (72) A (97) B (23) B (48) D (73) C (98) D l (24) D (49) B (74) B (99) C (25) A (50) A (75) B (100) C 6

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1 SENIOR-REACTOR OPERATOR EXAMINATION

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QUESTION- 1 1 Point l The following events occur:

-* The plant is at full power.

Rod Drive Clutches are being supplied from Instrument Buses '

A and C. *

Instrument Bus B is deenergized. i

+ .The operator then inadvertently switches a clutch power l supply from Instrument Bus A'to Instrument Bus B. !

Which one of the following describes the effect that this action I will have on CEA position? j

a. No effect.

b. The' shutdown CEAs will drop.

c. All CEAs will drop.

d. RPS'will generate a reactor trip on one channel.

sUESTION 2 1 Point During a startup, the connection between the drive mechanism for a high worth Shutdown CEA and its poison fingers becomes uncoupled. As a result, the drive mechanism withdraws normally but all poison fingers associated with it remain fully inserted' in the core. Which one of the following describes a symptom that the operators will see as a result of this event?

a. The affected rod bottom light will remain on.

b. The SCEAPIS will show no rod motion for that CEA.

c. Criticality will occur below the PDIL.

d. The ECP will fail to predict criticality at the correct

CEA position.

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_ , _ ' A. +<= - - - - + - A - - - * ' - 3a- e -e- 4 444e -e--,k <-,; + b4,,--AM }s =v-a~a45 SENIOR REACTOR OPERATOR EXAMINATION QUESTION 3 1 Point The following conditions exist:

A_ reactor trip due to a loss of offsite power has occurred.

An inadvertent SGIS occurred after the trip.

MS-291 ( ' A' S/G relief) is open.

MS-292 ('B' S/G relief) will not open.

Pressurizer level is 50%

+ Subcooling Margin is 50*F Which one of the following describes the expected natural circulation patterns that will develop under these condition?

a. No natural circulation will develop.

b. It will develop in the A loop, the B loop will be stagnant.

c. It will develop in the A loop, reflux boiling will develop in the B loop.

d. It will develop normally in both loops.

QUESTION 4 1 Point Which one of the following describes the automatic operation of PCV-1753 (Instrument Air / Service Air Cross Tie)?

a. It closes if 'Jervice air pressure decreases to 80 psig and reopens when pressure increases to 85 psig.

b. It closes if service air pressure decreases to 80 psig but must be reopened manually.

c. It closes when instrument air pressure decreases to 80 psig and reopens when pressure increases to 05 psig.

Ad. It closes when instrument air pressure decreases to 80 psig but must be reopened manually.

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i SENIOR REACTOR OPERATOR EXAMINATION QUESTION 5 1- Point The following conditions exist:

+ A LOCA has occurred. l 4

All HPSI pumps are injecting. I l PPLS has been reset.

l 4 Containment spray is in operation. j

Containment pressure is 6 psig.

l + The current source of water is the containment sump. j

RAS has not been reset. l Resetting RAS under these conditions will result in which one of

! the following consequences? 1 l a. Potential damage to the lockout relays.

l b. It will be possible to start the LPSI pumps.

i i j c. The containment spray pumps will trip.

l d. The water source will swap back to the SIRWT.

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, QUESTION 6 1 Point l

l 'The heated junction thermocouples measure percent of level over L which one of the following ranges? ]

a. Top of the vessel (100%) to bottom of the vessel (0%). l L

b. Top of the core (100%) to bottom of the core (0%).

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c. Top of the vessel (100%) to top of the core (0%). )

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d. Top of the core (100%) to the bottom of the vessel ^

(0%).

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 7 1 Point The following conditions exist:

RCS pressure =500 psia.

Tc=410*F

Th=440 F

CET Average =445 F Which one of the following actions is required concerning the 1

l RCPs? l J

a. No action is required.

b. Trip only one RCP. !

c. Trip one RCP in each loop.

d. Trip all RCPs.

QUESTION 8 1 Point The following conditions exist:

The reactor has tripped as a result of a loss of offsite power.

D1 and D2 have energized 1A3 and 1A4.

Auxiliary Feed Pumps will not start.

Steam Generator levels are currently 20% WR.

All other safety functions are met.

Which .>ne of the following procedures should be implemented first in order to recover the heat removal safety function?

a. EOP-02.

b. EOP-06.

c. EOP-20/HR-2 ad. EOP-20/HR-4

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SENIOR REACTOR OPERATOR EXAMINATION i

QUESTION 9 1 Point In the event of a total loss of feedwater following a reactor trip on low steam generator level from full power, which one of

the following specifies the minimum time that steam generator l inventory can be expected to last?

a. 10 minutes

b. 20 minutes

c. 40 minutes

d. 60 minutes QUESTION 10 1 Point Following a CIAS, sampling of the containment sump is possible because of which one of the following features?

a. Containment sump sample lines do not isolate on CIAS.

b. Manually operated sample lines are available- to bypass the containment isolation valves.

c. The' containment isolation valves can be bypassed and opened for a limited duration.

d. Once the CIAS is reset the sump pump discharge valves will automatically reopen I

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 11 1 Point Prior to placing a Gas Decay Tank in service, which one of the Lfollowing conditions must be verified?

a. Iodine-131 dose equivalent less than 1pCi/gm.

b. Hydrogen concentration greater than 6%.

c. Oxygen concentration less~than 3%.

d. Nitrogen concentration greater than 20%.

QUESTIONL 12 1 Point The plant is operating at full power when high radiation in the Auxiliary Building results in a VIAS. Which one of the following describes the response of the Spent Fuel Area Charcoal: Filters (VA-66) to this event?

a. They will not be affected,

b. Their. bypass damper (HCV-712A) will close and their-isolation damper (HCV-712B) will open.

c. Their bypass damper (HCV-712A) will close. Their isolation damper (HCV-712B) will not be affected,

d. Their bypass damper (HCV-712A) will not be affected.

Thcir isolation damper (HCV-712B) will open.

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l i QUESTION 13 1 Point

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Which one of the following is an indication of RCS void formation

! during a natural circulation cooldown?

1 1 a. Pressurizer level lowers while operating auxiliary l pressurizer spray.

l b. The RCS can not be depressurized to SDC entry i

conditions.

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c. RCS subcooling is 25'F. )

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d. A rapid increase in indicated Reactor Vessel Level on i QSPDS.

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QUESTION 14 1 Point j The following sequence of events occurs:

. An SIAS starts all ECCS pumps.

4 j - The diesels are running normally.

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Offsite power is lost.

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None of the RCP breakers open on Load Shed.

Which.one of the following describes the effect that these events ,

j. will have on the restart of the ECCS pumps as a result of load I t sequencer operation?

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a. All ECCS pumps will restart normally.

f b. Only the HPSI pumps will restart.

I j c. All except the HPSI pumps will restart.

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d. No ECCS pumps will restart.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 15 1 Point The following plant conditions exist:

.The reactor is-in Mode 4.

The pressurizer manway is in place.

Shutdown Cooling is in service.

Shutdown Cooling Isolation Valves (HC-347/348) then go fully closed.

Which one of the following is the most likely cause of these events?

a. Either pressurizer pressure channel P-115 or P-118 has failed low.

b. Pressurizer pressure channel P-118 has failed low.

c. Either pressurizer pressure channel P-115 or P-118 has lost power.

d. Power has been lost ;o pressurizer pressure channel P-118.

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l: SENIOR REACTOR OPERATOR EXAMINATION 1 i

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f QUESTION 16 1 Point t

] The following plant conditions exist: ,

4 The plant is operating at full power. j j

The Tave signal from Channel A RRS to the Pressurizer level !

i- control system fails upscale. j The operator immediately takes the A/B switch on panel CB-4 to B. t

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The Pressurizer level channel selector switch is selected to -

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l, Which one of the following is the expected consequence of these l

events? ,

l a. Actual and indicated pressurizer level will be j unaffected.

f' b. Indicated pressurizer level will decrease, actual level {

j will be unaffected. !

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c. Actual pressurizer level will decrease. ,

i f d. Actual pressurizer level will increase. !

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j 17 QUESTION 1 Point

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l Under which one of the following conditions will the Subcooled i

Margin Monitors on CB-4 provide invalid results?

j a. With one or more RCPs running.

J j b. With pressurizer pressure below 1700 psia.

i j c. With RCS Coolant temperatures below 465'F

d. With Containment Atmosphere temperature above 180*F.

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SENIOR REACTOR OPERATOR. EXAMINATION. ,

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a j QUESTION 18 1 Point

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The following conditions exist

-+ River temperature is 55'F.

+ [

-The plant is operating at full power. i Raw Water Pump AC-10A has been inop for the past 3 days. l' r +

Containment. Spray Pump SI-3B has.just been declared inop.

l In order to-satisfy the requirements of Tech Specs, these conditions require that the plant be taken to HOT SHUTDOWN within

. which one of the-following times?

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j a. The plant should already be in HOT SHUTDOWN.

b. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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c. 4M Days.

d. 7M days.

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SENIOR REACTOR OPERATOR EXAMINATION i l

l QUESTION 19 1 Point !

l The following conditions exist:

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The plant is in Cold Shutdown for a refueling outage.

l 4 The containment purge system is operating in the low purge rate mode with fan VA-77.

A high alarm occurs on radiation monitor RM-062 (stack gas monitor].

Which one of the following describes the expected response of the containment purge' system to these events?

a. The inboard containment isolation valves only would i close and the low purge rate fan would trip. l

b. 'The outboard containment isolation valves only would I close and the low purge rate fan would trip j i

c. Both the inboard and the outboard isolation valves )

would close and the low purge fan would trip. I

d. No automatic action would occur since there must be at i least 2 out of 3 radiation monitors alarming in order for a containment purge system isolation to occur.

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QUESTION 20 1 Point The MSIVs are open when power is lost on DC bus #2. Which one of I the following describes the effect that this event will have on l l the MSIVs?

a. An SGLS A will be generated and both MSIVs will close.

b. An'SGLS B will be generated and both MSIVs will close.

.c. An SGLS B will be generated and MSIV 1042A will close.

ld . An SGLS B will be generated but neither MSIV will ,

close. l l

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 21 1 Point The following conditions exist:

The plant is at 100% power.

All major breakers are in their normal lineup.

The electrical distribution system is aligned for automatic operation.

The control switch for breaker 1All is then turned to the open (green flag) position.

Which one of the following will occur as a result of these l conditions?

a. Breaker 1All will not open unless breaker 1A31 is closed first.

b. A fast transfer will occur with breaker 1A31 closing before breaker 1All opens.

c. A fast transfer will occur with breaker 1All opening before breaker 1A31 closes.

d. Breaker 1All will open but breaker 1A31 will not close.

l QUESTION 22 1 Point Diesel generator D1 has received a start signal as a result of a j reactor trip. The engine lube oil pump discharge pressure switch has failed in the low pressure position. Which one of the following describes the expected response of D1 to these events?

a. It will not start.

" It will start but will trip after 15 seconds,

c. It will start and then idle at 500 rpm.

ld . It will start and then run at 900 rpm. j l

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SENIOR REACTOR OPERATOR EXAMINATION ,

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! QUESTION 23 1 Point +

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With the plant operating at full power, which one of the l a following diesel generator operability histories is in compliance j 4 with the requirements of Tech Spec 2.7 2 (j) ?

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a. DG-1 is inop from 4/26 to 5/4 1 b. DG-2 is inop from'4/24 to 4/30 and from 5/2 to 5/5

c. DG-1 is inop from 4/20 to 4/25 and DG-2 is.inop from 4/26 to 4/30.

, d. DG 1 is inop from 4/25 to 4/30 and DG-2 is inop from

' 28 to 5/2.

QUESTION 24 1 Point Which one of the following conditions will cause the Control Room l Ventilation System to automatically switch to the Filtered Air j makeup mode of operation? !

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a. High inlet Chlorine. ;

b. Smoke detected in control room exhaust. I

c. High Iodine activity detected by RM-065.

d. CRHS Actuation 4

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 25 1 Point The following conditions exist:

RCS temperature is being maintained on Shutdown Cooling.

All controls are in auto.

The operator takes action to decrease RCS temperature.

Which one of the following describes the response of Shutdown Cooling Valves HCV-341 and FCV-326 to this action?

a. HCV-341 throttles open, FCV-326 throttles closed.

b. HCV-341 throttles closed, FCV-326 throttles open.

c. Both valves throttle closed.

d. Both valves throttle open.

QUESTION 26 1 Point With the reactor at power, which one of the following is the most reliable indication that a Pressurizer PORV is leaking?

a. PORV position indicator.

b. Tail pipe temperature,

c. Quench tank pressure.

d. Quench tank temperature.

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,' . QUESTION 27' 1 Point i

1 At which one of the following containment hydrogen concentrations is initiation of Hydrogen Parge required?

i a. 3%

l l 'b. 5%

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! c. 7%

4-j d. 9%

QUESTION 28 .

1 Point I

j If the turbine has failed to trip following a reactor trip, which one of the following explains why the contingency action of tripping the EHC pumps is preferred over closing the MSIVs and MSIV bypass valves?

a. To prevent a possible Turbine overspeed.

b. To retain the use of MS-291 and MS-292.

c. To retain the use-of the atmospheric and condenser steam dump valves.

d. To ensure that the feedwater heater non-return air check valves close.

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SENIOR REACTOR OPERATOR EXAMINATION l

QUESTION 29 1 Point The following conditions exist:

Raw Water pumps AC-10A & 10B are running.

Raw Water pumps AC-10C & 10D are in standby. I

Pump AC-10A trips on an overload fault. l Which one of the following lists the Raw Water pumps expected to be running after this event?

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a. 10C & 10D i l b. 10B & 10D

c. 10D only

d. 10B only QUESTION 30 1 Point l

Section IV of AOP-23, (Reset of Containment Isolation Actuation Signal (CIAS) and Reset of Ventilation Isolation Actuation Signal (VIAS)), step 4; directs the operator to ensure the Hand l

Controller thumbwheels for any open HCV-400'C' series CCW valve j are set fully counter-clockwise. Which one of the following describes why this direction is necessary?

a. Ensures adequate CCW flow to the Containment Cooling l coils when CIAS is actuated.

l i b. Ensures that CCW relief valves do not lift during I resetting of CIAS lockouts.

c. Ensures adequate CCW flow to the Containment Cooling coils when VIAS is actuated.

! d. Ensures that CCW relief valves do not lift during 4 resetting of VIAS lockouts.

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l SENIOR REACTOR OPERATOR EXAMINATION

. QUESTION 31 1 Point A reactor trip has occurred but one CEA failed to insert because its clutch failed to disengage. Which one of the following will prevent the affected CEA from driving to its LEL in response to a Rod Rundown-(RRD)?

a. Loss of power to the 400 Hz inverter.

b. Drive Mode Selector Switch in either of the auto positions (AS, AG).

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c. Drive Mode Selector i. witch in any of the manual !

positions (MS, MG, MI). i

d. Drive Mode Selector Switch in the OFF position.

1 QUESTION 32 1 Point 1 i

The following plant conditions exist:

-+

The plant is at 75% power.

All CEAs are out.

Boron Concentration is 650 ppm !

Core age is 10,000 MWD /T ;

Reactor power is to be increased to'100%. Neglecting the effects ,

of xenon, which one of the following is closest to the boron !

concentration at 100% power?

a. 550 ppm

b. 610 ppm

c. 630 ppm

d. 690 ppm 4

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SENIOR REACTOR OPERATOR EXAMINATION i

QUESTION 33 1 Point Which one of the following describes the expected response of the i CCW Heat Exchanger Bypass Valve (HCV-497) to an SIAS?

a. Goes fully open. l l

b. Goes fully closed. l I

c. Closes to minimum flow (15% open). )

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d. Does not change position. i i

QUESTION 34 1 Point The plant is operating at full power when Pressurizer Pressure Sigma Meter (A/P-102) fails high. Which one of the following is l the expected consequence of this event? )

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a. PPLS logic becomes 2/3, otherwise no actions occur.

b. PPLS will automatically block. j

c. Backup heaters energize, pressure increases, spray I I

valves open, and pressure stabilizes at a higher value.

d. Backup heaters deenergize, pressure decreases, ;

proportional heaters energize, and pressure stabilizes l at a lower value.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 35 1 Point EOP-05-(Uncontrolled Heat Extractior) directs the operators to terminate Containment Spray as soon as containment pressure decreases below 3 psig. Which one of the following is the basis for minimizing the amount of spray following a steam line break?

a. Containment Cooling Fans are not environmentally qualified to operate in a spray environment,

b. Reduce the possibility of Pressurized Thermal Shock.

c. Minimize the amount of hydrogen generation.

d. Allow the start of the containment cooling system.

QUESTION 36 1 Point The following conditions exist:

A steam leak has occurred in Room 19.

The leak was isolated after 30 minutes.

The leak was upstream of the~AFW steam supply check valve.

The leak was isolated by closing YCV-1045B and its warmup valves.

The operability of which one of the following components is LEAST likely to be affected by these events?-

a. FW-6.

b. FW-10.

c. The control room start air compressor,

d. The standby air compressor.

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SENIOR REACTOR OPERATOR EXAMINATION 1

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QUESTION 37 1 Point l A site blackout has occurred and DC loads have been minimized in I accordance with EOP-07. Which one of the following specifies the l amount of time that the control room instrumentation may be i relied upon under these conditions? !

a. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i

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b. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months j

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d. indefinitely I i

1 QUESTION 38 1 Point l

With a normal electrical system lineup, which one of the ;

following describes how Instrument Bus 'C' would be powered l following failure of its Inverter?

a. Power would be lost until manually restored.

b. The supply.would automatically switch to the bypass :

transformer for inverter C. !

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c. The Cross Tie breakers between instrument buses A and -

C would automatically close to supply instrument bus C. ,

d. The Cross Tie breakers between instrument buses 1 and C (

would automatically close to supply instrument bus C. :

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 39 1 Point Which one of the following describes the expected response of the Fire Protection System to a fire in the East Switchgear Room?

a. The first detector actuated causes the ventilation dampers to the affected space to shut. After a 60 second time delay, the halon bank discharge is initiated.

b. After two detectors have actuated in the same space, the dampers for both switchgear rooms shut and the halon bank discharge is initiated.

c. The first detector actuated causes the ventilation dampers in both switchgear rooms to shut. The second detector actuated causes the halon bank to discharge.

d. After two detectors have actuated in the same space, i the ventilation dampers in both switchgear rooms shut.

After a 60 second time delay, the halon bank discharge '

is initiated.

d

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SENIOR REACTOR OPERATOR EXAMINATION

-QUESTION 40 1 Point

'The following conditions exist:

The control room has been evacuated.

A plant cooldown must be conducted from the Alternate Shutdown Panel.

Which one of'the following describes the actions necessary to avoid PPLS during this cooldown?

~

a. PPLS must be blocked as part of the process of evacuating the control room.

b. PPLS will not auto initiate with control at the Alternate Shutdown Panel.

c. All affected equipment must be placed in Pull-to-Lock locally at their breaker panels,

d. The control power fuses of all affected equipment are removed from their breakers cabinets.

QUESTION 41 1 Point With the plant at power, which one of the following conditions requires entry into AOP-12 (Loss of Containment Integrity)?

a. HCV-746A (Pressure Relief) is opened.

b. One of the Personnel Air Lock doors is open.

c. An unexpected decrease in containment pressure has occurred.

d. A containment isolation MOV is inoperable but is locked closed.

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l SENIOR REACTOR OPERATOR EXAMINATION l QUESTION 42 1 Point EOP-06 (Loss of All Feedwater) directs the operators to trip all RCPs. Which one of the following describes the basis for this action?

a. Flow from the RCPs would interfere with bleed and feed cooling.

b. Eliminate the RCPs as a source of heat input to the RCS.

c. Reduce the risk of clad damage due to quenching if a void forms in the vessel.

1 I d. Allov; the stratification of phases so that liquid water remains in the low point (i.e. reactor vessel).

l QUESTION 43 1 Point Which one of the following RCS Activity Reports requires entry into AOP-21 (Reactor Coolant System High Activity)?

i

! a. E-Bar=2.504; RCS gross activity =38.2 pCi/gm.

b. E-Bar=3.301; RCS gross activity =28.1 pCi/gm.

c. E-Bar=2.504; RCS gross activity =28.1 pCi/gm.

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d. E-Bar=3.301; RCS gross activity =38.2 pCi/gm.

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l QUESTION 44 1 Point The following' conditions exist:

No operator actions have been taken.

Core life is near EOL. ,

Power level is 80% and increasing. I 4 Pressurizer-level is following its program level.

-+ '. T,,, is increasing.

-+ Containment pressure and temperature are normal.

Pressurizer pressure is normal.

+ All systems are in their normal mode.

Which one of the following is the most likely cause of these )

conditions? )

a. Partial loss of feedwater heating.

b. Continuous rod withdrawal.

c. Steam leak outside containment.

d. Closure of 1 MSIV.

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1

! QUESTION' 45 1 Point Which one of the following is'the expected response of nuclear i power to a dropped CEA?

a. The effect on power will be negligible but axial peaking factors will increase. !

b. Power will drop approximdtely 5% (depending on the l worth of the CEA) .and remain there. Peaking factors will be unaffected.

c. Power will drop and then return to near the predrop.

level. Radial peaking, factors will increase.

d. Power will drop and then return to near the predrop level. The Dropped Rod light on the drawer will-be extinguished.

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4 UESTION 46 1 Point Which one of the following describes why it is important for the 1 turbine to trip on a reactor trip?

a. To preserve steam generator inventory,

b. To prevent excessive cooldown of the RCS.

c. Tha prevent turbine damage due to high moisture in steam.

d. To, prevent motorizing the generator.

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SENIOR REACTOR OPERATOR EXAMINATION

. QUESTION 47 1 Point The following conditions exist:

The plant is operating at 100% power. j

' Quench tank pressure is being maintained at 7 psig.

' The source of the Quench Tank pressure is that Pressurizer Safety Valve (RC-142) is leaking.

Which one of the following is the temperature expected to be seen on Tailpipe Temperature monitor TIA-136?

a. 150*F

b. 230*F

c. 300*F

d. 640*F OUESTION 48 1 Point Which one of the following parameters is the most effective in discriminating between a Small Break LOCA and a Steam Line Break ,

Inside Containment? )

a. Containment Pressure

b. RCS Pressure

c. Containment Temperature

d. Steam Generator Pressure L !

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION. 49 1 Point l

The following conditions exist: '

.A Large Break LOCA has occurred. l

All safeguards components are operating as required. l

The LO on the primary has announced that he has received LO-LO level alarms on both concentrated boric acid tanks. 1

SIAS actuated 26 minutes ago. )

+- SIRWT level is 52 inches, I Which one of the following actions should be taken at this time? l

a. Place two-charging pumps in pull stop, open LCV-218-2, 1 close LCV-218-3, close HCV's-265, 268 and 258' '

1

b. Place all charging pumps'in' pull stop, close HCV-238, 239, 240, and 249, open HCV-247, 248 and 308. ;

c. Close HCV's-265, 258, and- 268, open HCV-308 or ;

HCV-2988 ;

d. Continue Emergency Boration until at least 30 minutes !

l have elapsed. !

QUESTION 50 1 Point l In a recent plant modification, valve (HCV-438C) CCW Containment ]

Isolation Valve was physically reversed. Which one of the following describes the reason that this modification was .

l necessary?

]

l a. Eliminate the need to cooldown and depressurize in I order to isolate a leaking RCP seal cooler, j- b. To facilitate the replacement of CRDM seals.

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c. The valve was initially installed incorrectly.

d. To reduce the possibility of waterhammer in the CCW system on CIAS.

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l QUESTION 51 1 Point 4 !

1 The'following conditions exist: J I

The plant on Shutdown Cooling.

i + The 'A' Shutdown Cooling Heat Exchanger is not available.

+ Shutdown cooling is provided through the 'B' Shutdown j Cooling Heat Exchanger. I

The plant has been shutdown for 10 days. l

+ RCS temperature is 120*F. l 4 The refueling. cavity is flooded. l j

Containment integrity is not set.

L - Cooling water is lost to the operating shutdown cooling heat exchanger.

]

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4 Which one of following states the amount of time before which containment integrity must be reset.

I i

a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months i

4 b. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months i E i

c. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1

d. There is no foreseeable need to reset containment j integrity.

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$ QUPSTION 52 1 Point i

i

} The reactor is critical at 10 d % power when an inadvertent j Emergency Boration Occurs. RCS boron concentration is raised by 1 10 ppm before it is stopped. Which one of the following describes the effect that this event will have on T/?

j a. It will decrease the most at BOL.

i

b. It will decrease the most at EOL.

4

c. It will decrease the same at EOL as at BOL.

d. It will not be significantly affected.

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s i SENIOR REACTOR OPERATOR EXAMINATION 1

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QUESTION 53 1 Point :

i l The plant is at 1x10 '% with a shutdown in progress. As power ,

l decreases which one of the following would provide positive- l Control Room indication that the Wide Range Nuclear j

- Instrumentation System was in the ' Extended Range'? ;

3 .

Between lod and 10 4% power an approximate two decade a.

I' DECREASE in indicated reactor power would occur and

, the reactor power indication on CB-4 switches from %

{ power to CPS.

t

j. b. Between 10 4 and 10 4 % power an approximate two decade

j. INCREASE in indicated. reactor. power would occur and the 1 red ' Extended Range' light will light on the WR Log i Drawer in the Control Room.

4

c. Between 104 And 104 % power an approximate two decade i INCREASE in indicated reactor-power would occur and the j reactor power indication on CB-4 switches from % power

. to CPS.

j d. Between 10 4 and 10 4 % power an approximate two decade ,

i DECREASE in indicated reactor power would occur and the red ' Extended Range' light will light on the WR Log j Drawer in the Control Room.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 54 1 Point The following plant conditions exist:

+ The plant is operating at full power.

CCW to Detector Well Cooling Containment Isolation valve HCV-467B fails closed.

Which one of the following describes the effect that this will have?

a. Wide range nuclear instrumentation will swap to ex'cended. range.

b. Primary Rod Position Indication must be declared inoperable. I

c. VOPT pretrip.

d. The Detector Well Cooling Fans will trip.

UESTION 55 1 Point Which one of the following describes the consequence of exceeding the limits on RCS activity?

a. Unacceptable Aux Building dose rates.

b. Higher dose rates from fuel handling due to crud j buildup. l

c. Unacceptable offsite doses resulting from a steam generator tube rupture. l 1

d. Dec'reased letdown demineralizer resin life. I l

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SENIOR REACTOR OPERATOR EXAMINATION I

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. QUESTION 56 1 Point l

Initiation of LTOP is described in the Floating Step; Blocking of l PPLS. Which one of the following states when the LTOP mode of l

the PORV is enabled? i

a. Whenever the PORV switches are in the AUTO position, i i

b. Automatically, whenever pressurizer pressure drops !

below 1600 psia. j s

4 c. When PPLS is blocked by the Operator. '

!. i j d. Always. ;

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QUESTION 57 1 Point The following conditions exist:

4

All offsite power has been lost.

The reactor has tripped. )

EDG #1 did not start and 1A3 is not energized. ;

#1 DC bus is deenergized due to a dead short. )

The reason for the EDG failure to start has been corrected. !

Which one of the following must be accomplished before the #1 i Diesel can be started and loaded?

a. Start the diesel locally, at AI-133.

b. Place the diesel back in AUTO.

c. Transfer DC Control Power to its alternate ccurce.

d. Start the diesel manually, remotely.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 58 1 Point The plant is in Mode 1 when the EONA reports that the area monitor in corridor 4 is in alarm and reads 200 mrem /hr. Which one of the following AOPs should be entered as a result of this condition?

a. None I

b. AOP-08 (Fuel Handling Incident) l

c. AOP-09 (High Radioactivity)

d. AOP-21 (RCS High Activity)

QUESTION 59 1 Point The following conditions exist:

The plant is operating at full power.

Stack radiation is increasing from the controlled access area of the auxiliary building.

4 VCT level is lowering.

Which one of the following compartments is the most likely source of the radioactivity?

a. Room 21 1

b. Corridor 26

c. The spent fuel storage pool

d. The letdown heat exchanger room 4

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SENIOR REACTOR OPERATOR EXAMINATION i d

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i QUESTION 60 1 Point i Which one of the following describes the relationship between )

plant conditions and indicated vs. actual pressurizer level?

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a. A steam leak in containment will cause indicated level-l to be higher than actual.

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b. A steam leak in containment will cause indicated level to be lower than actual.

j c. A Steam Generator Tube Rupture will cause indicated level to be higher than actual.

1 i d. A Steam Generator Tube Rupture will cause indicated level to be lower than actual.

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j QUESTION 61 1 Point i

j The following conditions exist:

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+ Fuel handling operations are in progress.

Personnel are working both in Containment and the Aux

, Building.

i + An Aux Building stack monitor alarms.

This initiates VIAS.

j + Area Monitor (RM-087) Spent Fuel Pool Wall alarms. Which j one of the following actions should be taken?

4 l a. Reset and restart containment cooling.

b. Verify containment integrity is set.

c. Evacuate the Aux Building.

1 l d. Trip all Aux Building Exhaust Fans. i l

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! . SENIOR REACTOR OPERATOR EXAMINATION i

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l QUESTION 62 1 Point i Following a loss of offsite power pressurizer level is to be maintained above 45%. Which one of the following is the reason i

that this is necessary?

] a. Assure continued heater operation to preserve

, subcooling. ,

1

, b. Assure adequate pressurizer level for RCP start when j power is restored. j i

c. Assure adequate RCS inventory during any subsequent l cooldown.

! d. Assure adequate inventory for reflux boiling if loss of j j power is prolonged.

I L SUESTION 63~ 1 Point a

! Which one of the following events would require the immediate ,

! termination of any Waste Gas Release in progress? i i

i a. Containment area monitor alarm. j

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b. Stack radiation monitor alarm.

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] c. Failure of a containment gas monitor. !

l' d. Failure of the waste gas flow rate recorder. !

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i SENIOR REACTOR OPERATOR EXAMINATION i 9

j QUESTION 64 1 Point ,

I In the course of conducting a Valve Alignment Verification

, Checklist, the operator discovers that a particular valve is not i in the position called for in the checklist. Which one of the following actions should be taken concerning this valve?

i

a. Reposition the valve to the position specified in the i

s. ' checklist.

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b. Place a Caution Tag on the valve,

c. Inform the Security Shift Supervisor and request an i investigation.

d. Contact the control room'for further instructions.

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! QUESTION 65 1 Point FW-2B has been tagged out of service for both mechanical and electrical work using a group tagout. The Electrical Group

! Foreman has requested a temporary clearance to perform some j testing on the motor. In addition to the Shift Supervisor, who l must approve this temporary clearance?

a. All persons listed on Attachment 1 to the Group Tagout

Sheet.

! b. All persons involved in the testing of the motor. !

i c. The maintenance planners involved with both the j electrical and the mechanical work.

d. The Duty Supervisor.

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i SENIOR REACTOR OPERATOR EXAMINATION i

QUESTION 66 1 Point The RWP Surveillance and ALARA coordinator has determined that an ALARA job briefing is required for performance of a job in the RCA. Which one of the following restrictions apply until all ,

affected workers attend an ALARA Job Briefing?

a. TLDs may not be issued to affected workers.

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b. Workers may not sign the RWP. l

l. c. Workers may not enter the protected area.

d. The Work Order may not be approved.

i p QUESTION 67 1 Point Under which one of the following circumstances may a non-licensed 4 member of the Plant Review Committee (PRC) enter the control room 4

without receiving permission from the Shift Supervisor, LSO, or i Licensed Operator?

i a. At any time.

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b. During Shift Turnover.

c. Under Emergency Conditions.

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d. During a plant outage.

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SENIOR REACTOR OPERATOR EXAMINATION.

QUESTION 60- 1 Point Which one of the following jobs require the use of a Ground Fault Circuit Interrupter (GFIC) ?

a. Rescue of an injured worker from a live electrical circuit.

b. Replacing light bulbs in indoor light fixtures,

c. LUsing a portable grinder on a piece'of stainless steel

-near the SIRWT.

d. Working on a de-energized electrical bus.

-QUESTION' 69 1 Point During an entry into a Confined Space within the RCA, the Confined Space. Entry Permit is maintained at which one of the following places?

a. Confined Space Access Point.

b. RCA Access Control Point.

c. Shift Supervisor's Office.

d. Industrial Safety Coordinator's Office.

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SENIOR REACTOR OPERATOR EXAMINATION l

l QUESTION 70 1 Point l l

l In responding to an oil spill and fire within the RCA, which one of the following serves as the Incident Commander?

a. Any Radiation Protection Tech trained in fire fighting.

b. The Plant Industrial Safety Coordinator.

l l c. The Shift SRO.

d. A Shift RO.

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QUESTION 71 1 Point l

Which one of the following CANNOT be used to determine the j current revision of a procedure? l l

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a. Check with Document Control.

b. Use the On-line CHAMPS index. j

c. Check an official copy at locations listed in SO-G-7.

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d. Check Attachment 1 to S0-G-7.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 72 1 Point Which one of the following conditions requires that EOP-00 be referenced but NOT entered?

a. RPS actuation following a manual reactor shutdown with MP, at 520 F.

b. A reactor trip from 1% power with the generator off-line.

c. A manual reactor trip from full power.

d. RPS actuation while on shutdown cooling with T, at 260*F.

-QUESTION 73 1 Point When using the Gaitronics System,=which one of the following channels is reserved for operations department use?

a. Line 1

b. Line 2 1

c. Line 3 l

d. Line 4 ;

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SENIOR REACTOR OPERATOR EXAMINATION l

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( QUESTION 74 1 Point l Which one of the following'is an example of a proper verbal

command at FCS?

l

a. Trip 'A' Reactor Coolant Pump.

l b. Start Condensate Pump, FW-2 Bravo.

c. Increase level in Steam Generator RC-2 Alpha to 70%

narrow range,

d. Run the setpoint on FCV-910 down to 10 psi.

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QUESTION 75 1 Point 1

I An RO initiated an containment vent but did not remember to log l

it for several hours. Which one of the following is the correct l way for this entry to be made?

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a. Insert the entry such that the sequence of events on i the.page is correct.

b. Make a normal log entry marking it as a late entry in

the time column.

, c. Make a normal log entry and then draw a line to the I

page location where it should have been entered initially.

L d. No action is required. Containment vents do not need l to,be logged.

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SENIOR REACTOR OPERATOR EXAMINATION l l

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QUESTION 76 1 Point i 1

Which one of the following describes the effect of a dropped rod i on DNBR over the hour following the event? (Assume no operator l action is taken.)

a. DNBR improves immediately and then remains constant over the hour due to the decrease in power level.

b. DNBR improves immediately due to power decrease and then deteriorates over the hour due to the effects of xenon.

c. DNBR gets worse immediately due to flux distribution and then improves over the hour due to the effects of fuel temperature.

d. DNBR gets worse immediately due to flux distribution and then gets worse over the hour due to the effects of xenon.

J QUESTION 77 1 Point During a LOCA, the EOPs may direct that all RCPs be secured.

Which one of the following is the basis for taking this action?

a. To retard the rate of RCS depressurization.

b. To prevent possible pump damage from running under voided conditions.

c. To, allow stratification of phases thereby reducing rate of inventory loss.

d. To remove the RCPs as a source of heat input to the RCS.

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1 SENIOR REACTOR OPERATOR EXAMINATION l

QUESTION 78 1 Point Which one of the following conditions would indicate that natural circulation cooling may be losing its effectiveness?

a. Cold leg temperature is 25 F lower than hot leg temperature.

b. Cold leg temperature is 25 F lower.than core exit thermocouple temperature.

c. Hot leg temperature is 25*F lower than core exit j thermocouple temperature. j

d. Hot leg temperature is 25*F lower than pressurizer temperature. !

QUESTION 79 1 Point The following plant conditions exist:

A station blackout has occurred.

4 The diesel engines have both failed to start.

4 Natural circulation cooling has been established.

Assuming no change in conditions, which one of the following courses of action should be taken by the operators?

a. Cooldown at the maximum rate possible to the point at ,

which shutdown cooling entry conditions are satisfied. l l

b. Cooldown at 100 F/hr until shutdown cooling entry conditions are met.

f c. -Establish once through cooling.

d. Maintain RCS at or near no load temperature until some

electrical power is restored.

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l SENIOR REACTOR OPERATOR EXAMIND_ TION l

l QUESTION 80 1 Point I The following conditions exist:

A Loss of All Feedwater occurred. ] '

A large void has formed in the reactor vessel.

Feedwater was then restored. .

Which one of the following describes the effect of starting the !

RCPs under these conditions?

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a. Pressurizer pressure and level will not change. i

b. Pressurizer pressure and level will raise.

c. Pressurizer pressure increase and level will lower.

d. Pressurizer pressure and level will lower.

QUESTION 81 1 Point l l

Which one of the following is the basis for the 2 of 4 SUR trip provided by the Nuclear Instrumentation System (NIS)?

a. It provides protection against an uncontrolled dilution during startup at EOL.

b. It provides protection against a large steam break l accident during startup when steam generator inventory j is the greatest at BOL.

c. It limits power overshoot prior to VOPT actuation on a continuous rod withdrawal during startup.

d. It' limits power overshoot prior to VOPT actuation from a ruptured steam generator during startup.

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i SENIOR REACTOR OPERATOR EXAMINATION

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j. QUESTION 1 Point

] Upon a gradual' loss of instrument air pressure, at which one of l

the following points must the reactor be manually tripped?

{

a. Upon auto closure of the cross _ tie to service air.

b. Upon loss of control of any containment isolation valve.

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t c. At 65 psig. -

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d. At 50 psig. ,

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1 i- QUESTION 83 1 Point i ,

i Which one of the following conditions would prevent the steam )

generator 2A'feedwater regulating valve (FCV-1101) rundown l l, following a reactor / turbine trip?

j a. Instrument air header pressure decreases to 90 psig.

! b. The Spec-200 controller for FCV-1101 has been placed in j AUTO.

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] c. The steam dump valve Auto / Inhibit switch has been

placed in INHIBIT.

i i d. Steam Generator '2A' downcomer level is low.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 84 1 Point During a refueling outage, prior to draining the steam generators, jumpers are placed on the interposing relays on all four RPS channels. Which one of the following describes the effect that these jumpers have on RPS functions?

a. Steam generator low downcomer level reactor trip is disabled. All other trips function normally.

b. All reactor trips, except manual and diverse scram, are disabled,

c. All reactor trips, except NIS generated trips, are disabled.

d. None of the RPS generated reactor trips are affected.

QUESTION 85 1 Point The following plant events occur:

A plant heatup is in progress.

Steam generator pressure is 400 psia.

A large steam leak occurs in the turbine building.

4 The MSIVs do not close.

Both steam generators start to blow down uniformly.

Which one of the following describes the expected response of the AFW system to these events?

a. Both AFW pumps will start when either steam generator level decreases to 32% WR.

b. Oniy the motor driven AFW pump will start when either steam generator level decreases to 32% WR.

c. Only the turbine driven AFW pump will start when both steam generator levels decrease to 32% WR.

d. The AFW system will not respond to these events.

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SENIOR REACTOR OPERATOR EXAMINATION i

l QUESTION 86 1 Point The power range instruments have been set in accordance with the most recent plant calorimetric heat balance calibration (XC-105). When the heat balance was performed, an error existed in the instrument used to measure feed flow. Actual feed flow was higher than measured feed flow. This will affect the degree of conservatism of the power range high power trip set point in which one of the following ways?

a. It is unaffected.

b. It becomes more conservative (trips at a lower power than required).

c. It becomes less conservative (trips at a higher power than required).

d. It depends upon flux shape and core life and cannot be predicted from this data.

QUESTION 87 1 Point j 4

l The following conditions exist:

4 TCV-202 is closed.

HCV-204 is open.

PCV-210 is closed.

Which one of the following is the most likely cause of these

! conditions?

a. High letdown temperature on TE-202.

b. High letdown flow on FIC-212. i l

c. High letdown pressure on PIC-210. l 1

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~ 'd . Low letdown pressure on PIC-242.

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QUESTION 88 1 Point The plant is operating at full power when the Extended Range.

Cutout Switch on Channel 'D' is inadvertently depressed. Which j one of the following is a consequence of this event??

a. There will be no effect on the nuclear instrumentation.

l b. Channel 'D' Power Range reading will decrease by j approximately 10% power.

l l c. Following the next shutdown, Channel 'D' will read l significantly lower than the other channels. I i l

d. Following the next shutdown, Channel 'D' will read )

significantly higher than the other channels. R l

i j QUESTION 89 1 Point ;

l The following conditions exist:

A normal plant cooldown is in progress.

l 4 The PPLS Block switches have been placed in the BLOCK position. ,

RCS pressure is 1650 psia. '

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Pressurizer pressure channel A/P-102 fails high. l l

Which one of the following will occur as a result of this j sequence of events? !

l l l a. .Only the PPLS 31ock 'A' circuit would be' automatically I reset.

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b. Both PPLS circuits would be automatically reset but could be reblocked by operator action.

c. Both PPLS circuits would be automatically reset and ;

could not be reblocked.

d. Both PPLS circuits would remain blocked.

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SENIOR REACTOR OPERATOR EXAMINATION 4

f QUESTION 90 1 Point

[ AFAS has initiated AFW flow to both steam generators. The j pressure in S/G RC-2A then falls to 100 psi less than the 1 pressure in.S/G RC-2B. Which one of the following describes the

' expected response of HCV-1107A and HCV-1107B to this event?

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a. Both will reclose.

i j b. Both will reclose if their control switches are placed j in the RESET position.

c. HCV-1107A will reclose immediately, HCV-1107B will

reclose if its control switch is placed in the RESET

position.

d. HCV-1107B will reclose immediately, HCV-1107A will j reclose if its control switch is placed in the RESET j position.

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j QUESTION 91 1 Point l The following conditions exist:

RCS pressure is 160 psia.

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RCS temperature is 250 F.

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Pressurizer level is 50%.

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Pressure in both S/Gs is 100 psia.

Which one of the following actions must be taken before an RCP i may be started?

f a. No action required, an RCP may be started now. I

b. Increase RCS pressure to 250 psia.

c. Decrease RCS temperature to 200 F.

dd. Decrease S/G pressure to 50 psia.

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i SENIOR REACTOR OPERATOR EXAMINATION j i

QUESTION 92 1 Point The following conditions exist:

4 A plant heatup is in progress. l j

SGLS has been blocked.

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Steam generator pressure has risen to 650 psia.

i 4 A malfunctioning steam dump then causes steam generator pressure.to drop to 490 psia.

! Which one of the following will occur as a result of these ;

events?

a. SGLS will not actuate and no other steam or feed system isolations will occur.

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b. SGLS will not actuate but the MSIVs will close on High Steam Flow. l l

c. SGLS will actuate but only the MSIVs will close. [

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d. SGLS will actuate and the MSIVs and Feedwater Isolation !

valves will close. i 2

i QUESTION 93 1 Point !

I' Refer to EOP-02; Loss Of Offsite Power / Loss of Forced .

i Circulation. Which one of the following goals will be !

j accomplished by performing steps 37 through 42? ;

i a. Restoration of forced circulation. ;

b. Restoration of vital 4160 VAC power.

, c. Preparation to enter Shutdown Cooling i

i d. Restore shutdown margin.

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l SENIOR REACTOR OPERATOR EXAMINATION QUESTION 94 1 Point The following plant conditions exist:

A plant startup is-in progress.

The plant is in MODE 2. 1

- Two Cire Water pumps are running.

Steam _ dumps / Turbine bypass are controlling Tave.

A maintenance error results in both running Circ Water pumps being stopped. !

Which one of the following describes the expected response of the steam dumps and turbine bypass valves? ]

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a. Any open valves will close immediately. I

b. Any open valves will close when condenser vacuum degrades to 19 inches.

c. The steam dumps will close immediately, the turbine bypass valve will close when condenser vacuum degrades to 19 inches. I

d. The turbine bypass valve will close immediately, the ,

steam dumps will close when condenser vacuum degrades !

J to 19 inches.

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SENIOR REACTOR OPERATOR EXAMINATION QUESTION 95 1 Point The following plant conditions exist:

The plant is at 90% during an increase in power.

A CEA in Control Group 4 is discovered to be at 50 inches.

All other Group 4 CEAs are at 120 inches. l

Attempts to move the rod are unsuccessful.

I&C investigates.and reports that the drive motor for that rod has failed and will take 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to repair.

Which one of the following actions is required as a result of these conditions? i

a. The power level increase and operations may continue without restriction.

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b. Power level must be maintained at or below 70% until the CEA is repaired.

c. Power level must be maintained at or below 20% until the CEA is repaired.

d. Verify shutdown margin and be in HOT SHUTDOWN within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . ;

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d SENIOR REACTOR OPERATOR EXAMINATION i-

. QUESTION 96 1 Point j i

j 'Four individuals received the following dose equivalents for the ,

4 year. l

Individual A B C D~

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Eff. Dose Equiv. (TEDE) 4R 8R 3R 5R i

Total Organ Dose Equiv. (TODE) 30R 18R 15R 60R j + Lens Dose Equivalent (LDE) 12R 12R 20R 10R Which one of these individual's dose equivalent is within

' allowable limits per 10CFR20?

j a. A 4 b. B

c. C 1

d. D QUESTION 97 1 Point

! The on-duty Shift Supervisor must be in the control room for which one of the following?

! a. During Diesel Generator Surveillance Tests.

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. b. During Reactor Startup.

i e c. Whenever the STA is absent from the control room.

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d. Whenever the LSO is absent from the control room.

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i SENIOR REACTOR OPERATOR EXAMINATION QUESTION- 98 1 Point-Use of the master annunciator-silence feature in the control room may be directed by which one of the following?

a. LSO or SS.

b. A RO or LSO.

c. STA or SS.

d. Any licensed operator.

QUESTION 19 9 1 Point Which one of the following is a potential consequence of low hydrogen concentration in the VCT?

a. Degraded performance of'the CVCS demineralizers,

b. Increased concentration of radioactive noble gases in the VCT.

c. Increased chlorine concentration in the RCS.

d. Increased oxygen concentration in the RCS. 1 l

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I QUESTION 100 1 Point i

Upon declaration of an Emergency Action Level, who has the ,

primary responsibility for dose assessment prior to activation of i t

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'the TSC and EOF? j

a. Shift Chemist !

b. Shift RP Tech

c. STA ,

d. Dose assessment is not performed prior to TSC/ EOF activation.

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i I REACTOR OPERATOR EXAMINATION i

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} QUESTION 1 1 Point i i

The following events occur:

The plant is at full power. *

Rod Drive Clutches'are being supplied from Instrument Buses

! A and C. !

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Instrument Bus B is deenergized. !

The operator then inadvertently switches a clutch power ,

supply from Instrument Bus A to Instrument Bus B.

' Which one of the following describes the effect that this action .

will have on CEA position?

i a. No effect.

i l b. The shutdown CEAs will drop.

4 c. All CEAs will drop. j l d. RPS will generate a reactor trip on one channel.

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gUESTION 2 1 Point ;

During a startup, the connection between the drive mechanism for a high worth Shutdown CEA and its poison fingers becomes 4 uncoupled. As a result, the drive mechanism withdraws normally j; but all poison fingers associated with it remain fully inserted i in the core. Which one of the following describes a symptom that j the operators will see as a result of this event?

a. The affected rod bottom light will remain on.

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b. The SCEAPIS will show no rod motion for that CEA.

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c. Criticality will occur below the PDIL.

1 i d. The ECP will fail to predict criticality at the correct

CEA position.

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REACTOR OPERATOR EXAMINATION QUESTION 3 1 Point The following conditions exist:

A reactor trip due to a loss of offsite power has occurred.

An inadvertent SGIS occurred after the trip.

MS-291 ( ' A' S/G relief) is open.

MS-292 ('B' S/G relief) will not open.

Pressurizer level is 50%

-Subcooling Margin is 50*F Which one of the following describes the expected natural circulation patterns that will develop under these condition?

a. No natural circulation will develop.

b. It will develop in the A loop, the B loop will be j stagnant.

c. It will develop in the A loop, reflux boiling will develop in the B loop.

d. It will develop normally in both loops.

QUESTION 4 1 Point Which one of the following describes the automatic operation of PCV-1753 (Instrument Air / Service Air Cross Tie)?

a. It closes if service air pressure decreases to 80 psig and reopens when pressure increases to 85 psig.

b. It closes if service air pressure decreases to 80 psig but must be reopened manually.

c. It closes when instrument air pressure decreases to 80 psig and reopens when pressure increases to 85 psig.

d. It closes when instrument air pressure decreases to 80 psig but must be reopened manually.

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REACTOR OPERATOR EXAMINATION QUESTION 5 1 Point The following conditions exist:

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A LOCA has occurred.

All HPSI pumps are injecting.

+ PPLS has been reset.

Containment spray is in operation.

+ Containment pressure is 6 psig. 4

+ !

The current source of water is the containment sump.

+ RAS has not been reset.

Resetting RAS under these conditions will result in which one of the following consequences?

a. Potential damage to the lockout relays.

b. It will be possible to start the LPSI pumps,

c. The containment spray pumps will trip.

d. The water source will swap back to the SIRWT.

QUESTION 6 1 Point The heated junction thermocouples measure percent of level over which one of the following ranges?

a. Top of the vessel (100%) to bottom of the vessel (0%).

b. Top of the core (100%) to bottom of the core (0%).

c. Top of the vessel (100%) to top of the core (0%).

d. Top of the core (100%) to the bottom of the vessel (0%).

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REACTOR OPERATOR EXAMINATION b

T QUESTION 7 1 Point ;

The following conditions exist: t

RCS pressure =500 psia.

Tc=410'F

Th=440'F

CET Average =445'F ,

Which one of the following actions is required concerning the RCPs? ,

a. No action is required.

b. Trip only one RCP.

c. Trip one RCP in each loop.

d. Trip all RCPs.

QUESTION 8 1 Point The following conditions exist:

l + The. reactor has tripped as a result of a loss of offsite-power.

D1 and D2 have energized 3h3 and 1A4. i

. Auxiliary Feed Pumps will not start.

Steam Generator levels are' currently 20%.WR.

All other safety functions are met.

Which one of the following procedures should be implemented first in order to recover the heat removal safety function?'

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a. EOP-02.

b. EOP-06.

c. EOP-20/HR-2 Ad. EOP-20/HR-4 I

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l REACTOR OPERATOR EXAMINATION 1 QUESTION 9 1 Point l

In the event of a total loss of feedwater following a reactor j trip on low steam generator level from full power, which one of the following specifies the minimum time that steam generator inventory can be expected to last?

a. 10 minutes

b. 20 minutes

c. 40 minutes

d. 60 minutes QUEL TION 10 1 Point Following a CIAS, sampling of the containment sump is possible because of which one of the following features?

a. Containment' sump sample lines do not isolate on CIAS.

b. Manually operated sample lines are available to bypass the containment isolation valves,

c. The containment isolation valves can be bypassed and I opened for a limited duration. !

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d. Once the CIAS is reset the sump pump discharge valves l will automatically reopen

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REACTOR OPERATOR EXAMINATION QUESTION 11 1 Point Prior to placing a Gas Decay Tank in service, which one of the following conditions must be verified?

a. Iodine-131 dose equivalent less than 1pCi/gm. I

b. Hydrogen concentration greater than 6%.

c. Oxygen concentration less than 3%.

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d. Nitrogen concentration greater than 20%. q l

QUESTION 12 1 Point The plant is operating at full power when high radiation in the j Auxiliary Building results in a VIAS. Which one of the following describes the response of the Spent Fuel Area Charcoal Filters I (VA-66) to this event?

a. They will not be affected.

b. Their. bypass damper (HCV-712A) will close and their isolation damper (HCV-712B) will open. j

c. Their bypass damper (HCV-712A) will close. Their isolation damper (HCV-712B) will not be affected. ,

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d. Their bypass damper (HCV-712A) will not be affected. I Their isolation damper (HCV-712B) will open. ]

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REACTOR OPERATOR EXAMINATION 1

QUESTION 13 1 Point Which one of the following is an indication of RCS void formation during a natural circulation cooldown?

a. Pressurizer level lowers while operating auxiliary pressurizer spray.

b. The RCS can not be depressurized to SDC entry conditions.

c. RCS subcooling is 25'F.

d. A rapid increase in indicated Reactor Vessel Level on QSPDS.

QUESTION 14 1 Point The following sequence of events occurs:

An SIAS starts all ECCS pumps.

The diesels are running normally.

Offsite power is lost.

None of the RCP breakers open on Load Shed.

Which one of the following describes-the effect that these events will have on the restart of the ECCS pumps as a result of load sequencer operation? ;

a. All ECCS pumps will restart normally,

b. Only the HPSI pumps will restart.

c. All except the !! PSI pumps will restart.

d. No ECCS purps will restart.

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REACTOR OPERATOR EXAMINATION i

l i QUESTION 15 1 Point The following plant conditions exist:

The reactor is in Mode 4.

The pressurizer manway is in place.

Shutdown Cooling is in service. j

- Shutdown Cooling Isolation Valves (HC-347/348) then go fully I closed. !

Which one of the following is the most likely cause of these l events?

a. Either pressurizer pressure channel P-115 or P-118 has i failed low.

b. Pressurizer pressure channel P-118 has failed low.

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c. Either pressurizer pressure channel P-115 or P-118 has l

, lost power.

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d. Power has been lost to pressurizer pressure channel P-118.

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REACTOR OPERATOR EXAMINATION

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i QUESTION 16 1 Point The following plant conditions exist: l The plant.is operating at full power.

The Tave signal from Channel A RRS to the Pressurizer level

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i control system fails upscale. .

The operator immediately takes the A/B switch on panel ~CB-4 to B.

- The Pressurizer level channel selector switch is selected to ,

X. 1 Which one of the following is the expected consequence of these !

events? i

)

a. Actual and indicated pressurizer level will be i unaffected,

b. Indicated pressurizer level will decrease, actual level will be unaffected.

c. Actual pressurizer level will decrease,

d. Actual pressurizer level will increase.

QUESTION 17 1 Point Under which one of the following conditions will the Subcooled Margin Monitors on CB-4 provide invalid results?

a. With one or more RCPs running.

b. With pressurizer pressure below 1700 psia. j

c. With RCS Coolant temperatures below 465*F )

d. With Containment Atmosphere temperature above 180*F.

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i REACTOR' OPERATOR EXAMINATION f I l l . QUESTION 18 1 Point i The following conditions exist: l I + River temperature is 55*F. l

+ The plant is operating at full power. i

Raw Water Pump AC-10A has been inop for the past 3 days.

Containment Spray Pump SI-3B has just been declared inop.

In order to satisfy the requirements of Tech Specs, these i conditions require that the plant be taken to HOT SHUTDOWN within 1

-which one of the following times?

I a. The plant should already be in HOT SHUTDOWN.

4 l l b. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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c. 4M Days.

f 3- d. 7M days.

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REACTOR OPERATOR EXAMINATION QUESTION 19 1 Point The following conditions exist:

The plant is in Cold Shutdown for a refueling outage.

The containment purge system is operating in the low purge rate mode with fan VA-77. <

A high alarm occurs on radiation monitor RM-062 [ stack gas l monitor].

Which one of the following describes the expected response of the containment purge system to these events? l l

a. The inboard containment isolation valves only would l close and the low purge rate fan would trip.

b. The outboard containment isolation valves only would j close and the low purge rate fan would trip

c. Both the inboard and the outboard isolation valves would close and the low purge fan would trip. .

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d. No automatic action would occur since there must be at least 2 out of 3 radiation monitors alarming in order for a containment purge system isolation to occur.

QUESTION 20 1 Point The MSIVs are open when power is lost on DC bus #2. Which one of the following describes the effect that this event will have on j the MSIVs?

a. An SGLS A will be generated and both MSIVs will close.

b. An'SGLS B will be generated and both MSIVs will close.

c. An SGLS B will be generated and MSIV 1042A will close, dd. An SGLS B will be generated but neither MSIV will close.

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REACTOR OPERATOR EXAMINATION QUESTION 21' 1 Point The following conditions exist:

The plant is at 100% power.

All' major breakers are in their normal lineup.

The electrical distribution system is aligned for automatic operation.

The control switca for breaker 1All is then turned to the open (green flag) position.

Which one of the following will occur as a result of these conditions?

a. Breaker 1All will not open unless breaker 1A31 is closed first.

b. A fast transfer will occur with breaker 1A31 closing before breaker 1All opens.

c. A fast transfer will occur with breaker 1All opening before breaker 1A31 closes.

d. Breaker 1All will open but breaker 1A31 will not close.

QUESTION 22 1 Point Diesel generator D1 has received a start signal as a result of a reactor trip. The engine lube oil pump discharge pressure switch has failed in the low pressure position. Which one of the following describes the expected rar fonee of D1 to these events?

a. It will not start.

b. It'will start but will trip after 15 seconds.

c. It will start and then idle at 500 rpm.

d. It will start and then run at 900 rpm.

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) I 1 REACTOR OPERATOR EXAMINATION i I

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_ QUESTION 23 1 Point j l 1 With the plant operating at full power, which one of the l

following diesel generator operability histories is in compliance l

} with the requirements of Tech Spec 2.7 2 (j ) ? )

1 l a. DG-1 is inop from 4/26 to 5/4 l

b. DG-2 is inop from 4/24 to 4/30 and from 5/2 to 5/5

c. DG-1 is inop from 4/20 to 4/25 and DG-2 is inop from 4/26 to 4/30.

d. DG-1 is inop from 4/25 to 4/30 and DG-2 is inop from 4/28 to 5/2. !

I QUESTION 24 1 Point !

Which one of the following conditions will cause the Control Room ;

Ventilation System to automatically switch to the Filtered Air makeup mode of operation?

a. High inlet Chlorine.

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b. Smoke detected in control room exhaust.

c. High Iodine activity detected by RM-065.

d. CRHS Actuation i

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QUESTION 25 1 Point l

1 i The following conditions exist:

RCS temperature is being maintained on Shutdown Cooling.

l 4 All controls are in auto. [

+ The operator takes action to decrease RCS temperature.

Which one of the following describes the response of Shutdown E Cooling Valves HCV-341 and FCV-326 to this action?

t l a. HCV-341 throttles open, FCV-326 throttles closed. ,

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b. HCV-341 throttles closed, FCV-326 throttles open.

c. Both valves throttle closed.

d. Both valves throttle open.

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l QUESTION 26 1 Point With the reactor at power, which one of the following is the most i reliable indication that a Pressurizer PORV is leaking?

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a. PORV position indicator.

! b. Tail pipe temperature.

c. Quench tank pressure.

d. Quench tank temperature.

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QUESTION 27 1 Point At which one of the following containment hydrogen concentrations )

is initiation of Hydrogen Purge required?

a. 3% ,

b. 5%

c. 7%

d. 9%

l QUESTION 28 1 Point If the turbine has failed to trip following a reactor trip, which '

one of the following explains why the contingency action of tripping the EHC pumps is preferred over closing the MSIVs and MSIV bypass valves?

a. To prevent a possible Turbine overspeed.

b. To retain the use of MS-291 and MS-292.

c. To retain the use of the atmospheric and condenser steam dump valves,

d. To ensure that the feedwater heater non-return air check valves close.

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REACTOR OPERATOR EXAMINATION QUESTION 29 1 Point The following conditions exist:

Raw Water pumps-AC-10A'& 10B are running.

Raw Water pumps AC-10C &_10D are in standby.

Pump AC-10A trips-on an overload fault.

Which one of the following lists the Raw Water pumps expected to be running after this event?

a. 10C & 10D

b. 10B & 10D

c. 10D only

d. 10B only QUESTION 30 1 Point Section IV of AOP-23, (Reset of Containment Isolation Actuation Signal (CIAS) and Reset of Ventilation Isolation Actuation Signal' (VIAS)), step 4; directs the operator to ensure the Hand Controller thumbwheels for any open HD.'- 4 0 0 ' C ' series CCW valve are set fully counter-clockwise. Which one of the following describes why this direction is necessary?

a. Ensures adequate CCW flow to the Containment Cooling coils when CIAS is actuated,

b. Ensures that CCW relief valves do not lift during resetting of CIAS lockouts.

c. Ensures adequate CCW flow to the Containment Cooling coils when VIAS is actuated.

d. Ensures that CCW relief valves do not lift during resetting of VIAS lockouts.

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REACTOR OPERATOR EXAMINATION i

QUESTION 31 1 Point 1

I A reactor trip has occurred but one CEA failed to insert because j its clutch failed to disengage. Which one of the following will prevent the affected CEA from driving to its LEL in response to a

, Rod Rundown (RRD)?

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a. Loss of power to the 400 Hz inverter. )

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b. Drive Mode Selector Switch in either of the auto positions (AS, AG).

c. Drive Mode Selector Switch in any of the manual positions (MS, MG, MI).

d. Drive Mode Selector Switch in the OFF position.

QUESTION 32 1 Point The following plant conditions exist: j

The plant is at 75% power.

All CEAs are out. I

Boron Concentration is 650 ppm l

Core age is 10,000 MWD /T Reactor power is to be increased to 100%. Neglecting the effects ;

of xenon, which one of the following is closest to the' boron concentration at 100% power?

a. 550 ppm

b. 610 ppm

c. 630 ppm

d. 690 ppm 4

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l REACTOR OPERATOR EXAMINATION ,

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. QUESTION 33 1 Point 4

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. Which one of the following describes the expected response of the !

, CCW Heat Exchanger Bypass Valve (HCV-497) to an SIAS? ;

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a. Goes fully open.

b. Goes fully closed.

c. Closes to minimum flow (15% open).

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d. Does not change position.

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QUESTION 34 1 Point i The plant is operating at full power when Pressurizer Pressure

. Sigma Meter (A/P-102) fails high. Which one of the following is 1

the expected consequence of this event?

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a. PPLS logic becomes 2/3, otherwise no actions occur. i

.' b. PPLS will automatically block.

c. Backup heaters energize, pressure increases, spray valves open, and pressure stabilizes at a higher value.

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] d. Backup heaters deenergize, pressure decreases,

proportional heaters energize, and pressure stabilizes

at a lower value.

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REACTOR OPERATOR EXAMINATION QUESTION 35 1 Point EOP-05 (Uncontrolled Heat Extraction) directs the operators to terminate Containment Spray as soon as containment pressure decreases below 3 psig. Which one of the following is the basis for minimizing the amount of spray following a steam line break?

a. Containment Cooling Fans are not environmentally qualified.to operate in a spray environment.

b. Reduce the possibility of Pressurized Thermal Shock.

c. Minimize the amount of hydrogen generation.

d. Allow the start of the containment cooling system.

l l QUESTION 36 1 Point l

The following conditions exist:

+ A steam leak has occurred in Room 19.

- The leak was isolated after 30 minutes.

The leak was upstream of the AFW steam supply check valve.

The leak was isolated by closing YCV-1045B and its warmup valves.

The operability of which one of the following components is LEAST likely to be affected by these events?

a. FW-6.

b. FW-10.

c. The control room start air compressor.

d. The standby air compressor.

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REACTOR OPERATOR EXAMINATION i 1

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, QUESTION 37 1 Point ;

l A site blackout has occurred and DC loads have been minimized in accordance with EOP-07. Which one of the following specifies the amount of time that the control room instrumentation may be !

relied upon under these conditions?

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a. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

b. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

! c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1

d. indefinitely

QUESTION 38 1 Point With a normal electrical system lineup, which one of the following describes how Instrument Bus 'C' would be powered following failure of its Inverter?

a. Power would be lost until manually restored.

b. The supply would automatically switch to the. bypass l -transformer for inverter C.

I c. The Cross Tie breakers between instrument buses A and l C would automatically close to supply instrument bus C.

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d. The Cross Tie breakers between instrument buses 1 and C would automatically close to supply instrument bus C.

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l REACTOR OPERATOR EXAMINATION j QUESTION 39 1 Point l Which one of the following describes the expected response of the Fire Protection System to a fire in the East Switchgear Room?

l l a. The first detector actuated causes the ventilation dampers to the affected space to shut. After a 60 ')

second time delay, the halon bank discharge is l initiated. I i

l b. After two detectors have actuated in the same space, )

the dampers for both switchgear rooms shut and the l halon bank discharge is initiated.

c. The first detector actuated causes the ventilation dampers in both switchgear rooms to shut. The second detector actuated causes the halon bank to discharge.

l d. After two detectors have actuated in the same space, l the ventilation dampers in both switchgear rooms shut.

After a 60 second time delay, the halon bank discharge is initiated.

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1 REACTOR OPERATOR EXAMINATION i i

QUESTION 40 1 Point l l

The following conditions exist-

- The control room has been evacuated. l

A plant cooldown must be conducted from the Alternate l Shutdown Panel. l Which one of the following describes the actions necessary to j avoid PPLS-during this cooldown? j l

a. PPLS must be blocked as part of the process of I evacuating the control room. '

b. PPLS will not auto initiate with control at the Alternate Shutdown Panel,

c. All affected equipment must be placed in Pull-to-Lock locally at their breaker panels.

d. The control power fuses of all affected equipment are removed from their breakers cabinets.

QUESTION 41 1 Point With the plant at power, which one of the following conditions requires entry into AOP-12 (Loss of Containment Integrity)?

a. HCV-746A (Pressure Relief) is opened.

b. One of the Personnel Air Lock doors is open.

c. An unexpected decrease in containment pressure has occurred.

d. A containment isolation MOV is inoperable but is locked closed. l l

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l REACTOR OPERATOR EXAMINATION QUESTION 42 1 Point )

l EOP-06 (Loss of All Feedwater) directs the operators to trip all !

RCPs. Which one of the following describes the basis for this 1 action? )

i

a. Flow from the RCPs would interfere with bleed and feed l cooling. l

b. Eliminate the RCPs as a source of heat input to the RCS.

c. Reduce the risk of clad damage due to quenching if a void forms in the vessel. .

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d. Allow the stratification of phases so that liquid water j remains in the low point (i.e. reactor vessel). ;

I OUESTION 43 1 Point Which one of the following RCS Activity Reports requires entry into AOP-21 (Reactor Coolant System High Activity)? ,

a. E-Bar=2.504; RCS gross activity =38.2 pCi/gm.

b. E-Bar=3.301; RCS gross activity =28.1 pCi/gm. ;

c. E-Bar=2.504; RCS gross activity =28.1 pCi/gm.

d. E-Bar=3.301; RCS gross activity =38.2 pCi/gm.

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REACTOR OPERATOR EXAMINATION l QUEGTION 44 1 Point The following conditions exist:

No operator actions have been taken.

Core life is near EOL.

Power level is 80% and increasing.

Pressurizer level is following its program level.

4 T.,, is increasing.

Containment pressure and temperature are normal.

Pre 6surizer pressure is normal.

All systems are in their normal mode, l

Which one of the following is the most likely cause of these conditions?

l i a. Partial loss of feedwater heating,

b. Continuous rod withdrawal.

c. Steam leak outside containment.

'd. Closure of 1 MSIV.

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l l REACTOR OPERATOR EXAMINATION QUESTION 45 1 Point Which one of the following is the expected response of nuclear .

power to a dropped CEA? !

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a. The effect on power will be negligible but axial l peaking factors will increase.

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b. Power will drop approximately 5% (depending on the worth of the CEA) and remain there. Peaking factors will be unaffected.

l l c. Power will drop and then return to near'the predrop l level. Radial peaking factors will increase.

d. Power will drop.and then return to near the predrop l level. The Dropped Rod light on the drawer will be j extinguished.

UESTION 46 1 Point Which one of the following describes why it is important for the turbine to trip on a reactor trip?

a. To preserve steam generator inventory.

b. To prevent excessive cooldown of the RCS.

c. To prevent turbine damage due to high moisture in steam.

d. To. prevent motorizing the generator.

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i REACTOR OPERATOR EXAMINATION i

QUESTION 47 1 Point i The following conditions exist:

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The plant is operating at 100% power.

a 4 -Quench tank pressure is being maintained at 7 psig.

!

The source of the Quench, Tank pressure is that Pressurizer Safety Valve (RC-142) is leaking.

Which one of the following is the temperature expected to be seen j on Tailpipe Temperature monitor TIA-136?

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a. 150*F ,

, b. 230*F i c. 300*F

d. 640 F 3

( 7UESTION 48 1 Point 2

l- Which one of the following parameters is the most effective in

discriminating between a Small Break LOCA and a Steam Line Break j Inside Containment?

a. Containment Pressure

b. RCS Pressure i c. Containment Temperature j d. Steam Generator Pressure i

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REACTOR OPERATOR EXAMINATION

-i QUESTION 49 1 Point The following conditions exist:

-- A Large Break LOCA has occurred.

All safeguards components are operating as required.

The LO on the primary has announced that'he has received-LO-LO level alarms on both concentrated boric acid tanks.

SIAS actuated 26 minutes ago.

SIRWT level is 52 inches, i Which one of the following actions should be taken at this time?

a. Place two charging pumps in pull stop, open LCV-218-2, !

close LCV-218-3, close HCV's-265, 268 and 258.

b. Place all charging pumps in pull stop, close HCV-238, 239, 240, and 249, open HCV-247, 248 and 308.

c. Close HCV's-265, 258, and 268, open HCV-308 or HCV-2988

d. Continue Emergency Boration until at least 30 minutes have elapsed.

QUESTION 50 1 Point In a recent plant modification, valve (HCV- 4 38C) CCW Containment Isolation Valve was physically reversed. Which one of the following describes the reason that this modification was necessary?

a. Eliminate the need to cooldown and depressurize in order to isolate a leaking RCP seal cooler.

b. To facilitate the replacement of CRDM seals.

c. The valve was initially installed incorrectly.

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d. To reduce the possibility of waterhammer in the CCW system on CIAS.

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REACTOR OPERATOR EXAMINATION j

i QUESTION 51 1 Point The following conditions exist: i

- The plant on Shutdown Cooling.

~ The 'A' Shutdown Cooling Heat Exchanger is not available. {

Shutdown cooling is provided through the 'B' Shutdown l l

Cooling Heat Exchanger.

The plant has been shutdown for 10 days.

RCS temperature is 120*F. l

The refueling cavity is flooded. ;

Containment integrity is not set.

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- Cooling water is lost to the operating shutdown cooling heat exchanger.

I Which one of following states the amount of time before which i containment integrity must be reset. )

a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

c. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

d. There is no foreseeable need to reset containment integrity.

l QUESTION 52 1 Point l

The reactor is critical at 10 d % power when an inadvertent Emergency Boration Occurs. RCS boron concentration is raised by 10 ppm before it is stopped. Which one of the following describes the effect that this event will have on T/? i l

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a. It will decrease the most at BOL.

b. It will decrease the most at EOL.

c. It will decrease the same at EOL as at BOL.

d. It will not be significantly affected.

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REACTOR OPERATOR EXAMINATION QUESTION 53 1 Point l 1

The plant is at 1x10% with a shutdown in progress. As power I i decreases which one of the following would provide positive Control Room indication that the Wide Range Nuclear i Instrumentation System was in the ' Extended Range'?

a. Between 10" and 104% power an approximate two decade DECREASE in indicated reactor power would occur and

, the-reactor power indication on CB-4 switches from %

l power to CPS. :

i b. Between 10 d and 104 % power an approximate two decade

INCREASE in indicated reactor power would occur and the red ' Extended Range' light will light on the WR Log {

l Drawer in the Control Room.

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c. Between 10 4 and 10*% power an approximate two decade ,

INCREASE in indicated reactor power would occur and the l i reactor power indication on CB-4 switches from % power to CPS.

d. Between 104 and 10 4% power an approximate two decade l DECREASE in indicated reactor power would occur and the ,

red ' Extended Range' light will light on the WR Log j Drawer in the Control Room. i 1

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i REACTOR OPERATOR EXAMINATION QUESTION 54 1 Point The following plant-conditions exist: !

The plant'is operating at full power. .

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+ CCW to Detector Well Cooling Containment Isolation valve j HCV-467B fails closed. l Which one of the following describes the effect-that this will l have? ;

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a. Wide range nuclear instrumentation will swap to !

extended range. l

b. Primary Rod Position Indication must be declared !

inoperable.

c. VOPT pretrip. l l

d. The Detector Well Cooling Fans will trip. I i

UESTION 55 1 Point Which one of the following describes the consequence of exceeding the limits on RCS activity?

a. Unacceptable Aux Building dose rates.

b. Higher dose rates from fuel handling due to crud buildup.

c. Unacceptable offsite doses resulting from a steam ;

generator tube rupture.

d. Decreased letdown demineralizer resin lif'e.

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REACTOR OPERATOR EXAMINATION d

QUESTION 56 1 Point l Initiation.of LTOP is described in the Floating Step; Blocking of l PPLS. Which one of the following states when the LTOP mode of l 1 the PORV is enabled? )

l i a. Whenever the PORV switches are in the AUTO position.

.b. Automatically, whenever pressurizer' pressure drops 4

below 1600 psia.

i.

. c. When PPLS is blocked by the Operator.

3.

d. Always.

! QUESTION 57 1 Point t

l -The following conditions exist:

.

All offsite power has been lost.

The reactor has tripped.

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EDG #1 did not start and 1A3 is not energized.

* #1 DC bus is deenergized due to a dead short. 1 l

4 The reason for the EDG failure to start has been corrected. '

j Which one of the following must be accomplished before the #1

} Diesel can be started and loaded?

i j a. Start the diesel locally, at AI-133.

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b. Place the diesel back in AUTO.

{ c. Transfer DC Control Power to its alternate source.

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j d. Start the diesel manually, remotely.

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REACTOR OPERATOR EXAMINATION I

QUESTION 58 1 Point The plant is in Mode l'when the EONA reports that the area monitor in corridor 4 is in alarm and reads 200 mrem /hr. Which one of the following AOPs should be entered as a result of this condition?

a. None

b. AOP-08 (Fuel Handling Incident)

c. AOP-09 (High Radioactivity)

d. AOP 21 (RCS High Activity)

QUESTION 59 1 Point f The following conditions exist:

l

- The plant is operating at full power.

! - Stack radiation is increasing from the controlled access area of the auxiliary building.

+ VCT level is lowering.

l Which one of the following compartments is the most.likely source l of the radioactivity?

a. Room 21 i b. Corridor 26 l

l c. The. spent fuel storage pool l d. The letdown heat exchanger room. i 1

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REACTOR OPERATOR EXAMINATION I

a QUESTION 60 1 Point Which one of the following describes the relationship between plant conditions and indicated vs. actual pressurizer level?

a. A steam leak in containment will cause indicated level to be higher than actual.

b. A steam leak in containment will cause indicated level !

to be lower than actual. I

c. A Steam Generator Tube Rupture will cause indicated level to be higher than actual.

I d. A Steam Generator Tube Rupture will cause indicated level to be lower than actual.

QUESTION 61 1 Point The following conditions exist: ;

Fuel handling operations are in progress.

'a Personnel are working both in Containment and the Aux Building.

An Aux Building stack monitor alarms.

This initiates VIAS.

Area Monitor (RM-087) Spent Fuel Pool Wall alarms. Which 4

one of the following actions should be taken?

a. Reset and rectart containment cooling.

b. Verify containment integrity is set.

c. Evacuate the Aux Building.

d. Trip all Aux Building Exhaust Fans.

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I REACTOR OPERATOR EXAMINATION !

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QUESTION 62 1 Point Following a loss of offsite power pressurizer level is to be maintained above 45%. Which one of the following is the reason i that this is necessary? l l 1 i a. Assure continued heater operation to preserve j i subcooling. ;

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b. Assure adequate pressurizer level for RCP start when power is restored.

d

! c. Assure adequate RCS inventory during any subsequent i cooldown.

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d. Assure adequate inventory for reflux boiling if loss of power is prolonged.

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OUESTION 63 1 Point l Which one of the following events would require the immediate. ,

4 termination of any Waste Gas Release in progress?

e j -a. Containment area monitor alarm.

l b. Stack radiation monitor alarm.

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c. Failure of.a containment gas monitor.

d. Failure of the waste gas flow rate recorder.

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I REACTOR OPERATOR EXAMINATION 1

l QUESTION 64 1 Point In the course of conducting a Valve Alignment Verification Checklist, the operator discovers that a particular valve is not i in the position called for in the checklist. Which one of the l following actions should be taken concerning this valve? l l

a. Reposition the valve to the position specified in the l checklist. )

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b. Place a Caution Tag on the valve.

c. Inform the Security Shift Supervisor and request an '

investigation.

d. Contact the control room for further instructions.

I QUESTION 65 1 Point I

FW-2B has been tagged out of service for both mechanical and j electrical work using a group tagout. The Electrical Group Foreman has requested a temporary clearance to perform some testing on the motor. In addition to the Shift Supervisor, who must approve this temporary clearance?

a. All persons listed on Attachment 1 to the Group Tagout Sheet.

b. All persons involved in the testing of the motor.

c. The maintenance planners involved with both the electrical and the mechanical work.

d. The Duty Supervisor.

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i s i REACTOR OPERATOR EXAMINATION QUESTION 66 1 Point l

The RWP Surveillance and ALARA coordinator has determined that an :

ALARA job briefing is required for performance of a job in the RCA. Which one of the following restrictions apply until all affected workers attend an ALARA Job Briefing? I

a. TLDs may not be issued to affected workers.

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b. Workers may not sign the RWP.

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c. Workers may not enter the protected area.

d. The Work Order may not be approved. ;

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QUESTION 67' 1 Point Under which one of the following circumstances may a non-licensed member of the Plant Review Committee (PRC) enter the control room without receiving permission from the Shift Supervisor, LSO, or Licensed Operator?

a. At any time.

b. During Shift Turnover.

c. Under Emergency Conditions.

d. During a plant outage. ;

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REACTOR OPERATOR EXAMINATION QUESTION 68 l' Point Which one of the following jobs require the use of a Ground Fault Circuit Interrupter (GFIC) ?

a. Rescue of an injured worker from a live electrical circuit.

b. Replacing light bulbs in indoor light fixtures.

c. Using a portable grinder on a piece of stainless steel near the SIRWT.

d. Working on a de-energized electrical bus.

QUESTION 69 1 Point During an entry into a Confined Space within the RCA, the Confined Space Entry Permit is maintained at which one of the following places?

a. Confined Space Access Point.

b. RCA Access Control Point.

c. -Shift Supervisor's Office.

d. Industrial Safety Coordinator's Office.

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I REACTOR OPERATOR EXAMINATION l QUESTION 70 1 Point j In responding to an oil spill and fire within the RCA, which one of the following serves as the Incident Commander?

a. Any Radiation Protection Tech trained in fire fighting.

b. The Plant Industrial Safety Coordinator.

c. The Shift SRO. j

d. A Shift RO.

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l QUESTION 71 1 Point Which one of the following CANNOT be used to determine the current revision of a procedure?

a. Check with Document Control.

b. Use the On-line CHAMPS index.

c. Check an official copy at locations listed in S0-G-7.

d. Check Attachment 1 to S0-G-7.

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REACTOR OPERATOR EXAMINATION 4

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QUESTION 72 1 Point

', Which one of the following conditions requires that EOP-00 be )

referenced but NOT entered?

] a. RPS actuation following a manual reactor shutdown with l T, at 520 F.

-b. A reactor trip from 1% power with the generator off-

] line.

j c. A manual reactor trip from full power.

d. RPS actuation while on shutdown cooling with T, at

} 260*F.

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[ QUESTION 73 1 Point i When using the Gaitronics System, which one of the following j channels is reserved for operations. department use? l t 1 e

a. Line 1 l

b. Line 2

c. Line 3 l.- d. Line 4 f

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, REACTOR OPERATOR EXAMINATION l l

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i l l QUESTION 74 1 Point j Which one of the following is an example of a proper verbal

, command at FCS?

i l a. Trip 'A' Reactor Coolant Pump.

j b. Start Condensate Pump, FW-2 Bravo.

c. Increase level in Steam Generator RC-2 Alpha to 70%

narrow range.

j d. Run the setpoint on FCV-910 down to 10 psi.

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QUESTION 75 1 Point i An RO initiated an containment vent but did not remember to log ;

it for several hours. Which one of the following is the correct !

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way for this entry to be made?

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a. Insert the entry such that the sequence of events on the page is correct.

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) b. Make a normal log entry marking it as a late entry in

the time column.

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, c. Make a normal log entry and then draw a line to the

! page location where it should have been entered initially.

d. No action is required. Containment vents do not need to.be logged. ;

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REACTOR OPERATOR EXAMINATION QUESTION 76 1 Point With no RCPs running and Tc less than 385'F, Limiting Condition for Operation 2.1.1 prohibits starting an RCP unless:

Pressurizer steam volume is >53% OR

AT between Tc and S/G is <30 F.

Which one of the following describes the potential consequence of failure to obey this requirement?

a. Decrease in Shutdown Margin due to introduction of cold water into the core.

b. Pressurizer insurge and possible solid pressurizer due to pump discharge pressure.

c. Pressure transient caused by thermal expansion from reverse heat transfer from a hot steam generator.

d. Pressure transient due to thermal expansion due to RCP heat.

QUESTION 77 1 Point In the event of a CIAS, RCP Seal Leakage flow will be directed to which one of the following destinations?

a. None, seal flow is isolated.

b. VCT.

c. RCDT.

d. Containment Sump.

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REACTOR OPERATOR EXAMINATION i

QUESTION 78 1 Point

. Assuming that the initiating signal is still present, which one of.the following letdown isolations can be temporarily overridden by holding the Letdown Isolation Valve (TCV-202) switch in the OPEN position?

! a. High Temperature.

b. High Flow

c. CIAS -

d. - None - a letdown isolation cannot be overridden in this manner. i

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j j QUESTION 79 1 Point The following plant conditions exist:

A normal plant cooldown is in progress.

The PPLS Block switches have been placed in the BLOCK position. i L

RCS pressure is 1650 psia, j

- Pressurizer. heaters are inadvertently energized and pressure ;

rises to 1850 psia. l 4

The heaters are then deenergized and RCS pressure is rapidly l l reduced to 1570 psia.

j Which one of the following undesired auto actions is most likely j to occur as a result of this sequence of events? ;

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a. No undesired auto actions should occur.

b. SIAS but not CIAS.

c. CIAS but not SIAS. i dd . Both SIAS and CIAS. j l.

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REACTOR OPERATOR EXAMINATION QUESTION 80 1 Point The following conditions exist:

The plant is operating at full power.

. Pressurizer Pressure instrument A/PT-102 has failed. '

+

Ten minutes later Pressurizer Pressure instrument B/PT-102 fails.

Tech Specs requires which one of the following actions to be taken?

a. Both channels must be placed in trip.

-b. Both channels must be bypassed.

c. One channel must be bypassed, the other channel must be placed in trip.

d. Commence a reactor shutdown within one hour.

7ESTION 81 1 Point The plant is operating at 50% power with the Channel A High Power trip unit in bypass. Which one.of the following describes the effect of deenergizing another High Power Trip-Unit?

a. The reactor will trip.

b. The reactor will trip only if the deenergized drawer is Channel C.

c. No-reactor trip will occur but trip logic becomes 2 of 2.

d. No reactor trip will occur but trip logic becomes 1 of 2.

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REACTOR OPERATOR EXAMINATION i r

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, QUESTION 82 1 Point l

The containment cooler inlet and outlet valves (HCV-400A/C, I 401A/C, 402A/C, and 403A/C) will' automatically close following a l CIAS if which one-of the following conditions exists?

a. CCW pump discharge pressure is less than 60 psig.

l b. A containment pressure high signal [CPHS) is not present.

j c. The fan associated with the containment cooling unit fails to start within 50 seconds.

l

d. There is low CCW flow from the containment cooler.

l QUESTION 83 1 Point-The plant is operating at full power when Steam Generator Level

! Detector (LT-903) fails high. Which one of the following describes the expected response of the affected steam generator's Feed Reg Valve?

a. It will shift to manual control and remain as is.

b. It will shift to manual control and close and remain I closed until reopened by the operator.

l c. It will shift to manual control, close and then shift back to auto and re-open to its original position.

p d. It will remain in auto but go and remain fully closed.

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j REACTOR OPERATOR EXAMINATION 4

i QUESTION 84 1 Point i

Prior to starting AFW pump (FW-6) from CB-10, 11 you first perform which one of the following actions?

a. Verify HCV-1384 is open. i

b. Verify no EFWST level alarms.

c. Verify its recire valve is open.

?

j. d. Verify switch FW/43 is in OFF.

i 4

j QUESTION 85 1 Point

. The following plant conditions exist:

l + A steam leak upstream of the MSIV on the A S/G has occurred. ,

j

Pressure in the A S/G is 480 psia. l 4

Level in the A S/G is 30%(WR). '

Pressure in the B S/G is 575 psia.

4 + Level in the B S/G is 60%(WR).

I

The MSIVs are closed.

Which one of the following is the current status of the AFW system?

a. AFW should be feeding the A S/G.

j b. AFW should be feeding the B S/G.

c. AFW should be feeding both S/Gs.

d. AFW should not have initiated yet.

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REACTOR OPERATOR EXAMINATION QUESTION 86 1 Point A. routine surveillance reveals that Containment Wide Range Radiation Monitor RM-91B is not operable. Assuming no repairs are made, which one of the following actions is reonired by Tech Specs?

1

a. No action required since the minimum number of channels are still operable.

b. Provide an alternative method of monitoring within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and submit a report to the NRC.

c. Be in HOT SHUTDOWN within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d. Repair within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

9UESTION 87 1 Point The plant'is in HOT SHUTDOWN having just shutdown due to an unidentified RCS leak of 1.3 gpm. Assuming the source of the leakage is still not identified, which one of the following actions is required by Tech Specs?

a. Remain in HOT SHUTDOWN or lower until the leak is identified.

b. Be in COLD SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. Repair the leak or be in COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. Identify the leek within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or go to COLD SHUTDOWN.

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REACTOR OPERATOR EXAMINATION QUESTION 88 1 Point The 120 VAC power supply to AI-196 has been lost. Which one of the following describes-the method or ability to bypass Diverse 1 Scram System Channel A?

a .- Place the TEST / BYPASS switch on AI-196 to the bypass position.

b. Place the TEST / BYPASS switches on both panels to the bypass position.

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c. It is not possible to bypass-a single sensor channel on loss of 120 VAC power.

d. The DSS channel will automatically bypass on loss of 120 VAC power.

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QUESTION 89 1 Point During full power operation a full length regulating CEA is discovered to be misaligned from the others in its group by 15 inches. Which one of the following describes the action that is required as a result of this condition?

l

a. Open the rod drop test switch for the affected rod !

within one hour. i

b. The CEA must be declared inoperable if not restored to proper alignment within one hour.

c. A power reduction to less than 70% must be started j wit'hin seven hours. Use only boration for necessary reactivity changes.

d. The reactor be placed in HOT SHUTDOWN within seven hours.

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REACTOR' OPERATOR EXAMINATION QUESTION 90 1 Point Which one of the following instrument errors would cause the reactor power calculated by XC-105 to be less than actual reactor power?

a. Turbine first stage pressure indicating lower than actual.

b. Feedwater temperature indicating higher than actual.

c. Feedwater flow indicating higher than actual,

d. Main generator electrical output indicating less than actual.

QUESTION 91 1 Point In the Vital Auxiliaries portion of EOP-20; Functional Recovery, operators are instructed to maintain S/G 1evel above 85%. Which one of the following is the reason that this is desirable?

a. Prevents dryout of AFW nozzles

b. Reduces thermal stress on the feed ring.

c. Minimizes the chance of feed ring damage due to waterhammer.

d. Provides an inventory ' cushion' that allows delays in restoring electric feed pumps.

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REACTOR OPERATOR EXAMINATION i

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QUESTION 92' 1 Point The plant is operating at steady state full power when level in one steam generator is seen to decrease. Which one of the following is a possible cause of this decrease?

a. Electrical control power has been lost to the affected S/G's Feed Reg Valve.

b. Control Air pressure has been lost to the affected S/G's Feed Reg Valve.

c. Steam pressure has failed low on the affected side.

d. Steam flow has failed high on the affected side.

QUESTION 93 1 Point The following conditions exist:

A plant startup is in progress.

The plant is at no-load Tm.

All CEAs are fully inserted.

Battery charger #3 has just been declared inop.

All other battery chargers are operable.

Which one of the following describes the restrictions that Tech Specs places upon operations as a result of these conditions?

a. A plant cooldown to less than 300 F must commence immediately.

b. The plant may remain in its present condition but the reactor may not be taken critical.

c. The plant must be taken to COLD SHUTDOWN within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

dd. The startup may continue without restriction.

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REACTOR OPERATOR EXAMINATION l

QUESTION 94 1 Point i

The. plant is operating normally at power when a transformer failure causes the voltage on bus 1A3 to decrease to 3000 VAC.

Which one of the following describes the response of the OPLS?

a. No OPLS will be generated.

b. OPLS will start Diesel Generator #1.

c. OPLS will start Diesel Generator #2.

d. OPLS will start both Diesel Generators.

. QUESTION 95 1 Point Which one of the following is capable of providing a source of l fire main water if the fire system pumps are inoperable?

a. Screen wash pumps.

b. Seal water pumps,

c. Raw water pumps.

d. Circulating water pumps. j l ?

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l REACTOR OPERATOR EXAMINATION QUESTION 96 1 Point Fire protection coverage for the containment charcoal filters has

, recently changed. Which one of the following describes the l current fire protection scheme for these filters?

a. The containment spray system is physically available but is not to be used to combat fires.

i

! b. The containment spray system has been physically l connected to the' filters and is now to be used to l combat fires. 1 l l

c. The containment spray system has been physically )

disconnected from the filters.

d. The containment spray connection has been replaced by a dedicated CO2 system.

JESTION 97 1 Point !

I The plant is at 10% power when the Main Turbine trips. No reactor trip occurs. Which one of the following valves, if it failed closed, is a possible cause of this event?

a. The #1 Turbine Stop Valve.

b. The #1 Turbine Control Valve.

c. The #2 Turbine Control Valve.

d. MSIV HCV-1042A.

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REACTOR OPERATOR EXAMINATION QUESTION 98 1 Point The following plant conditions exist:

The plant is at 70% during an increase in power.

A rod in Group 4 is discovered to be at 102 inches.

All other Group 4 rods at 120 inches.

Attempts to move the rod are unsuccessful.

I&C investigates and_ reports that all power _to that rod is l deenergized. !

l Which one of.the following actions is required as a result of I these conditions?

I

a. The power level increase and operations may continue without restriction.

b. Power operation may. continue for another 7 EFPD.

c. Power level must be maintained at or below 70% until the rod is repaired.

d. Verify shutdown margin and be in HOT SHUTDOWN within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

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i REACTOR OPERATOR EXAMINATION QUESTION 99 1 Point All Raw Water flow has been lost to the CCW heat exchangers.

Once the plant is tripped, which one of the'following. describes the best RCS cooling / pressure control mode allowed under these circumstances?

a. Natural circulation since all RCPs must be secured with no Raw Water cooling available.

b. Forced convection with 4 RCPs since RCP cooling will be unaffected.

c. Forced convection with 1 RCP per loop since CCW can usually support the operation of 2 RCPs for'a significant period.

d. Once through cooling due to loss or ability to enter shutdown cooling.

QUESTION 100 1 Point i The following plant conditions exist:

- An Alert has been declared.

No release of radioactive material has occurred.

A Plant Evacuation has been declared.

Under these conditions, all non-essential personnel should follow which one of the following evacuation routes?

a. To the North Omaha Power Station via the Normal Security Access Point.

b. To'the North Omaha Power Station via the North Security Access Point.

c. To the Admin Building via the Normal Security Access 4 Point.

d. To the Admin Building via the South Security Access Point.

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h ADMINISTRATIVE TOPICS SRO(I)

CANDIDATE:

EXAMINER:

CHIEF EXAMINER:

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QUESTION A.1-a:

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l I During a reactor startup, what action should be taken if criticality occurs outside of the i 1% I reactivity band specified on the ECP form?

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1 No reference should be required to answer question i

l ANSWER:

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Conservative action is required to put the reactor in a stable and subcritical condition and shall include CEA insertion or reactor trip.

Plant reference: OP-2A .

l' K/A: 010001 A2.07 (3.6/4.2) l The operator's response was:

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, QUESTION A.1-b:

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, During a reactor startup, what parameters are recorded as critical data? .

4 i i r 3 ~ l No reference should be required to answer question l

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4 ANSWER: '

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j Rod positions, Boron concentration, RCS average temperature, and time, f.

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.I Plam reference: TDB-V.I.b, Estimated Critical Conditions Worksheet ,

\ l j K/A: 194001 A1.06 (3.4/3.4) ,

i 4 .1 The operator's response was: I i

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J QUESTION A.1-c: I l,

1 i What is the maximum number of individuals you are allowed to escort within vital areas of the plant? -

No reference should be required to answer question l

'1 ANSWER:

A maximum of five individuals may be escorted within the vital area.

Plant reference: GET Training manual ,

i K/A: 194001 Kl.05 (3.1/3.4) j i

The operator's response was:

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QUESTION A.1-d:

I Where are bomb threat call checklists located? l 1

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l No reference should be required to answer question l l

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1 ANSWER:

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. Bomb threat checklists are located on the back of each plant phone directory.

Plant reference: GET training manual l K/A: 194001 Kl.05 (3.1/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

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QUESTION A.2-a:

When can a temporary modification be installed prior to PRC approval?

No reference should be required to answer question 4

l ANSHIR: '

In cases of emergency when approved by the shift supervisor.

l Plant reference: SO-O-25 l

K/A: 194001 A1.10 (2.9/3.9) ]

The operator's response was:

i SATISFACTORY UNSATISFACTORY l

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QUESTION A.2-b:

Where are drawings located which provide details on installed temporary modifications?

l No reference should be required to answer question ANSWER: l I

Temporary modifications are reCected on the control room and OCC drawings. j l

l Plant reference: SO-O-25 1

'I K/A: 194001 Al.07 (2.5/3.2) l l The operator's response was: .

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4 QUESI' ION A.4-a:

i A less of Coolant Accident has occurred, the CET's indicate 1700 o F, and the containment pressure l

. indicates 55 psig. What emergency classification would be appropriate for this condition? J

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1 j The candidate will require the use of EPIP-OSC-1 to answer this question. l 4

5 ANSWER:

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I This event should be classified as a General Emergency.

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Plant reference: EPIP-OSC-1, EAL 1.20 4 I

NRC K/A 1

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K/A: 194001 Al.16 . (3.1/4.4) !

l The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

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QUESTION A.4-b:

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What meteorological tower parameters are used to determine the appropriate atmospheric stability class

. for dose assessment?

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I No reference should be required to answer question l 4 ,

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ANSWER

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] Venical temperature difference is used to determine the appropriate stability class. i

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2 1 Plant reference: EPIP-EOF-6 1

l K/A: 194001 A1.16 (3.1/4.4) l i.

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August 23, 1996 1:19pm

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ADMINISTRATIVE TOPICS RO l i

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CHIEF EXAMINER:

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QUESTION A.1-a:

What action should be taken by a RO if a parameter is found to be out of specifications on the OP-ST-SHIFT-0001 log?

No reference should be required to answer question ANSWER:

It should be reported immediately to the Shift Supervisor or LSO.

Plant reference: S0-0-1 K/A 194001 A1.06 3.4/3.4 The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

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2 I QUESTION A.1-b: j i

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j. Ilow do you conduct a channel check of pressurizer pressure channels A/B/C/DP-102?

No reference should be required to answer question 4

i l ANSWER:

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1 j A Channel Check is conducted by comparing the channels with one another and with other channels j measuring pressurizer pressure.

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Plant reference: Tech Spec definition of " Channel Check."

! I j K/A: 194001 A1.06 (3.4/3.4) j The operator's response was:

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QUESTION A.1-c:

If you were scheduled to work from 1500 - 2300 on a Friday, and stayed over two additional hours to help with a surveillance test, when is the soonest time you could return to work a 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift on Saturday?

No reference should be required to answer question ANSWER:

Saturday at 0900. [Must have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months off between shifts.]

Plant reference: 50-0-1 K/A: 194001 A1.03 (2.5/3.4)

The operator's response was:

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QUESTION A.1-d:

When are you allowed to leave the "at the controls" area of the control room with fuel in the reactor? '

?

No reference should be required to answer question i P

ANSWER:

i When another licensed individual (RO or SRO) is in the "at the controls" area. ,

Plant reference 50-0-1 !

K/A: 194001 A1.03 (2.5/3.4) !

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I QUESTION A.2-a:

1 What is the difference between " Independent Verification" and " Concurrent Verification" as applied to tagouts?

l No reference should be required to answer question !

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ANSWER

l Independent verification is checking that components are in the required, safe configuration. This checking is done separate from the initial tagging or repositioning of components.

! Concurrent Verification is the act of checking the position or condition of a component concurrent with l the activities establishing the component's position or condition. ;

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l Plant reference:SO-G-20A !

K/A: 194001 Kl.02 (3.7/4.1) l I

The operator's response was:

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QUESTION A.2-b:

k Who can install and remove Hold Order Tags?

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No reference should be required to answer question e

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ll Only System / Electric Operations personnel are allowed to install or remove Hold Order Tags? i 1

i Plant reference: SO-G-20A K/A: 194001 Kl.02 (3.7/4.1) t The operator's response was:

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f QUESTION A.4-a: ,

l Who is called to the control room to make required notifications during an E-plan event?

No reference should be required to answer question ANSWER:

The control room communicator. l Plant reference: EPIP-OSC-1 K/A: 194001 A1.16 (3.1/4.4)

The operator's response was: l SATISFACTORY UNSATISFACTORY l i

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l QUESTION A.4-b: !

What are the four Emergency Classifications in order of severity, from lowest to highest? i l

No reference should be required to answer question j i

ANSWER:

Notice of Unusual Event, Alert, Site Area Emergency, General Emergency.

Plant reference: EPIP-OSC-1 K/A: 194001 A1.16 (3.1/4.4) l The operator's response was:

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EXAMINER: .

CHIEF EXAMINER:

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s QUESTION A.1-a:

What positions are expected to attend the pre-shift briefings?

No reference should be required to answer question ANSWER:

The licensed operators (SS, LSO and RO's), the STA, the NLO's, the shift chemist and the shift HP.

Plant reference: S0-0-1 K/A: 194001 A1.03 (2.5/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

QUESTION A.1-b: l i

Who may grant an exemption for attendance of operations department personnel at the pre-shift briefing?

No reference should be required to answer question ANSWER:

The SS or the LSO.

Plant reference: SO 4-1 K/A: 195001 A1.12 (3.1/4.1)

I The operator's response was:

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' l QUESTION A.1-c:

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How many wide range nuclear instrunwntation channels must be operable to conduct refueling i operations in the core?

i i r f- i

No reference should be required to answer question, however the candidate may wish to check Tech ;

! Specs. ,

!- l i- ANSWER: !

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t Two wide (source) range channels are required to be operable. >

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j Plant reference: Tech Spec 2.8 (4) ;

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! I a K/A: SG034 K5 (2.6/3.5) i 1

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QUESTION A.1-d:

What fuel assembly parameters are used to determine where a fuel assembly may be placed La the spent fuel pool?

No reference should be required to answer question ANSWER:

Initial enrichment and burnup.

Plant reference: Tech Spec 2.8 (11), figure 2-10 K/A: 000034 A2.03 (3.3/4.0) -

The operator's response was:

SATISFACTORY UNSATISFACTORY e

COMMENTS:

QUESTION A.2-a:

- An RPS channel failed an I&C surveillance test. It was then determined that the instrument used to perform the test was out of tolerance. Must the RPS channel be declared inoperable until another test can be conducted?

! ~ No reference should be required to answer question ANSWER:

No. [Immediate action to determine the status of the channel should be taken however.]

Plant reference: S0-0-1 K/A: 194001 Al.15 (3.1/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

QUESTION A.2-b:

It is discovered that a required surveillance test on a piece of equipment was not conducted as scheduled. it is past the " drop dead" date for the equipment. Is the equipment inoperable?

No reference should be required to answer question ,

ANSWER:

The equipment must be declared inoperable as required by Tech Specs.

Plant reference: S0-0-1 K/A : 194001 A1.15 (3.1/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

._._ _ .__ _ . . _ . _ _ . _ _ . _ _ - . . . _ _ . _ . ~ . . . . _ . _ . _ . . . . . . _ _ _ . . ..m.._____

l l

+

QUESTION A.4-a: .

I The plant has experienced a Total Loss of All Feedwater from full power operation. Attempts to ,

i restore main and/or AFW flow have been unsuccessful. As a result, both Steam Generator levels >

dropped below 20% WR and once-through-cooling has been established. After the PORV was opened, Pressurizer pressure dropped to 1000 psia and RCS temperature is 545 o F. What emergency classification would be appropriate for this condition? !

i 4

{ The candidate will require the use of EPIP-OSC-1 to answer this question. !

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! ANSWER:

l 5

l l

l A Site Area Emergency should be declared. 1 I i I

Plant reference: EPIP-OSC-1, EAL 2.8 _

J 1 F I I

j K/A: 194001 A1.16 (3.1/4.4) i

i The operator's response was:

SATISFACTORY UNSATISFACTORY I I 1

i i

COMMENTS:

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.- . - - . . . . . . _ .. ..~. - .. - ._.- . - - . ~ _ - - . _ - . . _ ~ . - . _

t t

i QUESTION A.4-h:

{

i What will be used as the source of meteorological data for dose assessment if the meteorological tower i is unavailable? I i

No reference should be required to answer question i

l ANSWER: I i

j The national weather service will be contacted for data. ;

. i l

Plant reference: EPIP-EOF-6 j 1

K/A: 194001 Al.16 (3.1/4.4) ;

1 I

The operator's response was:

i SATISFACTORY UNSATISFACTORY ;

1 1

COMMENTS:

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_ _ _ . _ . _ _ .. __ _ _ _ _ . . . . _ .- _ . _ _ . ~..- _. . .m- - -.

4

User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340 *

Directory:

4

Description:

j

August 23, 1996 4

- - - - pm 1:19 TTTTT RRRR M M *

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T R RMMM *

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List of Attachments - Fort Calhoun RO Exam l I

AOP Time to Boil Data l EOP Attachment 2.

Steam Tables Tech Spec 2.7 Tech Spec 2.10.2 l Tech Spec 2.1.4 Tech Spec 2-21 incl Table 2-10 Tech Spec 2.7 with interpretation 92-13 Tech Spec 2.4 Tech Data Book II; Pages 23 & 34 i i l

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User name: TRM (26) Queue: AR1/HPIIISI-AR1-340

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File name: Server: HPIIISI-340 * '

Directory: *

Description:

August 23, 1996 1:20pm *

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l. _ _ . - -

Fort Calhoun List of Required Attachments - SRO Exam AOP Time to Boil Data EOP-02, Steps 37 - 42 EOP Attachment 2.

Steam Tables Tech Spec 2.10.2 and PDIL Curve Tech Spec 2.4 Tech Spec 2.1.1 Tech Spec 2.7 with interpretation 92-13 Tech Data Book II; Pages 23 & 34 l

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._ - ~ ~ . . _-. - . - _ . - . - ... - - - . .

4 i f 4

Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Protection System

)

1 System (s) : AFW and Fire Protection ,

l 1

location (s) : Room 81 j i

Approximate Time: 20 minutes Actual Time :

l Reference (s): (1) AOP - 30 , R4 4

(2) NRC K/A 000061, K4.01 (RO3.9/SRO4.2)

)

(3) NRC K/A 000061, Al.04 (RO3.9/SRO3.9)

Verify current reference revisions match those listed above 3

t I

\

l Operator's Name: SS # :

l All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

j The operator's performance was evaluated as: SATISFACTORY l UNSATISFACTORY '

1 4

Evaluator's Signature : Date :

W Reason, if unsatisfactory :

l 1

Operator's review .: Date:

] Tools & Equipment : None i

a A

.. .-. -. . - . - . - _ . - . - . . . - . . - . - . . ~ - - . . -

}

?

ia

Revision: 0 October 24,1995 4

I Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i

q JPM No: JPM - NEW j Emergency Fill of the EFWST Using the Fire Protection System i

i.

?,

Safety Considerations: THIS JPM WILL BE PERFORMED AS A STATIC JPM IN THE PLANT.

i

'l

! Comments : The fire hose and adapter should not be moved from the fire brigade assembly area. I i l i

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A b a

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. . . - _ = . . . _ .- , .. .- - - - -- . .. . . . - - , -

Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE l

JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Protection System Initiating Cue:

A station blackout has occurred. AFW is being supplied to the steam generators from FW-10. FW-54 and Blair water are unavailable. The LSO directs you to prepare to replenish the EFWST using the fire system. START CRITICAL STEP

ELEMENT STANDARD

1. Close FW-652 ROOM 81 FW452 is closed

2. Close FW-654 FW-654 is closed l

l '

3. Obtain a 21/2 inch male-to male FIRE BRIGADE ASSEMBLY AREA l adapter and a 100 foot section of 21/2 Locate adapter and fire hose inch fire hose.

4. Connect male-to-male adapter to the Adapter connected male end of fire hose. NOTE: Have operator connect adapter to hose end and then disconnect and put back into place.

! 5. Connect both ends of the fire hose to ROOM 81

! the following valves: Both ends connected l a) FW-1275 l b) FP456

6. Open FW-1275 FW-1275 is open

7. Open FW-653 FW-653 is open CUE: EFWST level is 32 inches. AFW flow is 150 gpm l l l 8. Determine time for EFWST to empty EFWST will empty in slightly less than I hour

[ NOTE: This is first question.

CUE: EFWST will empty

9. Open FP-456 FP-456 is open

Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

! JPM No: JPM - NEW

Emergency Fill of the EFWST Using the Fire Protection System '

- r 1

10. Ensure FP-1B starts Verify pump start with control room

, FP-1B has started ,

a CUE: EFWST level is 91%

11. Close FP-456 FP-456 is closed l

STOP

, QUESTION: JPM-new-RO-1, SRO-1 i I l How long will it take for the EFWST to empty if the level is 32 inches and the AFW flow is 150 gpm?

i i

ANSMTR

)

The EFWST will empty in slightly less than one hour.

a i I

l i

REFERENCE:

4 s

1 AOP-30, Attachment A NRC K/A 000061 K4.01 (3.9/4.2) j

I l The operator's response was: j i

. SATISFACTORY UNSATISFACTORY l

1 COMMENTS:

i This question is answered as JPM step 8.

i 4

i d

t

t Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW l Emergency Fill of the EFWST Using the Fire Protection System l l 1

1 l

l QUESTION: JPM-new-RO-2 l l <

l !

What will cause the Diesel driven Fire Pump to start when FP-456 is cpened?

]

1 i

t ANSWER:

The pump will start on low fire header pressure.

l-l

REFERENCE:

)

l Fire Protection STM NRC K/A 000086 K4.02 (3.0/3.4)

The operator's response was:

i l

l l SATISFACTORY UNSATISFACTORY j

! l l

COMMENTS: ,

l i

i I

i L

___ ____--._m____._ _ . . _ . _ - _ - . . __. -. _.-..__ ..

1 1

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l Revision: 0 j October 24,1995 1

Fort Calhoun Station - Operations training i

! JOB PERFORMANCE MEASURE 1

t l JPM No: JPM - NEW l Emergency Fill of the EFWST Using the Fire Protection System ,

I l

QUESTION: JPM-new-SRO-2 l

i What is the basis for the technical specification on required EFWST Inventory?

l ANSWER:

l The inventory is sufficient to remove decay heat for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ..

REFERENCE:

t i

! Tech Spec ;

NRC K/A 000061 K4.02 (3.9/4.2) ,

i The operator's response was:

l SATISFACTORY UNSATISFACTORY l i

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COMMENTS:

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User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 * '

i

-* File.name: JPM010CC.ORG Server: HPIIISI-340 *

*- Directory: * '

j *

Description:

August 23, 1996 1 1:05pm

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Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - RCA RCA Entry and Exit Topic (s) : RCA Entry and Exit Imcation (s) : RCA Access Control Approximate Time: 10 minutes Actual Time :

Reference (s): (1) GET - Radiation Worker Training (2) NRC K/A 194001, Kl.03 (RO2.8/SRO3.4)

(3) NRC K/A 194001, Kl.04 (RO3.3/SRO3.5)

Verify current reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

, Reason, if unsatisfactory :

Operator's review : Date:

Toole & Equipment : None j

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - RCA RCA Entry and Exit Safety Considerations: This JPM requires entry into the RCA, Comments :

i i

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

i

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Revision: 0 l October 25,1995 i i -

Fort Calhoun Station - Operations training !

JOB PERFORMANCE MEASURE 1~ !

JPM No: JPM - RCA RCA Entry and Exit

i w

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j initiating Cue:

i An entry into the RCA is required as part of the operating exam. START !

f CRITICAL l STEP * - ELEMENT STANDARD l Review RWP. Read RWP Check survey maps Check survey maps for radiological conditions in areas to be entered .

Obtain dosimetry Verify TLD attached to security badge. Obtain ALNOR Sign in on appropriate RWP Insert ALNOR into reader, enter PID and I RWP number. ;

Inform RP Personnel about the nature of Tell RP at access control where you are going your entry and what you will be doing. -)

Enter RCA RCA entered j j

Comply with all posting within RCA No violation of posted requirements i Monitor for personnel contamination prior Monitor for contamination using PCM-1 or f to exiting frisker. l 1

Sign out of RCA Insert ALNOR in reader, Enter PID number. l I

confirm dose and place ALNOR in charging rack.

Revision: 0 )

October 25,1995 l

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - RCA RCA Entry and Exit i

QUESTION: JPM-RCA-RO/SRO-1 ;

1 What action should be taken if your ALNOR alarms? I l

1 1

ANSWER: I l

l Go to low dose waiting area and contact Radiation Protection..

REFERENCE:

GET Radiation Worker Training -

NRC K/A 194001 Kl.03 (2.8/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY l COMMENTS: 1 1

I

. . - - . . - - . - . - . - . _ - ~ . . - - . . . .. - -- - -. . .- . -

l i

! Revision: 0 i October 25,1995 l

Fort Calhoun Station - Operations training ,

JOB PERFORMANCE MEASURE JPM No: JPM - RCA RCA Entry and Exit i

l l

QUESTION: JPM-RCA-RO/SRO-2 i

What action should be taken if the PCM-1 alarms when frisking?

l ANSWER:

Back out of the frisking booth and follow directions on the LED readout. If the PCM-1 alarms a second time, note the contaminated area and contact Radiation Protection.

i I

I

REFERENCE:

I l

GET Radiation Worker Training j NRC K/A 194001 Kl.04 (3.3/3.5) l l

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

l l

- _- - . . - . .. . ..-. -. .~. . - - - - . - . - . . ~. . . . . - . -

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4

User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: JPM214.ORG Server: HPIIISI-340 *

Directory: *

Description:

August 23, 1996

- - - - pm 1:05

- h**w*******************

TTTTT RRRR M M *

T R R MM MM

l T R RMMM *

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l Revision: 5 October 24,1995 l

i Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room i

System (s) : Abnormal / Emergency Procedures I

Location (s) : Simulator Approximate Time: 7 minutes Actual Time :

Reference (s): (1) EOP@

(2) NRC K/A 000001, K4.05 (RO3.9/SRO3.9) .

(3) NRC K/A 000001, A4.02 (RO4.1/SRO3.9)

Verify current reference revisions match those listed above Operator's Name: SS # :

l All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY j UNSATISFACTORY J l

l Evaluator's Signature : Date :

1 Reason, if unsatisfactory :

l l

Operator's review : Date:_

Tools & Equipment : None Safety Considerations: Non:

Comments : Simalator Dynamic JPM

.. __. - _ . . . . ._ _ . _ . . ._. __..._._.._.__._.___..._._..._._._.._m . . _ _ _ . _ . .

M l

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s Revision: $

{ October 24,1995 f 4

4 ,

, Fort Calhoun Station - Operations training 1

JOB PERFORMANCE MEASURE 1

2 s JPM No: JPM - 008 ASP - R j Emergency Boration from the Control Room i

W 4

Override HCV-268 closed .ind LCV-218 2 Open.

l [VLV CVC24 0%[ [VLV CVC20100%] :

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Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room Initiating Cue:

A reactor trip has occurred and while performing EOP-00, you find that three regulating rods stuck out. You are the LO, the LSO directs you to immediately commence emergency boration. START CRITICAL STEP

ELEMENT STANDARD

1. Close FCV-269X and 269Y. CB-4 Control switches for FCV-269X & Y in CLOSED AND GREEN lights lit.

2. Open all of the following valves: a. Control switch for HCV-268 to OPEN until

a. HCV-268 only RED light lit.

b. HCV-265 b. Control switch for HCV-265 to OPEN until

c. HCV-258 only RED light lit.

c. Control switch for HCV-258 to OPEN until only RED light lit.

NOTE TO EVALUATOR: HCV-268 will not op:n. There will be no flow path from Boric Acid Pumps.

3. Start ALL of the following pumps: a. Control switches to start a.Both Boric Acid Pumps CB- 1,2,3

b. ALL charging pumps b. Control switches to start AND RED lights lit 7 4. Close LCV-218-2 Control Switch to CLOSE AND GREEN light lit.

NOTE TO EVALUATOR : LCV-218-2 will not close. VCf pressure will prevent gravity flow from Boric Acid Tanks.

5. Locally OPEN HCV-268 or iocally Direct EONA (simulator operator) to manua7 CLOSE LCV-218-2. open HCV-268 OR to manually close LCV-218-2. (It is acceptable to direct either or both actions.)

l l

l Revision: 5 October 24,1995 i

i Fort Calhoun Station - Operatiot s training l JOB PERFORMANCE MEASURE l

JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room NOTE TO EVALUATOR: Either one of these actions will be sufficient to establish Boric Acid flow to the RCS. Wait approximately 3 minutes end give the followirg cue.

l CUE: EONA reports that the first requested valve is in the proper position. (HCV-268 is open OR LCV- ,

218-2 is closed.)

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Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE ,

JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room 4

CRITICAL STEP

ELEMENT STANDARD

6. Ensure ALL of the following valves are CB - 1,2,3 closed: a. GREEN light lit.

a. LCV-218-3 l

b. HCV-257 CB-4

c. HCV-264 b. GREEN light lit !

c. GREEN light lit. l Termination Criteria : Borated water is being injected into the RCS.

l 2

i

\

Revision: 5 Octoter 24,1095 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room QUESTION: JPM-008 ASP-RO-l What would happen to RCS cold leg temperature if emergency boration was initiated with the reactor at power?

ANSWER: ,

b Cold leg temperature would lower,

REFERENCE:

NRC K/A 000024 EKl.01 (3.4/3.8) )

I The operator's response was:

I SATISFACTORY UNSATISFACTORY COMMENTS:

l I

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room i

5 l

, QUESTION: JPM-008 ASP- RO-2

)

What is a condition, other than control rods failing to insert, that would require emergency i 4 boration? !

l 1

1 4

l ANSWER: 1 1 :

1 i

],

Any one of the following: j 1

1

Uncontrolled plant cooldown. l l *CEAs inserted below PDIL Emergency Boration limits. '

Positive reactivity anomaly with all CEAs inserted.

]

Control room evacuation.

4 4

REFERENCE:

. AOP-03 R2 NRC K/A 000024 EK3.01 (4.1/4.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY l

COMMENTS:

\

l l

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room QUESTION: JPM-008 ASP-SRO-1 Why is it necessary to close LCV-218-2 when using only the gravity feed valves?

ANSWER:

VCT pressure may hold a check valve closed in the gravity feed header..

REFERENCE:

P&lD E-210-121 NRC K/A 000024 EK3.02 (4.2/4.4)

The operator's response was: )

i SATISFACTORY ' UNSATISFACTORY j i

l COMMENTS:

1 I

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Contml Room QUESTION: JPM-008 ASP-SRO-2 An emergency boration lineup is automatically initiated by an SIAS. What accident, in particular, is this designed to mitigate?

ANSWER:

A steam line break (or excessive heat removal event).

REFERENCE:

NRC K/A 000040 EKl.05 (4.1/4.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

Y t

i L

f Initiating Cue: t t

A reactor trip has occurred and while performing EOP-00, you find that three regulating i rods stuck out. You are the LO, the LSO directs you to immediately commence ,

emergency boration. START i, I

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t i

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)

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- - - - I

User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: JPM778.ORG Server: HPIIISI-340

3

Directory:

l

Description:

1

August 23, 1996 1:06pm *

- - - - i e

l

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]

T R R MM MM *

T R RMMM *

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j Revision: 1 1 October 24,1995 i Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW i Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps.

l 1

i System (s) : Abnormal / Emergency Procedures location (s) : Room 69 Approximate Time: 15 minutes Actual Time :

Reference (s): (1) AOP - 11, R4

(2) NRC K/A 000008 , K3.01 (RO3.4/SRO3.5)

(3) NRC K/A 000008, A2.01 (RO3.3/SRO3.6) I I

)

Verify current reference revisions match those listed above i

e

Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

2 The operator's performance was evaluated as: SATISFACTORY a

UNSATISFACTORY l

1 l l i Evaluator's Signature : Date : 1 1

Reason, if unsatisfactory :

l l

Operator's review : Date:

Tools & Equipment : None l l !

Safety Considerations: This JPM requires entry into the RCA. )

4 1

- ..-.- . . - - . - . _ _ . . - . . . ~ . . . - . . _ . - . . . - . - . _ - _ - . . . -. . . _ . . -

Revision: 1 October 24,1995 i Fort Calhoun Station - Operations training l JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps.

Comments : This JPM will be conducted as a static JPM in the plant..

I t

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I Revision: 1 l October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps. l l

initiating Cue:

1 The reactor has been tripped from 100% power. A total loss of all CCW has occured. Containment temperature is 118 degrees F. You are directed to establish Raw Water backup to the Containment Coolers as directed by the LSO. VA-3A and VA-3B are in service. START CRITICAL '

STEP

ELEMENT STANDARD CUE: Establish Raw Water flow to VA-1A. The control room reports that the HCV-400B/D switch is in the closed position.

Unlock and release the handjacks from: Room 69

a. IICV-400E Remove locking device and place the valves in

b. HCV-400F the open position ,

Open the following valves: a. 4-Way manual control valve in open '

a. IA-HCV-400E-TV position.

b. IA-HCV-400F-TV b 4-Way manual control valve in open position.

CUE: Establish Raw Water flow to VA-18. The control room reports that the HCV-401B/D switch is in the closed position.

Unlock and release the handjacks from: Room 69

a. HCV-401E Remove locking device and place the valves in

b. HCV-401F the open position Open the following valves: a. 4-Way manual control valve in open j

a. IA-HCV-401E-TV position. l

b. IA-HCV-401F-TV b. 4-Way manual control valve in open )

position. ;

Termination Criteria: Raw Water backup cooling has been established to VA-1 A and VA-1B.

1 i

J

Revision: 1 October 24,1995 Fon Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps.

QUESTION: JPM-0010RW- RO-1 Why is the CCW surge tank pressurized with nitrogen?

I 1

ANSWER:

To provide adequate NPSH for operation of the CCW pumps..

l

REFERENCE:

CCW STM j NRC K/A 000008 A2.01 (3.3/3.6)

The operator's response was:

, SATISFACTORY UNSATISFACTORY l

l COMMENTS:

i l

I 4

i t

r

Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps.

QUESTION: JPM-0010RW-RO-2 What conditions are necessary for HCV-438A/B/C/D to automatically close?

ANSWER:

CIAS and CCW pressure less than 60 psig. [For the required length of time.]

REFERENCE:

CCW STM NRC K/A 000026 EK3.02 (3.6/3.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

l I

J

' Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps.

QUESTION: JPM-0010RW-SRO-1 What would be the consequences of opening a Raw Water Interface valve during normal operation?

ANSWER:

A loss of CCW inventory through the Raw Water system to the river.

REFERENCE:

CCW STM NRC K/A 000008 A2.02 (3.2/3.5)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

1 Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW Loss of Component Cooling Water requiring Raw Water Backup to the HPSI pumps. l l

QUESTION: JPM-0010RW-SRO-2 i

llow could the CCW system be cooled fallowing a loss of Raw Water? l I

ANSWER: j l

By supplying Fire Protection water to the CCW/RW heat exchangers using fire hoses. l I

l

REFERENCE:

i I

I AOP-18, Attachment 2 NRC K/A 000076 A2.01 (3.5/3.7)

The operator's response was:

SATISFACTORY UNSATISFACTORY !

COMMENTS:

i

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

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Initiating Cue: i 1

l i The reactor has been tripped from 100% power. A total loss of all CCW has occured. i Contairunent temperature is 118 degrees F. You are directed to establish Raw Water i backup to the Containment Coolers as directed by the LSO. VA-3A and VA-3B are in i

! service. START i l

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User name:

TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340 *

Directory: *

Description:

j-

August 23, 1996 1:06pm *

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Revision: 6 ,

October 24,1995 '

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIR %T 1

i System (s) : CVCS !

l 1

Location (s) : Simulator 1 1

Approximate Time: 13 minutes Actual Time : j i

Reference (s): (1) OI-CH-4-6.10 R16 (2) TS-2.2, 2.3 (2) NRC K/A 000004 , Kl.01 (RO3.4/SRO3.9)

(3) NRC K/A 000004 , A2.06 (RO3.8/SRO3.9)

Verify current reference revisions match those listed above l

Operator's Name: SS # : '

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY I

Evaluator's Signature : Date :

Reason, if unsatisfactory :

)

Operator's review : Date:

Tools & Equipment : None Safety Considerations:

Comments : This JPM will normally be performed as a dynamic JPM on the Simulator. It is not intended to add all of the water and boric acid necessary per the calculation, but rather to prove the 4

Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIRWT ability to conduct the ERF procedure and then prove ability to operate the CVCS system to make up to the SIRWT.

Open CH-152 [ LOA CVC24100% ]

1 Revision: 6 October 24,1995 l

l Fort Calhoun Station - Operations training l JOB PERFORMANCE MEASURE JPM No: JPM - 0138 I Operate CVCS to makeup to the SIR %T 1

l l

Initiating Cue: I I

The plant is operating at 100% power. SI tanks have just been filled. The SIRWT level is 186 inches. I The latest SIRWT boron was 1910. ppm. Both Boric Acid tanks are at a concentration of 3%. The Shift Supervisor directs you, the LO, that the SIRWT be blended up to 190". Use CH-4A. Boric Acid pump. All prerequisites are met. START CRITICAL STEP

ELEMENT STANDARD

1. DETERMINE flow rate for Refer to OI-ERFCS-1, procedure 31 OR hand concentration of 1910 ppm. calculation.

2. Venfy WD-250 is locked open CUE: EONA reports WD-250 is locked open.

3. Ensure FCV-269 is in close. CB-4 l FCV-269 switch is in close and GREEN light is lit.

~

4. Place HC-269 in manual HC-269 switch in manual

5. Ensure Boric Acid recirculation valves Both switches in close position and GREEN are in closed: lights lit.

HCV-264 HCV-257

6. Station EONA to watch SIRWT vents. CUE: EONA is watching SIRWT vents

7. Place LCV-218-3 in close. CB - 1,2 .3 LCV-218-3 switch in closed and GREEN light lit.

8. Open CH-152 CUE: EONA has opened CH-152

9. Start Boric Acid pump CB-4 Place control switch for CH-4A to start and observe RED light lit.

10. Place FCV-269Y and FCV-269X in Switches in open and RED lights lit.

open.

11. Set the makeup flow controllers to the CB-4 desired flow rates to obtain proper boron Adjust flow control on FRC-269Y and FRC-concentration. 269X to obtain desired flow rates.

Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIRWT i

l CRITICAL STEP * ]

ELEMENT STANDARD 1

12. Obtain sample of blend l Direct Chemist (simulator operator) to obtain blend sample. 1 to SIRWT. j CUE: Simulator Operator will report concentration at blender

[ XBATBLDR]. ;

CUE: When concentration at blender is reported to be 1910

ppm or greater then provide cue that SIRWT level is 190".

13. Stop blend to SIRWT FCV-269Y switch in close. GREEN light lit.

14. Stop Boric Acid pump CH-4 A switch in after stop and GREEN light lit.

j 15. Flush piping with Leave FCV-269X open after FCV-269Y has been closed.

j demineralized water.

CUE: Flush of piping is complete.

16. Close FCV-269X CB-4 !

FCV-269X switch in close and GREEN light lit. !

j 17a. Close CH-152 CUE: EONA has closed CH-152.

17b. Place HC-269 in Switch placed in DILUTE DILUTE Place LCV-218-3 in AUTO LCV-218-3 switch in auto. GREEN and AMBER lights lit.

Termination Critena: SIRWT level is returned to normal.

Revision: 6 October 24,1995 Fon Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIR %T QUESTION: jpm-0138-RO-1 When securing the line-up for filling the SIRWT, how do you ensure that the makeup header to the VCT is not at the SIRWT baron concentration?

ANSWER:

By securing the boric acid make-up and flushing the header to the SIRWT with deminerelized l water. !

REFERENCE:

OI-CH-4 K/A 000004 A2.06 (4.2/4.3)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138

. Operate CVCS to makeup to the SIRWT I

f

. QUESTION: jpm-0138-RO-2 What type of device is used to measure SIRWT level as indicated on Al-30A and Al-30B7 I

! ANSWER:

Pneumatic bubblers are used to measure SIRWT level.

1 l

l

REFERENCE:

ECCS STM page 6

NRC K/A 000006 K4.16 (2.6/3.0) 4 The operator's response was

i

SATISFACTORY UNFATISFACTORY

COMMENTS: '

1 s

A 1

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1

N Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIRWT QUESTION: jpm-0138-SRO-1 What is the basis for the SIRWT boron concentration required by Tech Specs? l l

ANSWIR: 1 I

i I

To provide adequate shutdown margin following an accident. I l

l l

REFERENCE:

1 Tech Spec 2.3 Basis NP.C K/A 000006 K6.01 (3.4/3.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS: I

e - ,Ls/

Revision: 6 October 24,1995 Fort Calhoun Station Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIRWT QUESTION: jpm-0138-SRO-2 Why is simultaneous llot and Cold leg injection initiated 81/2 hours after a big LOCA?

ANSWER:

To prevent Boric Acid precipitation in the core.

REFERENCE:

ECCS STM NRC K/A 0000011 EK3.13 (3.8/4.2)

The operator's response was: ,

SATISFACTORY UNSATISFACTORY COMMENTS:

Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to the SIRMT l

linitiating Cue:

The plant is operating at 100% power. Si tanks have just been filled. The SIRWT level is 186 inches. The latest SIRWT boron was 1910. ppm. Both Boric Acid tanks are at a concentration of 3%. The Shift Supervisor directs you, the LO, that the SIRWT be blended up to 190". Use CH-4A, Boric Acid pump. All prerequisites are met.

START i

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User name:

_ TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340 *

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Description:

August 23, 1996 1:07pm *

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1 Revision: 10 l

October 24,1995 Fort Calhoun Station - Operations training

j. JOB PERFORMANCE MEASURE 1

JPM No: JPM - 0214 Shift Inservice Air Compressors System (s) : Compressed Air Location (s) : Room 19 Approximate Time: 12 minutes Actual Time :

Reference (s): (1) OI-CA-1 6.3 R21 (2) NRC K/A 000078 , 6001 (RO2.9/SRO3.1)

Verify current reference revisions match those listed above i

! Operator's Name: SS # :

i

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in l this JPM.

l The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date : l Reason, if unsatisfactory :

l l

Operator's review : Date: ,

i l

l Tools & Equipment : None Safety Considerations: None.

Comments: This JPM will be performed as a static JPM in the plant

l l

1 Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214 Shift inservice Air Compressors Initiating Cue:

The air compressor lineup is as follows: CA-1 A running, CA-IC in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for weekly rotation as follows: CA-lC running, CA-1B in standby, and CA-I A in Control room stan. START CRITICAL ~

STEP

ELEMENT STANDARD

1. Designate Air Compressor to be CA-lC to be started.

started.

2. Verify the following on the Air a. Check oil sight glass.

Compressor to be staned (CA-lC)

a. Oil level greater than 1/3 of b. Cooling water pressure PI-1942C sight glass.

a. Cooling water pressure greater than 30 psig.

3. Place load transfer switch on CA-lC to Switch to OFF position.

OFF.

4. Place the Air Compressor control Switch to CS position.

switch for CA-lC to CS.

5. Verify proper oil pressure (CA-lC) Oil pressure stabilizes in 15-20 seconds CUE: Oil pressure is 34 psig.

6. Verify cooling water flow Observe cooling water flow through bullseye.

FI-1955C

7. Place CA-lC load transfer switch in Select position 1 or 2 position 1 or 2.

NOTE: Either position is acceptable.

8. Verify CA-lC for proper operation. CUE:

Oil Pressure = 32 psig Intercooler Air Pressure = 30 psig Discharge Air Pressure = 102 psig Jacket Water Pressure = 43 psig Jacket Water Temperature = 102*F CUE: CA-IC is functioning properly.

9. Place CA-1 A load transfer switch in Switch to OFF position.

OFF. CUE: CA-lC is holding the air load.

10. Place CA-1 A control switch to OFF Switch to OFF position.

I Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214 Shift Inservice Air Compressors

11. Place the CA-1 A CR Control Switch Notify Control Room to place the Control to After Stop. Switch for CA-1A in After Stop CUE: Control Room reports that switch is in After Stop Position.

CRITICAL STEP

ELEMENT STANDARD

12. Place the local control switch for CA- Switch in CS position.

I A to CS.

13. Verify CA-1 A cooling water flow is Observe bullseye for NO flow. I stopped. CUE: There is no flow.

14. Place load transfer switch for CA-1 A Select position 1 or 2.

in position 1 or 2.

NOTE: either position is acceptable.

15. Place CA-1B local control selector Switch to STBY position switch in STCY.

16. Place tf *:A-1B CR Control Switch Request Control Room to place CA-1B control I to After Start, switch to After Start.

Cue: Control room reports switch is in After Start. l

17. Ensure ALL load transfer switches are All load transfer switches are in position 1 or '

in 1 or 2. 2.

NOTE: Either position is acceptable. l Termination Criteria: CA-lC is running, CA-1B is in standby and CA-1 A is in CR start.

l 1

. - . . - . - . .. .. . - - . - - . .. ~ . _ _ - . _ . - - . - - - - . .-

Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214 Shift Inservice Air Compressors QUESTION: JPM-0214-RO-1 What is the difference between service air and instrument air??

ANSWER:

Instrument air goes thrcugh an air dryer.

REFC2ENCE:

Service and Instrument Air STM I NRC K/A 000078 Kl.02 (2.7/2.8)

The operator's response was:

SATISFACTORY UNSATISFACTORY l !

COMMENTS: >

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f i

Revision: 10 October 24,1995 1

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214 Shift Inservice Air Compressors i

QUESTION: JPM-0214-RO-2 What are the normal and backup cooling water sources to the air compressors?

l ANS%IR:

Normal: Bearing Cooling Water (TPCW)

Backup: Potable Water

REFERENCE:

Service and Instrument Air STM NRC K/A 0000078 Kl.04 (2.6/2.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

l

Revision: 10 October 24,1995 Fort Calhoun Station - Operations gaining JOB PERFORMANCE MEASURE

JPM No: JPM - 0214

'1 Shift Inservice Air Compressors QUESTION: JPM-0214-SRO-1 a 1 l !

The procedure cautions against having too much cooling water to the standby compressor to l

prevent low pressure trips. What would happen if the cooling water valve was throttled too far ,

closed? 1 1

1 ANSWER: l i

, The compressor will eventually trip on high temperature. ;

i :

2 !

REFERENCE:

i 3 l

Service and Instrument Air STM NRC K/A 000078 Kl.04 (2.6/2.9)

The operator's response was:

i l I

SATISFACTORY UNSATISFACTORY i

COMMENTS:

y .. sos.- 4 s-.a-L 4-4 -,Ae J ,. R: +nL 1- 4 m n1 , b 2 - Ma. a ,

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Revision: 10 October 24,1995 Fort Calhoun Station - Operations training l

i JOB PERFORMANCE MEASURE JPM No: JPM - 0214

Shift Inservice Air Compressors t

l i

QUESTION: JPM-0214-SRO-2 l

What determines whether the Instrument Air containment isolation valves will close on a l containment isolation signal?

l ANSWER:

The instrument air pressure. [They will only close if pressure is less than 70 psig.]

REFERENCE:

l Service and Instrument Air STM NRC K/A 000078 Kl.03 (3.3/3.4) 6 l

l The operator's response was:

I 1 1

l l SATISFACTORY UNSATISFACTORY j l i l COMMENTS:

I 1

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< Initiating Cue: 'i j

j The air compressor lineup is as follows: CA-1 A running, CA-1C in standby, and CA- !

! 1B in Control Room Start. You are directed to rotate air compressors for weekly l rotation as follows: CA-1C running, CA-lu in standby, and CA-1 A in Control room :

i start. START l 4.

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User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340

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Description:

August 23, 1996 1:07pm

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Revision: 0 2 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Inverter Supply Power From Bypass to Normal i

System (s) : 125 volt AC Instrument Power r location (s) : Switchgear Room Approximate Time: 15 minutes Actual Time :

Reference (s): (1) OI-EE-4 Attachment 1 R20 (2) NRC K/A 000057, A1.01 (RO3.7/SRO3.7)

Verify current reference revisions match those listed above i

Operator's Name: SS # :

l a All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason, if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None Safety Consideratiot's:

Comments : This is an alternate path JPM . This JPM will be performed as a static JPM in the plant.

Revision: 0 i October 25,1995 .

i Fort Calhoun Station - Operations traimag JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch inveder Supply Power From Bypass to Normal l

l Initiating Cue:

Instrument Invener "A" is out of service. Al-40A is being supplied via the bypass transfonner. The electricians have cleared their tags on Invener "A" and the Shift Supervisor directs you, the LO, to stan up invener "A" and place it in service. START 1

CRITICAL STEP

ELEMENT STANDARD l

1. Ensure the input breaker EE-8H-CBI Check Breaker to OPEN position. ;

i at the inverter is open. i l

2. Ensure the DC source breaker at the EE-8F J DC panel is closed. DC Bus #1 l EE-8F-CB24 (Circuit Breaker-24) l l

Check Breaker to Closed position. )

3. Ensure the manual (bypass) transfer Check Si to bypass position. '

switch Si at the inverter is in bypass. I i

l

4. Prechr.rge the inverter. Push precharge button on invener and wait - 1 10 seconds 3

5. Close input breaker EE-8H-CBl. Place Breaker to CLOSED position.

6. Verify Synch Loss Light is LIT. Cue: Light is LIT

7. Verify Reverse Transfer Light is LIT. Cue: Light is LIT. j i

8. Place Manual Transfer Switch Si in Select INVERTER position with Switch.

INVERTER position 4

9. Ensure Sync. Loss Light is OFF. Cue: Light is LIT NOTE: This indicates an Inverter problem.

, DO NOT push Forward Transfer Button.

Terminate procedure and contact Shift Supervisor. Coutinue to allow bypass transformer to supply Instrument bus.

NOTE: It is acceptable, but not required, for operator to return switch Si to the bypass position and open input breaker EE-8H-CBI STOP l

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Invester Supply Power From Bypass to Normal QUESTION: JPM-0295 ASP -RO -1 Why is it necessary to ensure the " sync loss" light is out prior to placing the inverter in service?

ANSWER:

To ensure that the output of the inverter is at the proper voltage and frequency.

OR ,

I To prevent a transient on the instrument bus.

)

l

REFERENCE:

l AOP-30, Attachment A l

NRC K/A 062000 A2.15 (2.8/43.2)

The operator's response was:

l SATISFACTORY UNSATISFACTORY l

I COMMENTS:

l l

i l

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Inverter Supply Power From Bypass to Normal I

QUESTION: JPM-0295 ASP -RO -2 Why do the inveners ue DC wpm power rather than AC?

i

- ANSWER:

To assure that instrument power will be available following a station blackout.

REFERENCE:

l l

NRC K/A 000057 EA2.14 (3.2/3.6) !

The operator's response was:

SATISFACTORY UNSATISFACTORY l

i COMMENTS: j i

1 d

j Y

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Inverter Supply Power From Bypass to Normal QUESTION: JPM-295 ASP - SRO -1 is the instrument bus considered operable per Technical Specifications when powered from its bypass transformer?

ANSWER: ,

No. The instrument bus is not considered operable unless it is powered from its associated inverter.

REFERENCE:

NRC K/A 000057 G008 (3.2/3.6)

The operator's response was:

! SATISFACTORY UNSATISFACTORY 4

i COMMENTS:

4 6

g - , _ _

Revision: 0 October 25,1995 Fort Calhoun Station - 0;,erations training JOB PERFORM /JiCE MEASURE JPM No: JPM - 295 ASP Switch Inverter Supply Power From Bypass to Normal QUESTION: JPM-295 ASP - SRO -2 What actions are required to assure that instrument buses will remain energized for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a station blackout?

ANSWER:

DC bus loads must be minimized.

REFERENCE:

EOP/AOP Attachment 6 NRC K/A 000055 EK3.01 (2.7/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Inverter Supply Power From Bypass to Normal Initiating Cue:

Instrument Inverter "A" is out of service. AI-40A is being supplied via the bypass transformer. The electricians have cleared their tags on Inverter "A" and the Shift Supervisor directs you, the LO, to start up Inverter "A" and place it in service.

START

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User name: TRM (26) Oneue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340 *

Directory: *

Description:

August 23, 1996

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Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0323 Terminate Shutdown Cooling System (s) : Shutdown Cooling ocation (s) : Simulator Approximate Time: 20 minutes Actual Time :

Reference (s): (1) OI-SC-2 Att. 2 R7 (2) TS 2.1.1, 2.1.2 (3) NRC K/A Verify current reference revisions match those listed above I

Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason, if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None

. - .. ~,

1 Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0323 Terminate Shutdown Cooling Safety Considerations: None. !

Comments : This JPM is designed to be conducted as a static JPM in the simulator,

Initiating Cue:

The plant is in cold shutdown. Shutdown cooling is in operation with SI-1B running. RCS temperature .,

- is 115 o F and RCS pressure is 200 psia. RCS fill and vent is completed and RC-3A (RCP) is in operation. RCS oxygen is in specification, you, the LO, are directed to terminate long term shutdown cooling. The prerequisites are met. START i

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User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

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Directory: *

Description:

~ August 23, 1996 1:08pm

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Revision: 4 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0347 ,

Unload DG-1 :

System (s) : Diesel Generator Location (s) : Simulator Approximate Time: 5 minutes Actual Time :

Reference (s): (1) IO-DG-16.11, R17 (2) NRC K/A 000062 , K3.02 (RO4.1/SRO4.4) l (3) NRC K/A 000062, A2.1i (RO3.7/SRO4.1) i Verify current reference revisions match those listed above l

Operator's Name: SS # .

l l

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in j this JPM. !

l The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY l l

Evaluator's Signature : Date :

Reason, if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None Safety Considerations None l

l Comments : This is designed to be a dynamic JPM on the simulator.

1

Revision: 4 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0347 Unload DG-1 Initiating Cue:

Diesel Generator DG-1 has been operating loaded and synchronized to bus I A3, following a manual start. You the LO, are directed to unload and stop DG-1. All start signals to the Diesel Generator have been cleared. START CRITICAL STEP

ELEMENT STANDARD

1. Reduce load on DG-1 to approximately CB-20 300 kw. Use Governor Control DG-1 to lower Diesel Load.

2. Open Breaker l ADI Open Breaker l ADI and GREEN light lit

3. Operate Diesel Generator at 900 RPM Monitor Diesel.

for at least five minutes. CUE: 5 minutes have passed.

4. Ensure 86A/D1 and 86B/D1 are reset. AI-30A lockout Relays are RESET:

Blackflag and AMBER lights on.

5. Stop DG-1 Depress both stop pushbuttons and hold for 10 seconds.

6. Verify DG-1 stops O RPM indicated OR Diesel tripped OR Annunciated Engine Stop light lit.

NOTE: any one of these indications is adequate.

7. Verify DG-1 is lined up for emergency All alarms cleared except " Diesel Auto start. Standby" and " Breaker Auto Standby"

8. Station an operator at DG-1 to observe Direct EONT governor rundown. CUE: EONT is at DG-1

9. Ensure DG-1 is setup for idle speed Hold governor control in auto for 15 seconds.

start.

CUE: EONT reports that governor has run down Termination Criteria: DG-1 has been unloaded and is lined up for emergency standby.

l

Revision: 4 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0347 Unload DG-1 QUESTION: JPM-0347-RO-1 What would happen if the stop pushbuttons were pushed prior to unloading the D/G7 ANSWER:

The output breaker would trip open and the D/G would shutdown.

REFERENCE:

Diesel Generator STM NRC K/A 000064 A4.06 (3.9/3.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

. . _ . __ _ . _ _ - _ _ - - - ~

Revision: 4 October 24,1995

~

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i

JPM No: JPM - 0347 Unload DG-1 QUESTION: JPM-0347-RO-2 If the governor was not run down following the shutdown of the diesel generator, what would happen on the next uncomplicated reactor trip?

ANSWER:

The diesel generator would start and its speed would increase to 900 RPM,

REFERENCE:

Diesel Generator STM page 38 PRC meeting minutes " Diesel Generator Full Speed Start" NRC K/A 0000064 A4.06 (3.9/3.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

1 Revision: 4 October 24,1995 )

Fort Calhoun Station - Operations training l JOB PERFORMANCE MEASURE <

l 1

JPM No: JPM - 0347 Unload DG-1 l

QUESTION: JPM-0347-SRO-1 q l

What would be the affect on the D/G if a reactor trip occurred while you were pushing the STOP pushbuttons to stop the diesel?

l l

I ANSWER:

As soon as the stop pushbuttons were released, the diesel would restart..

REFERENCE:

Diesel Generator STM NRC K/A 0000064 A4.06 (3.9/3.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

Revision: 4 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0347 Unload DG-1 QUESTION: JPM-0347-SRO-2 How could a diesel generator be started if its normal source of DC control power is lost?

ANSWER:

DC control power could be switched to the alternate source using the transfer push-button..

REFERENCE:

Electrical System STM NRC K/A 000063 K4.01 (2.7/3.0)

I The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

1

- n Initiating Cue:

Diesel Generator DG-1 has been operating loaded and synchronized to bus IA3, following a manual start. You the LO, are directed to unload and stop DG-1. All start signals to the Diesel Generator have been cleared. START 4

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User name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

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File name: Server: HPIIISI-340

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Directory: *

Description:

August 23, 1996

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Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System Systein (s) : Hydrogen Purge System Location (s) : Auxiliary Building (RCA)

Approximate Time: 10 minutes Actual Time :

Reference (s): (1) OI-VA 1, Attachment 5,4.3 (2) NRC K/A 000028, A2.02 (RO3.5/SRO3.9)

Verify current reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM. j l

The operator's performance was evaluated as: SATISFACTORY 1 UNSATISFACTORY l

Evaluator's Signature : Date :

Reason, if unsatisfactory :

1 Operator's review : Date: , , _

Tools & Equipment : None Safety Considerations: This JPM requires entry into the RCA.

Comments : This JPM will be performed as a static JPM in the plant.

i

Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Ilydrogen Purge System 1

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I Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System l

I Initiating Cue:

The plant is in accident recovery following a LOCA. CIAS and VIAS have initiated. Containment hydrogen concentration is 3%. Containment integrity has not been satisfied in accordance with the Safety Function Status Check. A containment hydrogen purge is required. You have been directed to start a hydrogen purge using Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 have all been verified closed. START CRITICAI.

STEP

ELEMENT STANDARD !

1. Ensure VA-80A recirculation valves are Corridor 26 closed. VA-279 and VA-284 are closed

2. Open hydrogen purge fan suction and NOTE: Manual handwheels for these valves discharge valves: are in Corridor 26.

A. VA-292 B. VA-290 Unlock and OPEN valves C. VA-289

3. Open hydrogen purge containment Request control room to open HCV-882.

isolation valve.

CUE: Control room reports HCV-882 is open. i

4. Start hydrogen purge fan. Al-100 l VA-80A in pull to OVERRIDE.

NOTE: If candidate places control switch for VA-80A in AFTER START, tell him the l GREEN light is still lit. l Termination Criteria: Hydrogen purge has been started.

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Revision: 8 October 24,1995 Fort Calhoun Station - Operations training '

JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Stadup Hydrogen Purge System !

QUESTION: JPM-0719- SRO-1 What is the largest source of hydrogen p- ction in containment during a large LOCA?

ANSWER:

The zircalloy-water reaction in the core.

l REITRENCE: i NRC K/A 000028 K5.03 (2.9/3.6) i l l The operator's response was:

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Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 i Startup Hydrogen Purge System P

I QUESTION: JPM-0719-RO-1 What is the purpose of the charcoal filters in the hydrogen purge system?

ANSWER:

To remove radioactive iodine from the containment atmosphere being released to the environment. j l

l

REFERENCE:

)

i l

NRC K/A 000027 K5.01 (3.1/3.4) l ll The operator's response was:

SATISFACTORY UNSATISFACTORY l

1 1

COMMENTS:

I

__. . . _ . _ .~. __ . . _ _ . . _ _ . _ _ _ . _ _ _ - .. _ _ - _ __ ..

Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System l

QUESTION: JPM-0719-SRO-2 What major concern, other then hydrogen production, is associated with the Zircalloy-water reaction?

ANSWER:

The Zircalloy-water reaction produces heat which may lead to fuel damage..

REFERENCE:

NRC K/A 074000 EK3.11 (4.0/4.4)

The operator's response was:

l SATISFACTORY UNSATISFACTORY l

COMMENTS:

l I

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\

Revisior.: 8 October 24,1995 Fort Calhoun Station - Operations training

JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System QUESTION: JPM-0719-RO-2 What is another system that can be lined up to flow through the hydrogen purge charcoal ,

filters 7 ANSWER:

I Either of the following:

Gas decay tanks Condenser vacuum pump exhaust

REFERENCE:

I NRC K/A 000027 KS.01 (3.1/3A)

The operator's response was: j l

l SATISFACTORY UNSATISFACTORY l

1

Revision: 8 October 24,1995 Fon Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM 0719 Startup Hydrogen Purge System i

1 l

Initiating Cue:

The plant is in accident recovery following a LOCA. CIAS and VIAS have initiated.

Containment hydrogen concentration is 3 %. Containment integrity has not been satisfied in accordance with the Safety Function Status Check. A containment hydrogen purge is ;

required. You have been directed to start a hydrogen purge using Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 have all been verified closed.

START 1

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User-name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340 * ,

Directory:

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Description:

August 23, 1996 l

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Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T, Calibration on the RPS Panel ,

5 i

l System (s) : Reactor Protective System location (s) : Simulator :

Approximate Time: 9 minutes Actual Time :

Reference (s): (1) OI RPS-2, Attachment 1 .(R3)

(2) NRC K/A 000012 , K4.01 (RO3.7/SRO4.0)

(3) NRC K/A 000012, A1.01 (RO2.9/SRO3.4) ;

Vesify current reference revisions match those listed above l

Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM. l The operator's performance was evaluated as: SATISFACTORY j UNSATISFACTORY j i

Evaluator's Signature : Date :

Reason, if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None l

l

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I Revision: 5 October 24,1995 Fort Calhoun Station - Ogrations training JOB PERFORMANCE MEASURE JPM No: JPA 0778 Adjust T Calibration on the RPS Panel Safety Considerations: None I

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l Conunents : This JPM should be performed as a dynamic JPM on the simulator.

1 Use full power IC, Adjust Channel A Tc Cal. 0.4 o F below other channels. Obtain key for l Trip Unit 9. l l

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Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T Calibration on the RPS Panel Initiating Cue:

The plant has been operating for 30 days at 100% power. You, the LO, are taking your shift readings on OP-ST-SillFT-1 and you notice Channel "A" T Cal. Is 0.4 o F low. The shift supervisor directs you to take the appropriate action to adjust the " A" Channel T Cal. All other channels are indicating within 0.1 o F of each other. START CRITICAL STEP

ELEMENT STANDARD

1. Record T DVM readings on all Al-31 A/B/C/D channels. RPSCIP Complete form

2. Record DVM readings on all T,,ia Cal. Complete form channels.

3. Record T CAL. Pot settings Complete form i

4. Bypass channel "A" TM/LP trip unit. CUE: Hand trip unit #9 bypass key to candidate, i I

Al-31 A BYPASS trip unit number 9 on "A" channel, AMBER light . lit.

5. Log into Tech Spec 2.15(1) CUE: Log entry has been made. I I

6. Adjust T Cal. Pot so the T Cal. Adjust Cal. pot Reading on channel "A" DVM is the same as the highest Tm recorded.

7. Remove bypass key from channel "A" Remove key and AMBER light off TM/LP trip unit Return key to Shift Supervisor.

8. Exit Tech Spec 2.15(1) for the affected CUE: Log entry has been made, channel.

9. Record new T Cal. DVM readings. Complete form.

10. Record new Ta Cal. Pot readings Complete form j

4 1

Revision: 5 Octoter 24,1995 3 Fort Calhoun Station - Operations training

! JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T Calibration on the RPS Panel J

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Termination Criteria: All T Cal. Channels read within 0.1 o F of each other.

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el Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T Calibration on the RPS Panel QUESTION: JPM-0778-RO-1 Why do you adjust T Cal To the highest Tm?

ANSWER:

Using the highest temperature will generate the most conservative TM/LP setpoint.

REFERENCE:

I NRC K/A 000012 Al.01 (2.9/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

Revision: 5 October 24,1995

)

Fort Calhoun Station - Operations training i

JOB PERFORMANCE MEASURE '

JPM No: JPM - 0778 !

Adjust T Calibration on the PsPS Panel 1

QUESTION: JPM-0778-RO-2 flow can you force a trip unit's bistable into the " tripped" condition?

ANSWER:

By partially pulling the Trip Unit out of the RPS panel .

l 1

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REFERENCE:

1 i

RPS STM '

NRC K/A 000012 K4.06 (3.2/3.5) l The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

l

Revision: 5 ,

October 24.1995 Fort Calhoun Station - Operations training JOH PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T,a Calibration on the RPS Panel QUESTION: JPM-0778 SRO-1 Why does the TM/LP trip pressure setpoint increase as RCS cold leg temperature increases?

1 l

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ANSWER:

To provide protection from DNB induced fuel damage.

REFERENCE:

3 1

RPS STM ;

NRC K/A 000012 K5.01 (3.3/3.8) ;

i l

The operator's respense was: I SATISFACTORY UNSATISFACTORY I

COMMENTS:

)

i

b Revision: 5 October 24,1995 l

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T, Calibration on the RPS Panel 1

i 1 1 r

QUESTION: JPM-0778-SRO-2 i :

. ht RPS trip is designed to prevent DNB if one of the MSIVs closes at power 7 i i l 4

ANSWER

\

i The Asymmetric Steam Generator Transient (ASGT) trip. [135 psi difference between S/Gs]

1-

REFERENCE:

l RPS STM l NRC K/A 000012 K4.02 (3.9/4.3) i The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

i i

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Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust T Calibration on the RPS Panel Initiating Cue:

The plant has been operating for 30 days at 100% power. You, the LO, are taking your shift readings on OP-ST-SHIFT-1 and you notice Channel "A" T,ao Cal. Is 0.4 o F low. The shift supervisor directs you to take the appropriate action to adjust the "A" Channel T,oo Cal. All other channels are indicating within 0.1 o F of each other. START l

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User.name: TRM (26) Queue: AR1/HPIIISI-AR1-340 *

File name: Server: HPIIISI-340 *

Directory: *

Description:

- August 23, 1996 1:08pm *

TTTTT RRRR M M *

- T R R MM MM *

T R RMMM *

T RRRR MMM *

T RR M M *

T R R M M *

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ES-301 Scenario Events Form ES-301-3 Simulation Facility: Fort Calhoun Scenario No.: FCS- 1 l

Examiners: Applicants:

i l

Initial Conditions : 100% power - BOL ( IC- 1 ) ]

Tumover: FW-54 ( Diesel driven AFW pump) and SI-2B (11 PSI pump) tagged out of service.

Continue full power operation.

E nt Malf. Event Event Description No. No. Type

1 CRD6 C Dropped Control Rod 2 R/N Reduce power to 70% within I hour as required by Tech Specs 3 XMT I Pressurizer Pressure channel fails "as is" RCS80 4 XMT I PT-910 fails high causing turbine bypass valve to open RRS1 5 ESF6(A I/C Inadvertant Steam Generator Isolation. (MSIVs will fail open)

&B) 6 RPSl(A- M/C ATWS - Clutch Power Supply Breaker trip required D) 7 XMT I PI-499 (CCW pump discharge header pressure) fails low CCW 8 AFW1 M/C Total Loss of Feedwater P AFW2 9 M Initiate Once Through Cooling l

(N)ormal, (R)eactivity, (1)nstniment, (C)omponent, (M)ajor Examiner:

Chief Examiner:

ES-301 Operator Actions Form ES-301-4 Scenario No. FCS-1 Event No.: 1 Page 1 of 9 Event

Description:

Dropped Control Rod Time Position Applicant's Actions or Behavior RO Indentify event from alarms.

RO Determine only one rod has dropped.

SRO Enter AOP-02 SRO Direct BOP to adjust turbine load to match reactor power.

BOP Adjust turbine load to match reactor power.

SRO Direct RO to control pressurizer pressure and level.

RO Monitor pressurizer pressure and level.

SRO Notify Reactor Engineer.

SRO Consult Tech Spec 2.10.2.

SRO Inform RO and BOP that Tech Specs requires a power reduction to less than 70% within one hour.

SRO Notify System Operations of impending power reduction.

m

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4 ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 2 Page 2 of 9 Event

Description:

Power Reduction to 70% within one hour.

Time Position Applicant's Actions or Behavior SRO Direct RO and BOP to commence power reduction.

SRO Direct RO on method of boration to use.

RO Begin boration, t

j BOP Reduct turbine load to control RCS Tc.

RO Monitor and control primary parameters during power reduction.

BOP Monitor and control secondary parameters during power reduction.

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h ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 3 Page 3 of 9 Event

Description:

Controlling Pressurizer Pressure Channel Fails AS IS.

Time Position Applicant's Actions or Behavior RO Identify deviation between pressurizer pressure channels.

SRO Direct RO to swap controlling channels or to take manual control of pressurizer pressure.

RO Switch controlling channel or take manual control of

} pressurizer pressure.

< RO Monitor and maintain proper pressurizer pressure.

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I ES-301 Operator Actions Form ES-301-4 ;

Scenario No.: FCS-1 Event No.: 4 Page 4 of 9 Event

Description:

Steam IIeader Pressure (PT-910) fails high causing turbine bypass i valve to open.

Time Position Applicant's Actions or Behavior l BOP Identify rapid decrease in RCS Tc.

BOP Determine cause as bypass valve being open.

SRO Direct BOP to take manual control of PCi[-910 and close it.

BOP Take manual control of PCV-910 and close it.

BOP Monitor RCS Tc RO Monitor and control RCS parameters.

I

ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 5 Page 5 of 9 Event

Description:

Inadvertent SGIS Time Position Applicant's Actions or Behavior BOP Identify and communicate SGIS.

SRO Direct RO to manually trip the reactor.

RO Take action to manually trip the reactor.

ES-301 Operator Actions Form ES-301-4 Scenario No.. FCS-1 Event No.: 6 Page 6 of 9 Event

Description:

ATWS Time Position Applicant's Actions or Behavior RO Determine and communicate that the reactor failed to trip.

SRO Direct BOP to initiate DSS (Diverse Scram System).

BOP Take action to initiate a manual DSS trip.

BOP Determine and communicated that DSS did not actuate.

SRO Direct the RO to open the clutch power supply breakers.

RO Open the clutch power supply breakers.

BOP Determine and communicate that the rods have inserted.

SRO Direct RO and BOP to take Standard Post Trip Actions (SPTAs).

RO Perform Standard Post Trip Actions - Identify and communicate low CCW pump discharge pressure. (Event 7).

BOP Perform Standard Post Trip Actions - Indentify and communicate Loss of Feedwater. (Event 8).

4

. - - . ., _ . _ - . = . _ _ . - -. . - . . . . . . . - . - - - . _ .

t 4

ES-301 Operator Actions Form ES-301-4 e

.: Scenario No.: FCS-1 Event No.: 7 Pag: 7 of 9 Event

Description:

CCW Pump Discharge Header Pressure (PT-499) fails low.

Time Position Applicant's Actions or Behavior i

RO Identify and communicate CCW Pump discharge pressure is ;

indicating low. 1 RO Check other CCW parameters. i i RO Report other parameters are OK.

RO Direct EONAto check local CCW pump discharge pressure indication.

j (EONA) Reports normal CCW discharge pressure RO Determines and communicates failure of CCW pressure

instrument.

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ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 8 Page 8 of 9 Event

Description:

Total Loss of Feedwater.

Time Position Applicant's Actions or Behavior BOP Determine and communicate Imss of All Feedwater.

SRO Direct BOP to attempt to restore feedwater flow.

BOP Attempt to start motor driven AFW pump (FW-6).

BOP Attempt to start turbine driven AFW pump (FW-10).

BOP Report AFW pumps cannot be started. l SRO Direct BOP to override isolation of FW valves.

BOP Report that FW valves cannot be opened.

SRO Enter EOP-06 or EOP-20 SRO Direct RO to trip all RCPs RO Trip cli RCPs !

SRO Direct BOP to isolate blowdown.

BOP Isolate blowdown SRO Direct BOP to monitor S/G level for Once Through Cooling.

BOP Report when level is approaching 20% on both S/Gs

i ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 9 Page 9 of 9 Event

Description:

Initiate Once Through Cooling Time Position Applicant's Actions or Behavior j SRO Enter EOP-20/HR-4.

SRO Direct RO to initiate Once Through Cooling.

RO Open all HPSI loop injection valves.

RO Start all available HPSI and Charging Pumps.

RO Pull two HP RPS Trip Units in order to open the PORVs.

RO Verify PORVs have opened.

RO Report Once Through Cooling is initiated.

SRO Direct RO and BOP to monitor parameters.

RO Monitor primary parameters.

BOP Monitor secondary parameters.

. r

User name: TRM (26) Queue: AR1/HPIIISI-AR1-340

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' File name:

Server: HPIIISI-340 *

Directory: *

Description:

August 23, 1996 1:09pm *

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ES-301 Scenario Events Form ES-301-3 Simulation Facility: Fort Calhoun Scenario No.: FCS-2 Examiners: Applicants:

Initial Conditions : 50% power - MOL (IC - 8)

Turnover: FW-54 ( Diesel driven AFW pump) and SI-2B (HPSI pump) tagged out of service.

Continue increasing power toward 100%.

Event Malf. Event Event Description No. No. Type

1 EDS2B C Fault on bus IB3A-4A, No power to SI-2C 2 RCP9D C Lower and middle seals fail on RCP-D RCP10D 3 R/N Emergency Shutdown 4 XMT I PT-210 fails low causing loss of letdown flow CVC8,0 5 XMT I FT-907 (steam llow) fails low requiring manual S/G level control SGN8,0 6 RCSlH M Small LOCA (900 gpm) 7 ESG I Failure of automatic PPLS 8 LOA C Loss of power to bus I A3 (161 kv breaker to bus I A3 fails open on EDS256 reactor trip, D/G 1 field flashing failure) - No power to SI-2A 9 XMT I PIA-131 (PQT pressure) fails high

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner:

Chief Examiner:

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l l ES-301 Operator Actions Form ES-301-4 4 Scenario No.: FCS-2 Event No.: 1 Page 1 of 1 l Event

Description:

Fault on Bus 1B3A-4A !

Time Position Applicant's Actions or Behavior BOP Identify and Communicate fault on Bus IB3A-4A. l SRO Enter AOP-32 (Loss of 4160 V Bus or 480 V Bus Power) !

SRO Direct Plant Stabilization and Diagnostics section of AOP-

32. !

RO Verify CCW, RW, Charging Pumps, RCPs, and RCS )

Pressure. l BOP Verify Vital 4160 Bus, Bearing Cooling Water, Instrument Air, and S/G I2vels.

SRO Determine that there is no power to SI-2C.

SRO Consult Tech Spec 2.3 SRO Inform RO and BOP of 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO per Tech Spec.

SRO Make outside notifications of LCO status.

BOP log Tech Spec Entry, i

l

ES-301 Operator Actions Form ES-301-4 Scenario No. FCS-2 Event No.: 2 Page 2 of 1 Event

Description:

RCP 'D' Lower and Middle Seal Failures. ,

1 Time Position Applicant's Actions or Behavior 1

RO Identify and communicate High Seal Leakage from alarms.

SRO Enter Alarm Response Procedure. .

1 RO Monitor RCP seal pressures and determine lower and l middle seals have failed. l SRO Direct Emergency Shutdown and enter AOP-05 (Emergency l Shutdown) l l

J

ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-2 Event No.: 3 Page 3 of 1 1

, Event

Description:

Emergency Shutdown

?

Time Position Applicant's Actions or Behavior SRO Direct RO and BOP to commence Emergency Shutdown 1

SRO Direct RO to begin boration using SIRWT. l RO Switch charging pump suction from VCT to SIRWT.

BOP Reduce turbine load to control RCS Tc.

RO Operate control rods as necessary to control ASI.

l RO Monitor primary parameters.

BOP Monitor RCS Tc and secondary parameters.

4 3

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ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-2 Event No.: 4 Page 4 of 1 Event

Description:

Ixtdown Backpressure Instrument (PT-210) fails low - Letdown Isolates.

Time Position Applicant's Actions or Behavior ;

RO- Identify and communicate loss of I2tdown RO Determine and communicate loss of letdown due to PCV- I 210 being closed. ,

SRO Direct RO to take manual control of PCV-210 and reestablish letdown flow.

RO Take manual control of PCV-210 and reestablish letdown. i RO Report that PT-210 is failed.

SRO~ Notify I&C of PT-210 failure j RO Monitor and control letdown.

BOP Monitor secondary parameters l i

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_ . . . _ . _ _ . . _ . . _ _ _ _ _ . _ . . . _ _ _ _ . _ . _ . _ . . - - . _ _ . _ - . . _ . . _ . _ . _ _ _ . - . _ . _ . _ . _ = _ _ _ .

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l i I l ES-301 Operator Actions Form ES-301-4 !

1 I

4 Scenario No.: FCS-2 Event No.: 5 Page 5 of 1 'l -

l Event

Description:

Steam Flow (PT-907) Fails Highs !

Time Position Applicant's Actions or Behavior i BOP Identify and communicate lowering FW flow and level in S/G 'B' i-i SRO Direct BOP to take manual control of feedwater.

t l BOP Take manual contol and restore feewater flow. ;

$ BOP Identify FT-907 as failed instrument. '

SRO Inform I&C of failure of FT-907. l BOP Continue to monitor and control S/G level.

~

i j RO Monitor primary parameters.

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ES-301 Operator Actions Form ES-301-4 '

b Scenario No.: FCS-2 Event No.: 6 Page 6 of 1 '

Event

Description:

Small LOCA (900 gpm) -

.i Time Position Applicant's Actions or Behavior

, RO Identify and communicate lowering of pressurizer level and

pressure.

SRO May direct RO to manually trip the reactor.

4 RO Manually trip the reactor if directed by SRO. ,

, t j SRO Direct Standard Post Trip Actions (SPTAs) i

RO Perform SPTAs l

BOP Perform SPTAs l l

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ES-301 Operator Actions Form ES-301-4 l

Scenario No.: FCS-2 Event No.: 7 Page 7 of 1 1

Event

Description:

Failure of Automatic PPLS Time Position Applicant's Actions or Behavior RO Monitor for automatic PPLS actuation.

RO Determine and report that PPLS has failed to actuate.

SRO Direct RO to manually initiate PPLS RO Manually initiate PPLS.

RO Verify and report PPLS actuation.

l J

l ES-301 Operator Actions Form ES-301-4

_ 1 Scenario No. FCS-2 Event No.: 8 Page 8 of 1 Event

Description:

161 KV Breaker to bus I A3 fails open.

Time Position Applicant's Actions or Behavior BOP Determine and report no power on 1A3. I BOP Determine and report DG-1 has started but its breaker did not close.

l SRO Direct RO and EONT to investigate loss of power. i BOP Determine and report DG field did not flash.

SRO/ BOP Direct EONT to flash field locally. l (EONT) Report unable to flash field.

BOP Report local field flash attempt unsucessful RO Determine and report no IIPSI flow.

SRO Determine Inventory, Pressure Control and Heat Removal Safety Functions are not being met with no HPSI flow.

RO Trip RCPs (at least one in each loop)

t l

ES-301 Operator Actions Form ES-301-4 e

Scenario No.: FCS-2 Event No.: 9 Page 9 of 1 Event

Description:

Restore Power to 1A3.

Time Position Applicant's Actions or Behavior ;

SRO Direct BOP to supply power to Bus 1A3 using 345 KV ;

backfeed.

BOP Direct EONT to operate DST 1 key interlock.

BOP Open DST 1 BOP Close 345 KV supply breaker to IA3. t BOP Report IA3 is energized. j SRO Direct RO to start HPSI Pump SI-2A. .

i RO Start SI-2A, verify and report flow.

SRO Determine Safety Functions now being satisfied. i I

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User name: TRM (26) Queue: AR1/HPIIISI-AR1-340

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Directory: *

Description:

August 23, 1996 1:09pm

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ES-301 Scenario Events Form ES-301-3 Simulatiota Facility: Fort Calhoun Scenario No.: FCS-3 (Scare)

Examiners: Applicants:

Initial Conditions : 100% power - BOL ( IC- 1 )

Turnover: FW-54 ( Diesel driven AFW pump) and SI-2B (HPSI pump) tagged out of service.

Continue full power operation.

Event M alf. Event Event Description No. No. Type

1 SGN1B C S/G 'B' Tube Leak (30 gpm) 2 C RCV-978 (Supply to Aux Steam) does not close l

3 R/N Emergency Shutdown.

4 XMT I A/TT-il2H (Hot Leg Temperature) fails high.

RCS 5 PMP C Running CCW pump trips.

CVC 6 XMT I Pressurizer level - 101 X fails low.

RCS81 7 XMT I S/G level LT-903X fails high.

CCW 8 SGNIA M S/G Tube Leak (900 gpm) l

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner:

Chief Examiner:

ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-3 Event No.: 1 Page 1 of 8 Event

Description:

Steam Generator Tube Irak Time Position Applicant's Actions or Behavior RO Identify and report charging / letdown mismatch.

RO Identify and report condenser off gas radiation alarm.

SRO Enter AOP-22 SRO Direct RO to control pressurizer level.

l RO Control pressurizer level.

SRO Initiate Emergency Shutdown (AOP-22). (Event 3)

BOP Determine and report that RCV-978 (Supply to Aux Steam) did not close. (Event 2)

SRO Identify affected steam generator.

SRO Direct isolation of appropriate valves.

BOP Isolate appropriate valves.

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ES-301 Operator Actions Form ES-301-4 ;

i-,

1 Scenario No.: FCS-3 Event No.: 2' Page 2 of 8 ;

i Event

Description:

RCV-978 (Supply to Aux Steam) does not close, j

j. Time Position Applicant's Actions or Behavior f BOP Determine and report that RCV-978 did not close.

! SRO Direct BOP to close RCV-978.

BOP Take action to close RCV-978.

4 j BOP Determine and report that RCV-978 did not close.

. I SRO Direct EONT to close RCV-978. '

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4 j ES-301 Operator Actions Form ES-301-4 l- Scenario No.: FCS-3 Event No.: 3 Page 3 of 8 Event

Description:

Emergency Shutdown ,

Time Position Applicant's Actions or Behavior

! SRO Enter AOP-05 (Emergency Shutdown) - Direct Emergency i Shutdown.

f SRO Direct RO to begin boration using SIWRT.

i 1

RO Switch charging pump suction from the VCT to the i SIWRT. l 1 ,

! BOP Reduce turbine load tocontrol RCS Tc.

j RO Operate control rods as required to control ASI. ,

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) RO Monitor primary parameters.

l BOP Monitor RCS Tc and secondary parameters.

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3 ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-3 Event No.: 4 Page 4 of 8 Event

Description:

A/TT-112 (Hot leg Temperature) fails high Time Position Applicant's Actions or Behavior RO Identify and report hot leg temperature instrument failure.

SRO Enter Tech Spec 2.15 (Table 2-1).

SRO Determine that trip units 1,9, and 12 on RPS Channel A must be tripped within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

% -w SRO Direct RO to bypass Trip Units 1, 9, and 12 RO Bypass Trip Units as directed.

SRO Notify plant management.

BOP Monitor secondary parameters.

ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-3 Event No.: 5 Page 5 of 8 Event

Description:

Trip of running CCW pump Time Position Applicant's Actions or Behavior RO Determine and report trip of CCW pump.

RO Verify autostart of backup CCW pumps.

RO Inform SRO of CCW status.

SRO Direct EONA to check tripped and running CCW pumps.

RO Monitor CCW operation.

BOP Monitor secondary parameters.

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ES-301. Operator Actions Form ES-301-4 Scenario No.: FCS-3 Event No.: 6 Page 6 of 8 Event

Description:

Pressurizer level (101X) fails low.

Time Position Applicant's Actions or Behavior RO Determine and report failure of pressurizer level instrument.

SRO Direct RO to swap channels or take manual control of level.

RO. Swap channels or take manual control of pressurizer level.

RO Monitor and control pressurizer level.

BOP Monitor secondary parameters.

I I I j

! I ES-301 Operator Actions Form ES-301-4 l-4 l Scenario No.: FCS-3 Event No.: 7 Page 7 of 8

} Event

Description:

Steam Generator Level (LT-903X) Fails High i

Time Position Applicant's Actions or Behavior j BOP Determine and report failure of steam generator level !

j channel.

4 i SRO Direct BOP to take manual control of steam generator i level. i l 1 BOP Take manual control of FW Reg Valve. Restore normal level. j BOP Monitor and control steam generator level.

RO Monitor primary parameters, l

ES-301 Operator Actions Form ES-301-4 Scenario No. FCS-3 Event No. 8 Page 8 of 8 Event

Description:

Tube Rupture - Steam Generator 'A' Time Position Applicant's Actions or Behavior RO Determine and report RCS inventory loss.

SRO May direct reactor trip.

SRO Following manual or auto reactor trip, direct Standard Post Trip Actions (SPTAs)

RO Perform primary SPTAs.

BOP Perform secondary SPTAs.

BOP Manually ramp down feedwater flow.

SRO Diagnose tube mpture - Enter EOP-04 or EOP-20 SRO Direct cooldown Th to less than 510 F BOP Cooldown RCS.

RO Identify and verify PPLS.

SRO/ BOP Identify most affected steam generator. (S/G 'A')

SRO Direct BOP to isolate most affected steam generator ('A')

BOP Isolate the 'A' steam generator. l l

SRO Direct RO to depressurize RCS to less than 1000 psia '

RO Depressurize the RCS.

RO Maintain subcooling.

BOP Monitor and control secondary parameters.

RO Monitor and control primary parameters.

Scenario ends when steam generator ' A' is isolated and RCS pressure is less than 1000 psia.

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l ES-301 Scenano Events Form ES-301-3 Simulation Facility: Fort Camnun Scenario No.: FCS-1 Examiners: Applicants:

InitialConditions : 100% power- BOL (IC- 1 )

Turnover: FW-54 ( Diesel driven AFW pump) and SI-2B (HPSI pump) tagged out of service. Continue full power operation.

Event M alf. Event Event Description No. No. Type *

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2 XMT I Pressunzer Pressure channel fails "as is" (insert after dropped rod but RCS80 before power reduction) 3 R/N Reduce power to 70% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months as required by Tech Specs h[ [ i's ? ;

k l} hhk:'ff;'^

G asesa . we r:^t~ g s/ 'a ha s t e m - % tysw e, ; c ,e ,p994,ss a d,s e$$e <lg i-v;3

/s ;,'1 AB) ' ' ,m c x m '4 e, < ts , . ;> , , . >A 6 RPS1(A- M/C ATWS - Clutch Power Supply Breaker trip required D) 7 XMT I PI-499 (CCW pump discharge header pressure) fails low CCW 8 AFW1 M/C Total Loss of Feedwater P AFW2 9 M Initiate Once Thn> ugh Cooling

( NOTE: file ZWRSGLVL can be run to lower WR S/G Ievels faster )

NOTE Events 5,6,7, and 8 occur simultaneously on cue from examiner.

Shaded entries are to be initiated by a cue from the examiner, r-

(N)ormal, (R)cactivity, (I)nstrument, (C)omponent, (M)ajor Examiner: / -- M- f - /~c #

ChiefExaminer: / e/# -

M

CONFIDENTIAL - NRC EXAM - FCS #1 - Simulator Operator Instructions initial Condition - 100% power, BOC Use IC-1 SI-28 tagged out of service Hang Tag FW-54 tagged out of service LOA AFW21, stop(0)

LOA AFW22, local (1)

Hang Tag Night Shift Set wall clock to 2300 Initial Malfunctions Setup ATWS MAL RPS1 A , E MAL RPS18, E MAL RPS1C, E MAL RPS1D, E SWI RPSS, off SWI RPS8, off SWI RPS10, off SWI RPS28, off set XRPSCPCD=F Setup loss of AFW pumps MAL AFW1 PMP AFW2 Setup Inadvertant SGIS MAL ESF6B, T, C=JMLESF6(1)

SWI AFW10, off SWI AFW11, off VLV SGN12 "as is" VLV SGN13 "as is" START Verify Homs are on Drop Control rod #1 on NRC cue MAL CRD6,1. D Fail Pressurizer Pressure transmitter PT- XMT RCS80, as is (1) 103X "as is" (prior to power reduction)

Fail Steam Pressure. Channel, PT-910 high XMT RRS1,1000 on NRC Cue Inadvertant SGIS (can not override) MAL ESF6A, T On NRb Cue if NRC Cues rapid S/G levellowering FILE ZWRSGLVL When RO goes to pull high pressure RPS FILE ZOPENPRV trip units

l i

FORT CALHOUN STATION FORM FC-95 4

TODAY Days [ ] Afternoons [ ] Nights [ X ]

PLANT STATUS:

i

. MODE: 1 [X ], 2 [ ], 3 [ ] Rx Power: 100 % Rod Position: ARO inches l Pycs (>2075 psia): 2100 psia; Tmm (<543 F): 143 F; La (48 TO 60%): @_% ;

COMMENTS: RCS Boron concentration = 948 ppm i

a SAFEGUARD STATUS:

(Img any Out Of Service Safeguards Equipment, include major fire protectic n equipment)

SI-2B 4

RECENT TEMP MODS; (Within the last month)

TM NUMBER DATE DESCRIPTION RELEASES IN PROGRESS: YES NO Release No.

Monitor Tank [ A or B ] X Waste Gas Decay Tank [ A, B, C, or D ] X Containment Pressure Reduction X

. Lagoon [ East or. West ]

X 4

S0-0-1 FC/ FORM Page 1 of 3

FORT CALHOUN STATION FORM FC-95 i

ERQCEDURES and SURVEILLANCE IN PROGRESS / OVERDUE: l TEST REASON

l l

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1 a

4

. INSTRUMENT / ANNUNCIATOR (Only app ies when STATUS;d)

Compensatory Action is require

. ITEM / LOCATION DATE COMPENSATORY ACTION TAKEN 1

TEMPORARY CLEARANCFE1 TAGOUT NO. EOUIPMENT REASON MAJOR EQUIPMENT OUT-OF-SERVICE:

EOUIPMENT DATE / TIME REASON SI-2B 12/5/95 @ 1900 Seal Repair FW-54 12/4/95 @ 0900 Cooling Water Pump SO-O-1 FC/ FORM Page 2 of 3

FORT CALHOUN STATION FORM FC-95 TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS REPORT MADE EOUIP. OOS DATE/ TIME T.S. / ODCM / G-103 LCO _XES- _N_1 N/A SI-2B 12/5/95 1900 T.S. 2.3 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months X l

REMARKS:

OFF-GOING SHIFT ON-COMING SHIFT S.S.

L.S.O.

L.O.

L. O. .<

C.R. COMMUNICATOR STA S0-0-1 FC/ FORM Page 3 of 3

. . . . . - . . . - . _ . . - . . . . ~. . ..-. - . . -. -. . . . - - . - - . ~ . - . . . - - . -. - .

ES-301 Operator Actions Form ES-301-4 i

f l Scenario No.: FCS-1 Event No.: 1 Page I cf 9 i

Event

Description:

Dropped Control Rod i

Time Position Applicant's Actions or Behavior l RO Indentify event from alarms.

4 RO Determine only one rod has dropped.

SRO Enter AOP-02 (CEDM Malfunction) i j SRO Direct BOP to adjust turbine load to match reactor power.

BOP Adjust turbine load to match reactor power.

SRO Direct RO to control pressurizer pressure and level.

RO Monitor pressurizer pressure and level.

SRO Notify Reactor Engineer.

SRO Consult Tech Spec 2.10.2. (Note: Requirements of this Tech Spec are covered in the actions required by AOP-02)

SRO Inform RO and BOP that Tech Specs requires a power reduction to less than 70% within one hour.

SRO Notify System Operations ofimpending power reduction.

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ES-301 Operator Actions Form ES-301-4 l Scenario No.: FCS-1 Event No.: 3 Page 2 of 9 Event

Description:

Power Reduction to 70% within one hour.

Time Position Applicant's Actions or Behavior SRO Direct RO and BOP to commence power reduction.

SRO Direct RO on method of boration to use. (Options are nonnal !

boration, shifting charging pump suction to the SIRWT, or l entering AOP-05 (Emergency Shutdown)) j RO Begin boration. I BOP Reduct tur'oine load to control RCS Tc.

1 RO Monitor and control primary parameters during power reduction. !

BOP Monitor and control secondary parameters during power l reduction.

1 4

ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 2 Page 3 of 9 Event

Description:

Controlling Pressurizer Pressure Channel Fails AS IS.

Time Position Applicant's Actions or Behavior RO Identify deviation between pressurizer pressure channels.

SRO Direct RO to swap controlling channels or to take manual control of pressurizer pressure.

RO Switch controlling channel or take manual control of pressurizer pressure.

RO Monitor and maintain proper pressurizer pressure. l L l l

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ES-301 Operator Actions l'orm ES-3717 Scenario No.: FCS-1 Event No.: 4 Page 4 of 9 Event

Description:

Steam Header Pressure (I'I'-910) fails high causing turbine bypass valve Time Position Applicant's Actions or Behavior BOP Identify rapid decrease in RCS Tc.

BOP Determine cause as bypass valve being open.

SRO Direct BOP *c take manual control of PCV-910 and close it.

BOP Tek c ' ontrol of PCV-910 and close it.

BOP Monitor RCS Tc RO Monitor and control RCS parameters.

4

ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-1 Event No.: 5 Page 5 of 9 Event

Description:

Inadvertent SGIS Time Position Applicant's Actions or Behavior BOP Identify and communicate SGIS.

SRO Direct RO to manually trip the reactor.

RO Take action to manually trip the reactor.

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ES-301 Operator Actions Form ES-301-4 ,

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l Scenario No.: FCS-1 Event No.: 6 Page 6 of 9 Event

Description:

ATWS l A

Time Position Applicant's Actions or Behavior 4

l RO Determine and communicate that the reactor failed to trip.

SRO Direct BOP to initiate DSS (Diverse Scram System).

BOP Take action to initiate a manual DSS trip.

BOP Determine and communicated that DSS did not actuate, j

SRO Direct the RO to open the clutch power supply breakers. I RO Open the clutch power supply breakers. l BOP Determine and communicate that the rods have inserted.

SRO Direct RO and BOP to take Standard Post Trip Actions (SIrrAs).

RO Perform Standard Post Trip Actions - Identify and communicate low CCW pump discharge pressure. (Event 7).

BOP Perform Standard Post Trip Actions - Indentify and communicate Loss of Feedwater. (Event 8).

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ES-301 Operator Actions Form ES-301-4 1

l Scenario No.: FCS-1 Event No.: 7 Page 7 of 9 Event

Description:

CCW Pump Discharge Header Pressure (PT-499) fails low.

Time Position Applicant's Actions or Behavior RO Identify and communicate CCW Pump discharge pressure is i indicatmg low.

l RO Check other CCW parameters.

RO Report other parameters are OK.

RO Direct EONA to check local CCW pump discharge pressure j indication.

! (EONA) Reports normal CCW discharge pressure RO Determines and communicates failure of CCW pressure j instrument.

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4 ES-301 Operator Actions Form ES-301-4 1

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l Scenario No.: FCS-1 Event No.: 8 Page 8 of 9 Event

Description:

Total Loss of Feedwater.

j Time Position Applicant's Actions or Behavior j BOP Determine and communicate Loss of All Feedwater.

SRO Direct BOP to attempt to restore feedwater flow.

BOP Attempt to start motor driven AFW pump (FW-6).

) BOP Attempt to stut turbine driven AFW pump (FW-10).

2 BOP Report AFW pumps cannot be started.

j S'RO Direct BOP to override isolation of FW valves.

j BOP Report that FW valves cannot be opened.

i SRO Enter EOP-06 or EOP-20 SRO Direct RO to trip all RCPs i RO Trip all RCPs l SRO Direct BOP to isolate blowdown.

BOP Isolate blowdown

! SRO Dimet BOP to monitor S/G level for Once Through Cooling.

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] BOP Report when level is approaching 20% on both S/Gs

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i i ES-301 Operator Actions Form ES-301-4 i

Scenario No.: FCS-1 Event No.: 9 Page 9 of3

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! Event

Description:

Initiate Once Through Cooling Time Position Applicant's Actions or Behavior j SRO Enter EOP-20/HR-4.

i SRO Direct RO to initiate Once Through Cooling.

RO Open all HPSIloop injection valves.

RO Start all available HPSI and Charging Pumps.

i RO Pull two HP RPS Trip Units in order to open the PORVs. (Note:

Due to hardware limitations, pulling the trip units must be

! simulated. It may be necessary for the examiner to cue the j applicant that the trip units are pulled.)

RO Verify PORVs have opened.

RO Report Once Through Cooling is initiated.

l SRO Direct RO and BOP to monitor parameters.

j RO Monitor primary parameters.

l BOP Monitor secondary parameters.

I Scenario ends when Once Through Cooling has been initiated or PORVs are open.

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i ES-301 Scenario Events Tgm ES-301-3 Simulation Facility: Fort Calhoun Scenario No.: FCS-2 Examiners: Applicants:

Initial Conditions : 50% power - MOL (IC - 8)

Turnover: FW-54 ( Diesel driven AFW pump) and SI-2B (HPSI pump) tagged out of senice. Continue increasing power toward 100%.

Event M alf. Event Event Description No. No. Type *

[1hg;3 .EDS2B ~ LCPSg; :Pault en bos3B3M4MNo' power W SI-2Ci .<.m/^gMW 4 ' p' 7 sh MWi!!(

C"' -

Min f '~ V *9FTt@ gge$$ $ 8 @~lsA,S'

Ya <

1. XMc.-. T2n ,.. il.=e.,W, ,, PT-210 fhits,l,ow c,ausing loss,di,esdo,wn, flow '. , ,'

,. : ,s L l2.N,tiW , , s

@'%$h> > Y!$j,.,.)

s

^

g,$.!-3 ' " Ah O + ffij , s C, < 0. 's S- , , v </ t '; g ( > ' /x s

> 5 'g' j >

M

.Qi Jr..

^

!XMT. .ps4 T.a&g,@, s y ,-

.p[gd . ,iET.,&.M,.m,t.e.

.a y '

$jf['ig$[.2 "$$$ d , Z'?y jiV. y;fg am..,,,,'

,z

/d5f',j;;M,A,,ti,ls.i,w

, p.,

' attu,4'h[h'$

, . ' - i,, ?.,',irtag manual S/G lev y W'" 5. fi$dK ;pY ; ., e. s s<

l ^A ,,r R, =CP. 9....D. $w$a,s..

. R.,.n e. .,x fisG , . ,, : ?4 w w

W ** 14we,y>~ > .im awW ~y*/s t

M.w.pd

'4

~.

RCP10DE , .

r.,iod A;SJ.. ni,d. d..ien, 4s, .,,,,ga r

'o.n. .,~R. .CP-D 4

! 5 R/N Emergency Shutdown (RCSIHj. ys< !Small,m @ gpm) > , J "; ggt E ^ >,- ' y, l

4is - - .E[k.

.s a:y ,

ga.rfs <5

y. 3. g

, .

K. . .

.>,. .gg .g mx.

ss . s, ss s8-s

< s ' + "

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7 ESFSA I Failure of automatic PPLS (preset malfunction) i ESF5B Shaded entries are to be initiated by a cue from examiner.

i

(N)ormal, (R)cactivity, (I)nstrument, (C)omponent, (M)ajor !

Examiner: C Ms&2 - L fc //

/

Chief Examiner: ,T/ /,/* Mu /

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4 .x .,,, a a ~ - - - - --e aw e -a- -- .--.m4 4---* e'--

CONFIDENTIAL - NRC EXAM - FCS #2 - Simulator Operator Instructions initial Condition - 50% power, BOC Use IC-8 SI-2B tagged out of service Hang Tag FW-54 tagged out of service LOA AFW21, stop(0)

LOA AFW22, local (1)

Hang Tag Night shift Set clock on wall to 2300 Initial Malfunctions Setup RCP seal failure MAL RCP10D 100%, C=JMLRCP9(4)

Setup PPLS Failure MAL ESFSA F MAL ESF5B F START Verify Horns are on Fault on bus 183A-4A on cue from examiner MAL EDS2B PT-210 (letdown backpressure) fails low XMT CVC8, O FT-907 (SIG A Steam flow) fails low XMT SGN8, O Lower and middle se'als fail on RCP D MAL RCP9D 100%

900 gpm LOCA in loop 2B cold leg MAL RCS1H,0.5%

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TODAY Days [ ] Aftemoons [ ] Nights [ X ]

PLANT STATUS .

1 MODE: 1 [X ], 2 [ J,3 [ ] Rx Power: 50 % Rod Position: G4 @ 75 inches ;

1 P,cs (> 2075 psia): 2110. psia: Tcom (< 543*F): 140*F; Lua (48 TO 60%): 51 % ,

1 COMMENTS: RCS Boron concentration = 562 ppm Rate of oower increw 5-7%/hr i 1

Maintain ASIi0.01 SAFEGUARD STATUS:

(Log any Out Of Service Safeguards Equipment, include major fire protation equipment)

SI-2B RECENT TEMP MODS: (Within the last month)

TM NUMBER DATE DESCRIPTION RELEASES IN PROGRESS: YES NO Release No.

Monitor Tank [ A or B ] X-Waste Ga3 Decay Tank [ A, B, C, or D ] X Containment Pressure Reduction X Lagoon [ East or West ] X t

I of 3

PROCEDURES and SURVEILLANCE IN PROGRESS / OVERDUE: I TEST REASON

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I INSTRUMENT / ANNUNCIATOR STATUS:

(only app les when Compensatory Action is required)

ITEM / LOCATION DATE COMPENSATORY ACTION TAKEN IEMPORARY CLEARANCES:

TAGOUT NO. EOUIPMENT REASON l

MAJOR EOUIPMENT OUT-OF-SERVICE:

EOUIPMENT BATE / TIME REASON l

SI-2B 12/5/95 @ 1900 Seal Repair FW-54 12/4/95 @ 0900 Cooling Water Pump l

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2 of 3

1 TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS REPORT MADE l EOUIP. OOS DATEmME T.S. / ODCM / G-103 LCO YES _MQ N/A SI-2B 12/5/95 1900 T.S. 2.3 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months X i i

1 REMARKS:

OFF-GOING SIIIFT ON-COMING SIIIFT S.S.

L.S.O.

L.O.

L.O.

C.R. COMMUNICATOR STA

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l Scenario No.: FCS-2 Event No.: 1 Page 1 of 7 l

Event

Description:

Fault on Bus IB3A-4A 4

Time Position Applicant's Actions or Behavior I BOP Identify and Communicate fault on Bus IB3A-4A.

SRO Enter AOP-32 (Loss of 4160 V Bus or 480 V Bus Power)

SRO Direct Plant Stabilization and Diagnostics section of AOP-32.

RO Verify CCW, RW, Charging Pumps, RCPs, and RCS Pressure.

! BOP Verify Vital 4160 Bus, Bearing Cooling Water, Instrument 1 Air, and S/G Levels.

l SRO Determine that there is no power to SI-2C. l i SRO Consult Tech Spec 2.3 j SRO Inform RO and BOP of 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO per Tech Spec. l SRO Make outside notifications of LCO status.

j BOP Log Tech Spec Entry.

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ES-301 Operator Actions Form ES-301-4 Scenario No.: FCS-2 Event No.: 2 Page 2 of 7 Event

Description:

Letdown Backpressun: Instrument (PT-210) fails low - Letdown Isolates. r Time Position Applicant's Actions or Behavior RO identify and communicate loss of Letdown RO Determine and communicate loss of letdown due to PCV-210 being closed.

SRO Direct RO to take manual control of PCV-210 and reestablish letdown flow.

RO Take manual control of PCV-210 and reestablish letdown.

RO Report that PT-210 is failed.

SRO Notify I&C of irr-210 failure RO Monitor and controlletdown. -

BOP Monitor secondary parameters l

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i li ES-301 Operator Actions Form ES-301-4 l

i I Scenario No.: FCS-2 Event No.: 3 Page 3 of 7 l 1

j Event

Description:

Steam Flow (FT-907) Fails Highs I

1 j Time Position Applicant's Actions or Behavior )

BOP I.dentify and communicate lowering FW flew and level in S/G I B'

SRO Direct BOP to take manual control of feedwater.

BOP Take manual contol and restore feewater flow, i'

BOP Identify FT-907 as failed instrument.

SRO Inform I&C of failure of FT-907.

BOP Continue to monitor and control S/G level. l RO Monitor primary parameters.

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l ES-301 Operator Actions Form ES-301-4 i

j Scenario No.: FCS-2 Event No.: 4 Page 4 of 7

Event

Description:

RCP 'D' Lower and Middle Seal Failures.

Time Position Applicant's Actions or Behavior RO Identify and communicate High Seal Leakage from alarms.

SRO Enter Alarm Response Procedure.

RO Monitor RCP seal pressures and determine lower and middle seals have failed.

SRO Direct Emer Shutdown) gency Shutdown and enter AOP-05 (Emergency BOP Monitor Secondary Parameters 4

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ES-301 Operator Actions Form ES-301-4 j 1

Scenario No.: FCS-2 Event No.: 5 Page 5 of 7 e

, Event

Description:

Emergency Shutdown l

Time Position Applicant's Actions or Behavior

SRO Direct RO and BOP to commence Emergency Shutdown SRO Direct RO to begin boration using SIRWT.

j RO Switch charging pump suction from VCT to SIRWT.

BOP keduce turbine load to control RCS Tc.

]

l RO Operate control rods as necessary to control ASI.

l RO Monitor primary parameters.

d BOP Monitor RCS Tc and secondary parameters.

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ES-301 Operator Actions Form ES-301-4 l

Scenario No.: FCS-2 Event No.: 6 Page 6 of 7 Event

Description:

Small LOCA (900 gpm)

Time Position Applicant's Action, or Behavior RO Identify and communicate lowering of pressurizer level and pressure.

{

SRO May direct RO to manually trip the reactor.

RO Manually trip the reactor if directed by SRO.

SRO Direct Standard Post Trip Actions (SPTAs)

RO Perform SFTAs BOP Perform SFTAs RO Secure 1 RCP in each loop at 1350 psia.

RO Secure remaining RCPs on loss of NPSH SRO Transition to EOP-03 (LOCA). !

)

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. ES-301 Operator Actions Form ES-301-4 ,

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4

Scenario No.: FCS-2 Event No.: 7 Page 7 of 7

] Event

Description:

Failure of Automatic PPLS

{ Time Position Applicant's Actions or Behavior RO Monitor for automatic PPLS actuation. I RO Determine and repon that PPLS has failed to actuate, ,

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{ SRO Direct RO to manually initiate PPLS

, RO Manually initiate PPLS.

RO Verify and report PPLS actuation.

RO Verify and report meeting HPSI flow criteria.

'. Scenario ends when HPSI flow is restored and is meeting flow criteria.

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, ES-301 Administrative Tooics Outline Fonn ES - 301 - I Examination Level: RO

[ Facility: Fort Calhoun Week of Examination: 12/04/95 i j

Examiner's Name (print): .

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Administrative - Describe method of evaluation:

j Topic / Subject 1. ONE Admmistrative JPM, OR

Description 2. TWO Administrative Questions j- A.1 Plant a. What action should be taken by a RO if a parameter is found to be out of Pammeter specifications on the OP-ST-SHIFT-0001 log?

Verification

b. How do you conduct a channel check of pressurizer pressure channels?

?. i l Shift Staffmg c. Required time between shifts?

i Requirements

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' d. Personnel required to be in the "at the controls" area of the control room?

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, A.2 Tagging and What is the difference between " independent verification" and " concurrent l- verification" ?

j Clearances

$ l j Who can install and remove Hold Onler Tags?

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j A.3 Radiation JPM - RCA Entry l i Control i l 1

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l A.4 Emergency Who is called to the control room to make required notifications during an E-Plan plan event?

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What are the four Emergency Classifications in order of severity, lowest to W@m?

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2 CLOSED REFERENCE QUESTION A.1-a:

i What action should be taken by a RO if a parameter is found to be out of specifications on the OP-ST-SHIFT-0001 log?

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ANSWER: .

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It should be reported immediately to the Shift Supervisor or LSO. 1 Plant reference: SO-O-1 K/A 194001 A1.06 3.4/3.4 The operator's response was:

l SATISFACTORY UNSATISFACTORY COMMENTS:

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l CLOSED REFERENCE QUESTION A.1-b:

How do you coaduct a channel check of pressurizer pressure channels A/B/C/DP-102?

ANSWER:

A Channel Check is conducted by comparing the channels with one another and with other channels measunng pressurizer pressure Plant reference: Tech Spec definition of" Channel Check."

K/A: 194001 A1.06 (3.4/3.4) l The operator's response was:

1 SATISFACTORY UNSATISFACTORY COMMENTS:

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i CLOSED REFERENCE QUESTION A.1-c:

4 If you were scheduled to work from 1500 - 2300 on a Friday, and stayed over two additional hours to help with a surveillance test, when is the soonest time you could return to work a 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift on Satuniay, excluding turnover?

.l ANSWER:

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, Saturday at 0900. [Must have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months off between shifts.]

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1 Plant utference: S0-0-1 i K/A: 194001 A1.03 (2.5/3.4) l The operator's response was:

1 SATISFACTORY UNSATISFACTORY a

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COMMENTS:

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l CLOSED REFERENCE QUESTION A.1-d:

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The plant is in mode 1. You are the only licensed operator (RO/SRO) in the "at the controls" area of the l control room when an annunciator alarms on a back panel. Are you allowed to leave the "at the controls" area to acknowledge the alarm?

ANSWER:

NO (A licensed individual ,RO or SRO, is always required to be in the "at the contmis" area in mode 1. ,

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Plant reference: S0-O 1 i l

K/A: 194001 Al.03 (2.5/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

4

CLOSED REFERENCE QUESTION A.2-a:

What is the difference between " Independent Verification" and " Concurrent Verification" as applied to tagouts?

I ANSWER:

Independent verification is checking that components are in the required, safe configuration. His checking is done separate from the initial tagging or repositioning of components.

Concurrent Verification is the act of checking the position or condition of a component concurrent with the activities establishing the component's position or condition.

Plant erference:SO-G-20A l

K/A: 194001 Kl.02 (3.7/4.1)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS: !

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S CLOSED QUESTION A.2-b:

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What two organization's personnel can install and remove Hold Order Tags?

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l ANSWER. I l

l Only System Operations and Electric Operations personnel are allowed to install or remove Hold Order ,

Tags? l l

Plant reference: SO-G-20A j K/A: 194001 Kl.02 (3.7/4.1) i 1

'Ihe operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS: l l

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Topic (s): RCA Entry and Exit Location (s): RCA Access Control Approximate Time: 10 minutes ActualTime :

Reference (s): (1) GET . Radiation Worker Training (2) NRC K/A 194001. Kl.03 (RO2.8/SRO3.4)

(3) NRC K/A 194001, Kl.04 (RO3.3/SRO3.5)

Verify current reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reaton, if unsatisfactory :

i Operator's review : Date:

Tools & Equipment : None Safety Considerations: This JPM requires entry into the RCA.

t Coinments: i t

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initiating Cue

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1 An entry into the RCA is required as part of the operating exam. START i

CRITICAL STEP

ELEMENT STANDARD l 1.* Review RWP. Read RWP

2. Check survey maps Check survey maps for radiological conditions in areas to be entered 3.* Obtain dosimetry Verify TLD attached to security badge. Obtain i ALNOR I.

4.* Sign in on appropriate RWP Insert ALNOR into reader, enter PID and RWP number.

5. Infonn RP Personnel about the nature of Tell RP at access control where you are going 3

your entry and what you will be doing.

i, 6. Enter RCA RCA entered 7* Comply with all posting within RCA No violation of posted requirements i 8.* Monitor for personnel contamination prior Monitor for contamination using PCM-1 or to exiting frisker.

9.* Sign out of RCA Insert ALNOR in reader, Enter PID number, j confirm dose and place ALNOR in charging j rack.

Ternination Criteria: RCA has been exited.

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I l CLOSED REFERENCE QUESTION: JPM-RCA-RO/SRO-1 !

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I What action should be taken if your ALNOR alarms?

ANSWER: I l'

l Go to low dose waiting area and contact Radiation IYotection..

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REFERENCE:

I l GET Radiation Worker Training

( NRC K/A 194001 Kl.03 (2.8/3.4)

The operator's response was:

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l SATISFACTORY UNSATISFACI'ORY l

COMMENTS: 1 l

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CLOSED REFERENCE QUESTION: JPM RCA-RO/SRO-2 What action should be taken if the PCM 1 alanns when frisking?

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ANSWER:

Back out of the frisking booth and follow directions on the LED readout. If the PCM-1 alarms a second time, note the contaminated area and contact Radiation Protection.

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REFERENCE:

GET Radiation Worker Training NRC K/A 194001 Kl.04 (3.3/3.5)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

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CLOSED REFERENCE QUESTION A.4-a:

Who is called to the control room to make required notifications during an E-plan event?

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ANSWER: ;

I The control room conununicator. ;

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Plant reference: EPIP-OSC-1 K/A: 194001 Al.16 (3.1/4.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

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CLOSED REFERENCE QUESTION A.4-b:

What are the four Emergency Classifications in order of severity, from lowest to highest?

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ANSWER:

Notice of Unusual Event, Alert, Site Area Emergency, General Emergency.

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1 Plant reference: EPIP-OSC-1 l 1

I K/A: 194001 Al.16 (3.1/4.4) i 1

1 The operator's response was: l l

I SATISFACTORY UNSATISFACTORY l

l COMMENTS:

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1 PS.301 Iadivida=1 Walk-through Igg Oneline Form ES-3N : .

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- Examination Level: RO i Facility: Egg Calhoun Week of Exammation: 12.04/95

{

Examiner's Name (print):

System / JPM Safety Planned Follow-up Questions:

l K/A/G //Importance // Description Function -

l}

1.0008 ASP-Emergency I a. RCS temerature response to Emergency Boration.

000024EK1.01//3.4/3.8// Relationship - Temp to Boration Boration from the Control Room b. Conditions reqmring Emergency Boratian 000024EK3.01//4.1/4.4//When Emergency Boration Required

l. 2. 0293 - Backfeed 345 kv - VII a Whant relays followmg trip?

I to 22 kv 062000A4.01//3.3G.1// Operate and monitot breakers o

B. White light condition?

l 000006SG7//3.00.2// Purpose of controls.

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3. 0347 - Unload D/G #1 VII a. Push stop button prior to unloading D/G.

j 000064A4.06//3.9G.9// Manual start, load and stop of D/G

b.Effect of governor not run down on stoppmg D/G 000064A4 06/G.9/3.9// Manual start, load and stop of D/G

{

4. 0778- AdjustT-cold IX a.Why adjust to highestT cold?

calibration on the RPS 000012A1.01//2.9/3.4//I' rip setpoint adjustment Panel- b.How to trip RPS bastable?

l 000012K4.06/G.2/3.5// Enable RPS trips

5. 0138 - Operate CVCS to II a.Why flush mak .up header after fdling SIRWT7 makeup to the SIRWT 000004A2.06//4.2/4.3//inadvertant boration/ dilution -

' b.SIRWT levelinstr=nensation?

000006K4.16//2.6/3.0// Water loventory Control 1 Simulator JPMs above this line. Plant JPMs below this line

@ 0719 - Startup Hydrogen VI a. Purpose of charcoal fdters

{ 000027K5.01//3.1/3.4// Purpose of charcoal filters l Purge System

! b.Other systems that can use hydrogen purge filters.

000027K5.01//3.1/3.4// Purpose of charcoal filters i _

, '7.))295 - Switch Inverter VII a.Remann for " sync loss" light - 1

! Mupply from Bypass to 000062A2.15//2.8/3.2// Consequence - frequency mismatch j Normal (modify to alternate b.Why do inverters use DC power? ;

!- path) 000057EA2.14//3.2/3.6// Substitute Pt.wer sources on-line

8. 0214 - Shift Inservice Air VIII a. Serv;ce air / Instrument air difference i-Co wr w ars 000078K1.02//2.7/2.8// Service-Instrument air connections 3-

b. Normal and backup compressor cooling j-000078K1.04//2.6/2.9// cooling water to compressor j

i 9. 0010RW - Loss of X a.Why CCW surge tank r 6si?

Component Cooling 000008A2.01//3.3/3.6// lass of CCW pump i l Is.When do CCW contamment isolation valves close?

Water (Raw Water) l 000026EK3.02//3.6/3.9// Automatic Actions ESFAS V a. Tune to empty EFWST.

t'10jNew - Makeup to the l

hgencyIMtwater 000061K4.01//3.9/4.2// Water souxes and priority 4 Storage Tank Wog b. Diesel fire pump start signal Diesel Fire Pmp 000086K4.02//3.0/3.4// Maintain fire header pressure.

i ChiefExaminer: E ' A #" #

E*aminer: WM -

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CJNFIDENTIAL - NRC EXAM - JPMs 138 and 778 INITIAL, CONDITIONS - 100% Power Use IC#1 Tc channel A deviation Adjust Channel A 0.4'F below other channels f

1 4 Open CH-152 LOA CVC24100% 1 l

i Optain blend sample when requested MONV XBATBLDR i

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j CONFIDENTIAL - NRC EXAM - JPMs 008 ASP, 347 and 0293 s

INITIAL CONDITIONS - Hot Shutdown Shutdown Use IC-15

groups withdrawn Start DG-1 Start DG-1 and load to 2500 kw i i I Override HCV 268 closed VLV CVC24 0%

J j Override LCV-218-2 open VLV CVC20100%

Verify DS-Tl open

. Place lAl and 1A2 on 161 kv '

J Open breaker 3451-4 and 3451-5 A

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l Revision: 6 October 24,1995 Fort Calhoun Station - Operations training ,

JOB PERFORMANCE MEASURE l JPM No: JPM-0138 Operate CVCS to makeup to the SIRWT I 1

System (s): CVCS Location (s): Simulator Approximate Time: 13 minutes ActualTime :

Reference (s): (1) OI-CH-4-6.10 R16 (2) TS-2.2, 2.3 l (2) NRC K/A 000004, K1.01 (RO3.4/SRO3.9) i (3) NRC K/A 000004, A2.06 (RO3.8/SRO3.9) )

Verify current reference revisions match those listed above l

I Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY I

I Evaluator's Signature : Date :

i Reason,if unsatisfactory : !

l l

l Operator's review : Date:

i Toolg & Equipme .t : None Safety Considerations:

Comments : This JPM will normally be performed as a dynamic JPM on the Simulator. It is not intended to add all of the water and boric acid necessary per the calculation, but rather to prove the ability to conduct the ERF procedure and then prove ability to operate the CVCS system to make up to the SIRWT.

Open CH-152 [ LOA CVC24100%)

i Revi'fon: 6 October 24,1995 Fort Calhoun Station - Operations training i JOB PERFORMANCE MEASURE JPM No: JPM-0138 Operate CVCS to makeup to the SIRWT

, Initiating Cue:

4 The plant is operating at 100% power. SI tanks have just been filled. The SIRWT level is 186 inches. The latest SIRWT boren was 1910. ppm. Both Boric Acid tanks are at a concentration of 3%.

The Shift Supcivisor dincts you, the LO, that the SIRWT be blended up to 190". Use CH-4A, Boric Acid pump. All prerequisites are met. START CRITICAL STEP

ELEMENT STANDARD

1. Iscate copy of OI-CH-4 NOTE: Give copy of procedure to candidate after located.

1. DETERMINE flow rate for Refer to OI-ERFCS-1, procedure 31 OR hand conantration of 1910 ppm. calculation.

2. Verify WD-250 is locked open CUE: EONA reports WD-250 is locked open.

3. Ensure FCV-269 is in close. CB-4 FCV-269 switch is in close and GREEN light is lit.

4. Place HC-269 in manual HC-269 switch in manual i

5. Ensure Boric Acid recirculation valves Both switches in close position and GREEN are in closed: lights lit.

HCV-264 HCV 257

6. Station EONA to watch SIR %T vents. CUE: EONA is watchingSIRWT vents

7. Place 14V-218-3 in close. CB - 1,2 ,3 LCV-218-3 switch in closed and GRELW light lit.

8. Open CH-152 CUE: EONA has opened CH-152

CB-4

9. Start Boric Acid pump Place cont. : switch for CH-4 A to start and observe RED tight lit.

10. Place FCV-269Y and FCV-269X in Switches in open and RED lights lit.

open.

11. Set the makeup flow controllers to the CB-4 desired flow rates to obtain proper boron Adjust flow control on FRC-269Y and FRC-concentration. 269X to obtain desired flow rates.

Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 !

Operate CVCS to makeup to the SIRWT i

W CRITICAL 3

STEP

ELEMENT STANDARD

12. Obtain sample ofblend Direct Chemist (simulator operator) to obtain bien.1 sample.

to SIRWT.

CUE: Simulator Operator will report concentration at blender [ XBATBLDR).

CUE: When concentration at blender is reported to be 1910 ppen or gitater then provide cue that SIRWT level is 190".

13. Stop blend to SIRWT FCV-269Y switch in close. GREEN light lit. ,

5

14. Stop Boric Acid pump CH-4A switch in after-stop and GREEN light lit.

I

15. Flush piping with Leave FCV-269X open after FCV-269Y has been closed.

d mineralized water. CUE: Flush of piping is complete.

16. Close FCV-269X CB-4 FCV-269X switch in close and GREEN light lit.

17a. Close CH-152 CUE: EONA has closed CH-152.

17b. Place HC-269 in Switch placed in DILUI'E DILUTE

Place LCV-218-3 in AUTO LCV-218-3 switch in auto. GREEN and AMBER lights lit.

Termination Criteria: SIRWT level is atturned to normal l

1

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Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0138 Operate CVCS to makeup to tiie SIRWT 1

CLOSED REFERENCE QUESTION: JPM-0138-RO-1 4

When secunng the line-up for filling the SIRWT, how do you ensure that the ukeup header to the VCr is not at the SIRWT boron concentration?

1 ANSWER:

By secunng the boric acid make-up and flushing the header to the SIRWT with demineralized water.

l

REFERENCE:

OI-CH-4 K/A000004 A2.06 (4.2/4.3) 1 The operator's response was:

SATISFACTORY UNSATISFACTORY i

4 COMMENTS:

.(

e

.- . . . . . . . ~ . .. . . . . . . . .- ._ - _ . - . _ . - --. _

Revision: 6 October 24,1995 i

, Fort Calhoun Station - Operations training

JOB PERFORMANCE MEASURE JPM No: JPM-0138 !

Operate CVCS to makeup to the SIRWT l CLOSED REFERENCE QUESTION: JPM 0138-RO-2 What type of device is used to measure SIRWT level as indicated on AI 30A and AI-30117 l

ANSWER:

Pneumatic bubblers are used to nr.asure SIRWT level.

REFERENCE:

ECCS STM page 6 NRC K/A 000006 K4.16 (2.6/3.0)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTE:

.i

f Inlilating Cue:

The plant is operating at 100% power. SI tanks have just beca filled. The SIRWT level is 186 i laches. 'Ihc latest SIRWT borne was 1910.ppen. Both Boric Acid tanks are at a concentration of i 3%. The Shift Supervisor directs you, the LO, that the SIRWT be blended up to 190". Use CH-4A, l Boric Acid pump. All pienquisites are met. START l

I 1

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6 s

l FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 21 OF 32 R

Reference Use Attachment 7 i Filling the SIRWT l PREREQUISITES JMTm

1. Procedure Revision Verification Master Revision Number Date:

2. A Deaerated Water Booster Pump, DW-43A or DW-438, is in operation i OR if cross-connected to Demin Water, a Demineralized Water Booster i j Pump, DW-41 A or DW-41B, is in operation, j j 3. One Boric Acid Pump is operable.

PROCEDURE CAUTIONS If the Reactor is critical, the amount of Boric Acid remaining in the Boric l Acid Tank (s) must be sufficient to meet the requirements of Technical Specification 2.2(2)c. j When fuel is in the Reactor the simuitaneous filling of the SIRWT with ,

blended makeup while making up to the RCS via the Safety injection pumps should be avoided unless positive Chemistry analysis of the i

blended flow to the SIRWT verifies a boron concentrations at or above Refueling Boron Concentration. This is to prevent underborated water being injected into the Reactor Core.

1. Using OI-ERFCS-1 determine the Boric Acid and Makeup Water flow rates required to give a blended flow of at least the Refueling Boron Concentration

2. Verify WD-250 is locked open by either local observation or referring to the Locked Component Deviation Log to ensure that the valve has not been repositioned.

3. Ensure FCV-269, Makeup Water Control Valve, is in CLOSE.

4 R16 FC/OI

FORT CALHOUN STATION Ol-CH-4 OPERATING INSTRUCTION PAGE 22 OF 32 R

Reference Use Attachment 7 1 Filling the SIRWT i

P90CEDURE (Continued) M) INIL !

4. Place HC-269, Makeup Water Mode Selector Switch, in MANUAL

5. Ensure Boric Acid Pump Recirculation Valves are closed:

e HCV-264

HCV-257

6. Station the Auxiliary Building Operator to watch SIRWT Vents to prevent overfilling.

7. Place LCV-218-3 in CLOSE.

8. Opan CH-162, Manual SIRWT Makeup Stop Valve.

9. Start Boric Acid Pump CH-4A or 4B.

10. Place the following Makeup Flow Control Valves in OPEN:

e FCV-269Y, Boric Acid e FCV-269X, Demin Water

11. Set the Makeup Flow Controllers to the desired flow rates to obtain proper Boron Concentration.

e FC-269Y, Boric Acid e FC-269X, Demin Water

12. Notify Chemistry to sample blended flow for Boron Concentration.

13. WH5N the desired SIRWT level is reached, THGN close FCV-269Y.

14. Stop the Boric Acid Pump.

15. Flush the non Heat Traced portions of the Makeup Piping with Demineralized Water.

R16 FC/OI 1

FORT CALHOUN STATION Ol-CH-4 OPERATING INSTRUCTION A 23 OF 32 l R l Reference Use Attachment 7 Filling the SIRWT PROCEDURE (Continued) .lNIL

16. Close FCV-269X.

17. Restore Makeup system to normal as follows:

a. Close CH-152.

I

b. Place HC-269 in DILUTE. I

c. Place LCV-218-3 in Auto.

4 l

Completed by Date/ Time: /

R16 FC/OI

b FORT CALHOUN STATION OI-ERFCS-1 OPERATING INSTRUCTION 4

PAGE 70 OF 101 l

PROCEDURE 31 REACTOR BLEND CALCULATION PURPOSE To provide step-by-step instructions for using the Reactor Blend Calculation (BLE) to determine the required makeup water flowrate to achieve the proper boric acid blend to the RCS.

DESCRIPTION The Reactor Blend Calculation uses initial PPM boron, % weight of boric acid, and desired flow rate of % weight boric acid. These user inputs are used to calculate the required flowrate of Reactor Makeup Water.

PROCEDURE 1

1. Type "BLE". '

2. Press [DSP].

3. The Opcon will prompt you to enter Initial PPM Boron.

l Type the value of Initial PPM Boron. l l

Press [ENT]. i

4. The Opcon will prompt you to enter the t Weight Boric Acid.

Type the value of % Weight Boric Acid.

Press [ENT].

5. The Opcon will prompt you to enter the Desired Flowrate of Boric l Acid.

Type the value of Desired Flowrate (in gpm) of Boric Acid.

Press [ENT].

6. The final result will be displayed and printed.

.s R15

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i 1 1 Revision: 5 October 24,1995 j Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE a

JPM No: JPM -0778

, Adjust T u Calibration on the RPS Panel 1

4 4

\

System (s) : Reactor Protective Sysicm j l

i*

Location (s): Simulator )

Approximam Time: 9 minutes ActualTime :

Reference (s): (1) OI-RPS-2, Attachment 1 (R3) !

(2) NRC K/A 000012, K4.01 (RO3.7/SRO4.0) s (3) NRC K/A 000012. A1.01 (RO2.9/SRO3.4)

Verify carrent reference revisions match those listed above

I i

e j Operator's Name: SS # :

1 l

j All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM. ;

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY f

Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None

. Safety Coasiderations: None Comments : khis JPM should be performed as a dynamic JPM on the simulator.

Use full power IC, Adjust Channel A Tc Cal. 0.4-F below other channels. Obtain key for Trip Unit 9.

d

i i

Revision: 5

? October 24,1995

- 1 Fort Calhoun Station - Operations training

, JOB PERFORMANCE MEASURE JPM No: JPM-0778

- A4pist T w Calibration on the RPS Panel ,

! I i

l- Inidating Cue:

l 'Ihe -lant has been operating for 30 days at 100% power. You, the LO, are taking your shift readings on

{ OP-Si'-SHIFT 1 and you notace Channel "A" T ,,, Cal. Is 0.4-F low. The shift supervisor directs you to l take the appropriate action to adjust the "A" Channel T Cal. All other channels are indicating within 3 0.1-F of each other. START l l

CRITICAL STEP

ETRMENT STANDARD i

! 1. Otain a copy of OI-RPS-2, Anachment 1 Procedure has been obtained.

i

2. Record T,,,, DVM readmgs on all channels. AI-31A/B/C/D RPSCIP Cn=niane fann

. 3. Record DVM readings on all T.,,, Cal. Complete form channels.

i,

! 4. Record T,,,, CAL. Pot settings Complete form i

i

5.* Bypass channel"A" TM/LP trip unit. CUE: Hand trip unit #9 bypass key to 2

candidate.

j Al-31 A BYPASS trip unit number 9 on "A"

[ channel, AMBER light lit.

t 6. Log into Tech Spec 2.15(1)- CUE: Log entry has been minde.

I 7.* Adjust T., Cal. Pot so the T Cal. Adjust Cal. pot Readmg on channel"A" DVM is the same

! as the highest T.,,, recorded l 8.* Remove bypass key from channel"A" Remove key and AMBER light off !

TM/LP trip unit Return key to Shift Supervisor.

l

9..' Exit Tech Spec 2.15(1) for the affected CUE: Log entry has been minde.

channel.

l 10. Record new T ,,, Cal. DVM readmgs. Complete form j 11. Record new T,,, Cal. Pot readmgs Complete form Terednation Criteria: All T.,,, Cal. channels read within 0.1-F of each other, j <

i l

Revision 5

, October 24,1995 I i

. Fort Calhoun Station - Operations trauung i JOB PERFORMANCE MEASURE l JPM No: JPM -0778 1

Adjust T,.w Calibration on the RPS Panel I

t i

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CLOSED REFERENCE QUESTION: JPM-0778-RO-1 I

Why do you adjust T,,,, Cal. To the highest T,,,,7

- i i

I i ANSWER:

l i Using the highest temperature will generate the most conservative TM/LP setpoint I

)

REFERENCE:

NRC K/A 000012 A1.01 (2.9/3.4) t The operator's response was:

4 SATISFACTORY UNSATISFACTORY e

.c l

COMMENTS:

i 1

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Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0778 Adjust Ta Calibration on the RPS Panel CLOSED REFERENCE QUESTION: JPM-0778-RO-2 How can you force a trip unit's bistable into the " tripped" condition?

ANSWER:

By partially pulling the Trip Unit out of the RPS panel .

REFERENCE:

RPS STM NRC K/A 000012 K4.06 (3.2/3.5) ne operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

.c d

.. . - . . . - - . . . . . . . - . - _ . . = _ _ - _ - - -. . . . . - - . . . .

l Initiating Cue:

l l 'Ihe plant has been operating for 30 days at 100% power. You, the LO, are taking your shift readings on OP-ST-SHIFT-1 and you notice Channel "A" T, Cal. Is 0.4-F low. 'Ihe shift supervisor duects you to take the appropriate action to adjust the "A" Channel T Cal. All other channels are inaca ting within 0.1-F of each other. START l

1 1

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h 4

Fort Calhoun Station i 1

Unit No. 1 OI-RPS-2 OPERATING INSTRUCTION

Title:

REACTOR PROTECTIVE SYSTEM - TM/LP TCOLD CAL CALIBRATION FC-68 Number: 43015 Reason for Change: Add req of S0-G-100 and log LCO's when hyoassing channels. Delete req ' perform this OI daily.

Contact Person: Dave Bannister

.c 4

ISSUED: 06-24-94 4:00 pm R3

FORT CALHOUN STATION OI-RPS-2 l

OPERATING INSTRUCTION PAGE 1 OF 4 REACTOR PROTECTIVE SYSTEM - TM/LP TCOLD CAL CALIBRATION l l

SAFETY RELATED 1.0 PURPOSE I To adjust, if required, the Tcold c01 POT (s).

)

2.0 REFERENCES

i 1

2.1 Reactor Protective System Technical Manual, I-151.

2.2 Technical Specifications:

i

1.1: Safety Limits - Reactor Core l

2.15: Instrumentation and Control Systems

3.1, Table 3-3, Item 17a: Reactor Coolant Inlet Temperature 3.0 SPECIAL EOUIPMENT/ INSTRUMENTATION 3

None j

4.0 PREREOUISITES 1

4.1 Reactor is in Mode 1.

4.2 Reactor powcr is greater than 15%.

4.3 Reactor is at steady state conditions.

5.0 PRECAUTIONS 5.1 Adjusting Tcold cal POT may cause a TM/LP trip if that channel is not placed in the Bypass Condition.

.t R3

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FORT CALHOUN STATION OI-RPS-2 ,

OPERATING INSTRUCTION PAGE 3 OF 4 l c

Continuous Use l

l

}

ATTACHMENT 1 I INITIATR NOTE: For all steps, enter N.C. for all channels not calibrated.

7.0 7.1~ Record Tcold cal POT settings.

A B C D CAUTION Only gna channel will be calibrated at a time.

7.2 Bypass TM/LP trip unit on the affected channel.

A B C D 7.3 Log into Technical Specification 2.15(1) 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months LCO due to affected channels trip units being in bypass.

l 7.4 Adjust Tcold cal POT located on the front of )

RPSCIP panel on the affected channel until the 1 Tcold cal DVM reads the same as the highest Tcold DVM recorded in step 6.1.

i A B C D 7.5 Remove Bypass Key for affected TM/LP Trip Unit.

~

A B C D 76 3 Exit Technical Specification 2.15(1) for the affected channel.

7.7 Repeat Steps 7.2 through 7.5 for any remaining channels out of specification.

7.8 Record Tcold cal DVM readings.

F F F F A B C D R3

. _ . . - ~. _ - . ..

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Revision: 4 ,

October 24,1995 l Fort Calhoun Station - Operations trammg JOB PERFORMANCE MEASURE .

1 JPM No: JPM -0347 i

Unload DG-1 4

l l

System (s): Diesel Generator Location (s): Simulator Approximate Time: 5 minutes ActualTime :

Reference (s): (1) OI-DG-16.11, R17 (2) NRC K/A 000062, K3.02 (RO4.1/SRO4.4)

(3) NRC K/A 000062, A2.11 (RO3.7/SRO4.1) l Verify current reference revisions match those listed above '

Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

.t Tools & Equipment : None Safety Considerations None Comments : This is designed to be a dynamic JPM on the simulator.

.-. . .=- .. _ ~ . _ - .- . _ . . . - - . .- - _ _ . . . . .

,i Revisisn: 4 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0347 Unload DG-1 l

Initiating Cue:

Diesel Generator DG-1 has been operating loaded and synchronized to bus 1A3, following a manual start You the LO, art directed to unload and stop DG-1. All start signals to the Diesel Generator have been cleared. The EONT is stationed at DG-1. START CRITICAL STEP

ELEMENT STANDARD

1. IAcate Copy of OI-DG-1 NOTE: Give copy of proadure to candidate after located.

2. Reduce load on DG-1 to approximately CB-20 300 kw. Use Governor Control DG-1 to lour Diesel Imad to (275 325) amps.

3. Open Breaker I ADI Open Breaker lADI and GREENlight lit

4. Operate Diesel Generator at 900 RPM Monitor Diesel.

for at least five minutes. CUE: 5 minutes have passed.

5. Ensure 86A/D1 and 86B/D1 are reset. Al-30A Lockout Relays are RESET:

Blackflag and AMBER lights on.

6. Stop DG-1 Depress both stop pushbuttons and hold for 10 seconds.

7. Verify DG-1 stops 0 RPM indicated OR Diesel tripped OR Annunciated Engine Stop light lit.

NOTE: any one of these indications is adequate.

8. Verify DG-1 is lined up for emergency All alarms cleared except " Diesel Auto Standby" ,

start. and" Breaker Auto Standby" l

9. Ensure DG-1 is setup for idle speed start. Hold governor control in auto for 15 seconds.

CUE: EONT repods that governor has run down Ternsiaation Criteria: DG-1 has been unloaded and is liacd up for emergency standby.

, Revision: 4 October 24,1995 j

Fort Calhoun Station - Operations training 1

JOB PERFORMANCE MEASURE JPM No: JPM-0347 Unload DG-1 OPEN REFERENCE QUESTION: JPM-0347-RO-1 i

What would happen if the stop pushbuttons were pushed prior to unloading the D/G7 i

ANSWER:

The output breaker would trip open and the D/G would shutdown.

i i

REFERENCE:

l Dies:1 Generator STM NRC K/A 000064 A4.06 (3.9/3.9) i The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

.c

d Revision: 4 4

October 24,1995 2

Fort Calhoun Station - Operations trauung JOB PERFORMANCE MEASUkE d

JPM No: JPM-0347 4 Unload DG-1 OPEN REFERENCE QUESTION: JPM 0347-RO-2 i

i j If the governor was not run down following the shutdown of the diesel generator, what would J happer. on the next uncomplicated reactor trip?

1 1

ANSWER:

i The diesel generator would start and its speed would increase to 900 RPM.

I I

1

REFERENCE:

Diesel Generator STM page 38 PRC meeting minutes " Diesel Generator Full Speed Start" j NRC K/A 0000064 A4.06 (3.9/3.9) i The operator's response was:

SATISFACTORY UNSATISFACTORY COMbiENTS:

1 i

.. ..-. . . - . _ _ . . . . - - - . _ . _ . - -. . _ . - - = . .. . - _

l l

Initiating Cue:

Diesel Generator DG-1 bas been operating loaded and synchannized to bus 1A3, following a manual start. You the LO, are directed to unload and stop DG-1. All start signals to the Diesel Generator have been cleared. The EONT is stationed at DG-1. START l

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FORT CALHOUN STATION OI-DG-1 OPERATING INSTRUCTION p PAGE 19 0F 32 Reference Use OPERATOR CHECK 6.0 PROCEDURE (Continued) M) 6.11 Manual Unloadina/Stoppino Diesel Generator DG 1 6.11.1 Verify all start signals to Diesel Generator have been cleared or bypassed (Refer to 4.4 PREREQUISITES).

CAUTION Governor controls are extremely sensitive. Load reduction must be done cautiously to prevent a reverse power condition.

6.11.2 Reduce DG 1 load to approximately 300 KW by taking Diesel Gen D1 Governor to LOWER.

6.11.3 Open Bkr IAD1.

CAUTION To prevent damage to the Static Exciter, do NOT run diesel at speeds less than 900 RPM after Generator Field Flash.

6.11.4 Operate diesel unloaded at 900 RPM for at least five minutes, but no longer than ten minutes.

6.11.5 Ensure 86A/D1 and 86B/D1 (AI-30A) are reset prior to attempting to shutdown the diesel.

6.11.6 Depress and hold for ten seconds both DIESEL STOP push buttons on AI-30A.

6.11.7 Verify DG-1 stops.

6.11.8 Verify all annunciators on Panel AI-30A-D1 are clear except DIESEL AUTO STANDBY and BREAKER AUTO STANDBY.

[6.11.9] Station an Operator at DG1 to locally observe rundown of the governor. la

[ NOTE]: The following two steps must be perfonned concurrently.

la

[6.11.10] Hold Diesel Gen DI Governor in LOWER for 15 seconds. la

[ NOTE]: Full rundown of the governor consists of approximately 8 to 9 revolutions of the Speed Setting knob in the la counterclockwise direction.

[6.11.11] (LOCAL) Observe rundown of the Diesel Generator ja governor.

6.11.12 Complete Form FC-1046.

R17

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Costnd Room System (s) : Abnormal / Emergency Procedures

!=tiaa (s): Simulator Appmximate Time: 7 minutes ActualTime :

Referenm 'a): (1) EOP-00 (2) NRC K/A 000001, K4.05 (RO3.9/SRO3.9)

(3) NRC K/A 000001, A4.02 (RO4.1/SRO3.9)

VerWy caritat reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contamed in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY l

Evaluator's Signature Date :

Reason,if unsatisfactory :

Operator's review : Date:

..t Tools & Equipment : None Safety Considerations: None Comments : Simulator Dynamic JPM Override HCV-268 closed and LCV-218-2 Open.

[VLVCVC24 0%) [VLV CVC20100%)

Revision: 5

October 24,1995 l Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Boration from the Control Room Initiating Cue: ;

A stactor trip has occurred and while performing EOP-00, you find that all shutdown rods have stuck out. All attempts to trip or insert control mds have failed. You are the LO, the LSO directs you to immediately commence emergency boration. LCV-218-2 is tagged out, physically stuck la the open position. START CRITICAL STEP

ELEMENT STANDARD CUE: No proceduits are allowed for this JPM.

1. Close FCV-269X and 269Y. CB-4 Control switches for FCV-269X & Y in CLOSED AND GREENlightslit.

2. Open allof the following valves: a. Control switch for HCV-268 to OPEN until

a. MCV-268 only RED light lit.

b. HCV-265 b. Control switch for HCV-265 to OPEN until

c. HCV-258 only RED light lit.

c. Control switch for HCV-258 to OPEN until only RED light lit.

3. Start ALL of the following pumps: a. Centrol switches to start a.Both Boric Acid Pumps CB-1,2,3

b. ALL charging pumps b. Control switches to start AND RED lights lit

4. Locally OPEN HCV-268 Direct EONA (simulator operator) to manually open HCV-268.

CUE: Simulator operator will wait approximately 2 minutes, open HCV-268 on a

.4 one minute ramp.

CUE: When red light is on, EONA reports that HCV-268 is open.

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Esmergency Boration frosi the Control Roon CRITICAL STEP

ELEMENT STANDARD F

Ensure ALL of the following valves are CB - 1,2,3 closed: a. GREEN light ut.

a. LCV 218-3

b. HCV-257 CB-4

c. HCV-264 b. GREEN light lit

c. GREEN light lit.

Termination Criteria : Borated water is being injected lato the RCS.

.t

.. ._ _ _ m _ _ . . -. 2m. . ___ ._. _ _ , - . - - ._ . - -

I Revision: 5 October 24,1995 1 Fort Calhoun StLtion - Operations training j JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emewy Beration front the Control Room CLOSED REFERENCE QUESTION: JPM-008 ASP-RO-1 What would happen to RCS cold leg temperature if emergency boration was initiated with the reactor at power? 1 i

l l

ANSWER: )

4 l

Cold leg temperature wouldlower. !

l 1

REFERENCE:

l l

NRC K/A 000024 EK1.01 (3.4/3.8) l 1

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

.t l

I l

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R I Emergency Beration fman the Control Roon l CLOSED REFERENCE QUESTION: JPM-008 ASP-RO-2 ht is a condition, other than co rol rods failing to insert, that would require emergency boration?

ANSWER: l Any one of the following:

1

. Uncontrolled plant cooldown.

. CEAs inserted below PDIL Emergency Boration limits.

. . Positive reactivity anomaly with all CEAs inserted.

.. Control room evacuation.

I

REFERENCE:

AOP-03 R2 NRC K/A 000024 EK3.01 (4.1/4.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

i Initiating Cue:

A reactor trip has occurstd and while performing EOP-00, you find that all shutdown rois have stuck out. All attempts to trip or insert control rods have failed. You are tbc LO, the LSO dhrets you to immediately commence emergency boration. LCV-218-2 is tagged out, physically stuck in the epen position. START l

)

l l

i l

l 1

l l

Revision: 6 November 9,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM -0293 Backfred 345 kV to 22kV System (s) : Electrical Distribution Location (s): Simulator Approximate Time: 6 minutes ActualTime :

Reference (s): (1) OI-EE-1, Attachmeni?

(2) NRC K/A 000062, K1.04 (RO3.7/SRO4.2)

(3) NRC K/A 000062, A4.07 (RO3.1/SRO3.1)

Verify current reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulat u in accordance wi ht the standards contamed in this l JPM.

'Ihe operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

I l

Operator's review : _. Date: j Tools,A Equipment : None Safety Considerations: Ensure DS-Tl is open prior to backfeed from 345 kV i

Comments : This JPM will normally be performed as a dynamic JPM on the Simulator.

4 i

1

Revisisn: 6 November 9,1995 Fort Calhoun Station - Opetions training JOB PERFORMANC' 5IEASURE JPM No: JPM J293 Backfeed 345 kV .o 22kV Initiating Cue:

'Ibc Main Generator is off line. DS-Tl is open. The 345 kV system is available for service. You, the LO, are dincted to backfeed the Buses 1A1 and 1 A2 fism the 345 kV. All precautions air satisfied. START l

CRITICAL STEP

ELEMENT STANDARD l

1. Obtam a copy of OI-EE-1, Attachment 2 The proper attachment has been obtained. l

2. Turn on Synchroscope for 3451-4. Syik.hiumwye is on. l

3. Verify synchic.cepc is appronmately at the Synchroscope verified to be at 12 o' clock. ;

12 o' clock position. l 4.* Close 3451-4 3451-4 is closed.

5. Turn off synchiuscope Synchroscope is off.

6. Turn on Syra.;uum.upe for 3451-5 Syndgum.upe is on.

7. Verify synchroscope is approximately at the S.echroscope verified to be at 12 o' clock.

12 o' clock position.

8* Close 3451-5 34515 is closed.

9. Turnoffsynd uscope o Syncioow is off.

10. Ensure both 43/l Al-1 A3 and 43/1 A2-1 A4 Both Fast Transfer Switcher are in MANUAL.

Fast Transfer Switcla are in MANUAL.

CUE: TIA-1 and T1A-2 have been deenergized for one bour. 1

11. Turn on synduum.upe for l Al1. Synchie.wpe is on.

12. Verify incommg and runmng voltages CUE: Voltages are a'atched.

n matched.

13. Verify syncinuewpc is approximately at the Syrcinum,upe is at 12 o' clock.

12 o' clock position.

14.* Close l Al1 1 A11 is closed.

15.* Open 1A3I I A31 is closed O//N -

Turn off syndue.wyc

16. Syndow is off.

17. Turn on syra.luuw for 1 A22. Syra.hiw is on.

18. Verify i-ing and running voltages CUE: Voltages are matched.

.< matched.

19. Verify syix.luu.wyc is approximately at the Synchroscope is at 12 o' clock.

12 o' clock position.

20.* Close IA22 1 A22 is closed.

21.* Open 1 A42 1 A42 is closed Op/W

22. Turn off synciou.wyc. Synchiew is off.

Terniination Criteria: Buses l Al a I A2 are being supplied from 345 kV.

Revision: 6 l November 9,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0293 Backfeed 345 kV to 22kV l

CLOSED REFERENCE QUESTION: JPM-0293-RO-1 Following a reactor trip what lockout relays or trips must be reset prior to establisidr.g 345 kV backfeed?

ANSWER:

86-1 SVG1 and 86-2 SVG1 lockout relays.

REFERENCE:

OI-ST-2 K/A 062000 A4.01 (3.3/3.1)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

..t s

i l

Revision: 6 November 9,1995 i Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0293 Backfeed 345 kV to 22kV i

l i

CLOSED REFERENCE QUESTION: JPM-0293 RO-2

)

4 What condition does the white light assoc:ated with a 4160 breakers's control switch on CB-20 s

indicate?

i i l ANSWER:

]

Breaker trip (or mismatch).

REFERENCE:

i l 1

NRC K/A 000062 SG7 (3.0/3.2)

! The operator's response was:

1 1 SATISFACTORY UNSATISFACTORY I

COMMENTS:

.s

l l

l i

Initiating Cue:

l

'Ihe Main Generator is off line. DS-T1 is opea. The 345 kV systein is available for service. You, I the LO, are directed to backfeed the Buses IA1 and 1A2 frenu the 345 kV. All precautions are I antisfied. START !

i l

'l

<4

.~.

J FORT CALHOUN STATION Ol-EE-1 i OPERATING INSTRUCTION R PAGE 7 OF 19

i Reference Use

.l 5

l

, Attachment 2

]

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV i

! PREREQUISITES V) i INIT,

1. 345 KV is in service PER OI-EG-1.

i

2. IF Gen G1 is shutdown,

THEN ensure DS-T1, T1 Disconnect Switch, is OPEN PER Attachment 4.

3. IF 3451-4 and 3451-5 Breakers are to be operated, l THEN notify System Operation to ensure all Substation Personnel are t

clear of breakers.

i 4

i PROCEDURE C

! NOTE l i

, Steps 1 and 2 may be performed in any order. '

\'

1. IF Open and available, close 3451-4 as follows:

a. Turn on Synchroscope for 3451-4.

b. Verify Synchroscope is approximately at a 12 o' clock position.

i c. Close 3451-4.

d. Turn off Synchroscope.

2. IF Open and available, close 3451-5 as follows:

a. Turn on Synchroscope for 3451-5.

ty. Verify Synchroscope is approximately at a 12 o' clock position.

c. Close 3451-5.

d. Turn off Synchroscope.

3. Ensure both Fast Transfer Switches are in MANUAL:

e 43/1A1-1A3 e 43/1A2-1A4 R11

)

i Revision: 10

- October 24,1995 I 1

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE Y

JPM No: JPM -0214 Shift Inservice Air Compressors l

't r

I l

i System (s): Compressed Air Location (s): Room 19 Approximate Time: 12 minutes ActualTime : ;

1 Reference (s): (1) OI-CA-1 6.3 R21 (2) NRC K/A 000078,6001 (RO2.9/SRO3.1)

Verify current stferrace avvisions match those listed above i

Operator's Name: SS # :

All Critical Steps ( * ) must be penanned or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature - Date :

Reason,if unsatisfactory :

Operator's review : Date:

.c Tools & Equipment : None Safety Considerations: None.

Comments : This JPM will be performed as a static JPM in the plant

Revisign: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE l l

JPM No: JPM - 0214 f Shift Inservice Air Compressors initiating Cue:

I The air compressor lineup is as follows: CA-1 A running, CA-lC in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for wecidy rotation as follows: CA-lC running, l CA-1B in standby, and CA-1 A in Control room start. START l l

CRITICAL '

STEP

ELEMENT STANDARD l l

J

1. Obtain a copy of OI-CA-16.3 R21 Procedure has been obtained.

2.* Verify the following on the Air Compressor a. Chect nil sight glass.

to be started (CA-1C)

a. Oillevel greater than 1/3 of b. CoolingwaterpressurePI-1942C I

lass.

a. Cooling water pressure greater than 30 psi 2 3.* Place load transfer switch on CA-IC to Switch to OFF position.

OFF.

4.* Place the Air Compressor control switch for Switt:h to CS position.

CA-IC to CS.

5.* Verify proper oil pressure (CA-lC) Oil pressure stabilizes in 15-20 seconds CUE: Oil pressure is 34 psig.

6. Verify cooling water flow Observe cooling water flow through bullseye.

FI-1955C 7.* Place CA-IC load transfer switchin Select position 1 or 2 position 1 or 2.

NOTE: Either position is acceptable.

3. Verify CA 1C for proper operation. CUE:

Oil Pressuit = 32 psig Intercooler Air Patssure = 30 psig Discharge Air Pressure = 102 psig Jacket Water Pressure = 43 psig Jacket Water Temperaturt = 1020F 4 CUE: CA-lC is functioning properly.

9.* Place CA-1 A load transfer switch in OFF. Switch to OFF position.

CUE: CA-lC is bolding the air load.

10.* Place CA-1 A control switch to OFF Switch to OFF cosition.

I 1. Place the CA-1A CR Control Switch to Notify Control Room to place the Control Switch After Stop. for CA-1A in After Stop CUE: Control Room reports that switch is in After Stop Position.

Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0214 Shift Inservice Air Comipressors CRITICAL STEP

ELEMENT STANDARD 12.* Place the local control switch for CA-1 A to Switch in CS position.

CS.

13. Verify CA-1A cooling water flow is Observe bullseye for NO flow.

stopped- CUE: There is no flow.

14. Place load transfer switch for CA-1 A in Select position 1 or 2.

position 1 or 2.

NOTE: either position is acceptable.

15.* Place CA-1B local control selector switch Switch to STBY position in STBY.

16. Place the CA-1B CR Control Switch to Request Control Room to place CA-1B control After Start. switch to AAct Start.

Cue: Contest room reports switch is in After Start.

17.* Ensure Allload transfer switches are in 1 All load transfer switches are in position 1 or 2.

or 2.

NOTE: Either position is acceptable.

Termination Criteria: CA-lC is running, CA-1B is in standby and CA-1 A is in CR start.

6 s

Revision: 10 4 October 24,1995 )

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214

, Shift Inservice Air Compresson l

I i

i CLOSED REFERENCE QUESTION: JPM-0214-RO-1 l i

What is the difference in the flow path between service air and instrument air?

ANSWER: 1 1

a Instrument air goes through an air dryer.

i

REFERENCE:

4 Service and Instrument Air STM NRC K/A 000078 K1.02 (2.7/2.8) >

l i The operator's response was:

1 J

SATISFACTORY UNSATISFACTORY I

COMMENTS:

m

. .s

_ - . _ . . ~-

Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0214 Shift Inservice Air Compressors l

CLOSED REFERENCE QUESTION: JPM-0214-RO-2 l What are the normal and backup cooling water sources to the air compressors?

ANSWER: l l

Normal: Beanng Cooling Water (TPCW)

Backup: Potable Water

REFERENCE:

Service and Instrument Air STM NRC K/A 0000078 Kl.04 (2.6/2.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COhiMEN13:

4

1 l

1 1

i i

. 1

l l

4 4

i j

4 laitiating Cue:

The air compressor lineup is as follows: CA-1A runmng, CA-IC in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for weekly rotation as follows: CA-IC running, j CA 1B in standby, and CA-1 A in Control room start. START i

a 4

I 9

1 I

t l

1 a

4 4

?

(

s

FORT CALHOUN STATION OI-CA-1 j OPERATING INSTRUCTION R PAGE 15 OF 72 i ReferenceUse

! Attachment 4 i

Rotating Air Compressors l

PREREQUISITES l _(d. INIT.

1. Procedure Revision Verification f

{ ldaster Revision Number Date:

i PROCEDURE i

j NOTE l The forward sequence for rotating Air Compressors is to place the STBY i Compressor in service, off going Compressor to CR Start, and the previous CR Start Compressor to STBY. This results in a forward j rotation i.e. A to B to C for the running coiTyr ssor and ensures each

compressor is run weekly with the performance of Ol-CA-2.

l The reverse sequence for rotating Air Compressors is to place the CR Start Compressor in service, off going Compressor to STBY, and the

! previous STBY Compressor to CR Start. This results in a reverse

! rotation i.e. C to B to A for the running compressor and therefore the

! previous STBY compressor is not started for two weeks even with the

, performance of OI-CA-2.

i i 1. IF only rotating STBY and CR START Compressors, i THEN GO TO Step 16.

j

2. Verify the following for the On-coming Compressor.

l j e Crankcase Oil Level is greaier than one-third of the sight glass 4

1

!

Cooling Water. Pressure is greater than 30 psig i .' (PI-1942A, B, or C) i i

t t

ii j R21

. . - - - _ . - - . . - - - . . . -= . - . . - . _ - - - . .- . . - . . . - .

l. FORT CALHOUN STATION OI-CA-1

OPERATING INSTRUCTION g PAGE 17 OF 72 l

! l ReferenceUse i .

Attachment 4 Rotating Air Compressors i

PROCEDURE (continued) .L)_ INIT.

j 5. (continued) l b. Place the Control Switch to AFTERSTART: (CB-10/11) ;

i e CA-1 A 4

e CA-1B e CA-1C

c. Start by placing the Local Control Switch to CS:

CA-1 A

CA-1B e CA-1C

6. WHEN 20 seconds has elapsed, THEN verify oil pressure is greater than 15 psig:

CA-1A e CA-1B e CA-1C

7. Verify Cooling Water Flow (FI-1955) for the running compressors :

CA-1A

CA-1B e CA-1C 4

R21

_ _ . . _ .. _ . . . _ . _ _ . _ . _ . _ _ - . _ _ . _ _ . _ _ _ _ ._. ~ .. . _ _ .. ..._. __ ._ _ . _ . _ _ _ _

i l FORT CALHOUN STATION OI-CA-1 j OPERATING INSTRUCTION PAGE 19 OF 72 R

i i ReferenceUse

\

Attachment 4 l

l Rotating Air Compressors t

j PROCEDURE (continued) M INIT.

4 1

12. IF the Off-going Compressor is to be placed in CR START,

THEN perform the following

a. Stop by placing the Local Control Switch to OFF

o CA-1 A '

i o CA-1B e CA-1C

b. Place the Control Switch in AFTERSTOP: (CB-10/11) i e CA-1A i e CA-1B e CA-1C

c. Place the Local Control Switch to CS:

CA-1A e CA-1B e CA-1C

13. IF the Off-going Compressor is to be placed in STBY, THEN stop by placing the Local Control Switch in STBY:

e' CA-1A e CA-1B e ,CA-1C R21 m

i l

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Invener Supply Power From Bypass to Normal i

l i

System (s) : 125 volt AC lastrument Power e

In:ation (s): Switchgear Room Approximate Time: 15 minutes ActualTime :

i Reference (s): (1) OI-EE-4 Attachment 1 R20 (2) NRC K/A 000057, A1.01 (RO3.7/SRO3.7) 4 Verify current reference revisions match those listed above 4

?

1

, Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as:

SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

.c Operator's review : Date:

Tools & Equipmeat : None Safety Considerations:

Comments : This is an alternate path JPM . This JPM will be perfonned as a static JPM in the plant.

Revision: 0 .)

October 25,1995 l

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-295 ASP Switch Inverter Supply Power From Bypass to Normsl l

l i

i l

Initiating Cue: l 4

Instrument Inverter "A" is out of service. AI-40A is being supplied via the bypass transformer. The electricians have cleared their tags on Inverter "A" and the Shift Supervisor directs you, the LO, to start

, up Inverter "A" and place it in service. All other prerequisites have been met. START CRITICAL STE.P

ELEMENT STANDAFD

1. Obtain a copy of OI-EE-4, Attachment 1 Procedure has been obtained.

R20

2. Ensure the input breaker EE-8H-CBI at the Check Breaker to OPEN position.

inverter is open.

3. Ensure the DC source breaker at the DC EE-8F panelis closed. DC Bus #1 EE-8F-CB24 (Circuit Breaker-24)

Check Breaker to Closed position.

4. Ensure the manual (bypass) transfer switch Check Si to bypass position.

Si at the inverter is in bypass.

5.* Precharge the inverter. Push precharge button on inverter and wait ~ 10 seconds 6.* Close input breaker EE-8H-CBl. Place Breaker to CLOSED position.

7. Verify Synch Loss Light is LIT. Cue: Light is LIT

8. Verify Reverse Transfer Light is LIT. Cue: Light is LIT.

9.* Place ManualTransfer Switch S1 in Select INVERTER position with Switch.

INVERTER position ,,

10. Ensure Sync. Loss Light is OFF. Cue: Light is LIT NOTE: This indicates an Imtrter problem.

11.* Tenmaate procedure and contact Shift DO NOT push Forward Transfer Button.

Supemsor. Continue to allow bypass 4 transformer to supply Instrument bus. NOTE: It is acceptable, but not required, for operator to return switch Si to the bypass position and open input breaker EE-8H-CBI STOP

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-295 ASP Switch Inverter Supply Power Fmm Bypass to Normal i

CLOSED REFERENCE QUESTION: JPM-0295 ASP-RO-l Why is it necessary to ensure the " sync loss" light is out prior to placing the inverter in senice?

j ANSWER:

a To ensure that the output of the invener is at the proper voltage and frequency.

OR i'

To prevent a transient on the instrument bus.

REFERENCE:

AOF-30, Attachment A NRC K/A 062000 A2.15 (2.8/43.2)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMEN13:

.t

- . . . .. . = - _ . . . - . ..

Revision: 0 4 October 25,1995 i

Fort Calhoun Station . Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP Switch Inverier Supply Power Fmn Bypass to Normal s

4

)

CLOSED REFERENCE QUESTION: IPM-0295 ASP -RO -2 Why do the inverters use DC supply power rather than AC7 i

i l ANSWER:

1

, To assure that instrument power will be available following a station blackout.

i

REFERENCE:

l NRC K/A 000057 EA2.14 (3.2/3.6)

The operator's response was:

1 i SATISFACTORY UNSATISFACTORY i

i COMMENTS: j

.< j 1

{

1 I

l l

. - - . .. . .. - - - =. . . _ . - - . .

5

\

i I

Initiating Cue

Instrument Inverter "A" is out of service. AI-40A is being supplied via the bypass transformer. The electricians have cleared their tags on Inverter "A" and the Sinft Supervisor directs you, the LO, to start up Inverter "A" and place it in service. All other prerequisites have been met. START 1

1 I

..(

4

FORT CALHOUN STATION 01-EE-4 OPERATING INSTRUCTION PAGE 3 0F 73 6.0 PROCEDURE M)

NOTE 1: Instrument bus panels AI-40A, B, C and D and AI-42A and B each have T pair of white lights for indicating grounds. During normal operations both lights are dimly lit if no grounds are present on the bus. If a ground occurs, one light will be brighter than the other. When the ground is removed, the lights will automatically reset to their normal mode (both lights dimly lit).

, A ground can cause an inverter trouble alarm to come in on C8-20. However, it is aossible for the white lights to be indicating a ground witicut the trouble alarm being in. This is because the voltage sensing relay supplying the alarm will only do so with a "hard" ground.

NOTE 2: Only applicable Steps need to be performed.

6.1 Use the following attachment for Static Inverter operation:

/erter Attachment l

A (EE-8H) I l B (EE-8J) 2 C (EE-8K) 3 D (EE-8L) 4 1 (EE-8P) 5 2 (EE-8Q) 6 6.2 Perform Attachment 7 for transferring Clutch Power Supplies.

6.3 Perform checklist 01-EE-4-CL-A.

7.0 DATA SHEET / CHECKLIST Pace 7.1 Attachment 1, Inverter A (EE-8H) Operation 4 7.2 Attachment 2, Inverter B (EE-8J) Operation 11 7.3 Attachment 3, Inverter C (EE-8K) Operation 18

'7.4 Attachment 4, Inverter D (EE-8L) Operation 25 7.5 Attachment 5, Inverter 1 (EE-8P) Operation 32 7.6 Attachment 6, Inverter 2 (EE-8Q) Operation 37 7.7 ' Attachment 7, Clutch Power Supplies 42 7.8 Checklist 01-EE-4-CL-A, Plant Electrical Distribution 45 R20

FORT CALHOUN STATION 01-EE-4 OPERATING INSTRUCTION PAGE 5 0F 73 C

continuous Use ATTACHMENT I Page 2 of 7 INVERTER A (EE-8H) OPERATION PROCEDURE (Continued) V) 3.0 Inverter StartuD and Transfer with BYDass Transformer in ;

Operation: '

3.1 Ensure Inverter A Input Breaker (DC) EE-8H-CBI is OPEN.

3.2 Ensure Instrument Bus AI-40A Inverter Breaker EE-8F-CB24 on DC Bus 1 is CLOSZD.

3.3 Ensure the Manual Transfer Switch S-1 is in BYPASS.

3.4 Momentarily push the Precharge Button, THEN wait approximately ten (10) seconds.

3.5 Close EE-8H-CBl.

3.6 Verify SYNC LOSS light is ON.

3.7 Verify REVERSE TRANSFER light is ON. ___

3.8 Place the Manual Transfer Switch S-1 in the INVERTER position. ,

1 3.9 Ensure SYNC LOSS light is OFF.

3.10 Push the Forward Trant;fer Button.

3.11 Verify REVERSE TRANSFER light is 0FF.

3.12 Verify FORWARD TRANSFER light is ON.

3.13 Ensure Inverter A Cooling Fans Breaker, EE-8H-CB3, is CLOSED.

CAUTION Adjustments to inverter output frequency or output voltage shall only be made by Electrical Maintenance.

3.14 Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz (normal 60.0 H7 }

3.15 Verify Inverter A Outpu? Nltage is between 117.6 and 122.4 Volts AC (normal . O Volts AC).

R20

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 7 0F 73 C

Continuous Use ATTACHMENT 1 Page 4 of 7 INVERTER A (EE-8H) OPERATION PROCEDURE (Continued) h/)

4 5.0 Supplyino Bus A and Al with inverter C (EE-8K):

5.1 Ensure no grounds are present on Instrument Bus A.

5.2 Remove all loads supplied by 120 Volt AC Instrument Bus A1.

5.3 Remove all loads supplied by 120 Volt AC Instrument

Bus A.

4 5.4 Open 120 Volt AC Instrument Bus A Main Disconnect IA-1

{ (AI-40A).

5.5 Close 120 Volt AC Instrument Bus A Breaker I-BUS-AC-1 i (AI-40A).

5.u Close 120 Volt AC Instrument Bus C Breaker I-BUS-AC-2 (Al-40C).

l CAllTION INVERTER C TROUBLE annunciator (A-15, C-6) may indicate an overload condition exists. Overload conditions must be

! corrected by removing Non-essential loads. Maximum Inverter

load is 62.5 amps.

5.7 Sequentially load 120 Volt AC Instrument Bus A.

5.8 Seq'uentially load 120 Volt AC Instrument Bus A1.

5.9 Verify Inverter C OVERLOAD light is 0FF.

5.'10 Verify that the AC output current from Inverter C does not exceed 62.5 amps.

5.11 Open Inverter A Cooling Fans Breaker, EE-8H-CB3.

~

5.12 ' Open Inverter A Output Breaker EE-8H-CB2.

5.13 Open Inverter A Input Breaker (DC) EE-8H-CBl.

R20

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

4 1

FORT CALHOUN STATION OI-EE-4 j OPERATING INSTRUCTION PAGE 9 0F 73 C

,2 Continuous Use ATTACHMENT 1 Page 6 of 7

INVERTER A (EE-8H) OPERATION PROCEDURE (C6atinued) M)

! 7.0 Returning Buses A and Al Supolv from Instrument Bus C to BvDass Transformer EE-4N or Inverter A (EE-8H):

7.1 Ensure no grounds are present on Instrument Bus A.

7.2 Ensure 120 VAC Instrument Bus A Main Disconnect IA-1 is OPEN.

i 7.3 Ensure Inverter A Input Breaker (DC) EE-8H-CBI is l OPEN.

i

! 7.4 Ensure Inverter A Manual Transfer Switch S-1 is in j BYPASS.

7.5 Ensure Inverter A Bypass Transformer Supply Breaker MCC-381-E3R on DC Bus No. 1 is CLOSED.

7.6 Ensure Breaker EE-8F-CB24 on DC Bus No. 1 is CLOSED.

7.7 Close Inverter A Output Breaker (AC) EE-8H-CB2.

j 7.8 Open 120 VAC Instrument Bus C Breaker I-BUS-AC-2 (Al-40C).

7.9 Open 120 VAC Instrument Bus A Breaker I-BUS-AC-1 (AC-40A).

7.10 Close 120 VAC Instrument Bus A Main Disconnect IA-1 (AI-40A).

i NOTE: The following steps will place Inverter A in j service.

! 7.11 Momentarily push the Precharge Button on Inverter A, THEN wait approximately ten (10) seconds.

7.12 Close EE-8H-CBI on Inverter A.

! 7.13 Verify SYNC LOSS light is ON.

. 7.14 Verify REVERSE TRANSFER light is ON.

l 7.15 Place the Manual Transfer Switch S-1 in the INVERTER position.

l 7.16 Ensure SYNC LOSS light is OFF.

4 i .12 0

Revision: 0 4.tober 24,1995 Fort Calhoun Station - Operations trammg 4

JOB PERFORMANCE MEASURE !

4 JPM No: JPM - NEW

$ Emergency Fill of the EFWST Using the Fire Protection System i System (s): AFW and Fue Protection Location (s): Room 81 Approximate Tune: 20 minutes ActualTune :

Reference (s): (1) AOP . 30, R4 (2) NRC K/A 000061, K4.01 (RO3.9/SRO4.2)

(3) NRC K/A 000061, A1.04 (RO3.9/SRO3.9)

Verify current reference revisions match those listed above Operator's Name: SS # :

All Critical Step ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

'Ibe operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory:

Operator's review : Date:

Tools & Equipment : None Safety Considerations: TIIIS JPM WILL BE PERPORMED AS A STATIC JPM IN TIIE PLANT.

Comments : The fire hose and adapter should not be inoved from the fire brigade assembly area.

- - - _- -. - - -. . = - -

w I

a Revision: 0 l October 24,1995 l i

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fier Protection System J l laitiating Cue:

A station blackout has occurred. AFW is being supplied to the steam generators from FW-10(Turbine Driven AFW Pump.). FW-54 (Diesel Driven AFW Pump.) and Blair water are unavailable. The LSO directs you to prepare to replenish the EFWST using the fire system. START l CRITICAL STEP

ELEMENT STANDARD

1. Obtain procedure AOP-30 AOP-30 is obtained and verified.

2.* Close FW-652 ROOM 81 FW-652 is closed l 3.* Close FW-654 FW-654 is closed 4.* Obtain a 21/2 inch male-to male adapter FIRE BRIGADE ASSEMBLY AREA and a 100 foot section of 21/2 inch fire Locate adapter and fire hose.

hose. CUE: Fire Hose has been obtained (after examinee locates base.)

5.* Connect male-toeale adapter to the male CUE: The Adapter is connected end of fire bose, 6.* Connect both ends of the fire bose to the ROOM 81 following valves: CUE: Both ends connected a) FW-1275 b) FP-456 7.* Open FW-1275 FW-1275 is open 8.* Open FW-653 FW-653 is open

9. Determme time for EFWST to empty CUE: The time to empty has been determined. 'Ibe LSO directs you to begin filling the EFWST.

10.* Open FP-456 FP-456 is open

.t

11. Ensure FP-1B starts Verify pump start with control room FP-1B has started CUE: EFWSTlevelis 91%

12. Close FP-456 FP-456 is closed STOP Termination Criteria: EFWST level is 91% and fill is termmated.

Revision: 0 .

October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fui of the EFWST Using the Fire Protection System OPEN REFERENCE QUESTION: JPM-new-RO-1, SRO-1 l

How long will it take for the EFWST to empty if the level is 32 inches and the AFW flow is 150 epm?

ANSWER:

i 1

The EFWST will empty in one hour or less.

I I

REFERENCE:

i AOP-30, Attachment A NRC K/A 000061 K4.01 (3.9/4.2)

The operator's response was:

MTISFACTORY UNSATISFACTORY COMMENTS:

This question is answered as JPM step 8.

.s i

Revision: 0 October 24,1995 Fort Calhoun Station - Operations training a JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Prtgection System CLOSED REFERENCE QUESTION: JPM-new-RO-2 a

What will cause the Diesel driven Fue Pump to start when FP 456 is opened?

i ANSWER:

1 The pump will start on low fire header pressure.

i

~

REFERENCE:

i Fire Protection STM !

NRC K/A 000086 K4.02 (3.0/3.4) i l

l The operator's response was:

SATISFACTORY UNSATISFACTORY l

! COMMENTS:

.r i ,

l l

1

~

l i

Initiating Cue:

A station blackout has occurred. AFW is being supplied to the steam generators from FW-10(Turbine Driven AFW Pump.). FW-54 (Diesel Driven AFW Pump.) and Blair water are unavailable. 'Ibe LSO directs you to prepare to replenish the EFWST using die fue system. START j

l l

1

)

l 4

4

\

AOP-30 Page 17 of 23 INSTRUCTIONS CONTINGENCY ACTIONS 1

i i

9. Verifv EFWST level is greater than or 9.1 IF EFWST level is less than 91%, l 3

equal to 91%. THEN .QQ TQ Step 11.

I i

10. _GQIQ. Section 5.0, Exit Conditions. '

i

(

11. Preoare to replenish EFWST level using j

the Fire System by performing the following steps (Room 81):

1

a. Close FW-652, "EMGY .

1 FEEDWATER STORAGE TNK FW-19 DEMIN MAKE-UP WTR I VLV LCV-1189 INLET VALVE".

l

b. Close FW-604, "EMGY FEEDWATER STORAGE TNK FW-19 DEMIN MAKE-UP WTR I

VLV LCV-1189 BYPASS VALVE".

c. Obtain BOTH of the following items from the fire brigade assembly area.

2% inch, male-to-male adapter

100 foot,2% inch fire hose (continue)

Part 1 R4

I AOP-30 Page 18 of 23 !

INSTRUCTIONS CONTINGENCY ACTIONS l

11. (continued) l l

d. Connect the 2% inch male-to-male adapter to the male end of the fire hose.

e. Conned the fire hose to BOTH of the following valves (Room 81);

e FW-1275, " FIRE PROTECTION EMERGENCY MAKE-UP VALVE"

FP-456, " FIRE HOSE CABINET FP-10D 2-%" AUX HOSE 1 CONNECTION VALVE" j l

f. Open FW-1275.

g. Open FW-653, "EMGY FEEDWATER STORAGE TNK FW-19 DEMIN MAKEUP WTR VLV !

LCV-1189 OUTIET VALVE".

j 4

4 Part 1 R4

i f AOP-30 j Page 19 of 23

!' INSTRUCTIONS CONTINGENCY ACTIONS 4

) 12. IF EFWST level lowers to less than l 50%,

1 THEN determine the time to emptying li the EFWST by performing the following

steps

i

a. Monitor EFWST level.

l l

b. Determine how much time remains i before EFWST empties PEB Attachment A, EFWST Emotvina Characteristics. at least once per l 15 minutes.

NOTES

1. ' Filling the EFWST with Fire Water will result in significantly degraded Steam Generator chemistry.

2. Degraded Fire Pump pedormance may be caused by plugging of the strainer. If power is lost to the strainer rotation motor, it wi!I be necessary to backwash manually (locally).

13. IF the EFWST will empty, THEN open FP-456, " FIRE HOSE CABINET FP-10D 2-%" AUX HOSE CONNECTION VALVE" (Room 81).

14. Ensure FP-18, Diesel Fire Pump, starts.

Part 1 R4

AOP-30 '

1 Page 20 of 23 INSTRUCTIONS CONTINGENCY ACTIONS

, 15. WHEN EFWST levelis greater than or 15.1 IF EFWST empties, a

equal to 91%, THEN.GQIQ AOP 28, AFW System l THEN close FP-456. Malfunctions.

, l 4

l 4

d i

i i

j .,

End of Section 4.0 Part 1 R4

AOP-30 Page 21 of 23 5.0 EXIT CONDITIONS i

This Emergency Fill of Emergency Feedwater Storage Tank procedure may be exited when both of the following conditions exist:

1 A. An approved procedure exists for long term operation.

B. EFWST level has been restored to greater than or equal to 91%.

l I

I

,.4 Part 1 R4

AOP-30 Page 22 of 23 l l Attachment A j EFWST Emotvina Characteristics i

j 4

i i EFWST EMPTYING CHARACTERISTICS FOR VARIOUS INITIAL TANK LEVELS 100.00 63 10 4 l 1

s g ;

E 39.81 l l

bc 2 ^

. 5 Y%h

[$ l*5'12 l" R A'h i

6 31 -

3 98 -

2.51 0 1007. (160")

$ 1'58 - '^ ^#

' + 707. (I 12")

s 1.00 X. A N % -

, O 50". (80")

- 0.63 a: %

o 307. (48")

0.40 '

X 207. (32")

H '

0.16

~'

v 107. (16")

4 0 50 100 150 200 250 300 AUXILIARY FEEDWATER FLOWRATE (GPM)

.s End of Attachment A Part 2 R4

Revisim: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0010RW IAss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

System (s) : Abnormal / Emergency Procedures IAcation(s): Room 81 Approximate Time: 15 minutes ActualTime :

Reference (s): (1) AOP - 11, R4 (2) NRC K/A 000008, K3.01 (RO3.4/SRO3.5)

(3) NRCK/A000008, A2.01 (RO3.3/SRO3.6)

Verify current reference revisions match those listed above Operator's Name: SS#:

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contamed in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operdor's review : Date:

Tools & Equipment : None Safety Considerations: None Comments : This JPM will be conducted as a static JPM in the plant..

I i

l Revision: 1 October 24,1995 Fort Calhoun Station - Operations training l JOB PERFORMANCE MEASURE 1

JPM No: JPM-0010RW l 14ss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

I l

Initiating Cue:

r The reactor has been tripped from 100% power. A total loss of all CCW has occured. You are directed to establish Raw Water backup to the Control Room Air Conditioners as directed by the LSO. VA-46B is in service. START i CRI11 CAL STEP

ELEMENT STANDARD J

1. Obtain a copy of AOP-11, R4 AOP-11, R4 has been obtained.

CUE: The centrul rwom reports that BC55 2899A&B have been closed.

2.* Unlock and release the hujacks from: Room 69 i

a. HCV-2899C Remove locking device and place the vahrs in i

b. HCV-2899D the open position 3.* Open the following valves: a. 3-Way manual control valve in open position.

a. IA-HCV-2399C-TV b. 3-Way mannal control valve in open position,

b. IA-HCV-2899D-TV Termination Criteria: Raw Water backup cooling has been established to VA-46B.

I l

4 4

j d

Revisi:n: 1 October 24,1995

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i

JPM Nc: JPM - 0010RW j IAss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

2 i

CLOSED REFERENCE QUESTION: JPM 0010RW- RO-1 Why is the CCW surge tank pressunzed with nitrogen?

ANSWER:

i I

To provide adequate NPSH for operation of the CCW pumps..

1

REFERENCE:

i CCW STM l NRC K/A 000008 A2.01 (3.3/3.6) 1 The operator's response was:

SARSFACTORY UNSATISFACTORY i COMMENTS:

4 e

)

4 J

Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM -0010RW Loss of Component Cooling Water stquiring Raw Water Backup to Control Room Cooling.

1

.l CLOSED REFERENCE QUESTION: JPM-0010RW-RO-2 What conditions are necessary for HCV 438A/B/C/D to automatically close?

4 ANSWER:

s CIAS and CCW pressure less than 60 psig. [For the required length of time.]

4

REFERENCE:

1 CCW STM

, NRC K/A 000026 EK3.02 (3.6/3.9)

The operator's response was:

4 SATISFACTORY UNSATISFACTORY COMMENTS:

.c 1

3

h l

l l

l i l I

\

Initiating Cue:

1 The reactor has been tripped from 100% power. A total loss of all CCW has omued. You are directed to establish Raw Water backup to the Control Room Air Conditioners as directed by the LSO. VA-46B is in

! service. START i 1

2 a

4 4

4 .

b 4 I i '

1 i

4 l

l i

s i

.i &

d 4

i

]

1 1 :

i

( 8

.i 1

4 ,(

i ,

i 5

+

d l

i i l.

4

4 AOP-11 -

Page 28 of 54 INSTRUCTIONS CONTINGENCY ACTIONS

11. (continued) 1 I

, i. IF VA-46A, Control Room i

Ventilation Fan, is in service, i 1

THEN establish RW flow to VA-46A, by performing the following steps:

j NOTE 5

Manual isolation of RW direct cooling is required when LAS-2898 alarms.

1) Close HCV-2898A/B, CCW

$ Valves.

4

2) Unlock and release the hand-Jacks from BOTH of the following RW Interface Valves (Room 81):

4

e HCV-2898C, ' CONTROL ROOM VA UNIT VA-46A RAW WATER INLET

VALVE'

., e HCV-2898D, " CONTROL ROOM VA UNIT VA-46A RAW WATER OUTLET VALVE' i

(continue)

Part 1 R4

I 2 1 AOP-11 Page 29 of 54 INSTRUCTIONS CONTINGENCY ACTIONS 11.1 (continued)

3) Open BOTH HCV-2898C/D,

, VA-46A RW Valves by placing the following valves to "OPEN" (Room 81):

e IA-HCV-2898C-TV, "3-WAY MANUAL CONTROL l VALVE" i

e IA-HCV-2898D-TV, "3-WAY l MANUAL CONTROL l

, VALVE" i i J. IF VA-46B, Control Room Ventilation Fan, is in service, 1

THEN establish RW flow to

j. VA-46B by performing the following steps:

NOTE i

Manual isolation of RW direct cooling is required when LAS-2899 alarms.

.4

1) Close HCV-2899A/B, VA-46B CCW Valves.

(continue)

Part 1 R4

AOP-11 Page 30 of 54 INSTRUCTIONS CONTINGENCY ACTIONS 11.J (continued)

2) Unlock and release the hand-Jacks from BOTH of the following RW Interface Valves (Room 81):

e HCV-2899C, " CONTROL ROOM VA UNIT VA-46B RAW WATER INLET VALVE" e HCV-2899D, "CONTHOL ROOM VA UNIT VA-46B RAW WATER OUTLET VALVE"

3) Open BOTH HCV-2899C/D, VA-46B RW Valves by placing the following valves to "OPEN" (Room 81):

e IA-HCV-2899C-TV, "3-WAY MANUAL CONTROL VALVE" e IA-HCV-2899D-TV, "3-WAY MANUAL CONTROL

,,, VALVE" (continue)

Part 1 R4

1 Revidon: 8 October 24,1995 6

Fort Callem Station - Operations training

JOB PERFORMANCE MEASURE JPM No: JPM -0719

Startup Hydrogen Purge System I

System (s): Hydrogen Purge System i l

Location (s): Auxiliary Building (RCA)

Approximate Time: 10 nunutes ActualTime : l 1

Reference (s): (1) OI VA-1, Attachment 5,4.3 d

(2) NRC K/A 000028, A2.02 (RO3.5/SRO3.9) i

) Vedfy current referrace avvisions match those listed above j

Operator's Name: SS # :

All Critical Stepr ( * ) must be performed or simulated in accordance with the stamfards contained in this JPM.

] The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY 1

Evaluator's Signature : Date : l t

l i

! Reason,if unsatisfactory : l l

J l 1

4 Operator's review : Date:

s Tools & Equipment : None Safety Considerations: This JPM requires entry into the RCA.

Comments : This JPM will be performed as a static JPM in the plant.

5

- _ . _- _ . -.. _ ~ _ _ _ _ _ . ._

Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System Initiating Cue:

The plant is in accident recovery following a LOCA. CIAS and VIAS have initiated. Containment hydrogen concentration is 3% Containment integrity has not been satisfied in accordance with the Safety Function Status Check. A containment hydrogen purge is required. You have been directed to start a hydrogen purge using Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 have all been verified closed. START CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of OI-VA-1, Attachment 5, Procedure has been ahtained 4.3 , , _ , , _ _ , _ , , , , _

2. Ensure VA-80A recirculation valves are Corridor 26 closed. VA-279 and VA-284 are closed 3.* Open hydrogen purge fan suction and NOTE: Manual handwheels for these vsives are discharge valves: in Corridor 26.

A. VA-292 B. VA-290 Unlock and OPEN valves C. VA-289

4. Open hydrogen purge containment isolation Request control room to open HCV-882.

valve.

CUE: Control roons reports HCV-882 ls open.

5.* Start hydrogen purge fan. Al-100 VA-80A in pull to OVERRIDE.

NOTE: If candidate places control switch for VA-80A in AFTER START, tell him the GREEN light is stilllit.

Terinisation Criteria: Hydrogen purge has been started 4

4

M

}

4 Revision: 8 October 24,1995 Fon Calhoun Station - Operations training JOB PERFORMANCE MEASURE

]

i JPM No: JPM-0719 l Startup Hydrogen Purge System 1

CLOSED REFERENCE QUESTION: JPM-0719-RO-1 T

,' What is the purpose of the charcoal filters in the hydrogen purge system? l i

i ANSWER:

i 5

To remove radioactive iodine from the containment atmosiehere being released to the environment.

1

REFERENCE:

1 NRC K/A 000027 K5.01 (3.1/3.4) 4 1-The operator's response was: ,

J SATISFACTORY UNSATISFACTORY 1

i COMMENTS:

6 i

I k

Revision: 8 October 24,1995 Fort Calhoun Station - Operations training i JOB PERFORMANCE MEASURE ,

l JPM No: JPM - 0719 )

Startup Hydrogen Purge System l l

l l

1 CLOSED REFERENCE QUESTION: JPM-0719-RO-2, SRO-1 l

l What is another system that can be lined up to flow through the hydrogen purge charcoal filters?

ANSWER

1 3 Either of the following:

4 Gas decay tanks Condenser vacuum pump exhaust i

REFERENCE:

i NRC K/A 000027 K5.01 (3.1/3.4)

Tbc operator's response was:

SATISFACTORY UNSATISFACTORY e9 i

J t

Revision: 8 l October 24,1995 l i'

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System I litiating Cue: i i'

The plant is in accident recovery following a LOCA. CIAS and VIAS have initia -A. Containment hydrogen concentration is 3% Containment integrity has not been satisfied in accordance with the Safety Function Status Check. A containment hydrogen purge is required. You have been directed to start a hydrogen purge usingn Hydrogen Purge Fan VA-80A. VA-412 VA-294, VA-368 and VA-369 have allbeen verified closed. START i

I l

l l

.I ,

FORT CALHOUN STATION OI-VA-1

OPERATING INSTRUCTION PAGE 23 OF 97 t

, i d

I information use

{

l ATTACHMENT 4 Page 3 of 3

~

CEDM COOLING OPERATION (VA-2A & VA-2B) 4.O PROCEDURE (Continuedi INITIALS l 4.5 Alternatina CEDM Fann NOTE: Fans will be alternated on a weekly basis. l

) 4.5.1 Start the oncoming Fan:

Igg M) i VA-2A VA-2B l 4.5.2 Stop the offgoing Fan:

Egg Mi VA-2A VA-2B ._

4.5.3 Monitor the oncoming Fans temperature instruments to verify proper operation:

VA-2A M) VA-2B M)

TIC-738 TIC-740 TIC-739 TIC-741 l I

l J

R25

i 9 I i

1 FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 25 OF 97 C

f "h use i

d j ATTACHMENT 5 Page 2 of 9

HYDROGEN PURGE OPERATION l (VA-80A & VA-80B) 3.0 PRECAUTIONS (Continued) INITIATR/DATE 3.2 Except during the operational weekly ;

, test and the monthly full flow test I i (with suction from the Auxiliary Building), this system CAN NOT be i operated unless the Reactor is in at j least a Cold shutdown condition 4

(Mode 4). This ensures the Containment

! Integrity requirements of Tech.

4 Spec. 2.6 will not be violated.

5 4.O PROCEDURE f 4.1 Hydroced Purce Startun Normal Operation

4.1.1 Close or check closed the following valves

! Valve Description Mi l VA-412 Condenser Evacuation Stack Isolation Valve

, VA-294 Condenser Evacuation System i combined Drain Valve

! VA-368 Drain Trap VD-29 i Isolation Valve VA-369 Drain Trap VD-29 Bypass Valve /

.c R25

.__ ~ - . _ - - . _ _ _ . - . . . . - . - . - . - . - . . - - - . - . . - _ .

i FORT CALHOUN STATION OI-VA-1 1

OPERATING INSTRUCTION PAGE 27 OF 97 C

l Contmuous Use ATTACHMENT 5 Page 4 of 9 i

HYDROGEN PURGE OPERATION (VA-80A & VA-80B) i 4.O PROCEDURE (Continued) INITIALS /DATE i

) 4.2 Hydrocen Purae Shutdown Normal Oneration 4

4.2.1 Stop operating Hydrogen Purge Fan (s) (AI-100). /

. 4.2.2 Close Hydrogen Purge Containment Isolation Valves (AI-43A) opened in Step 4.1.3:

Valve Descrintion M)

HCV-881 VA-80B Cont. Isolation HCV-882 VA-80A Cont. Isolation /

4.2.3 Ensure all valves opened in Step 4.1.2 are in the required position:

Valve Reauired 1

LOCKED i

VA-289 CLOSED l l VA-290 CLOSED VA-292 CLOSED

, LOCKED VA-280 CLOSED 4

VA-281 CLOSED

. I i VA-283 CLOSED /

4.2.4 Independently verify the s following valves locked closed:

I Valve Recuired M)

LOCKED 2 VA-289 CLOSED LOCKED VA-280 CLOSED /

. Ind Ver 4.2.5 If desired, restore Condenser Evacuation in accordance with OI-CE-1. /

4 R25

3 FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 29 OF 97 C

Conunuous Use ATTACHMENT 5 Page 6 of 9 HYDROGEN PURGE OPERATION (VA-80A & VA-80B) 4.0 PROCEDURE (Continued) INITIALS /DATE 4.3.4 Open the following valves for VA-80A (N/A if not applicable): M)

Descrintion VA-292 VA-80A Discharge VA-290 VA-80A Suction .

VA-289 VA-80A Cont. Isolation /

4.3.5' Open the following valves for VA-80B (N/A if not applicable): M)

Description VA-283 VA-80B Discharge VA-281 VA-80B Suction VA-280 VA-80B Cont. Isolation /

NOTE: With CIAS present HCV-881~and HCV-882 nust be taken to OVERRIDE to open these valves. '

4.3.6 Open the at (AI-43A) applicable valves for the Hydrogen Purge Fans to be operated by placing the Control Switch in OVERRIDE.

Fan Valve Override VA-80A HCV-882 I

VA-80B HCV-881 / l

.s l

l l

R25

4 FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 31 OF 97

C

Contmuous Use ATTACHMENT 5 Page 8 of 9 1

i HYDROGEN PURGE OPERATION (VA-80A & VA-80B) 4.0 PROCEDURF (Continued) INITIALS /DATE 4.4.1 B. CLOSE HCV-882, Containment Isolation Valve for VA-80A. /

J C. CLOSE the following valves for VA-80A: M)

VA-292 a

VA-290 f

4 VA-289 /

j D. Lock closed VA-289. /

I I

/

Ind Verif 1

j 4.4.2 IF VA-80B is to be shutdown, THEN perform the following steps (N/A each step if not

applicable):

., A. Stop the H2 Purge Fan by j taking the Control Switch to j AFTER STOP. /

i B. CLOSE HCV-881, Containment

) Isolation Va.1ve for VA-80B. /

C. CLOSE the following valves for VA-80B: M)

) VA-283 s

VA-281 VA-280 D. Lock closed VA-280 /

/

Ind Verif 4.4.3 IF VA-82 Bypass Valve VA-411 was

' opened in Step 4.3.8, THEN CLOSE VA-411 (N/A if not applicable). / ,_

R25

.r-c-s

)

i I

ES-301 Administrative Tonics Outline Form ES - 301 - 1 l

Examination Level: SRO (I)

Facility: Fort Calhoun Week of Examination: 12/04/95 i

Examiner's Name (print):_

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions )

A. Plant a. During e. reactor startup, what action should be 1 Parameter taken if c iticality does not occur within the ,

verification allowable reactivity band? {

)

b. During a reactor startup, what parameters are )

recorded as " critical data"?

Security c. What is the maximum number number of visitors you 1 are allowed to escort within a vital area? l

d. Where are bomb threat call checklists located? l A. Temporary a. When can a temporary modification be installed 2 Modifications prior to PRC approval?

b. Nhere are drawings located which provide details on installed temporary modifications?

A. Radiation JPM - RCA Entry l 3 Control j j

l A. Emergency Emergency Classification - LOCA with CET's reading 4 Plan 1700'F and 55 psig containment pressure.

Meteorological tower parameters used to determine atmospheric stability class for dose assessment.

Examiner: 2 M- d Chief Examiner: 7 A #-

& ,c .s

1 l

CLOSED REFERENCE QUESTION A.1 a: l During a reactor startup, whai ection should be taken if criticality occurs outside of the i 1% reactivity band specified on the ECF form?

ANSWER:

Conservative action is required to put the reactor in a stable and subcritical condition and shall include CEA insertion or reactor trip. l 1

Plant reference: OP-2A K/A: 010001 A2.07 (3.6/4.2) j

'Ibe operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS: i I

I 1

l J

.( I

CLOSED REFERENCE QUESTION A.1 b:

During a reactor startup, what four parameters are recorded as critical data? .

1 ANSWER:

l 1

Rod positions, Boron concentration, RCS average temperature, and time.

l l

l Plant reference: TDB-V.I.b, Estimated Critical Conditions Worksheet K/A: 194001 A1.06 (3.4/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

.c

\ i

l 1

.i i

j CLOSED REFERENCE QUESTION A.1 c:

l

What is the maximum number of individuals you are allowed to escort within vital areas of the plant?

h t ANSWER:

4 A maximum of five individuals may be escorted within the vital area.

Plant reference: GET Training manual ,

K/A: 194001 Kl.05 (3.1/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS: ,

i ei 1

l

CLOSED REFERENCE QUESTION A.1-d:

i You are located in the OCC where is the nearest Bomb Threat Call Checklist located?

ANSWER:

. Bomb threat checklists are located on the back of each plant phone directory.

Plant reference: GET training manual K/A: 194001 K1.05 (3.1/3.4)

! ne operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

l I

d l

I

I 4

4 j

4 l CLOSED REFERENCE QUESTION A.2-a:

j i When can a temporary modification be installed prior to PRC approval?

i i

4 e

f 1

' ANSWER:

4 1

1

In cases of emergency (when approved by the shift supervisor). j 1,

i

I I

i Plant reference: S0-0-25 K/A: 194001 A1.10 (2.9/3.9) l The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

..t l

t

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

CLOSED REFERENCE QUESTION A.2 b:

At what two locations can drawings providing details of installed temporary modifications be found?

ANSWER:

Control Room and OCC Plant reference: S0-0-25 K/A: 194001 A1.07 (2.5/3.2)

Tne operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

l t

o$

i i

l 2

l y -- - - - - _ .-

- ~ .. . .. ..

Topic (s): RCA Entry and Exit i

Location (s): RCA Access Control Approximate Time: 10 minutes ActualTime :

Reference (s): (1) GET . Radiation Worker Training (2) NRC K/A 194001, K1.03 (RO2.8/SRO3.4)

(3) NRC K/A 194001, Kl.04 (RO3.3/SRO3.5) q l

Verify current reference revisions match those listed above l l

Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY l l

Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None Safety Considerations: This JPM requires entry into the RCA.

l Cbmments :

Initiating Cue:

)

An entry into the RCA is required as pan of the operating exam. START l l

l CRITICAL STEP

ELEMENT. STANDARD i

1.* Review RWP. Read RWP

. 2. Check survey maps Check survey maps for radiological conditions l in areas to be entered 3.* Obtain dosimetry Verify TLD attached to security badge. Obtain ALNOR ,

l 4.* Sign in on appropriate RWP Insert ALNOR into reader, enter PID and RWP i number.

i 1 5. Inform RP Personnel about the nature of Tell RP at access control where you are going

your entry and what you will be doing.

'l'

6. Enter RCA RCA entered I

d 7.* Comply with all posting within RCA No violation of posted requirements i

8.* Monitor for personnel contamination prior Monitor for contamination using PCM-1 or to exiting frisker.

9.* Sign out of RCA Insert ALNOR in reader, Enter PID number, !

confirm dose and place ALNOR in charging j rack.

]

Ternination Criteria: RCA has been exited. j e

CLOSED REFERENCE QUESTION: JPM-RCA RO/SRO-1 What action should be taken if your ALNOR alanns?

I ANSWER:

Go to low dose waiting area and contact Radiation Protection..

REFERENCE:

GET Radiation Worker Training NRC K/A 194001 K1.03 (2.8/3.4)

"Ihe operator's response was:

SATISFACTORY UNSATISFACTORY l

COMMENTS-l l

.t i

1 1

4 i

CLOSED REFERENCE QUESTION: JPM-RCA-RO/SRO-2 What action should be taken if the PCM-1 alarms when frisking?

I J

ANSWER:

d Back out of the frisking booth and follow directions on the LED readout. If the ICM 1 alanns a second time, note the contaminated area and contact Radiation Protection.

REFERENCE:

GET Radiation Worker Training NRC K/A 194001 Kl.(M (3.3/3.5)

The operator's response was:

I SATISFACTORY UNSATISFACTORY !

COMMENTS:

.t a

4 i

l l

4 OPEN REFERENCE QUESTION A.4-a:

1 i

I A Loss of Coolant Accident has occurred, the CET's indicate 1700 F. and the containment pressure indicates 55 psig What emergency classincation would be appropriate for this condition?

i

! The candidate will require the use of EPIP-OSC-1yis n OSED PI4"ENCE QUEailuI i

ANSWER

This event should be classified as a General Emergency.

a

(

Plant reference: EPIP-OSC-1 EAL 1.20

- NRC K/A l K/A: 194001 Al.16 (3.1/4.4) 1 The operator's response was:

l 6 SATISFACTORY UNSATISFACTORY 1

1 a

l COMMENTS:

4 i

n .I i

i I

2

E l

l

~

CLOSED REFERENCE QUESTION A.4-b:

4 What meteorological tower parameters are used to determine the appropriate atmospheric stability class for dose assessment? l 4

ANSWER:

Vertical temperature difference is used to determine the appropriate stability class.

5 Plant reference: EPIP-EOF-6 1 i K/A: 194001 A1.16 (3.1/4.4) 1 He operator's response was:

SATISFACTORY UNSATISFACTORY I COMMENTS:

4 5

d 9

4 4

1

+

J

_ _ _. _ - . _ _ _ __ . . _ . _ _ . _ _ _ _ _ _.. .. _m ES-301 Administrative Tonics Outline Form ES - 301 -1 l

Examination Level: SRO (U)

Facility: Fort Calhoun Week of Examination: 12/04225 Examiner's Name (print) :_

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. Shift a. Who is required to attend the pre-shift briefing?

1 Turnover l b. Who may grant an exemption for attendence of operations department personnel at the pre-shift briefing?

l Fuel c. How many wide range nuclear instrumentation handling channels must be operable to conduct refueling operations in the core?

d. Parameters used to determine allowable locations of fuel assemblies within the spent fuel storage

! pool?

A. Surveillance a. A RPS channel failed an I&C surveillance test.

2 Testing Upon returning to the shop, the I&C techs determined that the instrument used to conduct the test was out of tolerance. Is the RPS channel operable?

b. It is discovered that a required surveillance test on a piece of equipment was not conducted as scheduled. It is past the drop dead date for the

! equipment. Is the equipment operable?

A. Radiation JPM - RCA entry 3 Control l

l l

l A. Emergency Emergency Classification- Once-Through Cooling

! 4 Plan l

t Source of meteorological data for dose assessment if the meteorological tower is unavailable.

Examiner: E Mf-- d Chief Examiner: E ' +

/" Fer 4

l l

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

I I r

CLOSED REFERENCE QUESTION A.1 a

I What positions are expected to attend the pre-shift briefings?

1 ANSWER:

i ,

I Tbc licensed operators (SS, LSO and RO's), the STA, the NLO's, the shift chemist and the shift HP.

i E

Plant reference: S0-0-1 K/A: 194001 A1.03 (2.5/3.4) 1 The operator's response was:

i SATISFACTORY UNSATISFACTORY I

T a

COMMENTS:

I f

i 4

,a$

I

't 5

I 4

I 1

1. -

. - . - .. . ~ -

4 i.

2 1

4 .

CLOSED REFERENCE QUESTION A.I b:

What two shift personnel may grant an exemption for attendance of operations department personnel at the pre. shift briermg?

L 1

a

< ANSWER:

1

. 'Ibe SS or the LSO.

4 4

) Plant reference: S0-0-1 K/A: 195001 A1.12 (3.1/4.1) 1

The operator's response was

! SATISFACTORY UNSATISFACTORY j

i COMMENTS: ,

s' s

I i

t 4,

,h

'J i

4 4

4 1

A J

CLOSED REFERENCE QUESTION A.1 c:

liow many and what kind of nuclear instrumentation channels must be operable to conduct refueling operations in the core? :

i l

l i

ANSWER:

Two wide (source) range channels are required to be operable.

l Plant reference: Tech Spec 2.8 (4)

K/A: SG034 K5 (2.6/3.5) l The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS: !

l l l t

ei t

i 4

OPEN REFERENCE QUESTION A.1-d:

Where in spent fuel pool region 2 can a spent fuel assembly with an initial enrichment of 3.2 weight % U-235 and a burnup of 22,000 MWD /MT be stored?

ANSWER:

Anywhere in region 2.

Plant reference: Tech Spec 2.3 (11), figure 2-10 K/A: 000034 A2.03 (3.3/4.0) 1 The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

4 4

i

\

l \

l l

CLOSED REFERENCE QUESTION A.2.a: l An RPS channel failed an I&C surveillance test. It was then determined that the instrument used to

! perform the test was out of tolerance. The RPS channel does not have to be declared inoperable.

However, what two actions must be taken?

' ANSWER:

i l

1. Conduct another test to determine the status of the channel. l l 2. Initiate a Condition Report.

! i

! I l

Plant reference: SO4-1

! K/A: 194001 A1.15 (3.1/3.4) i Tbc operator's response was:

SATISFACTORY UNSATISFACTORY

( l l

l 4

COMMENTS:

l l

l

..t I

i 4

. . . . .- . _ - . - ~- . - . . _ . . - . - - . - . - . _ - -- . - . - ._ . . -

CLOSED REFERENCE QUESTION A.2 b:

It is discovered that a required surveillance test on a piece of equipment was not conducted as scheduled.

+

It is past the " drop dead" date for the equipment. Is the equipment inoperable?

ANSWER:

The equipment must be declared inoperable ( as required by Tech Specs).

4 i

Plant reference: S0-0-1 4

K/A : 194001 A1.15 (3.1/3.4) ,

a i

t ne operator's response was:

j SATISFACTORY UNSATISFACTORY a

i i

4 COMMENTS:

4 4

i i

1

l l

_. - - . _ . . _ . _ . . _ - . _ _ . . . _ . _ _ . _ _ - . _ - _ - ~ . _ . _ . . - _ _ _ . . _ _ _ - . . . _ . . . _ _ _ .

4

Topic (s): RCA Entry and Exit 1

Location (s): RCA Access Control Approximate Time: 10 minutes ActualTune :

Reference (s): (1) GET. Radiation Worker Training (2) NRC K/A 194001, K1.03 (RO2.8/SRO3.4) j (3) NRC K/A 194001, K1.04 (RO3.3/SRO3.5)

Verify current reference revisions match those listed above j . . -. _ _

{ Operator's Name: SS # :

1 4

4 All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this

JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY i Evaluator's Signature : Date :

i 2

Reason,if unsatisfactory :

)

Operator's review : Date:

I Tools & Equipment : None l Safety Considerations: his JPM requires entry into the RCA.

comments :

1, f

d h

N 4

4

Initiating Cue:

An entry into the RCA is required as part of the operating exam. START CRITICAL STEP

ELEMENT STANDARD 1.* Review RWP. Read RWP

2. Check survey maps Check survey maps for radiological conditions in areas to be entered 3.* Obtain dosunctry Verify TLD attached to security badge. Obtain ALNOR 4.* Sign in on appropnate RWP Insert ALNOR into reader, enter PID and RWP number.

5. Inform P.P Personnel about the nature of Tell RP at access control where you are going your entry and what you will be doing.

6. Enter RCA RCA catered 7.* Comply with all posting within RCA No violation of posted requirements

)

8.* Monitor for personnel contamination prior Monitor for contamination using PCM-1 or - i to exiting frisker.

9.* Sign out of RCA Insert ALNOR in reader. Enter PID number, confirm dose and place ALNOR in charging rack.

Termination Criteria: RCA has been exited.

.t I

6 4

,, m, =m

CLOSED REFERENCE QUESTION: JPM-RCA-RO/SRO-1 What action should be taken if your ALNOR alarms?

ANSWER:

Go to low dose waiting area and contact Radiation Protection..

REFERENCE:

GET Radiation Worker Training ;

NRC K/A 194001 K1.03 (2.8/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

4 I

. -.-.- - . . . . - . . . . ~. - . . - . . - _ . . - - . - _ . - . . .- . ~ . . _ - . . . .

CLOSED REFERENCE QUESTION: JPM-RCA-RO/SRO-2 What action should be taken if the ICM-1 alanns when frisking?

ANSWER:

Back out of the frisking booth and follow directions on the LED readout, if the ICM-1 alanns a second time, note the contaminated area and contact Radiation Protection.

REFERENCE:

GET Radiation Worker Training l NRC K/A 194001 Kl.04 (3.3/3.5)

The operator's response was:

SATISFACTORY UNSATISFACTORY ,

COMMENTS:

.t l

4 i

i mrA - '

tk.

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

OPEN REFERENCE QUESTION A.4-a:

i The plant has experienced a Total Loss of All Feedwater from full power operation. Attempts to restore main and/or AFW flow have been unsuccessful. As a result, both Steam Generator levels dropped below 20% WR and once-through-cooling has been established. After the PORV was opened. Pressurizer pressure dropped to 1000 psia and RCS temperature is 545.F. What emergency classification would be appropriate for this condition?

)

1 l

l ANSWER: j A Site Area Emergency should be declared.

Plant reference: EPIP-OSC-1, EAL 2.8 K/A: 194001 A1.16 (3.1/4.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

4 4

CLOSED REFERENCE QUESTION A.4-b:

Wh:0 will be used as the source of meteorological data for dose assessment if the meteorological tower is unavailable?

ANSWER:

The national weather service will be contacted for data.

Plant reference: EPIP-EOF-6 K/A: 194001 A1.16 (3.1/4.4)

De operator's response was:

SATISFACI'ORY UNSATISFACTORY COMMENTS:

_= _ __ __

i ES-301 Individual Walk-through Icsl Outline Form ES-301-2 Examination Level: SRO(1) ,

Facility: Eon Calhoun Week of Examination: 12/M/95 l Examiner's Name (print):

System / JPM Safety Planned Follow-up Questions:

Function K/A/G // Importance // Description 1.0008 ASP-Emergency I a.Why close VCT outlet valve for Emergency Boration?

Boration from the Control 000024EK3.02//4.2/4.4// Emergency Boration Actions Room b.What accident mitigated by Emergency Boration?

i 000040EKl.05//4.1/4.4//Cooldown reactivity effects i

2. 0293 - Backfeed 345 kv VII a. Reason for transfer switches in manual.

to 22 kv 000062A2.15//2.8/3.2// Out of phase or voltage mismatch j d

b. Purpose of breaker test position 000062SG13//3.4/3.4// Perform integrated plant procedures

3. 0347 - Unload D/G #1 Vil a.Effect of reactor trip while stopping D/G 000064A4.06//3.9/3.9// Manual start. load and stop of D/G

b. Loss of control power to D/G 000063K4.01//2.7/3.0// Manual transfer of control

4. 0778 - Adjust T-cold IX a.Why does TM/LP setpoint vary with pressure?

calibration on the RPS 000012K5.01//3.3/3.8// Knowledge of DNB Panel b. Basis for ASGT trip?

000012K4.02//3.9/4.3// Basis for trip.

5. 0138 - Operate CVCS to 11 a. Basis for SIRWT boron concentration?

makeup to the SIRWT 000006K6.01//3.4/3.9// Borated water sources b.Why Simultaneous hot and cold leg injection?

000011EK3.13//3.8/4.2//Ilot leg injection / recirculation l Simulator JPMs above this line. Plant JPMs below this line

6. 0719 - Startup Hydrogen VI b.Other systems that can use hydrogen purge filters.

Purge System 000027K5.01//3.1/3.4// Purpose of charcoal filters

b. Hydrogen analyzer flowpath.

000028A4.03//3.1/3.3// Monitor hydrogen sampling.

7. 0295 - Switch laverter VII a.TS operability on bypass transformer?

Supply from Bypass to 000057SG008//3.2/3.6//1'ech Spec entry conditions Normal (modify to alternate b. Actions required on blackout.

path) 000055EK3.01//2.7/3.4// Length of time for batterv.

8. 0214 - Shift Inservice Air VIII a. Iligh temperature compressor trip.

Compressors 000078K1.04//2.6/2.9//cochng water to compressor.

B. Instrument Air containment isolation.

000078Kl.03//3.3/3.4// Containment Air

9. 0010RW - Loss of X a. Consequences of opening interface ulve.

Component Cooling 000008A2.02//3.2/3.5// low surge tank les el Water (Raw Water) b.CCW cooling with no raw water.

000076A2.01//3.5/3.7// Loss of service water system

10. New - Makeup to the V a. Time to empty EFWST.

Emergency Feedwater 000061K4.01// 3.9/4.2// Water sources and priority Storage Tank using b. Design basis for inventory tech spec Diesel Fire Pump 000061K4.01//3.9/4.2//. Water sources and priority Examiner: J. -- ^~4 Chief Examiner: W 4 b ' W ~ 4

,+,c.-a <

_ _ . . . = . . . . . .. _- . - - _

i 3

Revision: 6 October 24,1995 I

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0138 Operate CVCS to makeup to the SIRWT j 4

System (s): CVCS

, Location (s): Simulator Approximate Time: 23 minutes ActualTime :

Reference (s): (1) OI-CH-4 6.10 R16 4

(2) TS-2.2, 2.3 j (2) NRC K/A 000004, KLOl (RO3.4/SRO3.9) j (3) NRC K/A 000004, A2.06 (RO3.8/SRO3.9) j 1

Verify current reference revisions match these listed above i Operator's Name: SS # : ;

i All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this !

JPM. l The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

To,ols & Equipment : None Safety Considerations:

Comments : This JPM will normally be performed as a dynamic JPM on the Simulator. It is not intended to add all of the water and boric acid necessary per the calculation, but rather to prove the ability to conduct the ERF procedure and then prove ability to operate the CVCS system to make up to the SIRWT.

Open CH-152 [ LOA CVC24100%]

l 1

l l

Revision: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0138 Operate CVCS to makeup to the SIRWT Initiating Cue:

Tbc plant is operating at 100% power. SI tanks have just been filled. The SIRWT level is 186 inches. The lates? SIRWT bossa was 1910. ppm. Both Boric Acid tanks are at a concentration of 3%.

The Shift Supervisor directs you, the LO, that the SIRWT be blended up to 190". Use CH-4 A, Boric Acid pump. All prerequisites are met. START CRt11 CAL STEP

ELEMENT STANDARD

1. Locate copy of OI-CH-4 NOTE: Give copy of procedure to candidate after located.

1. DETERMINE flow rate for Refer to OI-ERFCS-1, procedure 31 OR hand concentration of 1910 ppm. calculation.

2. Verify WD-250 is locked open CUE: EONA reports WD-250 is locked open.

3. Ensure FCV-269 is in close. CB-4 FCV-269 switch is in close and GREEN light is j lit. j

4. Place HC-269 in manual HC-269 switch in manual

5. Ensure Boric Acid recirculation valves Both switches in close position and GREEN are in closed: lights lit.

HCV-264 i HCV-257 l

6. Station EONA to watch SIRWT vents. CUE: EONA is watching SIRWT vents

7. Place LCV-218-3 in close. CB - 1,2 ,3 LCV-218-3 switch in closed and GREEN light lit.

8. Open CH-152 CUE: EONA has opened CH-152

9. Start Boric Acid pump CB-4 Place control switch for CH-4A to start and observe RED light lit.

10. Place FCV-269Y and FCV-269X in Switches in open and '.ED lights lit.

open.

11. Set the makeup flow controllers to the CB-4 desired flow rates to obtain proper boron Adjust flow control on FAC-269Y and FRC-mncentration. 269X to obtain desired flow rates.

-. .- . = .. -- - . .. - - - . - -

j

- Revisi n: 6 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0138 Operate CVCS to makeup to the SIRWT l CRITICAL STEP

ELEMENT STANDARD 4

12. Obtain sample of blend Direct Chemist (simulator operator) to obtain blend sample.

to SIRWT.

CUE: Simulator Operator will report concentration at l blender [ XBATBLDRl.

CUE: When concentration at blender is reported to be 1910 ppm or girater then provide cue that SIRWT level is 190".

13. Stop blend to SIRWT FCV-269Y switch in close. GREEN light lit.

14. Stop Boric Acid pump CH-4A switch in after-stop and GREEN light lit.

l l

15. Flush piping with Leave FCV-269X open after FCV-269Y has been closed. ]

demineralized water. CUE: Flush of pipingis complete. j

. l 1

16. Close FCV-269X CB-4 I

) FCV-269X switch in close and GREEN light lit. l 17a. Close CH-152 CUE: EONA has closed CH-152. l 1

< 17b. Place HC-269 in Switch placed in DILUTE l DILUTE

Place LCV-218-3 in AUTO LCV-218-3 switch in auto. GREEN and AMBER lights lit. l i

Termination Criteria: SIRWT level is returned to normal F

..< l i

l 4

i Revision: 6 October 24,1995 Fort Calhoun Statien - Operations training JOB PERFORMANCE MEASURE ,

JPM No: JPM-0138 Operate CVCS to makeup to the SIRWT CLOSED REFERENCE QUESTION: JPM-0138-SRO-1 i

What is the basis for the SIRWT boron concentration required by Tech Specs?

ANSWER:

To provide adequate shutdown margin following an accident.

REFERENCE:

Tech Spec 2.3 Basis NRC K/A 000006 K6.01 (3.4 /3.9) l i

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

J

i I

l Revision: 6 !

October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

, JPM No: JPM - 0138 Operate CVCS to makeup to the SIRWT

> l CLOSED REFERENCE QUESTION: JPM-0138-SRO-2 i

Why is simultaneous Hot and Cold leg injection initiated 81/2 hours after a big LOCA? I 1

4 a

ANSWER: i

. l l

To prevent Boric Acid precipitation in the core. ;

- 1

! l l

REFERENCE:

1 ECCS STM NRC K/A 0000011 EK3.13 (3.8/4.2) j i

The operator's response was:

SATISFACTORY UNSATISFACTORY l

COMMENTS:

4 l

1 l

Initiating Cue:

'Ibe plant is operating at 100% power. SI tanks have just been filled. The SIRWT level is 186 !

laches. The latest SIRWT borin was 1910. ppm. Both Boric Acid tanks are at a concentration of l 3%. The Shift Supenisor directs you, the LO, that the SIRWT be blended up to 190". Use CII-4A, {

Boric Acid pump. All prerequisites are met. START l

l i

1 i

4 l

1

)

I 1

Revision: 5 l

October 24,1995 l Fort Calhoun Station . Operations training JOB PERFORMANCE MEASURE l 1

JPM No: JPM.0778 I Adjust T w Calibration on the RPS Panel I

1

. 1 System (s) : Reactor Protective System Location (s): Simulator Approximate Time: 9 minutes ActualTune :

Reference (s): (1) OI-RPS-2, Attachment 1 (R3)

(2) NRC K/A 000012, K4.01 (RO3.7/SRO4.0)

(3) NRC K/A 000012, A1.01 (RO2.9/SRO3.4)

Verify current reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

Opprator's review : Date:

Tools & Equipment : None Safety Considerations: None Comments :'Ihis JPM should be performed as a dynamic JPM on the simulator.

Use full power IC, Adjust Channel A Tc Cal. 0.4-F below other channels. Obtain key for Trip Unit 9.

Revision: 5 October 24,1995 Fort Calhoun Station - Operations trairdng JOB PERFORMANCE MEASURE JPM No: JPM - 0778 Adjust Tm Calibration on the RPS Panel Initiating Cue:

The plant has been operating for 30 days at 100% power. You, the LO, are taking your shift readings on OP-ST-SHIFT-1 and you notice Channel "A" T. Cal. Is 0.4-F low. The shift supervisor directs you to take the appropriate action to adjust the "A" Channel T. Cal. All other channels are indicating within 0.1-F of each other. START CRITICAL STEP

ELEMENT STANDARD 1

1. Otain a copy of OI-RPS-2, Attachment i Procedure has been obtained.

2. Record T. DVM readings on all channels. AI-31A/B/C/D RPSCIP Complete fonn

3. Record DVM readings on all T. Cal. Complete fonn ,

channels. I

4. Record T. CAL. Pot settings Complete form l

5.* Bypass channelA"TM/LP trip unit. CUE: IIand trip unit #9 bypass key to ,

I candidate.

Al-31 A BYPASS trip unit number 9 on "A

channel, AMBERlightlit.

6. Log into Tech Spec 2.15(1) CUE: Log entry has been made.

7.* Adjust T. Cal. Pot so the T. Cal. Adjust Cal. pot Reading on channel"A" DVM is the same as the highest T. recorded.

8.* Remove bypass key from channel"A" Remove key and AMBERlight off TM/LP trip unit Return key to Shift Supervisor.

.9f Exit Tech Spec 2.15(1) for the affected CUE: Log entry has been made.

channel.

10. Record new T Cal. DVM readings. Complete form

11. Record new T. Cal. Pot readings Complete form Termination Criteria: All T. Cal. Channels read within 0.1-F of each other.

I s

1 1

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE j i

JPM No: JPM-0778 l Adjust Ta Calibration on the RPS Panel l l

l CLOSED REFERENCE QUESTION: JPM-0778-SRO-1 Why does the TM/LP trip pressure setpoint increase as RCS cold leg temperature increases?

ANSWER: l l

j I

To provide protection from DNB induced fuel damage.

REFERENCE:

RPS STM NRC K/A 000012 K5.01 (3.3/3.8) l 1

l The operator's response was:

I SATISFACTORY UNSATISFACTORY l

4 COMMENTS: l

i Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i

JPM No: JPM - 0778 Adjust T u Calibration on the RPS Panel ;

I l

l CLOSED REFERENCE QUESTION: JPM-0778-SRO4.

What RPS trip is designed to prevent DNB if one of the MSIVs closes at power? j j

ANSWER:

l ne Asymmetric Steam Generator Transient (ASGT) trip. [135 pst difference between S/Gs]

I

REFERENCE:

RPS STM NRC K/A 000012 K4.02 (3.9/4.3)

The operator's response was:

l SATISFACTORY UNSATISFACTORY COMMENTS:

i

1 i

1 l

i i

i Initiating Cue: ;

The plant has been operating for 30 days at 100% power. You, the LO, are taking your shift j readings on OP-ST-SHIFT-1 and you notice Channel "A" T Cal. Is 0.4-F low. The shift supervisor directs you to take the appropriate action to adjust the "A" Channel T Cal. All .

other channels are indicating within 0.1-F of each other. START l l

I i

,.4 1

Revision: 4 October 24,1995 l

Fort Calhoun Station - Operations training !

JOB PERFORMANCE MEASURE JPM No: JPM-0347

Unload DG-1 4

I System (s): Diesel Generator !

Location (s): Simulator Approximate Time: 5 minutes ActualTime :

Reference (s): (1)' OI-DG-16.11, R17 (2) NRC K/A 000062, K3.02 (RO4.1/SRO4.4) e (3) NRC K/A 000062, A2.ll (RO3.7/SRO4.1) ,

l Verify curnat refenace revisions match those listed above 1

Operator's Name: SS # : i All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM. l The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY l 1

Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

.t Tools & Equipment : None Safety Considerations None Comments : This is designed to be a dynamic JPM on the simulator.

Revision: 4

, October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0347 Unload DG-1 Initiating Cue:

4 Diesel Generator DG-1 has been operating loaded and synchronized to bus 1A3, following a manual start. You the LO, are directed to unload and stop DG-1. All start signals to the Diesel Generator !

have been cleared. The EONT is stationed at DG-1. START CRITICAL STEP

ELEMENT STANDARD

1. Locate Copy of OI-DG-1 NOTE: Give copy of procedure to candidate after located.

CB-20

2. Reduce load on DG-1 to approximately 300 kw. Use Governor Control DG-1 to lower Diesel Load to (275-325) amps.

3. Open Breaker I AD1 Open Breater I AD1 and GREENlight lit

4. Operate Diesel Generator at 900 RPM Monitor Diesel.

for at least five minutes. CUE: 5 minutes have pasried.

5. Ensure 86A/D1 and 86B/D1 are reset. Al-30A Lockout Relays are RESET:

Blackflag and AMBER lights on.

6. Stop DG-1 Depress both stop pushbuttons and hold for 10 seconds.

7. Verify DG-1 stops 0 RPM indicated OR Diesel taipped OR Annunciated Engine Stop light lit.

NOTE: any one of these indications is adequate.

8. Verify DG-1 is lined up for emergency All alarms ::Icared except " Diesel Auto Standby" start. and" Breaker Auto Standby"

9. Ensure DG-1 is setup for idle speed start. Hold governor control in auto for 15 seconds.

CUE: EONT reports that governor has run down T/rmination Criteria: DG-1 has been unloaded and is lined up for emergency standby.

1

\

l 4

Revision: 4 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0347 Unload DG-1 1

i l

OPEN REFERENCE QUESTION: JPM-0347-SRO-1 What would be the affect on the D/G if a reactor trip occurred while you were pushing the STOP pushbuttons to stop the diesel?

l ANSWER:

l As soon as the stop pushbuttons were released, the diesel would restart.

REFERENCE:

Diesel Generator STM NRC K/A 0000064 A4.06 (3.9/3.9)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

.t 4

~.. - .- .- - - .

I Revision: 4 l October 24,1995 j i

Fort Calhoun Station - Operations training ;

JOB PERFORMANCE MEASURE JPM No: JPM-0347 Unload DG-1 j i

l l

OPEN REFERENCE QUESTION: JPM-0347-SR.O-2 4 How could a diesel generator be started if its normal source of DC control power is lost?

ANSWER:

DC control power could be switched to the alternate source using the transfer push-button..

I i

i

REFERENCE:

1 Electrical System STM NRC K/A 000063 K4.01 (2.7/3.0)

De operator's response was:

SATISFACTORY UNSATISFACTORY I

i 1

COMMENTS:

Initiating Cue:

Diesel Generator DG-1 has been operating loaded and synchronized to bus 1A3, following a manual ]

start. You the LO, are directed to unload and stop DG-1. All start signals to the Diesel Generator J have been cleared. He EONT is stationed at DG-1. START i

I I

.c

Revision: 5 i October 24,1995 ;

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

) JPM No: JPM - 008 ASP - R Emergency Beration from the Control Room j l

J System (s) : Abnormal / Emergency Procedures j Location (s): Simulator Approximate Time: 7 minutes ActualTime :

j Reference (s): (1) EOP-00

' NRC K/A 000001, K4.05 (2) (RO3.9/SRO3.9) ,

J (3) NRC K/A 000001, A4.02 (RO4.1/SRO3.9)

$ Verify current reference utvisions match those listed above P

f 3 l Operator's Name: SS # :

i All Critical Steps ( * ) must be perfonned or simulated in accordance with the standards contained in this

JPM.

l

. The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason, if unsatisfactory :

4 Operator's review : Date:

s Tools & Equipment: None Safety Considerations: None Comments : Simulator Dynamic JPM l

Overside HCV-268 closed and LCV-218-2 Open.

[VLVCVC24 0%) [VLV CVC20100%]

4 !

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency 11 oration from the Control Room l

Initiating ( ue:

A reactor trip has occurred and while performing EOP-00, you find that all shutdown rods have stuck out. All attempts to trip or insent control rods have failed. You are the LO, the LSO directs you to immediately commence emergency boration. LCV-218-2 is tagged out, physically stuck in the open position. START CRITICAL STEP

ELEMENT STANDARD CUE: No procedures art allowed for this JPM.

1. Close FCV-269X and 269Y. CB-4 Controlswitches for FCV-269X & Yin CLOSED AND GREENlights lit.

2. Open allof the following valves: a. Control switch for HCV-268 to OPEN until

a. HCV-268 only RED light lit.

b. HCV-265 b. Control swit;h for HCV-265 to OPEN until

c. HCV-258 only RED light lit. l

c. Control switch for HCV-258 to OPEN until only RED light lit.

3. Start ALL of the following pumps: a. Control switches to start a.Both Boric Acid Pumps CB-1,2,3

b. ALL charging pumps b. Control switches to start AND RED lights lit 1

4. Locally OPEN HCV-268 Direct EONA (simulator operator) to manually 1 open HCV-268.

CUE: Simulator operator will wait

.. s approximately 2 minutes, open LCV-218-2 on ,

a one minute ramp. j CUE: When red light is on, EONA reports I that HCV-268 is open. i t

l i

-. _._ _ . .. . =_. . .. . - . . - . -

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP- R Emergency Boration frem the Control Room r

CRITICAL STEP

ELEMENT STANDARD

6. Ensure ALL of the following valves are CB - 1,2,3 ,

closed: a. GREENlightlit.

a. LCV-218-3 I b. HCV-257 CB-4

c. HCV-264 b. GREEN light lit

c. GREEN light lit.

Termination Criteria : Borated water is being injected into the RCS.

l l

l

,i i

t J d

1 4

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R '

Emergency Boration from the Control Room t CLOSED REFERENCE QUESTION: JPM@8 ASP-SRO-1 Why is it necessary to close LCV-218-2 when using only the gravity feed valves?

ANSWER:

VCT pressure may hold a check valve closed in the gravity feed header..

REFERENCE:

P&ID E-210-121 NRC K/A 000024 EK3.02 (4.2/4.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

4

Revision: 5 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 008 ASP - R Emergency Beration from the Contml Room CLOSED REFERENCE QUESTION: JPM-008 ASP-SRO-2 l

An emergency boration lineup is automatically initiated by an SIAS. What accident, in particular, is this designed to mitigate?

i i

ANSWER:

A steam line break (or excessive heat removal event).

REFERENCE:

NRC K/A 000040 EKl.05 (4.1/4.4)

The operator's response w~as:

l SATISFACTORY UNSATISFACTORY ]

i COMMENTS:

l e$

{

4 4

j i

a 4 Initiating Cue:

A tractor trip has occurred and while perfonning EOP-00, you find that all shutdown rods have stuck out. All attempts to trip or insert control rods have failed. You are the LO, the LSO directs you to immediately commence emergency boration. LCV-218-2 is tagged out, physically stuck in the open position. START 1

t i

a a

4 >

a 4

1

. 5 D

4 L

1

I 2

Revision: 6 November 9,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0293 Backfeed 345 kV to 22kV d

i System (s) : Electrical Distribution Location (s): Simulator Approximate Time: 6 minutes ActualTime :

Reference (s): (1) OI-EE-1, Attachment 2 (2) NRC K/A 000062, Kl.04 (RO3.7/SRO4.2)

(3) NRC K/A 000061, A4.07 (RO3.1/SRO3.1)

Vedfy current reference revisions match those listed above j

i Operator's Name: SS # :

, All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

. Operator's review : Date:

Topis & Equipment : None Safety Considerations: Ensure DS-Tl is open prior to backfeed from 345 kV Comments : This JPM will normally be performed as a dynamic JPM on the Simulator.

4 M

l Revision: 6 November 9,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i

JPM No: JPM - 0293 Backfeed 345 kV to 22kV Initiating Cue:

The Main Generator is offline. DS-T1 is open. The 345 kV system is available for senice. You, the LO, are directed to backfeed the Buses 1A1 and 1A2 from the 345 kV. All precautions are satisfied. START CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of OI-EE-1, Attachment 2 h proper attachment has been obtained.

2. Turn on Synchroscope for 3451-4. Synchroscope is on.

3. Verify synchroscope is approximate!y at the Synchroscope verified to be at 12 o' clock.

12 o' clock position.

4.* Close 3451-4 3451-4 is closed.

5. Turn off synchroscope Synchroscope is off.

6. Turn on Synchroscope for 3451-5 Synchroscope is on.

7. Verify synchroscope is approximately at the Synchroscope verilled to be at 12 o' clock.

12 o' clock position.

_8.* Close 3451-5 3451-5 is closed.

9. Turn off synchroscope. Synchroscope is off.

10. Ensure both 43/l Al-1 A3 and 43/l A2-1 A4 Both Fast Transfer Switches arc in MANUAL.

Fast Transfer Switches are in MANUAL.

CUE: T1A-1 and TIA-2 have been deenergized for one hour.

11. Turn on synchroscope for 1 All. Synchroscope is on.

12. Verify incoming and nmning voltages CUE: Voltages are matched.

matched.

13. Verify synchroscope is approximately at the Synchroscope is at 12 o' clock.

12 o' clock position.

14.* Close 1 A11 1 Al1 is closed.

15.* Open I A31 1 A31 is closed.

16. Turn off synchroscope. Synchroscope is off.

17. Turn on synchroscope for 1 A22. Synchroscope is on.

18. Verify incoming and running voltages CUE: Voltages are matched.

.' matched.

19. Verify synchroscope is approximately at the Synchroscope is at 12 o' clock.

12 o' clock position.

2_0.* Close 1 A22 1A22 is closed.

21.* Open I A42 1 A42 is closed.

22. < Turn off synchroscope. Synchroscope is off.

Termination Criteria: Buses l Al and 1 A2 are being supplied from 345 kV.

Revision: 6 November 9,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0293 Backfeed 345 kV to 22kV CLOSED REFERENCE QUESTION: JPM-0293-SRO-1 Why must the 43/l Al-1 A3 and 43/l A2-1 A4 Auto-Manual transfer switches be placed in the MANUAL position prior to synchronizing and closing breakers?

ANSWER:

If the 43/l Al-1 A3 and/or 43/l A2-1 A4 Auto-Manual transfer switches are NOT shifted to MANUAL, breakers I All and/or I A22 will not close.

REFERENCE:

NRC K/A 062000 A2.15 (2.8/3.2)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

9 Revision: 6 November 9,1995

~

Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE d

JPM No: JPM-0293 Backfeed 345 kV to 22kV l

CLOSED REFERENCE QUESTION: JPM-0293-SRO-2 In order to verify proper operation of the interlocks associated with a pump supplied by a 480 V or 4160 V bus without actually starting the pump, what position should the pump's breaker be 2

racked into?

i

, ANSWER:

The TEST position.

REFERENCE:

r NRC K/A 000062 SG13 (3.4/3.4) 4 5

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

.t

1 i

)

I l l

Initiating Cue:

I

The Main Generator is off line. DS-T1 is open. The 345 kV system is available for service. You, i the LO, an directed to backfeed the Buses IA1 and 1A2 from the 345 kV. All precautions are l i satisfied. START 1

M 1

i i

3 3

i 4

r 1

i i

j 1

i l

9 !

ab I

1 l

i i

1 i

. . . . _ _ . __ _. ._ __ . _ . . . ~ _ . . . _ _

< Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0214 Shift Inservice Air Compressors 4

4 System (s): Compressed Air Location (s): Room 19 Approximate Time: 12 minutes Actual Time :

Reference (s): (1) OI-CA-1 6.3 R21 (2) NRC K/A 000078,6001 (RO2.9/SRO3.1)

Verify current reference revisions match those listed above

, l

Operator's Name: SS # :

1 All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's perfortnance was evaluated as: SATISFACTORY UNSATISFACTORY l

Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

.c Tools & Equipment : None Safety Considerations: None.

Comments : This JPM will be performed as a static JPM in the plant i

)

l Revision: 10 October 24,1995 i l

, Fort Calhoun Station - Operations traimng JOB PERFORMANCE MEASURE !

l JPM No: JPM - 0214 Shift Insenice Air Compressors Initiating Cue:

The air compressor lineup is as follows: CA-1 A running, CA-1C in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for weekly rotation as follows: CA-lC runnmg, CA-1B in standby, and CA-1 A in Control room start. START CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of OI-CA-16.3 R21 Procedme has been obtained. !

2.* Verify the following on the Air Compressor a. Check oil sight glass.

to be started (CA-lC)

a. Oillevel greater than 1/3 of b. CoolingwaterpressurePI-1942C lass.

a. Cooling water pressure greater than 30 psig.

3.* Place load transfer switch on CA-IC to Switch to OFF position.

OFF.

4.* Place the Air Compressor control switch for Switch to CS position.

CA-lC to CS.

5.* Verify proper oil pressure (CA-lC) Oil pressure stabilizes in 15-20 seconds CUE: Oil pressure is 34 psig.

6. Verify cooling water flow Observe cooling water flow through bullseye. i I

FI-1955C 7.* Place CA-lC load transfer switch in Select position 1 or 2 position 1 or 2.

NOTE: Either position is acceptable.

8. Verify CA-lC for proper operation. CUE:

Oil Pressure = 32 psig Intentooler Air Pressure = 30 psig Discharge Air Pressure = 102 psig Jacket Water Pressure = 43 psig Jacket Water Temperature = 1020F CUE: CA-1C is functioning properly.

9.* Place CA-1 A load transfer switch in OFF. Switch to OFF position.

CUE: CA-1C is holding the air load.

10.* Place CA-1 A control switch to OFF Switch to OFF position.

I1. Place the CA-1A CR Control Switch to Notify Control Room to place the Control Switch After Stop. for CA-1A in After Stop CUE: Control Room reports that switch is in After Stop Position.

Revision: 10 October 24,1995 4

i Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214 Shift Inservice Air Compressors CRITICAL STEP

ELEMENT STANDARD 12.* Place the local control switch for CA-I A to Switch in CS position.

CS.

13. Verify CA-1 A cooling water flow is Observe bullseye for NO flow.

stopped CUE: 'Ibere is no flow.

14. Place load transfer switch for CA-1 A in Select position 1 or 2.

position 1 or 2.

NOTE: either position is acceptable.

15.* Place CA-1B local control selector switch Switch to S'IBY position in STBY.

16. Place the CA-1B CR Control Switch to Request Control Room to place CA-1B control After Start. switch to After Start.

Cue: Control room arports switch is in After Start.

17.* Ensure ALL load transfer switches are in 1 All load transfer switches are in position 1 or 2.

or 2.

NOTE: Either position is acceptable.

Termination Criteria: CA-lC is running, CA 1B is in standby and CA-1 A is in CR start.

1

.c l

j

Revision: 10

! October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0214 Shift Inservice Air Compressors CLOSED REFERENCE QUESTION: JPM-0214-SRO-1 1

The procedure cautions agamst having too much cooling water to the standby compressor to prevent low pressure trips. What would happen if the cooling water valve was throttled too far closed?

ANSWER:

I ne compressor will eventually trip on high temperature.

REFERENCE:

Service and Instrument Air STM l NRC K/A 000078 K1.04 (2.6/2.9)

The operator's response was: j SATISFACTORY UNSATISFACTORY I COMMENTS:

.s I

7 l

1

Revision: 10 October 24,1995 Fort Calhoun Station - Operations trauung a JOB PERFORMANCE MEASURE l JPM No: JPM-0214 Shift Insenice Air Compressors CLOSED REFERENCE QUESTION: JPM-0214-SRO-2 What determines whether the Instrument Air containment isolation valves will close on a containment isolation signal?

l ANSWER

ne instrument air pressure. [They will only close if pressure is less than 70 psig.]

REFERENCE:

} Service and Instrument Air STM NRC K/A 000078 Kl.03 (3.3/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

..t l

. . . , . . .. _. . .- . .. . _= . - . - . - . . . . - - - - . -. . . - . - .

t Initiating Cue:

The air compressor lineup is as follows: CA-1A running, CA-IC in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for weekly rotation as follows: CA-lO running, i CA-1B in standby, and CA-1 A in Control room start. START j

l I

i

..(

e

i Revisio.+. O October 25,1995 l Fort Calhoun Station - Operations training ;

JOB PERFORMANCE MEASURE JPM No: JPM-295 ASP l Switch Inverter Supply Power Fmm Bypass to Nonnal l I

System (s) : 125 volt AC Instrument Power IMon(s): Switchgear Room Approximate Time: 15 minutes ActualTime :

Reference (s): (1). OI-EE-4 Attachment 1 R20 (2) NRC K/A 000057, A1.01 (RO3.7/SRO3.7)

Vedfy current reference revisions match those listed above Operator's Name: SS # :

All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this i JPM. i The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY j Evaluator's Signature : Date :

l Reason,if unsatisfactory :

..t Operator's review : Date:

None Tools & guipment.:

Safety Considerations:

Comments : " Ibis is an alternate path JPM . This JPM will be performed as a static JPM in the plant.

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-295 ASP Switch Inverter Supply Power From Bypass to Normal Initiating Cue:

Instrument Inverter "A" is out of service. AI-40A is being supplied via the bypass transformer. The electricians have cleared their tags on Inverter "A" and the Shift Supenisor directs you, the LO, to start up Inverter "A" and place it in service. All other prerequisites have been met. START CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of OI-EE-4, Attachment 1 Procedure has been obtained. ;

R20

2. Ensure the input breaker EE-8H-CBI at the Check Breaker to OPEN position.

inverter is open.

3. Ensure the DC source breaker at the DC EE-8F panel is closed. DC Bus #1 ,

EE-8F-CB24 (Circuit Breaker-24) l l

Check Breaker to Closed position.

4. Ensure the manual (bypass) transfer switch Check Si to bypass position.

Si at the inverter is in bypass. ,

5.* Precharge the inverter. Push precharge button on inverter and wait ~ 10 I seconds 6.* Close input breaker EE-8H-CBl. Place Breaker to CLOSED position.

7. Verify Synch Loss Light is LIT. Cue: Light is LIT

8. Verify Reverse Transfer Light is LIT. Cue: Light is LIT.

9.* Place ManualTransfer Switch S1 in Select INVERTER position with Swi tch.

INVERTER position

10. Ensure Sync. Loss Light is OFF. Cue: Light is LIT NOTE: This indicates an Inverter problem.

11.* Terminate procedure and contact Shift DO NOT push Forward Transfer Button.

Supervisor. Continue to allow bypass transformer to supply Instrument bus. NOTE: It is acceptable, but not required, for operator to return switch Si to the bypass position and open input breaker EE-8H-CBI STOP

Revisi:n: 0 October 25,1995 4

j Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 295 ASP I Switch laverter Supply Power From Bypass to Normal l

l

.! i CLOSED REFERENCE QUESTION: JPM-295 ASP - SRO -1 l

Is the instrument bus considered operable per Tecimical Specifications when powered from its bypass transformer?

i ANSWER:

1' No. The instrument bus is not considered operable unless it is powered from its associated inverter.

, l

REFERENCE:

NRC K/A 000057 G008 (3.2/3.6) i The operator's response was:

SATISFACTORY UNSATISFACTORY d

CgMMENTS:

j I

)

a

i l

Revisi:n: 0 l October 25,1995 Fort Calhoun Station - Operations training ,

JOB PERFORMANCE MEASURE l

JPM No: JPM-295 ASP l Switch Inverter Supply Power From Bypass to Normal 1

. CLOSED REFERENCE QUESTION: JPM-295 ASP - SRO -2 What actions are required to assure that instrument buses will remain energized for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months y

following a station blackout?

! ANSWER:

. DC bus loads must be mininuzed.

I

REFERENCE:

1 EOP/AOP Attachment 6 NRC K/A 000055 EK3.01 (2.7/3.4) i i l

l The operator's response was:

1 SATISFACTORY UNSATISFACTORY I

i d

COMMENTS:

.s

I i

4 1

Initiating Cue:

9 Instrument Inverter "A" is out of service. AI-40A is being supplied via the bypass transformer. The ;

s electricians have cleared their tags on Inverter "A" and the ShiA Supervisor directs you, the LO, to start !

up Inverter "A" and place it in service. All other prerequisites have been met. START 4

i i

3 1

l

]

4 a

4 1 I i' 4

1 3

d i

i I

eI i

. .. . .. _ . . _ _ _ _ - .. .. -_ . - . - . . . ~ _ . . . . - .

l

, Revision: 0 October 24,1995 l l

Fort Calhoun Station . Operations training l JOB PERFORMANCE MEASURE JPM No: JPM-NEW i Emergency Fill of the EFWST Using the Fist Pmtection System I

System (s): AFW and Fire Protection Location (s): Room 81 Approximate Time: 20 minutes ActualTune :

Reference (s): (1) AOP . 30, R4 (2) NRC K/A 000061, K4.01 (RO3.9/SRO4.2)

(3) NRC K/A 000061, A1.04 (RO3.9/SRO3.9)

Verify current reference revisions match those listed above Operator's Name: SS # :

1 All Critical Steps ( * ) must be perfonned or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

l Reason,if unsatisfactory :

i Operator's review : Date: ;

1 4

Tools & Equipment : None Safety Considerations: TIIIS JPM WILL BE PERFORMED AS A STATIC JPM IN TIE PLANT.

Comments : The fire hose and adapter should not be moved from the fire brigade assembly area.

Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Pmtection System l

Initiating Cue: l l

A station blackout has occurred. AFW is being supplied to the ster n generators from FW-10(Turbine l Driven AFW Pump.). FW-54 (Diesel Driven AFW Pump.) and Blair water are unavailable. The LSO directs you to prepare to replenish the EFWST using the fire system. START l

CRmCAL l STEP

ELEMENT STANDARD i

l

1. Obtain procedure AOP-30 AOP-30 is obtained and verified. !

2.* Close FW-652 ROOM 81 FW-652 is closed I 3.* Close FW-654 FW-654 is closed 4.* Obtain a 21/2 inch male-to male adapter FIRE BRIGADE ASSEMBLY AREA and a 100 foot section of 21/2 inch fire Locate adapter and fire hose.

hose. CUE: Fire Hose has been obtained (after examinee locates hose.)

5.* Connect male-to-male adapter to the male CUE: The Adapter is connected end of fire hose.

6.* Connect both ends of the fire hose to the ROOM 81 following valves: CUE: Both ends connected a) FW-1275 b) FP-456 7.* Open FW-1275 FW-1275 is open 8.* Open FW-653 FW-653 is open

9. Determine time for EFWST to empty CUE: The time to empty has been determined. The LSO directs you to begin filling the EFWST.

1,0.* Open FP-456 FP-456 is open

11. Ensure FP-1B starts Verify pump start with control room FP-1B has started CUE: EFWSTlevelis91%

12. Close FP-456 FP-456 is closed STOP Termination Criteria: EFWST levelis 91% and fill is terminated.

Revision: 0 October 24,1995 Fo:t Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Protection System OPEN REFERENCE QUESTION: JPM-new-RO-1, SRO-1 How long will it take for the EFWST to empty if the level is 32 inches and the AFW flow is 150 SPm?

ANSWER:

The EFWST will empty in one hour or less.

REFERENCE:

AOP-30 Attachment A NRC K/A 000061 K4.01 (3.9/4.2) l The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

This question is answered as JPM step 8.

Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Protection System CLOSED REFERENCE QUESTION: JPM-new-SRO-2 What is the basis for the technical specification on required EFWST Inventory?

ANSWER:

'Ibe inventory is sufficient to remove decay heat for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ..

REFERFECE:

Tech Spec NRC K/A 000061 K4.02 (3.9/4.2)

The operator's response was:

SATISFACTORY 'JNSATI5mACTORY COMMENTS:

l l

i i

l l

1

Initiating Cue:

A station blackout has occurred. AFW is being supplied to the steam generators from FW-10(Turbine Driven AFW Pump.). FW-54 (Diesel Driven AFW Pump.) had Blair water are unavailable. The LSO directs you to prepare to replenish the EFWST using the fire system. START t

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E 0

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4 I

Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW Loss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

System (s) : Abnormal / Emergency Procedures Location (s): Room 81 Approximate Time: 15 minutes ActualTime :

Reference (s): (1) AOP - 11, R4 (2) NRC K/A 000008, K3.01 (RO3.4/SRO3.5)

(3) NRC K/A 000008, A2.01 (RO3.3/SRO3.6)

Verify current reference revisions match those listed above Operator's Name: SS # :

l All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

..t Operator's review : Date:

l l

l Tools & Equipment : None Safety Considerations: None Comments : This JPM will be conducted as a static IPM in the plant..

l

_ __. _ = _ .- _ _ _ -. _

Revision: 1 October 24,1995 I Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i JPM No: JPM-0010RW i 14ss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

l Initiating Cue:

4 The reactor has been tripped from 100% power. A total loss of all CCW has occured. You are directed to establish Raw Water backup to the Control Room Air Conditioners as directed by the LSO. VA-46B is in service. START 4

k CRITICAL ;

STEP

ELEMENT STANDARD

1. Obtain a copy of AOP-11, R4 AOP-11. R4 has been obtained.

CUE: The control room reports that HCV-2899A&B have been closed.

i 2.* Unlock and release the handjacks from: Room 69 l a. HCV-2899C Remove locking device and place the valves in

b. HCV-2899D the open position

3.* Open the following valves: a. 3-Way namual control valve in open position.

l

a. IA-HCV-2899C-TV b. 3-Way manual control valve in open position.

b. IA-HCV-2899D-TV Termination Criteria: Raw Water backup cooling has been established to VA-46B.

4 4

i I

a 1

4 6

Revision: 1 October 24,1995 l Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM -0010RW IAss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling. ,

l

\

l CLOSED REFERENCE QUESTION: JPM4)010RW-SRO-1 ;

i What would be the consequences of opening a Raw Water Interface valve during normal opemtion?

l ANSWER:

l l

A loss of CCW inventory through the Raw Water system to the river. I i

REFERENCE:

CCW STM :

NRC K/A 000008 A2.02 (3.2/3.5) i 1

The operator's response was-SATISFACTORY UNSATISFACTORY COMMENTS:

..t i

1

Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW Loss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling. (

l 1

1 CLOSED REFERENCE QUESTION: JPM-0010RW-SRO-2 1 How could the CCW system be cooled following a loss of Raw Water?

1 l

ANSWER:

1 By supplying Fire Protection water to the CCW/RW heat exchangers using fire hoses.

l l

REFERENCE:

)

l AOP-18, Attachment 2 NRC K/A 000076 A2.01 (3.5/3.7) l The operator's response was:

l i

SATISFACTORY UNSATISFACTORY !

COMMENTS:

4

._. . . . . _ . . _ _ . _. _. - . . _ _ . ~ . . _ _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ . _ _ _ - . . . . . _ . _ . _ . _ . . _ .

4 1

1 i

4 1

1

Initiating Cue: .

The reactor has been tripped from 100% power. A total loss of all CCW has occured. You are directed to establish Raw Water backup to the Control Room Air Conditioners as directed by the LSO. VA-46B is in service. START A

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3 E

4 4

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2 !

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Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0719 Startup Hydrogen Purge System J

System (s): Hydrogen Purge System i

Location (s): AunhazyBuilding (RCA)

Approximate Time: 10 minutes ActualTime :

i i Reference (s): (1) OI-VA-1, Attachment 5,4.3 1

(2) NRC K/A 000028, A2.02 (RO3.5/SRO3.9)

.1 l Verify current reference revisions match those listed above

. Operator's Nune: SS # :

i All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

4 Opprator's review - Date:

Tools & Equipment : None Safety Considerations: This JPM requires entry into the RCA.

a Comments : This JPM will be performed as a static JPM in the plant.

Revision: 8 October 24,1995 4

j Fort Calhoun Sta@ . Operations training JOB PERFORMANCE MEASURE

. JPM No: JPM-0719 j Startup Hydrogen Purge System i

R Initiating Cue:

2 The plant is in accident recovery following a LOCA. CIAS and VIAS have initiated. Contamment

hydrogen concentration is 3%. Coaainwnt integrity has not been satisfied in accordance with the Safety Function Status Check. A containwnt hydrogen purge is required. You have been directed to start a '

hydrogen purge using Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 have all been verified closed. START

]

4 CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of OI-VA-1, Attachment 5, Procedure has been obtamed.

4.3

2. Ensure VA-80A recirculation valves are Corridor 26

, closed. VA-279 and VA-284 are closed 3.* Open hydrogen purge fan suction and NO'IE: Manual handwheels for these valves are discharge valves: in Corridor 26.

A. VA-292 B. VA-290 Unlock and OPEN valves C. VA-289

4. Open hydrogen purge containment isolation Request control room to open HCV-882.

valve.

CUE: Contml room reports HCV-882 is open.

5.* Start hycrogen purge fan. AI-100 VA-80A in pull to OVERRIDE.

NOTE: If candidate places control switch for VA-80A in AITER START, tell him the GREEN light is still lit.

Termination Crlieria: Hydrogen purge has been started

.c

{ Reviaon: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

)

e 14 No: JPM - 0719 Staru.p Hydrogen Purge System i

CLOSED REFERENCE QUESTION: JPM-0719-RO-2 SRO-1 What is another system that can be lined up to flow through the hydrogen purge charcoal filters?

4 ANSWER:

Either of the following:

Gas decay tanks Condenser vacuum pump exhaust

REFERENCE:

j NRC K/A 000027 K5.01 (3.1/3.4) 4 i

Tbc operator's response was:

SATISFACTORY UNSATISFACTORY

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h

Revision: 8

', October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0719 Startup Hydrogen Purge System 1

l i

CLOSED REFERENCE QUESTION: JPM-0719-SRO-2 I

i When the containment hydrogen analyzers are in operation, where is the gas leaving the analyzer directed?

i i

1

ANSWER:

i Back to the containment atmosphere. I i

l n 1

REFERENCE:

i NRC K/A 000028 A4.03 (3.1/3.3)

.i The operator's response was:

3 3

i SATISFACTORY UNSATISFACTORY i

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4 k

l l

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

i i i

Revision: 8 October 24,1995 )

Fort Calhoun Station - Openthas trauung !

JOB PERFORMANCE hifASURE ;

JPM No: JPM-0719 !

Startup Hydrogen Purge System ,

)

\

litiating Cue:

The plant is in accident recovery following a LOCA. CIAS and VIAS have initiated. Containment hydrogen concentration is 3% Contaimner.t integrity has not been natisfied in accordance with the l

Safety Function Status Check. A containment hydrogen purge is required. You have been directed to l start a hydrogen purge usingn Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 l have allbeen verified closed. START l

l l

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l l

i I 1

l l

I 6'

l l

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ES-301 Individual Walk-through Itsi Outline Form ES-301-2 Examination Level: SRO(U)

Facility: Een Calhoun Week of Examination: 12/04/95 Examiner's Name (print):

System / JPM Safety Planned Follow-up Questions:

Function K/A/G // Importance // Description

/

Simulator JPMs above this line. Plant JPMs below this line

6. 0719 - Startup Ilydrogen VI b.Other systems that can use hydrogen purge filters.

Purge System 000027K5.01//3.1/3.4// Purpose of charcoal filters b.llydrogen analyzer Dowpath.

000028A4.03//3.1/3.3// Monitor hydrogen sampling.

7. 0295 - Switch Inverter VII a.TS operability on bypass transformer?

Supply from Bypass to 000057SG008//3.2/3.6//rech Spec entry conditions Normal (modify to attemate b. Actions required on blackout.

Eth) 000055EK3.01//2.7/3.4// Length of time for battery.

8 0214-ShiftInservice Air VIII a. Iligh temperature compressor trip.

Compressors 000078K1.04//2.6/2.9// cooling water to compressor.

B. Instrument Air containment isolation.

000078K1.03//3.3/3.4// Containment Air

9. 0010RW - Loss of X a. Consequences of opening interface valve.

Component Cooling 000008 A2.02//3.2/3.5// low surge tank level Water (Raw Water) b.CCW cooling with no raw water.

000076 A2.01//3.5/3.7// Loss of service water system

10. New - Makeup to the V a. Time to empty EFWST.

Emergency Feedwater 000061K4.01// 3.9/4.2// Water sources and priority Storage Tank using b. Design basis for inventory tech spec Diesel Fire Pump 000061K4.01//3.9/4.2//. Water sources and priority Examiner: %^d Chief Examiner: -M-X #),

s d~ /er

Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0214 Shift Insenice Air Compressors System (s): Compressed Air 14 cation (s): Room 19 Approximate Time: 12 minutes ActualTime :

Reference (s): (1) OI-CA-1 6.3 R21 (2) NRC K/A 000078,6001 (RO2.9/SRO3.1)

Verify current reference resisions match those listed above Operator's Name: SS # :

1 All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

Operator's review : Date:

Tqols & Equipment : None Safety Considerations: None.

Comments : Tids JPM will be performed as a static JPM in the plant 4

1 1

Revision: 10 October 24,1995 Fort Calhoun Station - Operations training

, JOB PERFORMANCE MEASURE l JPM No: JPM-0214 Shift Inservice Air Compressors I Initiating Cue: i i

The air compressor lineup is as follows: CA-1 A running, CA-lC in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for weekly rotation as follows: CA-lC running, j CA-1B in standby, and CA-1 A in Control room start. START CRITICAL l STEP

ELEMENT STANDARD

1. Obtain a copy of OI-CA-16.3 R21 Procedure has been obtained.

2.* Verify the following on the Air Compressor a. Check oil sight glass.

to be started (CA-lC)

a. Oillevel greater than 1/3 of b. Cooling water pressure PI-1942C glass.

! a. Cooling water pressure greater than 30 psig.

j 3.* Place load transfer switch on CA-IC to Switch to OFF position. l OFF.

l 4.* Place the Air Compressor control switch for Switch to CS position. l CA-1C to CS. i 5.* Verify proper oil pressure (CA lC) Oil pressure stabilizes in 15-20 seconds CUE: Oil perssure is 34 psig. '

{'

6. Verify cooling water flow Observe cooling water flow through bullseye.

FI-1955C l 7.* Place CA-lCload transfer switchin Select position 1 or 2 i position 1 or 2. j NOTE: Either position is acceptable. l

8. Verify CA-lC for proper operation. CUE:

Oil Pressurt a 32 psig

Intercooler Air Pressure = 30 psig Discharge Air Pressure = 102 psig Jacket Water Pressure = 43 psig Jacket Water Temperature = 1020F CUE: CA-1C is functioning properly.

9.* Place CA-1 A load transfer switch in OFF. Switch to OFF position.

' CUE: CA-lC is holding the air load.

10.* Place CA-1 A mntrol switch to OFF Switch to OFF position. l

11. Place the CA-1A CR Control Switch to Notify Control Room to place the Control Switch After Stop. for CA-1 A in After Stop c CUE: Control Room reports that switch is in After Stop Position.

l i

a l

, Revision: 10 l October 24,1995 Fort Calhoun Station - Operations training i i '

JOB PERFORMANCE MEASURE JPM No: JPM -0214 i Shift Inservice Air Compressors l l

CRITICAL STEP

ELEMENT STANDARD l l

12.* Place the local control switch for CA-1 A to Switch in CS position.

CS.

13. Verify CA-1 A cooling water flow is Observe bullseye for NO flow.

stopped. CUE: There is no flow.

14. Place load transfer switch for CA-1 A in Select position 1 or 2.

position 1 or 2.

NOTE: either position is acceptable.

15.* Place CA-1B local control selector switch Switch to STBY position in STBY. I

16. Place the CA-1B CR Control Switch to Request Control Room to place CA-1B control AAer Start. switch to After Start.

i Cue: Control room reports switch is in After Start. i 17.* Ensure ALL load transfer switches are in 1 All load transfer switches are in position 1 or 2.

or 2.

NOTE: Either position is acceptable.

Termination Criteria: CA-lC is running, CA-1B is in standby and CA-1 A is in CR start.

l l

1

. . . - .- = . - . . . . . . -.

l l

Resision: 10 i October 24,1995 Fort Calhoun Station - Operations training ,

JOB PERFORMANCE MEASURE l 1

JPM No: JPM - 0214 Shift Inservice Air Compressors i

CLOSED REFERENCE QUESTION: JPM-0214-SRO-1 The procedure cautions agamst having too much cooling water to the standby compressor to prevent low pressure trips. What would happen if the cooling water valve was throttled too far closed?

I i

l ANSWER:

1 1

The compressor will eventually trip on high temperature.

i

REFERENCE:

1 Service and Instrument Air STM NRC K/A 000078 K1.04 (2.6/2.9) ,

1 The operator's response was:

SATISFACTORY UNSATISFACTORY l

l COMMENTS:

.t

Revision: 10 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0214 Shift Inservice Air Compressors CLOSED REFERENCE QUESTION: JPM-0214-SRO-2 What determines whether the Instrument Air containment isolation valves will close on a containment isolation signal?

ANSWER:

The instrument air pressure. [They will only close if pressure is less than 70 psig.]

REFERENCE:

Service and Instrument Air STM NRC K/A 000078 Kl.03 (3.3/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

,.c f

t I

Initiating Cue:

i The air compressor lineup is as follows: CA-1A running, CA-lC in standby, and CA-1B in Control Room Start. You are directed to rotate air compressors for weekly rotation as follows: CA-lC mnning, i CA-1B in standby, and CA-1 A in Control room statt. START i

l i

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4 I

i

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Revision: 0 ,

October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-295 ASP ;

Switch Invester Supply Power From Bypass to Normal System (s) : 125 volt AC Instrument Power Location (s): Switchgear Room Approximate Time: 15 minutes ActualTime :

Reference (s): (1) OI-EE-4 Attachment 1 R20 l

(2) NRC K/A 000057, A1.01 (RO3.7/SRO3.7)

! Verify current utference revisions match those listed above l

1 Operator's Name: SS # :

I All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM. j l

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY l

l Evaluator's Signature : Date :

Reason,if unsatisfactory: )

I I

l ,4 ,

I I

Operator's review : Date:

Tools & Equipment : None i Safety Considerations:

2 Comments : This is an alternate path JPM . This JPM will be performed as a static JPM in the plant.

i l

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. . .-._ ~- . .

l l

Revision: 0 i October 25,1995

, Fort Calhoun Station - Operations training l JOB PERFORMANCE MEASURE l JPM No: JPM-295 ASP Switch Inverter Supply Power From Bypass to Normal 4

Initiatirig Cue:

i Instrument Invener "A" is out of service. AI-40A is being supplied via the bypass transformer. The electricians have cleared their tags on Invener "A" and the Shift Supervisor directs you, the LO, to start 4

up Inverter "A" and place it in service. All other prerequisites have bu:n met. START l J

l CRITICAL s STEP

ELEMENT STANDARD ,

I

, 1. Obtain a copy of OI-EE-4, Attachment 1 Procedure has been obtained.

4 R20 i

2. Ensure the input breaker EE-8H-CB1 at the Check Breaker to OPEN position.

! inverter is open. ,

3. Ensure the DC source breaker at the DC EE-8F 0 panelis closed. DC Bus #1 i EE-8F-CB24 (Circuit Breaker-24) s Check Breaker to Closed position.

j 4. Ensure the manual (bypass) transfer switch Check Si to bypass position. ,

Si at the inverter is in bypass. l

5.* Precharge the inverter. Push precharge button on inverter and wait ~ 10 seconds j 6.* Close input breaker EE-8H-CBl. Place Breaker to CLOSED position.

I 7. Verify Synch Loss Light is LIT. Cue: Light is LIT

8. Verify Reverse Transfer Light is LIT. Cue: Light is LIT.

. 9.* Place ManualTransfer Switch S1 in Select INVERTER position with Switch.

INVERTER position

10. Ensure Sync. Loss Light is OFF. Cue: Light is LIT

NOTE: This indicates an Inverter problem.

11.* Terminate procedure and contact Shift DO NOT push Forward Transfer Button.

Supervisor. Continue to allow bypass transfortner to supply Instrument bus. NOTE: It is acceptable, but not required, for operator to return switch Si to the bypass position and open input breaker EE-8H-CBI STOP 4

I I

4 9

1 I a

Revision: 0 October 25,1995

)

4 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM -295 ASP Switch Inverter Supply Power From Bypass to Normal CLOSED REFERENCE QUESTION: JPM-295 ASP - SRO -1 1s the instrument bus considered operable per Technical Specifications when powered from its bypass transformer?

ANSWER:

No. The instrument bus is not considered operable unless it is powered from its associated inverter.

REFERENCE:

NRC K/A 000057 G008 (3.2/3.6)

The operator's response was:

. SATISFACTORY UNSATISFACTORY CpMMENTS:

. _m. -_ .___ __ __ ._ _. _

Revision: 0 October 25,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-295 ASP Switch Inverter Supply Power From Bypass to Normal i

l CLOSED REFERENCE QUESTION: JPM-295 ASP - SRO -2 What actions are required to assure that instrument buses will remain energized for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a station blackout?

4 ANSWER:

i DC bus loads must be minimized.

REFERENCE:

4 t EOP/AOP Attachment 6 NRC K/A 000055 EK3.01 (2.7/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY l COMMENTS:

i 4

l i

- _ _ . . _ . . .. m . . _ _ _ . . . . > _ . _ _ _ . . _ _ . _ . _ . _ . . . . . _ . - _ . _ . _ _ _ . ___ . . _ _ _ . _ _ _ _ _ . _ _ . _ _ _

A I-

', laitiating Cue:

4 Instrument Inverter "A" is out of service. AI-40A is being supplied via the bypass transformer. The electricians have cleared their tags on Inverter "A" and the Shift Supervisor directs you, the LO, to start i up Inverter "A" and place it in service. All other prerequisites have been met. START i

i 2

i 4

Revision: 0 October 24,1995 Fort Calhoun Station . Operations training JOB PERFORMANCE MEASURE JPM No: JPM.NEW Emergency Fill of the EFWST Using the Fire Protection System System (s) 4W and Fbt Protection Location (s): Room 81 Approximate Tune: 20 minutes ActualTune :

Reference (s): (1) AOP - 30, R4 (2) NRC K/A 000061, K4.01 (RO3.9/SRO4.2)

(3) NRC K/A 000061, A1.04 (RO3.9/SRO3.9)

Verify current reference revisions match those listed almve Operator's Name: SS #:

i All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

'nic operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason, if unsatisfactory :

Operator's review : Date:

4 Tools & Equipment : None Safety Considerations: THIS JPM WILL BE PERFORMED AS A STATIC JPM IN TIIE PLANT.

Comments : The fire hose and adapter should not be moved from the fire brigade assembly area.

.~ -- -.-

l Revision: 0 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW l Emergency Fill of the EFWST Using the Fire Protection System 1 l

l Initiating Cue: J A station blackout has occurred. AFW is being supplied to the steam generators from FW-10(Turbine !

Driven AFW Pump.). FW-54 (Diesel Driven AFW Pump.) and Blair water are unavailable. The LSO l directs you to prepare to replenish the EFWST using the fire system. START !

I CRITICAL STEP

ELEMFET STANDARD i

1. Obtain procedure AOP-30 AOP-30 is obtained and verified.

2.* Close FW-652 ROOM 81 FW-652 is closed j 3.* Close FW-654 FW-654 is closed 4.* Obtain a 21/2 inch male-to male adapter FIRE BRIGADE ASSEMBLY AREA and a 100 foot section of 21/2 inch fire Locate adapter and fire hose.

hose. CUE: Fire Hose has been obtained (after examinee locates hose.)

Connect male-to-male adapter to the male CUE: The Adapter is connected l 5.* i end of fire hose.

6.* Connect both ends of the fire hose to the ROOM 81 following valves: CUE: Both ends connected a) FW-1275 b) FP-456 7.* Open FW-1275 FW 1275 is open 8.* Open FW-653 FW-653 is open

9. ~ Determine time for EFWST to empty CUE: The time to empty has been determined. 'Ibe LSO directs you to begin filling the EFWST.

10.* Open FP-456 FP-456 is open

.s

11. Ensure FP-1B starts Verify pump start with control room FP-1B has started l CUE: EFWSTlevelis91% !

12. Close FP-456 FP-456 is closed STOP Termination Criteria: EFWST level is 91% and fill is terminated.

l u

._ _.____ _ _._ _. _ . _ . _ _- .- _ _m _ .

i

)

Revision: 0 :

October 24,1995 I I !

l Fort Calhoun Station - Operations training i

JOB PERFORMANCE MEASURE j a

JPM No: JPM - NEW Emergency Fill of the EFWST Using the Fire Protection System i

l OPEN REFERENCE QUESTION: JPM-new-RO-1, SRO-1 i

l How long will it take for the EFWST to empty if the level is 32 inches and the AFW flow is 150 l 4

epm?

1 l.

ANSWER:

t The EFWST will empty in one hour or less.

i

REFERENCE:

, AOP-30, Attachment A NRC K/A 000061 K4.01 (3.9/4.2)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

This question is answered as JPM step 8.

4

l 1

I i

Revision: 0 l I

October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - NEW Emergency Fill of the EIMST Using the Fire Protection System CLOSED REFERENCE QUESTION: JPM-new-SRO-2 What is the basis for the technical specification on required EFWST Inventory?

ANSWER:

'Ihe inventory is sufficient to remove decay beat for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ..

REFERENCE:

i l

Tech Spec NRC K/A 000061 K4.02 (3.9/4.2) l The operator's response was:

SATISFAGORY UNSATISFAGORY j 1

COMMENTS:

l

.(

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

l s.

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Initiating Cue:

A station blackout has occurred. AFW is being supplied to the steam generators from FW-10(Turbine !

Driven AFW Pump.). FW-54 (Diesel Driven AFW Pump.) and Blair water are unavailable. 'Ibe LSO !

directs you to prepare to replenish the EFWST using the fire system. START {

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Revision: 1 .

October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

. JPM No: JPM - 0010RW IAss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

System (s) : Abnormal / Emergency Procedures i

Location (s): Room 81 Approximate Time: 15 minutes Actual Time :

Reference (s): (1) AOP - 11, R4 (2) NRC K/A 000008, K3.01 (RO3.4/SRO3.5)

(3) NRC K/A 000008, A2.01 (RO3.3/SRO3.6)

Verify current reference revisions match those listed above l

Operator's Name: SS # :

l All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this JPM.

The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY Evaluator's Signature : Date :

Reason,if unsatisfactory :

,.4 Operator's review : Date:

Tools & Equipment : None Safety Considerations: None Comments : This JPM will be conducted as a static JPM in the plant..

Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW Loss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

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Initiating Cue:

l' The reactor has been tripped from 100% power. A total loss of all CCW has occured. You are directed to establish Raw Water backup to the Control Room Air Conditionens as directed by the LSO. VA-46B is in service. START CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of AOP-11, R4 AOP-11, R4 has been obtained.

CUE: The control room reports that HCV-2899A&B have been closed.

2.* Unlock and release the handjacks from: Room 69

a. HCV-2899C Remove locking device and place the valves in

b. HCV-2899D the open position 3.* Open the following valves: a. 3-Way manual control valve in open position.

a. IA-HCV-2899C-TV b. 3-Way manual control valve in open position.

b. IA-HCV-2899D-TV Termination Criteria: Raw Water backup cooling has been established to VA-46B.

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Revision: 1 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MFASURE JPM No: JPM-0010RW Loss of Component Cooling Water requiring Raw Water Backup to Control Room Cooling.

I CLOSED REFERENCE QUESTION: JPM@l0RW-SRO-1 What would be the consequences of opening a Raw Water Interface valve during normal operation? i l

ANSWER: l A loss of CCW inventory through the Raw Water system to the river.

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REFERENCE:

CCW STM NRCK/A 000008 A2.02 (3.2/3.5)

The operator's response was:

SATISFACTORY UNSATISFACTORY COMMENTS:

o

1 Revision: 1 Octaber 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE

! JPM No: JPM - 0010RW Loss of Component Cooling Water requidag Raw Water Backup to Control Room Cooling.

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CLOSED REFERENCE QUESTION: JPM-0010RW-SRO-2 4

How could the CCW system be cooled following a loss of Raw Water?

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i ANSWER:

By supplying Fire Protection water to the CCW/RW heat exchangers using fire hoses.

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REFERENCE:

AOP-18, Attachment 2

, NRC K/A 000076 A2.01 (3.5/3.7)

The operator's response was:

SATISFACTORY UNSATISFACTORY 1

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i COMMENTS:

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Initiating Cuc. ,

The reactor has been tripped from 100% power. A total loss of all CCW has occured. You are directed to establish Raw Water backup to the Control Room Air Conditioners as directed by the LSO. VA-46B is in ;

service. START l l

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Revision: 8 i October 24,1995 .

Fort Calhoun Station - Operations training i JOB PERFORMANCE MEASURE JPM No: JPM-0719 I j- Startup Hydrogen Purge System I

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System (s): Hydrogen Purge System

! Location (s): Auxiliary Building (RCA)

Approximate Time: 10 minutes ActualTime :

I Reference (s): (1) OI-VA-1, Attachment 5,4.3 NRC K/A 000028, A2.02 (2) (RO3.5/SRO3.9)

Verify current reference resisions match those listed above i

.i Operator's Name: SS # :

4 All Critical Steps ( * ) must be performed or simulated in accordance with the standards contained in this

JPM. ;

1 The operator's performance was evaluated as: SATISFACTORY UNSATISFACTORY l

)

Evaluator's Signature : Date :

r Reason,if unsatisfactory :

Operator's review : Date:

Tools & Equipment : None Safety Considerations: This JPM requires entry into the RCA.

Comments : This JPM will be performed as a static JPM in the plant.

Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM - 0719 Startup Hydrogen Purge System Initiating Cue:

The plant is in accident recovery following a LOCA. CIAS and VIAS have initiated. Containment hydrogen concentration is 3%. Contauunent integrity has not been satisfied in accordance with the Safety Function Status Check. A containment hydrogen purge is required. You have been directed to start a hydrogen purge using Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 have all been verified closed. START CRITICAL STEP

ELEMENT STANDARD

1. Obtain a copy of OI-VA-1, Attachment 5, Procedure has been obtained.

T' E e VA-80A rectreulation valves are Corridor 26 closed. VA-279 and VA-284 are closed 3.* Open hydrogen purge fan suc. tion and NOTE: Manual handwheels for these valves are discharge valves: in Corridor 26.

A. VA-292 B. VA-290 Unlock and OPEN valves C. VA-289

4. Open hydrogen purge containment isolation Request control room to open HCV-882.

valve.

CUE: Control room reports HCV-882 is open.

5.* Start hydrogen purge fan. Al-100 VA-80A in pull to OVERRIDE. j NOTE: If candidate places control switch for VA-80A in AFTER START, tell him the GREEN light is stilllit.

Termination Criteria: Hydrogen purge has been started.

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Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE i JPM No: JPM-0719 i Startup Hydrogen Purge System )

l CLOSED REFERENCE QUESTION: JPM 0719-RO-2, SRO-1 What is another system that can be lined up to flow through the hydrogen purge charcoal filters?

ANSWER:

Either of the following:

l l l Gas decay tanks l Condenser vacuum pump exhaust l

REFERENCE:

1 NRC K/A 000027 K5.01 (3.1/3.4)

The operator's response was:

SATISFACTORY UNSATISFACTORY 4

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l Revision: 8 October 24,1995 Fort Calhoun Station - Operations training l

JOB PERFORMANCE MEASURE JPM No: JPM-0719 Startup IIydrogen Purge System CLOSED REFERENCE QUESTION: JPM-0719-SRO-2 When the containment hydrogen analyzers are in operation, where is the gas leaving the analyzer directed?

ANSWER:

s Back to the containment atmosphere.

REFERENCE:

NRCVJA 000028 A4.03 (3.1/3.3)

The operator's response was:

SATISFACTORY UNSATISFACTORY

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Revision: 8 October 24,1995 Fort Calhoun Station - Operations training JOB PERFORMANCE MEASURE JPM No: JPM-0719 Startup Hydrogen Purge Systent i

W Iitiating Cue:

ne plant is in accident recovery following a LOCA. CIAS and VIAS have initiated. Containment hydrogen concentration is 3% Containment integrity has not been satisfied in accordance with the Safety Function Status Check. A containment hydrogen purge is required. You have been directed to start a hydrogen purge usingn Hydrogen Purge Fan VA-80A. VA-412, VA-294, VA-368 and VA-369 have allbeen verified closed. START t

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