Text

Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered During Week of 990607
	ML20217A797
Person / Time
Site:	Palisades
Issue date:	10/06/1999
From:	Bies M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217A808	List: ML20217A797; ML20217A819;
References
	NUDOCS 9910120087
	Download: ML20217A797 (400)
	v • d • e

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. ,pa nse UNITED STATES j

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NUCLEAR REGULATORY COMMISSION i

~8 REGION til N L E LL NO 6 3 1 October 6,1999 NOTE TO: NRC Document Control Desk Mail Stop 0-5-D-24 FROM: Mary Ann Bies, Licensing Assistant y Operations Branch, Elli 1

SUBJECT:

OPERATOR LIC5NSING EXAMINATION ADMINISTERED THE I WEEK OF JUNE 7,1999, AT THE PALISADES NUCLEAR POWER !

PLANT, DOCKET NO. 50-255 l During the week of June 7,1999 Operator Licensing Examinations were administered at the referenced facility. Attached, you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR: 1 l'am #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070.

b) As-given operating examination, designated for distribution under RIDS Code A070.

stem #2 - Examination Report with the as-given written examination attached, designated for distribution under RIDS Code IE42.

Attachments: As stated d

9910120087 991006 FN ADOCK 05000255 V PDR J

S-ADMINISTERED OPERATING TEST FOR THE ES EMMINArgDN - THE wygg og ,uNE 7, 7999 ll b690

4 FINAL AS-ADMINISTERED ADMINISTRATIVE JPMS FOR THE PALISADES EXAMINATION - THE WEEK OF JUNE 7,1999 i

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l ES-301 Administrative Topics Outline Form ES-301-1 l

Facility: PAllSADES Date of Examii.ation: June 7 - 11.1999 Examination Level (Circle): ' RO Operating Test Number: 1 3

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Adminis,trative Questions .

A.1 Plant JPM - Determine Average Qualified CET Temperature Parameter Verification Mode Changes JPM - Determine Feedwater Reserve Inventory and Time Interval l for Heat Removal A.2 Tagging and JPM - Determine Tagging Requirements for a LPSI pump Clearances i

A.3 Radiation KA 2.3.1 (2.6)- Radiation Exposure limit Control

)

1 KA 2.3.10 (2.9)- Airbome Contamination exposure l A.4 Emergency JPM - Make Emergency Notifications Communication

N ;PM R0;A

, 11 R E G IO N lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO/A.1-1 1

Determine Average Qualified CET Temperature CANDIDATI EXAMINER I

(

I 1 JPM RO/A.1 1 l' ' '3 Page 2 cf 6 4

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REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l Task:

Determine average quahfied CET temperature.

1 Alternate Path: j

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W d, F Nige' wie a W :s w > x ?W.a.s'AM,m,M e <rg#,.-J.M"M.O

~m d'vs'ducLu +*~ w<

w ~~ n t a- ,< s so a 44aL- a l

Facility JPM #:

If2dOjiMIMMIAHS1*2Fidf57fd@iTJMiESSLECE2H25 ilL, ,

K/A Ratinals):

2.1.19 Task Standard:

Use the plant recorders to obtain and evaluate parametric information on system or component status.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X in-Plant Perform X Simulate 1

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References:

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\

I Operator Aid 108 EOP Supplement i Validation Time: 6 min. Time Critical: No

================================================---- ====================-----

Candidate: Time Start ;

NAME Time Finish:

Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: /

NAME SIGNATURE DATE

=----------=.._========_.____====================================

COMMENTS Tools /Eaulpment/ Procedures Needed:

JPM RO/A.1-1 Page 3 of 6 Ensure sufficient clean copies of OA-108 and EOP Supplement 1 are available for use.

NOTEC Data used was obtained using 1C-11 on the simulator. If possible, initialize the simulator to IC-11 and allow candidate to obtain data using running simulator, if simulator cannot be used provide candidate with cues as described in the steps of this JPM.

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall

. be performed for this JPM, including any required communications. I will provid.e initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The plant is operating at 100% power. Pressurizer pressure is 2000 psia.

INITIATING CUES:

The Shift Supervisor has directed you to determine the average qualified CET temperature and subcooling

'using the plant recorders.-

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JPM RO/A.1-1

. Pag 3 4 of 6 START TIME:

STEP 1: Obtains copy of Operator Aid 108.

STANDARD: Operator Aid 108 obtained.-

COMMENTS: _ UNSAT l

STEP 2 Obtains at least two (2) qualified CET readings per core quadrant using CET CRITICAL recorders. STEP. j STANDARD: Operator reads CET temperatures off recorders and records on OA 108. _ SAT Critical step to obtain correct data for calculation.

_ UNSAT COMMENTS:

STEP 3 Operator determines average CET reading using previously obtained data. CRITICAL STEP l STANDARD: Determines average CET temperature to be 593*F (592*F to 594*F) if CET #2 )

is used. If CET #2 is not used, average CET temperature is determined to be ~

SAT !

594*F (593*F to 595*F).

NOTE: Candidate may recognize that CET #2 falls outside the t 15*F range and not use this CET when lirst collecting data. This is acceptable. __UNSAT Critical step to properly calculate average CET.

COMMENTS:

5-JPM RO/A.1-1 'I i Pagg 5 of 6

.l STEP 4: ' Operator, compares individual CETs with average CET and does not utilize CRITICAL ;

CE. ,outside the 115*F range. STEP !

STANDARD Determines CET #2 (if used) falls outside the allowed range. _ SAT Criticalstep is to eliminate CETs outside the range to obtain proper average.

COMMENTS _ UNSAT

~

STEP 5 . Operator re-calculates average CET, not using CETs outside the i 15'F . CRITICAL range. STEP STANDARD: Determines average CET temperature to be 594 F (593*F to 595*F). _ SAT Critical step to pmporty calculate average CET.

COMMENTS _ UNSAT.

i SIEP_f Obtains copy of EOP Supplement 1.

STANDARD EOP Supplement 1 obtained. _ SAT

- COMMENTS _ UNSAT STEP 7 Operator determines subcooling based on average CET and given pressure CRITICAL using EOP Supplement 1J STEP STANDARD:' Determines subcooling to be 41*F (36*F to 46*F). _ SAT Critical step is to property apply use of graph.

NOTE: ' Saturation temperature for 2000 psia on graph is approximately 635*F. Range _ UNSAT provides adequate margin ibr reading graph.

COMMENTS END OF TASK TIME STOP:

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JPM RO/A.1-1

,. Pegg 6 of 6 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETlON OF TASK) o INITIAL CONDITIONS:

. The plant is operating at 100% power. Pressurizer pressure is 2000 psia.

INITIATING CUES:

The Shift Supervisor has directed you to determine the average qualified CET temperature : nd subcooling using the plant recorders.

OPERATOR AfD 108 Page 1 of 1 QUALIFIED CET CALCULATION FORM NOTE: Use this Operator Aid C (Pag 11 o, 313) is not available, m

1. INSTRUCTIONS:

i h

a. Obtain at least two Med CET readings Dat rdEn cuadrant (utilize CET recorders).

b. Average the temperature readings used. If any individual temperature .

readings exceeds t 15'F from the average, then:

1. Do not utilize that individual temperature reading.

2. Return to Step la.

c. Refer to pressure - temperature curve (EOP Supplement 1) to determine subcooling value utilizing average determined in Step 1b.

2. DATA RECORplNG/ CALCULATIONS:

QUALIFIED TIME TIME TIME TIME TIME TIME QUADRANT CET # Nou/

2_____ --O 7 1h_ic7 A'll 9 6_ __

.____9__/ __ .. ..__ __ . . ____ _ . . . . . . . . . .

1 10 687 ___.. . .__:.....

l 5 6C6 l

11 66____7_. ._______. .._ _ .__. . .__ .. . . _ _ . . . . . .

2 16 fog 4 15 p g-(TM 98 019) 23 677 25 667 -------- ---------

3

- - - - - - - - - - j 31 (oo3 . _ _ . _ _ _ _ ..___. . . . . . _ _ . . . . .

35 69/

27 400 .................. .. - ______ ..

........._I 30 697.__ .................... ...........)

4 . ____... ____.....

606 {,

33_.__ . __......................... ..__... .. __.. ...........a 36 69/ i n i ,, , .

TOTAL 7T v' d< 'IlY AVERAGE M 894 Initiated: SROaklev. ,

Operator Aid 108 May 27,1998 Approved 'by: DAMLtaMXe OpehonOMport Supervisor

E ._.

JPM RO/A.12

-*' Page 1 of 8 R E GIO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l 1

1 I

JPM RO/A.1-2 Determine Feedwater Reserve Inventory and Time Interval '

for Heat Removal CANDIDATE EXAMINER j J

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'JPM RO/A.1-2

. Page 2 of 8

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REGIONlli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE IR9&I Determine feedwater reserve inventory and time interval for heat removal.

Altercate Pattu N'A Easility JPM #:

1 TBAA01A(MOOlFIED); -

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KIA Ratinafs)-.

E06EA2.1 Iask Standard:

Accurately calculate the time interval available for heat removal. ;

Preferred Evaluation LM=*lon: Preferred Evaluation Method:

Simulator X In-Plant Perform ___ X Simulate References; EOP Supplement 2 Validation Time: 15 min. Time Critical: No

=----- - =- =--

- ------=____ - _______=___ -----

Candidate; Time Start :

NAME Time Finish:

Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: /

NAME SIGNATURE DATE

=========c-----=== ---

-==t_________==___-= ===----- ==----------

COMMENTS

g. 4 JPM RO/A.1-2

,, Page 3 of 8 Tools /Eauinment/ Procedures Needed.

Ensure enough copies of EOP Supplement 2 copies of are available, if the candidate marks up a controlled copy ensure the staff replace the copy.

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

While the plant was at 100% power a condensate system piping rupture occurred. The reactor was manually tripped and the operators transitioned to EOP 8.0. The following plant conditions exist:

. MCC 6 id out of service for a ground.

. it is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months a'ter shutdown.

. T-81 to T-2 transfer is available, but not in progress.

. Bus IA and 1B did not fast transfer.

. T-2 is at 80%, T-81 is at 60%, and T-939 is at 68%.

. Tis are stable at 530*F INITIATING CUES:

The Shift Supervisor has directed you to complete EOP Supplement 2, PCS Cooldown Strategy.

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P 1 JPM RO/A.12 Page 4 of 8 l

START TIME:

STEP 1* Enter T-2 Inventory" curve with Condensate Storage Tank T-2 level and CRITICAL determine: T-2 available inventory in gallons (thousands) STEP

- SAT STANDARD: T-2 inventory is 90 thousand gallons. (89-91 allowed)

Critical step is to accurately determine Inventory.

RSMMENTS:

I STEP 2 Determine other sources that can be taken credit for as a source o' available CRITICAL feedwater inventory: STEP STANDARD T-81 and T-939 are availat;'e. _ SAT Critical step is to ensure that only available sources are considered. The Hotwellis NOT <

Cyallable. _ UNSAT COMMENTS

STEP 3 Determine "T-81 Inventory'* CRITICAL STEP STANDARD: T-81 inventory is 19.2 thousand. (19-20 allowed)

_ SAT Critical step is to accurately determine inventory.

COMMENTS _ UNSAT

JPM RO/A.1-2

. Pag 3 5 of 8 STEP 4 Determine "T-939 inventory" CRITICAL STEP STANDARD T-939 inven}ory is 190 thousand. (188-192 allowed)

_ SAT Critical step is to accurately determine inventory.

COMMENTS ,_ UNSAT STEP 5 Add the results of Steps 1 and 2. CRITICAL STEP .

STANDARD Tchl of steps 1 and 2 determined to be 109.2 thousand gallons. (108-111) .

_ SAT Crit lc:1 step is to accurately determine Technical SpeclRcation compliance.

_ UNSAT COMMENTS STEP 6 Add the results of Steps 1 and 3. CRITICAL STEP STANDARD Total of steps 1 and 3 determined to be 299.2 thousand gallons. (296 to 303)

_ SAT Critical step is to accurately determine totalInventory. -

_ UNSAT I COMMENTS

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STEP 7 Determine present Loop T. (T, initial).

'SIANDARD T, initial is ~530 F. _ SAT COMMENTS-

_ UNSAT b

u.

JPM RO/A.12 Pags 6 of 8 STEP 8 Enter " Sensible Heat Removal" curve with data from Step 7 and determine CRITICAL inv0ntory required to remove sensible heat: STEP STANDA.RD: Sensible Heat Removal inventory is 41 thousand gallons. '(40-42 allowed) _ SAT Critical step is to accurately detennine required inventory.

COMMENTS _ UNSAT STEP 9 Subtract Step 8 resuits from Step 6 results. CRITICAL STEP STANDARD 258.2 thousand gallons. (254 to 263 allowed)

_ SAT Critical step is to accurately determine totalInventory.

_ UNSAT COMMENTS SIEP 10 Enter applicable " Decay Heat Removal" curve for number of PCPs operating CRITICAL with elapsed time after shutdown and result of Step 9 and determine the Time STEP interval for heat removal.

STANDARD Time interval for heat removal is >32 hours. (Interpolation not required) _ SAT Critical step is to accurately determine time interval.

COMMENTS _._UNSAT l 1

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e JPM RO/A.1-2 E Page 7 of 8' I 3 k

STEP 11: ' Notify the Shift Supervisor that the time interval is > 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months and that an additional source of inventory is not required. _ SAT

4. STANDARD ' SS notified.-

_ UNSAT COMMENTS

END OF TASK TIME STOP:

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1 JPM RO/A.1-2 Pags 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

,\<.

INLIML&ONDillONS; While the plant was at 100% power a condensate system piping rupture occurred.~ The reactor was manually tripped and the operators transitioned to EOP 8.0. The following plant conditions exist:.

. MCC 6 is out of service for a ground.

e It is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after shutdown.

. T-81 to T-2 transfer is available, but not in progress.

. Bus lA and 1B did not fast transfer,

. T-2 is at 80%, T-81 is at 60%, and T-939 is at 68%.

T/s are stable at 530 F INITIATING CUES:

The Shift Supervisor has directed you to complete EOP Supplement 2, PCS Cooldown Strategy.

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$XAM / n/Et2.'s ig S {

Proc No EOP Supplement PALISADES NUCLEAR PLANT Supplement 2 EMERGENCY OPERATING

' Revision 5

" * " " PROCEDURE Page 1 of 17 TITLE: PCS Cooldown Strategy CAUTION T2 level less than 5% could result in inadequate NPSH to the AFW pumps.

1.0 DETERMINE THE AVAILABILITY OF FEEDWATER INVENTORY SOURCES: -

1. T-81 Primary System Makeup Tank is available if ANY of the following conditions are satisfied:

P-79A available

P-798 available

Primary Make-up systern flow path to T-2 available

2. T-939 Demineralized Water Taniiis available if ALL of the following conditions are satisfied:

I

Bus 91 energized

P-936 available

CV-2010 operable

DMW system flow path to T-2 available

3. Hotwell inventory is available if ANY of the following conditions are satisfied:

CONDITION 1

Condensate Pump P-2A or P-2B in operation

MV-CD129 open rejecting the hotwell to T-2 CONDITION 2

MCC 6, Breaker 52-655 energized

P-214 in operation

Hotwell being transferred to T-2 per SOP-11 l

_ . _ . . _ _ . . _ . . . . . . ~ _ _ . _ . . _ . . . . . _ . . . . . . . . . -

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"^ Pr N E P Supplement PALISADES NUCLEAR PLANT supplenient 2 EMERGENCY OPERATING

"*"I"

L_, PROCEDURE Page 2 of 17 TITLE: PCS Cooldown Strategy 2.0 DETERMINE INVENTORY OF EACH AVAILABLE SOURCE

1. Determine and record below Condensate Storage Tank T-2 level, utilizing "T-2 Inventory" curve:

T-2 available inventory in gallons = 90, 00 0 [6 9 -9/)

2. IF T-81 has been determined to be an available source of inventory, THEN determine and record T-81 available inventory in gallons from .

"T-81 AVAILABLE INVENTORY" curve:

T-81 available inventory in gallons = /9j oo b f ' '2- )

3. IF T-939 has been determined to be an available source of inventory, i THEN determine and record T-939 available inventory in gallons from l "T-939 INVENTORY" curve:

T-939 available inventory in gallons = MO,000 h M - /92-) ,

4. IF the Hotwell will be used as an available source of inventory to the l Condensate Storage Tank, T-2, THEN close the following valves to prevent draining the Condensate Storage Tank, T-2 to the hotwell: J l

a. Close 3" Makeup Valve CV-0732 Outlet, MV-CD133, to isolate '

Three Inch Makeup Valve, CV-0732.

LOCATION: AFW Pump Room

b. Close 6" Makeup Valve CV-0729 Outlet, MV-CD136, to isolate Six inch Makeup Valve, CV-0729.

LOCATION: AFW Pump Room

c. Close 12" Makeup Inlet, MV-CD138, to isolate Twelve Inch Makeup Valve, CV-0733. l LOCATION: Pit near Air Ejector Condenser

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" '"8"""'***"*

PALISADES NUCLEAR PLANT Supplement 2 EMERGENCY OPERATING Revision 5

c"" " PROCEDURE Page 3 of 17 TITLE: PCS Cooldown Strategy

5. is the Hotwell was determined to be an available source of inventory, THt-N determine and record Hotwell available inventory as follows:

e. . Utilizing the "Hotwell Available inventory" curve and the graph line for the corresponding condition determine and record the applicable available Hotwell inventory: '

CONDITION 1 P-2A or P-2B Inventory gallons =

OR CONDITION 2 P-214 inventory gallons = N

b. IF CONDITION 1 is selected, THEN use the "Hotwell Inventory (P-214 or 3" Reject)" curve and the 200 gpm graph line to determine and record available Hotwell inventory :

CONDITION 1 Hotwell inventory gallons = MA

c. IF CONDITION 2 is selected, THEN perform the following:

1) Determine if FI-0732 (LOCATION: Across from entrance to Auxiliary Feed t ' Pump room) is available.

2) IF F1-0732 is NOT available, THEN use the "Hotwell Inventory (P-214 or 3" Reject)"

curve and the 150 gpm graph line to determine and record available Hotwell inventory:

Hotwell Inventory gallons =

' "^ Proc No EOP Supplement PAI.lSADES NUCLEAR PLANT Supplement 2 EMERGENCY OPERATING Rev..ision 5 auctun eu"' PROCEDURE Page 4 of 17 TITLE: PCS Cooldown Strategy

3) IF F1-0732 is available, THEN perform the following:

a) Use the table below to determine the graph line to I be used on "Hotwell Inventory (P-214 or 3" {

Reject)" curve. l umiFlowireadingMW Bf4ew valueWeaph

> 250 250 gpm

< 250 and > 200 200 gpm

< 200 and > 150 150 gpm

< 150 and > 100 100 gpm

< 100 aom O aom Use the graph line selected above and the "Hotwell I b) inventory (P-214 or 3" Reject)" curve to determine and record available Hotwellinventory.

Hotwell inventory gallons =

d. Record below the lowest available Hotwell inventory value from 2.5.a, 2.5.b, or 2.5.c above:

Hotwell Inventory gallons =

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Pr N E P Supplomant PALISADES NUCLEAR PLANT supplement 2 EMERGENCY OPERATING

""" PROCEDURE Page 5 of 17 TITLE: PCS Cooldown Strategy 3.0 CALCULATE AVAILABLE INVENTORY

1. Determine the technical specification required inventory to remain in Hot Shutdown or above by adding results of Steps 2.1 and 2.2 Step 2.1, T-2 available inventory (gal) 70,000 [B9-9/)

Step 2.2, T-81 available inventory (gal) + / 4, oo (/9-2o)

Total TS available inventory (gal) /09 wo

, (/oS - ///)

2. IF the total of T-2 and T-81 inventory is less than 100,000 gallons,

~

j THEN a cooldown to cold shutdown conditions within the next '

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is required by Technical Specification 3.5.

3. Determine total available inventory by adding the results of Steps 2.3, 2.5.c.4), and 3.1.

Step 2.3, T-939 available inventory (gal) /90, o o o [/66 -/

io ,.mov. ..n..w. n..i>

(2% - 30s) -(q2 ,,s o) (

W '" % 5.)
4. Utilizing the following:
Applicable " Decay Heat Removal" curve for the number of PCPs operating Graph line for the elapsed time after shutdown Amount of inventory available to remove decay heat (graph),
determine and record the time interval for heat removal.
Time interval available for heat removal (hours) =
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' JPM RO/A 2 6
Page 1 of 6 R E G IO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO/A.2 1 l
Determine Tagging Requirements for a LPSI Pump CANDIDATE EXAMINER l
o JPM RO/A.2 8- Page 2 of 6 REGIONlil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Determine tagging requirements for LPSI pump.
Alternate Path:
N/A1 a: . , <. - wfN;0 /dNiistfu a:# ; !;, .
Facility JPM #:
C:7lEMM:MTREl2W%2G2Mg228Kigg g;m K/A Ratinals):
2.2.13 Task Standard:
Accurately determine tagging requirements for LPSI pump, to ensure personnel safety.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator _ X in-Plant Perform Simulate X
References:
SOP-3 and Drawing M-204 sheet 1,1 A, and 1B Validation Time: 15 min. Time Critical: NO
-------========..______============---------- ===================___ _
Candidate: Time Start :
NAME Time Finish:
Performance Ratina: SAT UNSAT Question Grade Performance Time Exsminer: /
NAME SIGNATURE DATE
========.______ --_.. ================================================
COMMENTS Tools /Eauipment/ Procedures Needed:
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1 JPM RO/A 2 o Page 3 of 6 Ensure enough copies of controlled prints are available.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All cc 1 trol room steps shall ,
be performed for this JPM, including any required communications. I will pruide initiating cues !
and reports on other actions when directed by you. Ensure you indicate to n e when you understand your assigned task. To indicate that you have completed your assigned task retum the handout sheet I provided you.
!NITIAL CONDITIONS:
The plant is preparing for refueling. The SIRWT has been drained to the Reactor Refueling uvity. A small leak was reported on the LPSI pump 67B miniflow orifice.
INITIATING CUES:
The Shift Supervisor directs you to determine the electrical and mechanical isolation requirements to take P478 out of service, it is necessary that the pump be drained and vented for the inspection. No computers are available.
4 JPM RO/A 2 e'- Page 4 of 6 START TIME:
STEP 1: Operator locat'es referencesc _, SAT STANDARD:' References located COMMENTS: __,UNSAT STEP 2 Determine required tagging requirements. - CRITICAL .
STEP STANDARD: The following components are required to be tagged in the position indicated.
e MO-3190 P478 Suction from SDC ,LOSED
-SAT
-e MO-3189 P47B Suction from SIRWT CLOSED e MV-ES 3194 P-67B Miniflow CLGOED
- e MV-ES 3345 P478 Vent OPEN _ UNSAT e MV-ES 515 P475 Casing Drain OPEN e MV-ES 3193 P47B Discharge Valve CLOSED-e 152-111 Breaker DISCONNECTED
'e 152-111 Control Power Fuse PULLED (may include in 152-111 breaker)
Critical step is to ensure personnelsafety and equipment protection is met.
COMMENTSi STEP 3 Determine additional tagging requirements.
STANDARD: The following components may also be tagged in the position indicated. ,_, SAT e LPSI Handswitch P47B NEUTRAL AFTER TRIP, GREEN FLAG (optional since this is NOT an actual tagout) .
e MV-CC132 and MV-CC-135 CCW to P478 CLOSED (optional since this is NOT on side ._,UNSAT to be worked) -
NOTE: The candidate may add the P478 Low Level Trip Switch on C-02 in the disabled
- position. This is NOT required.
COMMENT 6:
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4- . JPM RO/A.2 Paga 5 of 6 STEP 4: : Record the recommended tagging reyirements and delivers to the Shift Supervisor.
_ SAT STANDARD: The Shift Supervisor has the tagging requirements.
- QQMMENTS: _ UNSAT END OF TASK t
TIME STOP:
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JPM RO/A.2
e. Page 6 of 6 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
lNITIAL CONDITIONS:
The plant is preparing for refueling. The SIRWT has been drained to the Reactor Refueling Cavity. A smallleak was reported on the LPSI pump 678 miniflow orifice.
INITIATING CUES:
The Shift Supervisor directs you to determine the electrical and mechanical isolation requirements to take P-678 out of service. It is necessary that the pump be drained and vented for the inspection. No computers are available. -
)
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.. sorm as: . -97 CONSUMERS ENERGY '
. SWITCHING AND TAGGING ORDER ll W fl CH AfSN I~ 7' & $ &1 12 r_,lA 2
, $x A-61/ N Ei,' ' > 14& y O'd*' N o' l' Page of Order Given By - Location Orfer Wntten By ' Date and Time Given Approved By : Date and Time Started C;rried Out By - Date and Time Completed
- Purpose
, ACTIONS PERFORMED
/ No. Be sure this procedure covers existing electrical and/or mechanical conditions when these operations are executed.
Dbcomtec r -
Brea + < ici. iti P- s, 78 puti-so .
3,estre< / r 2. -/ /t '('o., /<c,/ Powe, hses LL os 60 -
No -3/90, P-/678 Sve&s., &c~ S D C-CLosso -
.Mo - 3169, P-4,78 Soc M ., from Si c vu 7-C Los &f) -~ /W-ES 3194. P-478 M:.,t-flow
. CLosso -
MJ-G s at Vd. P-678 D,'sc 4 <s a. ~
V.e /< e-OP&W - M v'-BS - 354l, P-/.18 Ven f CPGH - PW - 2 $ 6~/ 5' , P-478 Ce su s D.a.%
E Nfor/2AL Af 76fL Tr2/ P fG26&N PLA(a) -
LPS1~ /L dsm,Vc4 P-478 Y CLoSGO -
MV-C4 /3 2 , cc kl -s's P-476
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l Date and time
, Working Clearance issued By
,rking Clearance Received By Working Clearance Released By W rking Clearance Released To FILE FOR THIRTY DAYS BEFORE DESTROYING
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R E GIO N lli INITIAL LICENSE EXAMINATION i JOB PERFORMANCE MEASURE JPM RO/A.3 Radiation Control CAN0lDATE j
I EXAMINER 1
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lNITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Knowledge of conduct of operations requirements.
Alternate Path:
HM3fQUEBBOEW enM R 12!iid)L37%EE,MEFS S E FS E 2p p df g . . 7 8 Facility JPM #:
Q272MEMtiEJjilitf6F33?iEM.WEMM"N71@MMEss?ilshi)!E;cjed l' -
K/A Ratinafs):
2.3.1 2.3.10 Task Standvd:
Correctly respond to administrative questions.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator in-Plant Perform _X Simulate Befste_nsen:
ADM 7.04 Radiation Dosimetry ar'd HP-11.4 Evaluating Control of Airborno Radioactivity and Respiratory Protection Validation Time: 10 min. Time Critical: No o========== ==-- -_ ===============----====_:.======----- ===v======================
Candidate: Time Start :
NAME- Time Finish: .
I Performance Ratino: SAT UNSAT Question Grade Performance Time i
l Examiner: / j NAME- SIGNATURE DATE o===-----====================------ =============================a=================
COMMENTS 1
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JPM RO/A 3 Page 3 of 6 q
JPM QUESTION # 1 REFERENCE ALLOWED: YES /
yes no Question: An Auxiliary Operator was recently hired from a Texas nuclear utility. His exposure for this year at the othe Ltility was 1500 mrem TEDE.
WHAT is the total exposure he can receive this year at Palisades without getting approval to exceed the allowed dose level? EXPLAIN.
Answer: He can receive up to 2000 mrem TEDE at Palisaces.
The limit for a worker who received occupational exposure at another utility is 4000 mrem TEDE, but only 2000 mrem TEDE may be received at Palisades facilities.
A Jose review would be required at 1500 mrem. (Not required for full credit.)
CANDIDATE'S RESPONSE Time: 5 min.
K/A Rating:
2.3.1(2.6)
References:
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ADM 7.04 l
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JPM RO/A.3 Page 4 of 6 JPM QUESTION # 2 REFERENCE ALLOWED: YES /
yes no Question: You and two (2) otMr operators are assigned to perform a task in an area where the dose rate is 50 mrem /hr. The area also has some airborne radioactivity.
From previous experience, it is known that it will take 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to perform the task if respirators are wom and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months without wearing respirators. if the task is performed without a respirator, each worker will receive 5 DAC/hr of internal dose.
Will the total exposure be lower if respirators are worn or if respirators are not worn?
What will be the difference in exposure to each worker depending on whether or not respirators are worn?
Answer: The total exposure will be lower if respirators are NOT wom.
Not wearing a respirator will result in a reduction in total exposure to each worker of 25 mrem.
WITH RESPIRATOR:
(3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months )(50 mrem /hr) = 150 mrem per worker WITHOUT RESPIRATOR:
(2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )(50 mrem /hr) + (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )(5 DAC/hr)(2.5 mrem /DAC) = 125 mrem per worker CANDIDATE'S RESPONSE Time: Smin.
KlA Rating: 2.3.10(2.9)
References:
HP 11.4 l
d- JPM RO/A 3 Page 5 of 6 l
JPM QUESTION'# 2 CANDIDATE COPY i
REFERENCE ALLOWED: YES / I
.yes no (To BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: You and two (2) other operators are assigned to perform a task in an area where the dose rate is 50 mrem /hr, The area also has some airborne radioactivity.
From previous experience, it is known that it will take 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to perform the task if respirators are worn and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months without wearing respirators. If the task is performed without a respirator, each worker will receive 5 DAC/hr of internal dose.
Will the total exposure be lower if respirators are worn or if respirators are not worn?
What will be the difference in exposure to each worker depending on whether or not respirators are wom?
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.JPM RO/A 3 Page 5 of 6 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES /
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: You and two (2) other operators are assigned to perform a task in an area where the dose rate is 50 mrem /hr. The area also has some airborne radioactivity.
From previous experience, it is known that it will take 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to perform the task if respirators are worn and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months wnhout wsaring respirators. If the task is performed without a respirator, each worker will receive S DAC/hr of internal dose.
Will the total exposure be lower if respirators are worn or if respirators are not worn?
What will be the difference in exposure to each worker depending on whether or not respirators are wom?
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F. j JPM RO/A 3 1 Page 6 of 6 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES /
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: An Auxiliary Operator was recently hired from a Texas nuclear utility. His exposure for this year at the other utility was 1500 mrem TEDE.
WHAT is the total exposure he can receive this year at Palisades without getting approval to exceed the allowed dose level? EXPLAIN.
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r JPM RO/A 4 Page 1 of 7 R E GI O N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO/A.4 Make Emergency Notifications CANDIDATE EXAMINER
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JPM RO/A.4 Page 2 of 7 REGIONlil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Iast Make emergency notifications required by the site emergency plan.
Altemate Eattu N/A Facility JPM #:
SEP02(MODIFIED)
K/A Ratino(s):
2.4.43 Task Standard:
Demonstrate the ability to make emergeraf notifications using the emergency plan.
Preferred Evaluation Location: Preferred fvifuatiggMethod; Simulator X In-Plant Psform _ __ X Simulate
References:
El-1 and El-3 Validation Time: 15 min. Time Critical: YES
-- --- =======c___- _ =========. ___ ...==--- =-----===----- ================
Candidate Time Start :
NAME Time Finish:
Performance Rating: SAT UNSAT Question Grade Performance Time Examiner; /
NAME SIGNATURE DATE
= = - - - - - - - - - = = , . = - -_ - _
- - _==========--------------=-- -------==---- ========
COMMENTS
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JPM RO// A ,
Page 3 of 7 1
InolslEnulement/ProcedureARaeded; i Ensure enough copies of completed attachment 1 of El-1 and attachment 1 and 2 of El-3 are available. f Ensure a person on the security agreement is available to answer the phones that the candidate will use to i make notifications. Ensure this person is briefed to not provide any information to the candidate and only l repeat back what information has been transferred. j NOTE: Ensure that the performance of this JPM will NOT cause actual notifications
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READ TO OPERATOR DIRECTION TO TRAINEE:
J l will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return tt e handout sheet I provided you.
INITIAL CONDITIONS; J
l The Shift Supervisor, who is now serving as the SED, has declared an ALERT. J INITIATING CUES:
]
The SS/ SED has directed you make emergency notifications required by the E-Plan and hands you the El-1 form.
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JPM RO/A.4 Page 4 of 7
' START TIME:
STEP 1- Verify Emergency Notification Form is approved (initialed) by the SED.
SIANDARD Form checked for SED initials. __ SAT COMMENTS 1
__,UNSAT STEP 2 Contact Van Buren County CRITICAL STEP STANDARD Van Buren County Sheriff contacted, within 15 min. of emergency declaration.
Phone number is 616-657-2058 or 616-657-3101. _. SAT l
Critical step is to initiate contact.
NOTE: Steps 2,3,4, &5 must be complete within 15 minutes of DECLARATION. ,_ UNSAT COMMENTS-STEP 3 . Relay information on Emergency Notification Form. CRITICAL STEP STANDARD Correct information relayed and name of person contacted entered on Emergency Notification Form. _. SAT Critical step Is to transfer the Information contained in steps 3-7 of the Emergency NotHication Fonn.
_,,UNSAT The requiredInformation is:
2A 1, 3B Alert,3E Start Time -4 minutes, Today, 3F Loss of Most or AII Alarms in the ;
Control Room,4A Stable,4D Plant is stable @ 0% power, 5 No, 6 A from 93 to 273, 68 3 i mph, 6C A, 60 NMP,6E No, 7 No COMMENTS
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JPM RO/A.4
- Page 5 of 7 STEP 4 Contact the State of Michigan. CRITICAL STEP STANDARD: State of Michigan contacted, within 15 min. of emergency declaration. Phone number is 517-336-6250. _ SAT Critical step is to initiate contact.
COMMENTS' _ UNSAT STEP.5 Relay information on Emergency Notification Form. CRITICAL STEP STANDARD Correct information relayed and name of person entered on Emergency Notification Form. _ SAT Cridcol step is to transfer the infonnation contained in steps 3 7 of the Ememency NotlRcation Fonn.
_ UNSAT The requiredinformation is:
2A 1, 3B Alert, 3E Start Time -4 minutes, Today, 3F Loss of Most or All Alarms in the Control Room, 4A Stable, 4D Plant is stable @ 0% power, 5 No, 6 A from 93 to 273, 6B 3 mph, 6C A, 60 NMP, 6E No, 7 No CQMMENTS STEP 6 Contact the NRC. CRITICAL STEP STANDARD NRC contacted using the direct line to NRC Operations Center.
_ SAT Criticalstepis to contact the NRC.
COMMENTS'
_ UNSAT I
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JPM RO/A.4 Page 6 of 7 STEP 7 Relay information on Emergency Notification Form. CRITICAL STEP STANDARD: Correct information relayed and name of person entered on Emergency Notification Form. _ SAT Critical step is to transfer the information contained in steps 3-7 of the Emergency Notification Form.
_ UNSAT The requiredinformation is:
2A 1,3B Alert,3E Start Time 4 minutes, Today,3F Loss of Most or All Alarms In the Control Room, 4A Stable, 4D Plant is stable @ 0% power, 5 No, 6 A from 93 to 273, 6B 3 mph, 6C A, 6D NMP, GE No, 7 No CUE: Inform the candidate that the NRC does not desire continuous contact at this time.
C,QMMENTS:
STEP 8 Notify the Shift Supervisor / SED that notifications are complete.
STANDARD Shift Supervisor / SED notified. _ SAT C.QlAMENTS ___UNSAT END OF TASK i
I TIME STOP:
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(i JPM RO/A.4 Page 7 of 7 '
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS: !
The Shift Supervisor, who is now serving as the SED, has declared an ALERT, INITIATING CUES:
The SS/ SED has directed you make emergency notifications required by the E-Plan and hands you the El-1 form, i l
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77A C /4 N6 A/ T~ TC JPM Ac[/1. 4 Proc ND El 3 Atttchmtnt 1 EMERGENCY NOTIFICATION FORM Revision 18 Page 1 of 1 q- cr -
provat: Zrw W" REQUIRED INFORMATION Date: Car!!L&NT~
This is a drdi. 0 3'This is net a drdi. Time: G rZe' E d."o~'
rom: )(CR 0 TSC DEOF
1. To: O County Name: _
O State Nan.4: Time:
a NRC Name: Time:
2. PALISADES Time:
3. CLASS OF EMERGENCY 2A. PLANT MESSAGE NUMBER /
A. O Unusual Event B. Alert E.
F.
This classification declared tby Plan)(at: Time: M CO Site Area Emergency
<w.w b c.so Date:
D durm.* O Genaral Emergency initiating Conditions / Description of Event: -
L.c o e :/- mos t tw a // a N w s i s-s (on he f (2uoM
'4 PLA T STATUS A. Stable B. D Degrading . C. O improving fa sl4 //t & G Vo ,oc.we r .
- 5. RADIOLOGICAL RELEASE IN PROGRESS: 0 YES )( NO
6. METEOROLOGICAL DATA A. Wind Direction, Degrees From: D To: 3O' B. Wind Speed, MPH: 3 C. Stability Class: A D. Three Downwind Sectors: A/A1 P E. Precipitation: 0 YES K NO
7. PROTECTIVE ACTION R OMMENDATIONS A. O YES NO Note: If YES fillin folio information.
B. PAR based on: O Dose Calculations a Plant Status 0 C. In-place Shelter (Areas) Other D. Evacuation (Areas) i 8. AS AVAILABLE MADIOLOGICAL RELEASE DATA A. Time release started Projected duration of release
. B. O Airborne Q Waterborne o Waterborne Analysis Attached C. Effluent Points D. Noble gas release rate, CUsec Sample E.' Average energy per disintegration, MeV Monitor Estimate Sample Monitor F. Equivalent 1-131 release rate, Ci/sec Sample Estimate Monitor Estimate G. Particulate release rate CUsec Sample Estimate
9. CALCULATED OFFSITE DOSES A. O Actual o Potential B. Based on: O Monitor (in Plant) 0 Sample (in Plant) O Back Calculation from field data o Other Plant Conditions C. Calculated Dose Rate (mrom/hr)
Time of Calculation Distance TEDE (mrom/hr)
Site Boundary Adult Thyroid CDE (mrom/hr) 2 Miles 5 Miles 10 Miles D. Calculated Accumulated Dose (mrom)
Calculated Duration, Hours Distance TEDE (mrom) Adult Thyroid CDE (mrom)
Site Soundary
' 2 Miles
- 5 Miles 10 Miles E. Sectors Affected
10. MEASURED OFFSITE DOSE MATES A. Distance Time Reading (mR/hr)
Site Boundary. Affected Sector
- ' " ~ miles miles miles
8. Ad3TtTo'nalInformation L.
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t ES-301 i Administrative Topics Outline Form ES-301-1 Facility: PALISADES ' Date of Examination: June 7 - 11.1999 Examination Level (Circle): 'SRO Operating Test Number. ,1 Administrative'- Describe method of evaluation: -
Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Que'stions A.1 Plant ! JPM - Review Average Qualified CET Temperature Parameter Determination Verification -
Mode Changes JPM - Determine Feedwater Reserve inventory and Time Interval for Heat Removal A.2 Tagging and . JPM - Review Tagging Requirements for a LPSI pump ,
Clearances
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A.3 ' Radiation KA 2.3.1 -( 2.6) - Radiation Exposure limit l
. Control KA 2.3.10 (2.9)- Airbome Contamination exposure A.4 Emerge scy JPM '- Determine Protective Action Recommendations during a Communication General Emergency.
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t Pa e 10 5 R E G IO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l
JPM SRO/A.1-1 Review Average Qualified CET Temperature Determination CANDIDATE EXAMINER 1
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f JPM SRO/A.1-1 Page 2 of 5 REGION lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task

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' Review average qualified CET temperature determination.
Alternate Path:
WLMENihnh%skAdikh$$$$$$A55$lAEN$l?!dhi$$$6Nhl%dat dShi. .a su.x.:.
Facility JPM #:
hEfMIN$1MEIELMt3Id%7t3EiU$2 GAM 2EE15$5;:W K/A Ratinals):
'2.1.1f, Task Standard:
Use the plant recorders to obtain and evaluate parametric information on system or component status.
Preferred Evaluation Location: Proforred Evaluation Method; Simulator X In-Plant Perform X Simulate
References:
Operator Aid 108 EOP Supplement 1 Validation Time: 6 min. Time Critical: No
_s.___ .==a======================_==========================_==========
Candidate: Time Start :
NAME Time Finish:
Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: /
NAME SIGNATURE DATE
s___..================u====================================-----=============
COMMENTS l
Tools /Eauipment/ Procedures Needed: i i
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'. JPM SRO/A.1-1 Page 3 of 5 Ensure sufficient clean copies of OA-108 and EOP Supplement 1 are available for use.
NOTE: Data used was obtained using IC-11 on the simulator if possible, initialize the simulator to IC-11 and allow candidate to obtain data using running simulator. If simulator cannot be used provide candidate with cues as described in the steps of this JPM.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The p' ant is operating at 100% power. Pressurizer pressure is 2000 psia.
INITIATING CUES:
The Turbine Operator has just determined the average qualified CET temperature using the plant recorders.
You are to review the results. ]
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JPM SRO/A 1 1 4
Pag 3 4 of 5 START TIME: '
STEP 1* Review completed copy of Operator Aid 108.
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STANDARD: Completed Operator' Ald 108 reviewed.
COMMENTS:
_ tJNSAT-STEP 2- Identify any errors on completed Operator Aid 108. CRITICAL STEP STANDARD: Determines CET #2 in Quadrant i falls outside the 115'F from average criteria.
_ SAT Critical step to is to identify incorrect data used by operator using CET #2.
COMMENTS:
END OF TASK TIME STOP:
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JPM SRO/A.1 1 a
Pags5 of5
,,(~
f CANDIDATE CUE SHEET
- (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONSi The plant is operating at 100% power.' Pressurizer pressure is 2000 psia.
INITIATING CUES:
' The Turbine Operator has just determired the average qualified CET temperature using the plant recorders. You are to review the results.
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. AfD 108 Page1of1 QUAllFIED CET CALCULATION FORM NOTE: Use this Operator Aid if PPC (Page 311 or 313)is not available.
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1. INSTRUCTIONS:
a. Obtain at least two (2) qualified CET readings ont rdEn nuaduun (utilize CET recorders),
b. Average the temperature readings used, if any individual temperature i readings exceeds i 15'F from the average, then:
1. Do not utilize that individual temperature reading.
2. Return to Step la.
c. Refer to pressure - temperature curve (EOP Supplement 1) to determine subcooling value utilizing average determined in Step 1b. j 1
2. DATA RECORplNG/ CALCULATIONS:
QUALIFIED TIME TIME TIME TIME TIME TIME QUADRANT CET # Now' 2 fG'l - ____. . __. - _______ _________ _ _ _ _ _ _ _ _ ,
9 69/
1 10 687 ___:____.
19 694 5 6C8 11 669 2 is sc4 15 g,og (TM 92 019) 23 679 25 687 -- - - - - - - -----
3 31 (o r> 3 35 69/
27 4 oc>
30. - 69
=_____7_____
4 ............._________ ...______... ________._____. ___.
33 1 666 36 69/
TOTAL 946/
AVERAGE 693 l 1
A W A C 11 M 8 ^f T T~O /+ p M i a JPM .SROlA,1-I l Operator Aid 108 Initiated: SHOaklev. s May 27,1998 Approved 'by: 2MaMm OpeMonOMport Supervisor t-
OPERATOR AlD 108 Page 1 or 1 QUAllFIED CET CALCULATION FORM NOTE: Use this Operator Aid ' C IPag 11 or 313) is not available.
1. INSTRUCTIONS: ,
a. Obtain at least two ed CET readings ont nota ausdrant (utilize CET recorders).
b. Average the temperature readings used. If any individual temperature readings exceeds i 15'F from the average, then:
1. Do not utilize that individual temperature rea iing.
2. Return to Step 1a.
c. Refer to pressure - temperature curve (EOP Supplement 1) to determine subcooling value utilizing average determined in Step 1b.
2. DATA RECORDING / CALCULATIONS:
QUALIFIED TIME TIME TIME TIME TIME TIME QUADRANT CET # Ncd 2 .-E W<7 b.l) 9 ..__. .__69 /.___.______.....___ . __._______... ____ . . . . . . . . . . . 1 to 567 19 694-5 6C6 ..- -__ . ..__ ________ ............. l i 11 669
2. ..
1e .. __ so+__ __... . .... __. . _ . ...__.....__ . _ _ _ _ . . . . . 15 gg (TM 98 o19) 23 679.. .___..___ ___ ___ .__________.. _ _ _ . . . _ _ _ _ . 3 ---------- -- -- ----------- - - - - - - - - - - - 31 bO3 ________._ - ..___..... . . . . . . . 35 69/ ti is00 . ___ _ ......__...... so 617 1 4 33 666 36 59/ , l TOTAL iYCI d9lY l i AVERAGE M 594 Initiated: SRoaklev , Operator Aid 108 May 27,1998 Approved 'by: MotMXe OpeWonOMport Supervisor
g JPM SRO/A.1-2 e f i Page 1 of 8 l REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE 1 JPM SRO/A.1-2 l Determine Feedwater Reserve Inventory and Time Interval for Heat Removal CANDIDATE EXAMINER 1 i
g JPM SRO/A.1-2 ; Page 2 of 8 ' REGIONlil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE InsA; Determine feedwater reserve inventory and time interval for heat removal. Alternate Path: N/A Facility JPM #: TBAA01A(M7EFIE9)' K/A Ratina(s): E06EA2.1 Task Standard: Accurately calculate the time interval available for heat removal. Preferred Evaluation Location: Preferred Evalumelon Method: Simulator X In-Plant Perform _X Simulate
References:
EOP Supplement 2 Validmelon Time: 15 min. Time Critical: No
= - - - - - - __
_=_-- _ _ , _ _ _ = _ _ _ -______ { I Candidate: Time Start : l NAME Time Finish: Performance Rating: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
=======;___=- -- - --- =====---- ___ - _= - - ------ ====
I COMMENTS ! l l I l J
JPM SRO/A.1-2 ?~ Pagn 3 of 8 i
. Ipols/Eauloment/Proceduta1Ettdedi Ensure enough copies of EOP Supplement 2 copies of are available. If the candidcte marks up a controlled j copy ensure the staff replace the copy.
l I READ TO OPERATOR DIRECTION TO TRAINEE: i i will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned te sk. To indicate that you have completed your ass,tned task return the handout sheet I provided you. INITIAL COhDITIONS: While the plant was at 100% power a condensate system piping rupture occurred. The reactor was manually tripped and the operators transitioned to EOP 8.0. The following plant conditions exist:
. MCC 6 is out of service for a ground.
e it is 4 hours after shutdown. e T-81 to T-2 transfer is available, but not in progress. l
. Bus lA and 1B did not fast transfer. . T-2 is at 80%, T-81 is at 60%, and T-939 is at 68%.
T,'s are stable at 530*F I
INITIATING CUES: The Shi^. Supervisor has directed you to complete EOP Supplement 2, PCS Cooldown Strategy. l I l I I ~ )
JPM SRO/A,1-2 Page 4 of 8 START TIME: STEP 1. Enter "T 2 inventory" curve with Condensate Storage Tank T-2 level and CRITICAL determine: T 2 available inventory in gallons (thousands) STEP SAT STANDARD: T-2 inventory is 90 thousand gallons. (89-91 allowed) Critical step is to accurately detennIne inventory. _ UNSAT COMMENTS: GTEP 2 Determine other sources that can be taken credit for as a source of available CRITICAL feedwater inventory: STEP STANDARD T-81 and T-939 are available. ,__ SAT Critical step is to ensure that only avellnNe sources are considered The Hotwellis NOT availaMe. _ UNSAT COMMENTS STEP 3 Determine "T a1 Inventory" CRITICAL l STEP j STANDARD: T-81 inventory is 19.2 thousand. (19-20 allowed) 1 __ SAT Critical step is to accurately detennisw inventory. COMMENTS: __ UNSAT l
[. ) JPM SRO/A.1-2 Paga 5 of 8 l - . . _ SIEP_.4- Determine _"T-939 inventory" CRITICAL STEP l STANDARD 'T 939 inventory is 190 thousand. (188-192 allowed) _. SAT
= Critical step is to accurately determine Inventory.
i. COMMENTS _.UNSAT i
STEP 5' . Add the results of Steps 1 and 2. CRITICAL STEP STANDARD Total of steps 1 and 2 determined to be 109.2 thousand gallons. (108-111) _ SAT Critical step is to accurately determine Technical SpeclRcation compilance. _ UNSAT COMMENTS-s
STEP 6* Add the results of Steps 1 and 3. CRITICAL STEP STANDARD Total of steps 1 and 3 determined to be 299.2 thousand gallons. (296 to 303) )
_ SAT l Critical step is to accurately determine totalInventory. l _ UNSAT COMMENTS
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l. ,
STANDARD T, Initial is -530 F. _ SAT I COMMENIS: _ UNSAT I L. >
JPM SRO/A.1-2 Pagt 6 of 8 STEP 8 Enter " Sensible Heat Removal" curve with data from Step 7 and determine CRITICAL inventory required to remove sensible heat: STEP STAN9ABD Sensible Heat Removal Inventory is 41 thousand gallons. (40-42 allowed) _ SAT Critical step is to accurately determine required inventory. COMMENTS _ UNSAT STEP 9 Subtract Step 8 results from Step 6 results. CRITICAL STEP STANDARD 258.2 thousand gallons. (254 to 263 allowed) _ SAT Criticalstep is to accurately determine totalInventory. _ UNSAT COMMENTS STEP 10 Enter applicable " Decay Heat Removal" curve for number of PCPs operating CRITICAL with elapsed time after shutdown and result of Step 9 and determine the Time STEP interval for heat removal. i STANDARD LTime interval for heat removal is >32 hours. (Interpolation not required) _ SAT Critical step is to accurately determine time interval. COMMENTS- _ UNSAT l j
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~JPM SRO/A.i 2 Page 7 of 8 STEP 11: Notify the Shift Supervisor that the time interval is > 32 hours and that an additional source of inventory is not required. _ SAT STANDARD . SS notifed.
_ UNSAT
.'COMMENIS:
END OF TASK I
~' TIME STO?:
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JPM SRO/A.1-2 l Pagt 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONSJ While the plant was at 100% power a condensate system piping rupture occurred. The reactor was manually tripped and the operators transitioned to EOP 8.0. The following plant conditions exist: e MCC 6 is out of service for a ground.
. It is 4 hours after shutdown. . _ T-81 to T-2 transfer is available, but not in progress. . Bus IA and 1B did not fast transfer. . T-2 is at 80% T-81 is at 60%, and T-939 is at 68% . T,'s are stable at 530*F I
INITIATING CUES: The Shift Supervisor has directed you to complete EOP Supplement 2, PCS Cooldown Strategy. 1 m . -
w, ... ..,n. - 1 EKAMt A/ S(2 's KEY PA Proc No EOP Suppl: ment PALISADES NUCLEAR PLANT Supplement 2 EMERGENCY OPERATING no Rev.ision 5 nuca m euar PROCEDURE Page 1 of 17 TITLE: PCS Cooldown Strategy CAUTION T-2 level less than 5% could result in inadequate NPSH to the AFW pumps. 1.0 DETERMINE THE AVAILABILITY OF FEEDWATER INVENTORY SOURCE __S__:_ i
1. T-81 Primary System Makeup Tank is available if ANY of the following conditions are satisfied:
P-79A available

P-798 available

Primary Make-up system flow path to T-2 available
2. T-939 Demineralized Water Tank is available if ALL of the following conditions are satisfied:
Bus 91 energized

P-936 available

CV-2010 operable I

DMW system flow path to T-2 available
3. Hotwellinventory is available if ANY of the following conditions are satisfied:
CONDITION 1
Condensate Pump P-2A or P-2B in operation

MV-CD129 open rejucting the hotwell to T-2 CONDITION 2

MCC 6, Breaker 52-655 energized

P 214 in operation

Hotwell being transferred to T-2 per SOP-11 {I
)
I
I . l
" Pr N E P Supplement PALISADES NUCLEAR PLANT Supplement 2 EMERGENCY OPERATING ' "*"" 5 * * " " PROCEDURE 1 Page 2 of 17 TITLE: PCS Cooldown Strategy 2.0 DETERMINE INVENTORY OF EACH AVAILABLE SOURCE
1. Determine and record below Condensate Storage Tank T-2 level, utilizing "T-2 Inventory" curve: i T-2 available inventory in gallons = If, 000 Nf'
(
2. IF T-81 has been determined to be an available source of inventory, j THEN determine and record T-81 available inventory in gallons from .
{
"T-81 AVAILABLE INVENTORY" curve: '
T-81 available inventory in gallons = /9, M* h9'N
3. IF T 939 has been determined to be an available source of inventory, THEN determine and record T-939 available inventory in gallons from "T-939 INVENTORY" curve:
T-939 available inventory in gallons = / 9q, w> c h6G db j l
4. IF the Hotwell will be used as an available source of inventory to the
]
Condensate Storage Tank, T-2, THEN close the following valves to prevent draining the Condensate Storage Tank, T-2 to the hatwell:
a. Close 3" Makeup Valve CV-0732 Outlet, MV-CD133, to isolate Three Inch Makeup Valve, CV-0732.
LOCATION: AFW Pump Room
b. Close 6" Makeup Valve CV-0729 Outlet, MV-CD136, to isolate Six inch Makeup Valve, CV-0729.
LOCATION: AFW Pump Room i l
c. Close 12" Makeup Inlet. MV-CD138, to isolate Twelve Inch Makeup Valve, CV-0733. !
LOCATION: Pit near Air Ejector Condenser J
p, - 4 Pr N E P Supplement PALISADES NUCLEAR PLANT supplement 2 EMERGENCY OPERATING
""" 5 ,, ... ,,, PROCEDURE Page 3 of 17 TITLE: PCS Cooldown Strategy
5. IF the Hotwell was determined to be an available source of inventory, THEN determine and record Hotwell available inventory as follows:

a. Utilizing the "Hotwell Available Inventory" curve and the graph line for the corresponding condition determine and record the applicable available Hotwell inventory:
CONDITION 1 P-2A or P 2B Inventory gallons = OR CONDITION 2 P-214 inventory gallons =
b. IF CONDITION 1 is selected, THEN use the "Hotwell Inventory (P-214 or 3" Reject)" curve and the 200 gpm graph line to determine and record available Hotwell inventory :
CONDITIO.M_1. Hotwell Inventory gallons =
c. IF CONDITION 2 is selected, THEN perform the following:

1) Determino if I:-0732
,( LOCATION: Across from entrance to Auxiliary Feed Pump room) is available.
2) IF F1-0732 is NOT available, THEN use the "Hotwell Inventory (P-214 er 3" Reject)" j curve and the 150 gpm graph line to determir.9 and ;
' record available Hotwell inventory:
Hotwell Inventory gallons = l
r l
\
Proc No EOP Suppismant I PALISADES NUCLEAR PLANT Supplement I 2 EMERGENCY OPERATING Revision 5 PROCEDURE Page 4 of 17 TITLE: PCS Cooldown Strategy
3) IF F1-0732 is availabM, THEN perform the follov.'ing:
a) Use the table below to determine the graph line to be used on "Hotwell Inventory (P-214 or 3" Reject)" curve.
###4 Flow' reading MS Mf%ew Value for graphI > 250 250 gpm < 250 and > 200 200 gpm ' < 200 and > 150 150 gpm < 150 and > 100 100 gpm < 100 oom Ooom b) Use the graph line selected above and the "Hotwell Inventory (P-214 or 3" Reject)" curve to determine and record available Hotwell inventory.
Hotwell Inventory gallons =
d. Record below the lowest available Hotwell inventory value from 2.5.a, 2.5.b, or 2.5.c above:
AIA Hotwell Inventory gallons = _ i i
( . Proc No EOP Suppl:msnt T" k PALISADES NUCLEAR PLANT EMERGENCY OPERATING
""""'e m e n t 2
Revisi n s tim,m, FROCEDURE Page 5 of 17 TITLE: PCS Cooldown Strategy 3.0 CALCULATE AVAILABLE INVINTORY
1. Determine the technical specification required inventory to remain in Hot Shutdown or above by adding results of Steps 2.1 and 2.2 Step 2.1, T-2 available inventory (gal) ###
/ bf-f')
Step 2.2, T-81 available inventory (gal) + M, wo ( /9 - 2o) Total TS available inventory (gal) /09,200 goe -nf )
2. IF the total of T-2 and T-81 inventory is less than 100,000 gallons, THEN a cooldown to cold shutdown conditions within the next 24 hours is required by Technical Specification 3.5.

3. Determine total available inventory by adding the results of Steps 2.3, 2.5.c.4), and 3.1.
Step 2.3, T-939 available inventory (gal) N# C##
> b68'/f d Step 2.5.c.4), Hotwell available inventory (gal) d Step 3.1, TS available inventory (gal) + /#9' # 0#C"O I Total available feedwater inventory (gal) 29f wo 49- a c3J l
*AEs40es , PALISADES NUCLEAR PLANT Pr N EPsmisnient supplenient 2 % EMERGENCY OPERATING 5" Revision 5 " " * * * ' PROCEDURE Page 6 of 17 TITLE: PCS Cooldown Strategy 4.0 DETERMINE COOLDOWN RATE FOR AVAILABLE INVENTORY
1. Determine and record present highest Loop Tc (Tc initial):
Te initial = DW
2. Utilizing "Tc initial" determine and record inventory required to remove sensible heat from the " Sensible Heat Removal" curve: ;
Sensible Heat Removal Inventory = M/j C00 [Vo -4 2-)
~
3. Subtract Step 3.3 resu.ts from Step 4.2 results:
299, wo ~
. 4/, co o , 286, zoo (Step 3.3 Total Feedwater inventory (Steo 4.2 in'ventory required (Inventory Avealab5 to remove decay heatl
['2-9L - 5 03) hl1*y"*$')**" (ZTY-245)
4. Utilizing the following:
Applicable " Decay Heat Removal" curve for the number of PCPs operating {
Graph line for the elapsed time after shutdown Amount of inventory available to remove decay heat (graph),
determine and record the time interval for heat removal. Time interval avei!able for heat removi,1 (hours) = > 3 2 /ro u c 3
)
l l 1
I 1
f'
- JPM SRO/A.2 Page l of 5 REGIONlil '
INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l l 1 JPM SRO/A.2 l Review Tagging Requirements for a LPSI Pump i CANDIDATE _ EXAMINER l l i b M.
y 4 JPM SRO/A 2 6' Page 2 of 5 i REGION lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE
'11f5 Review tagging requirements for LPSI pump.
Alternate Path: A55dMW5sEiihihaEhMininiEi&dh' JW't - <K Facility JPM #: K5&M@$sES?$slGlT33iiMMffBiaEf0LT,flTEldGf22GEjniM aus,. ?c: . K/A Ratinois):
?. 2.13 Task Standard:
Accurately determine tagging requirements for LPSI pump, to ensure personnel safety. Preferred Evaluation Location: Plafendivaluati lrLMeth2d! Simulator X in-Plant Perform Simulate X
References:
. SOP-3 and Drawing M-204 sheet 1,1A, and 1B Validation Time: 15 min. Time Critical: NO ======================____;;=====================---- =============================
Candidate:. Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
========================____=-----=-----------w____e...=======================_====
COMMENTS Tools /Eautoment/ Procedures Nees 2g;
p JPM SRO/A.2 8
, Pig) 3 of 5 e
Ensure enough copies of controlled prints are available. READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for thl3 JPM, including any required communications. I will provide initiating cues and reports on oth6r actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task retum the handout sheet I provideri you. . INITIAL CONDITIONS: The plant is preparing for refueling. The SIRWT has been drained to the Reactor Refueling Cavity. A small leak was reported on the L' PSI pump 678 miniflow orifice. INITIATING CUES: . You have directed an operator to determine the electrical and mechanical isolation requirements to take P-67B out of service. It is necessary that the pump be drained and vented for the inspection. No computers are available. You are to verify the attached ta0ging requirements. t I i l i I l l l l t.
f,' . JPM SRO/A 2 Pagn4 of 5 START TIME: _ STEP 1: Reviews attached tagging order. __. SAT
. ETANDARD: Reviews tagging order.
COMMENTS: _ UNSAT STEP 2: Determines any missed tagging requirements. CRITICAL STEP
- STANDARD: Determines that the operator failed to tag the Breaker 152-111 Control Power fuses PULLED. ,_ SAT Critical step is to ensure personnel safety and equipment protection is met.
___UNSAT
' COMMENTS:
END OF TASK TIME STOP: I l l { l 1 I l
Y JPM SR0/A.2
. r ,
Pag 3 5 0f 5 CANDIDATE CUE SHEET
. (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDIT!ONS: The plant is preparing for refueling. The SIRWT has been drained to the Reactor Refueling Cavity. A small leak was reported on the LPSI pump 678 miniflow orifice. INITIATING CUES: You have directed an operator to determine the electrical and mechanical isolation requirements to take P 678 out of service. It is necessary that the pump be drained and vented for the inspection. No computers are available. You are to verify the attached tagging requirements.
l
., ' serm Js:' 4 CONSUMERS ENERGY SWITCHING ANDTAGGING ORDER ) rr M M M A n r. rt- 'J PM 'M ' l ^
Order No.
< OrderGiven By [h - / ' ' " ' W Location 4// 3 'b s Ord;r Written By N C b' Date and Time Given ( . . . < < .s /~
Approved By ' Date and Time Started b '" e d Carried out By Date and Time Completed Purpose G lYoM L J e b* *>**s 9 e' f v ! L e' -
/ />$ E j.'),, g
(% L f13
.jsc lac- lea la ' c i, su; ;Fla on ee ACTIONS PERFORMED / No. Se sure this procedure covers existing electrical and/or mechaniul conditions when these operations are executed. - IA' G " 74*fH91V9 No
2.+ ci H 9 z c o
/ P i s c os.n / E t r~ - Bregler / SL-/// , P-676 L C c.csED -
610 - 3/90 P-458 Soc /to., fr on, SDC. 3 ; ccces s o - me : 3 i s i F- 4 7e wen.- fr-~ sie ~ r-
'l Ciusso -
MV-Ss 3)94 7-b78 M.'., .',Clu w 5' CLusso - Mi-25 3/9 3l f-478 D:wk ge nhe 4 'CPEH - hiv-Es 33ys , AL 78 Venf 1 CPBd -
/v1 V-BS 6/5 ' P { 78 [q ,;,, \ D,,jn $ C. 4 0 1"! O M TO N6JTW4 L A t-TB A- 732IJ fGA6&M FLAG } !rYb (PSE Ns P4 Vi f L'LG$8O ~~ M V - C C, /3 2.- Cl* LAJ TC f *C 18 10 C ucS SD ~
M v' - C C lb b. CCvG Yo P-418 Date and Time
. Wtrking Clearance issued By .tking Clearance Received By ~
Working Clearance Released By Working Clearance Released To FILE FOR THIRTY DAYS BEFORE DESTROYING L-
.M "Q" '^ R E G IO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO/A.3 Radiation Control CANDIDATE EXAMINER JL mu s
4 JPM SRO/A.3 0 Page 2 of 6 REGION 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Knowledge of conduct of operations requirements. Alternate Path: c., SQUlii$TIONSONINsJEisM!#a?ffiUJSfk%AsR:W&l m e,.c Facility JPM #: MQ:$glt) g ; '" . . ;, %Mgg$QqZSQq[zyg K/A Ratinofs): 2.3.1 2.3.10 Task Standard: l Correctly respond to administrative questions. Preferred Evaluation Location: Preferred Evaluation Method: Simulator in-Plant Perform X Simulate
References:
ADM 7.04 Radiation Dosimetry and HP-11.4 Evaluating Control of Airbome Radioactivity and Respiratory Protection Validation Time: 10 min. Time Critical: Ng
==..___s----- --========______.s=====================================================
candidate: Time Start : NAME Time Finish: l i P_grformance Ratina: SAT UNSAT Question Grade Performance Time
/
Examiner: NAME SIGNATURE DATE
======================================s___===========-:============================= l COMMENTS l
1 i w - I
JPM SRO/A.3
, Page 3 of 6 JPM QUESTION # 1 REFERENCE ALLOWED: YES /
yes no Question: An Auxiliary Operator was recently hired from a Texas nuclear utility. His exposure for this year at the other utility was 1500 mrem TEDE. WHAT is the total exposure he can receive this year at Palisades without getting approval to exceed the allowed dose level? EXPLAIN Answer: He can receive up to 2000 mrem TEDE at Palisades. The limit for a worker who received occupational exposure at another utility is 4000 mrem TEDE, but only 2000 mrem TEDE may be received at Palisades facilities. A dose review would be required at 1500 mrem. (Not required for full credit.) CANDIDATE'S RESPONSE Time: 5 min. KIA Rating: 2.3.1 (2.6)
References:
ADM 7.04
I . JPM SRO/A.3
o Page 4 of 6 JPM QUESTION # 2 REFERENCE ALLOWED: YES /
yes no Question: You and two (2) other operators are assigned to perform a task in an area where the dose rate is 50 mrem /nr. The area also has some airborne radioactivity. From previous experience, it is known that it will take 3 hours to perform the task if respirators are worn and 2 hours without wearing respirators. if the task is performed without a respirator, each worker will receive 5 DAC/hr of internal dose. f Will the total exposure be lower if respirators nre worn or if respirators are not worn? What will be the difference in exposure to each worker depending on whether or not respirators are worn? Answer: The total exposure will be lower if respirators are NOT worn. Not weanng a respirator will resu!t in a reduction in total exposure to each worker of 25 mrem. WITH RESPIRATOR: (3 hours)(50 mrem /hr) = 150 mrem per worker WITHOUT RESPIRATOR: (2 hours)(50 mrem /hr) + (2 hours)(5 DAC/hr)(2.5 mrem /DAC) = 125 mrem per worker CANDIDATE'S RESPONSE Time: Smin. KIA Rating: 2.3.10(2.9)
References:
HP 11.4
.]
p-JPM SRO/A 3 Page 5 of 6 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: You and two (2) other operators are assigned to perform a task in an area where the dose rate is 50 mRemihr. The area also has some airborne radioactivity. From previous experience, it is known that it will take 3 hours to perform the task if respirators are worn and 2 hours without wearing respirators. If the task is performed without a respirator, each worker will receive 5 DAC/hr of internal dose. Will the total exposure be lower if respirators are worn or if respirators are not worn? What will be the difference in exposure to each worker depending on whether or not respirators are wom? 1 I 1 l I L I
F . JPM SRO/A 3 Page 6 of 6 JPM QUESTION # 1 CANDIDATE COFY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: An Auxiliary Operator was recently hired from a Texas nuclear utility. His exposure for
.this year at the other utility was 1500 mrem TEDE. -
WHAT is the total exposure he can receive this year at Palisades without getting approval to exceed the allowed dose level? EXPLAIN. t j
F~ JPM SRO/A 4 o'
' Page 1 of 6 I REGION lli INITIAL LICENSE EXAMINAT!ON JOB PERFORMANCE MEASURE JPM SRO/A.4 Determine Protective Action Recommendations during a General Emergency CANDIDATE EXAMINER <
l l i
( . 3 JPM SRO/A 4
* ^
Page 2 of 6 i V l REGION 111 INITIAL LICENSE EXAMINATION I JOB PERFORMANCE MEASURE ; 1 Task: Determine protective action recommendations for plant accident conditions. Alternate Path: bEMNINA3I5Mi$ifdifl516KfTisTdffffElhAM593fElf!@k! *%g; @i;dL b;;5, q l Facility JPM W. 1 i n M' s ' L e . ' 'Yl,. , - SY ~- , Sk ~ .; r:' 4' ; l i K/A Ratinals): 2.4.44 l l Task Standard: l Accurately make offsite protective action recommendation and county notification within 15 minutes of event declaration. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate I i i Referenstg; ; El-6.13 Validation Time: 15 min. Time Critical: YES
===============_==_-=----- =______====____==- -================================
Candidate: Time Start : l NAME Time Finish: l l Performance Ratina: SAT UNSAT Question Grade Performance Time i Examiner: / l NAME SIGNATURE DATE
======____________.._____.______u_____ ___============______ ======================
COMMENTS _i
p-4 JPM SRO/A.4 Pag 3 3 of 6 Tools /Eauipment/ Procedures Needed: Ensure enough copies of El 6.13 Att.1are available. If the candidate marks up a controlled copy ensure the staff replace the copy. Ensure the conditions for this JPM are entered into the Release Rate Program and the results are handed to the candidate. READ TO OPERATOR DIRECTION TO TRAINEE: l l will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you inoicate to me when you ; understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:
. LOCA is in progress. . Safety injection flow is inadequate. ) . Failed fuel monitor RIA-0202 is off scale high j e Failed fuel analysis is in progress with no results to report. j e An actual release is occurring through the plant stack e A General Emergency condition has been declared at this time.
A tornado waming is in effect for Van Buren County and precipitation is heavy. The wind is from 185 degrees at 13 mph.
INITIATING CUEI); During activation of the Site Emergency Plan, you (acting as the SED) are to determine the Minimum initial Protective Action Recommendations required for this event per El-6.13 and the attached El-3, Attachment 1, " Emergency Notification Form." . l This is a TIME CRITICAL JPM. t ..J
I , JPM SRO/A 4 '
Page 4 of 6 START TIME:
STEP 1: Operator enters proper procedure.
- SAT STANDARD: Examinee enters El 6.13 Att.1.
COMMENTS: _ UNSAT STEP 2 initial Recommendation. CRITICAL STEP STANDARD: Recommend shelter 2-mile radius (sector 1) und 5 miles in sectors 1 & 2 per El 6.13 Att.1. _ SAT Critical step Is to ensure that the candidate recognizes that severe weather changes the PAR to shelter vice evacuation. _ UNSAT COMMENTS: STEP 3 Record the recommended protective action and affected area on the El 3 CRITICAL Attachment 1 and hand sheet to the SED. STEP STANDARD- 5 3 Att.1 section 7 filled out as determined above and handed to SED (ie - SAT evaluator). 7A = YES,78 = Plant Status,7C = S:ielter 2 mile radius and 5 miles in sectors 1 & 2,7D = N/A or blank. _ UNSAT The critical step is to complete the recommendations to allow for communications. COMMENTS: l k . .j
f. .
JPM SRO/A.4
. PegG 5 of 6 STEP 4: Contact Van Buren County CRITICAL .. STEP STANDARD: ' Van Buren County Sheriff contacted, within 15 min. of emergency declaration.
Phone number is 616-657 2058 or 616-657-3101. __ SAT h . Criticalstep is to initiate contact. NOTE: Must be complete witnin 15 minutes of DECLARATION. __UNSAT COMMENTS: ETEP5 Relay information on Emergency Notification Form. CRITICAL STEP STANDARD: Minimum of Step 7 of Emergency Notifica'. ion Form correctly relayed and name of person contacted entered on Emergency Notification Form. - Shelter __ SAT 2 mile radius (sector 1) and 5 miles in sectors 1 & 2. Criticalstep is to transfer the information contained in steps 7 of the Ememency Notification Form. __.UNSAT COMMENTS: END OF TASK TIME STOP:
/*~
JPM SRO/A 4 Page 6 of 6 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF. TASK) l INITIAL CONDITIONS: l . LOCA is l'n progress.
. Safety injection flow is inadequate. . Failed fuel monitor RIA-0202 is off scale high.
l
. Failed fuel analysis is in progress with no results to report. . An actual release is occurring through the plant stack. . A General Emergency condition has been declared at this time.
. A tomado waming is in effect for Van Buren County and precipitation is heavy. The wind is from 185 degrees at 13 mph.
. jf[lTIATING CUES: ' During activation of the Site Emergency Plan, you (acting as the SED) are to determine the Minimum initial Protective Action Recommendations required for this (vent per El-6.13 and the attached El-3, Attachment 1, " Emergency Notification Form."
l This is a TIME CRITICAL JPM. l l l l l .j
p-
)$Ha etmm f k ~J / w/:.in A. y Prec No El-3 Attichmsnt 1 EMERGENCY NOTIFICATION FORM ~ Revision 1B !
Page 1 of 1 A tvol: REQUIRED INFORMATION Thisis a drui. o This es not a drill. Date: C u/'f6 Al T Time: C cdM 4 r- j rtm: .-(CR aTSC. To: )c County 0 EOF ,. ' 1. Name: : 0-State Time: l Name: l !- O NRC ' Time: Name: ! 2.. PAllSADES Time:
3. ' CLASS OF EMERGENCY 2A. PLANUXEEEKGE'NUlW8ER A. o Unusual Event ' 8. 0 Alert C.
E.. This classification declared by Mant at: c. Time: O Site Area Emergency D.. General Emergency c v a /z h r Date: C v4 d e. F. Initistmg Conditionp/ Description of Event: fou ci + c c. <.< /<a wf- fro m .PCs u; . H. les s +/.an' r e e v,'< e d e,ue<qe m evet; , Fica " u i 4 PLANT STATUS *
' l A. 0- Stable ' B. )( Degrading C.. O improving D. Additionalinforms ' : .,# o n a v.:se nin s i., effe d 4< Va- B.. u e (,oa.< 4r i
1
5. O NO RADIOLOGICAL RELEASE IN PROGRESS: K YES

6. < METEOROLOGICAL DATA c l o
A. Wind Direction, Degrees From: /U To:
. O, Three Downwind Sectors:
Ie B. Wind Speed, MPH: /3 C. Stability Class: O i aAe E. Precipitation: )( YES O NO , 7. PROTECTIVE ACTION RECOMMENDATIONS - i A. o YES .O NO' ! Note: if YES fW in fotowing information. i
5. PAR based on: o Dose Calculations a Mant Status c Other 1
C. in-piece Shelter (Areas) ,, D. Evacuation (Arees) 8. AS AVAILABLE RADIOLOGICAL RELEASE DATA A. Time rolesse started Projected dwation of release
8. 0- Airbome D Waterborne a Waterbome Analysis Attached ,
C. Effluent Points j
, D. Nesbie gas release rate, Ci/sec Sample Monitor Estimate E. Average energy per disintegration, MeV , Sample Monitor F. Equivalent I-131 release rate, Ci/sec Estimate Sample Monitor Estimate G. Particulate release rate Ci/sec Sample Estimate i 9. CALCULATED OFFSITE DOSES A. O ' Actual O; Potential B. Based on: 0 Monitor (in Mant) o Sample (in Mant) - c Back Calculation from field data o Other Mont Conditions C. Calculated Dose Rate (mrom/hr)
Time of Calculation Distence - TEDE (mrom/hr) Adult Thyroid CDE (mrom/hr) Site Boundary 2 Miles ~ 5 Miles 10 Miles D. Calculated Accumulated Dose (mrom) Calculated Duration, Hours Distance TEDE (mrom) Adult Thyroid CDE (mrom) Site Boundary i
' 2 Miles i 5 Miles !'
10 Miles . EJ Sectors Affected
- 10. MEASURED OFFSITE DOSE RATES A. Distance Time Reading (mR/hr) Affected Sector Site Boundary i
miles miles ~
meles S. KEonal information l l
V. + fj ga e im+., /
g( I'r*f/M AV Proc No El 3 F--
Attachment 1 EMERGE _ MPT. ICATION FORM Revision 18 Page 1 of 1 REQUIRED INFORMATION Approval: K This is a drill. O This as not a drill. Date: C ut?c6 r/ T Time: C MG -
- From: XCR 0TSC 0 EOF
1. To: a County Name: Time:
O State Name: ! Time: l 0 NRC Name: Time: !
2. PALISADES

3. 2A. PLANT MESSAGE NUMBER f CLASS OF EMERGENCY A. o Unusual Event B. O Alert C. O Site Area Emergency D.
l E. This classification declared by Plant at: Time: c vi2 /2 G_u e Date: Cv4 tz /5A, r-X General Emer! F. Initiating
/cmConditionl/
c> c Description c, o t a n t of Evft: on PCs w.+k les> +/. a n r-e w ;..e.cf c o a t . ., , -Flow e m e , y a., ,4 i u
4. PLANT STATUS '
A. O Rtable B, K Degrading C. O Improving D. Addition:1information:
,*
r. , a da w a m i., s i., e[$e d b>< % B n-, Co u.,4, I
6. RADIOLOGICAL RELEASE IN PROGRESS: jl( YES o ND

6. METEOROLOGICAL DATA o A. Wind Direction, Degrees From: /6Ia To: 5' o s. wind Speed, MPH: O C. Stability Class: O D. Three Downwind Sectors: aA8 E. Precipitation: )( 'YES' O NO

7. PROTE E ACTION RECOMMENDATIONS '
A. YES c NO ' Note: ES fill in following information.
8. PAR based on: 0 Do N Plant Status O Other i
C. in-place Shelter (Areas) .g Calculations /saile 4a/J Sd.;I, Av./,'v5 4/ & .r w / [ 2. D. Evacuation (Areas) as AS AVAILABLE
8. RADIOLOGICAL RELEASE DATA A. Time release started Projected duration of release

8. O Airborne o Waterborne o Waterborne Analysis Attached C. Effluent Points D. Noble gas release rate, Ci/sec Sample Monitor Estimate E. Average energy per disintegration, MeV Sample Monitor Estimate F. Equivalent 1131 release rate, Ci/sec Sample Monitor Estimate-G. Particulate release rate Ci/sec Sample Estimate

9. CALCULATED OFFSITE DOSES A. O Actual O Potential B. Based on: O Monitor (in Plant) O Sample (in Plant) o Back Calculation from field data O Other PIent Cone C. Calculated Dose Rate (mrom/hr)
Time of Calculation Distance TEDE (mrom/hr) Adult Thyroid CDE (mrom/hr) Site Soundary 2 Miles 5 Miles 10 Miles D. Calculated Accumulated Dose (mrom) Calculated Duration, Hours Distance TEDE (mrom) Adult Thyroid CDE (mrom) Site Boundary 2 Miles 5 Miles 10 Miles E. Sectors Affected
10. MEASURED OFFSITE DOSE RATES A. Distance Time Reading (mR/hr) Affected Sector Site Boundary miles miles males B. Additional Information m a
3 l J
)
i FINAL AS-ADMINISTERED WALKTHROUGH JPMS FOR THE l I l PALISADES EXAMINATION - THE WEEK OF JUNE 7,1999 I 1 1 i i s'
ES-301 Individua! Walk-through Test Outline Form ES-301-2 Facility: PALISADES Date of Examination: June 7 - 11.1999 Exam Level (Circle): RO Operating Test No.:_1 System / JPM Title / Type Codes
Safety Planned Follow-up Questions:
Function K/A/G // Importance // Description
1. Makeup to the VCT using Blended Flow 1 a. 004K129 (4.3) Detection mode for leaking I
(N)(S) PORV/ relief valve.
b. 004A311 (3.6) Automatic operation of Charging / Letdown.

2. Respond to an LTOP Actuation 3 a. 027AK304 (2.8) Reason for slow pressure (N)(A)(L)(S) . recovery following a loss of level.

b. 010K403 (3.8) PRZ PCS design feature for over pressure control.

3. Equalize Boron Conc between SDC 4 a. 025AK303 (3.9) Loss of CCW actions in EOP and SIRWT (N)(L)(S) b. 005K402 (3.2) RHRS modes oiceration

4. Verify Containment Spray Response to 5 a. 026K404 (3.7) CSS design feature to reduce Recirc Actuation temperature / pressure following a LOCA (N)(A)(L)(S)

b. 026K102 (4.1) CSS interconnection with Cooling Water System f, insert and Remove RPS Channel Trip 7 a. 012K402 (3.9) RPS design for automatic Rx trip flypass (N)(S) b. 012K404 (3.1) RPS design for redundancy

6. Shift Operating CCW Pumps 8 a. 008K301 (3.4) Effect on loads cooled by CCWS l (N)(A)(S)

b. 008K102 (3.3) Loads cooled by CCWS

7. Transfer PRI Level Control from 2 a. 011 A211 (3.4) Predict'iailure of PRZ level MANU AL to C/.SCADE instrument low

b. 011K512 (3.3) Purpose of PRZ level program

8. hLanually Align Y-01 to Emergency 6 a. 2.1.24 (2.8) Ability to interpret plant drawings Power Supply (M)(P) b. 062K103 (4.0) DC distribution interrelations with AC sourcas

9. Start M49A Hydrogen Recombiner 5 a. 028K502 (3.9) Flammable gas conc limit (M)(P)

b. 028K301 (4.0) Hydrogen conc in containment

10. Locally Start P-8B using 4 a. 061K403 (2.9) AFW design feature for automatic CV-0522A isolation of blowdown / sampling

b. 061K302 (2.9) AFW malfunction effect on S/Gs
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow Power, (P)lant, (R)CA e .- __.
r 3, f$e"SiVf" R E G IO N lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE . l JPM RO-1/SIM Makeup to the VCT using Blended Flow CANDIDATE EXAMINER
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-4 g JPM RO-1/SIM 4-Page 2 of 16 REGION lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Restore VCT level to normal using blended flow. I Alternate Path: d rMM4dd$d"fM$11b&IddGTdAd$%AllisiS18dsdadli:.;hi;;c C ,c.&gy Facility JPM #:
':il21% M W lfi6ilfSil? R T M M I@ M WNZZ.W?:Gl2hGLfiUVLC3%;fibiiiSEJW i
K/A Ratinois): ! 004A2.18 Task Standard: VCT level has been returned to the normal operating band. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate
References:
SOP-2A Section 7.4.2.b Validation Time: 15 min. Time Critical: No
==2----.-.=======================----=====e=========e===:=========================
C_andidate: Time Start : NAME Time Finish: , Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
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COMMENTS J
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y ,-A JPM RO-1/SIM P:g3 3 of 16 SIMULATOR OPERATOR INSTRUCTIONS: e initialize to IC 11. s
Fr , 4 JPlul RO-1/SIM g Page 4 of 16 Tools /Eauipment/ Procedures Needed: Ensure enough copies of SOP-2A are available in the Simulator. ) READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required commu.iications. I will provide initiating cues and reports on other actions when directed by you. Ensure, you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: . The plant is at 100% power with all systems in normal line-up. BAST concentration is 12,500 ppm and PCS boron concentration is 1260 ppm. INITIATING CUES: The Control Room Supervisor has directed you to raise VCT level 3% using the 'boration and dilution' method of SOP 2A section 7.4.2b. L
3-JPM RO-1/SIM l Pag) 5 of 16 I START TIME: i STEP 1: Restore VCT level to 65% using SOP-2A Section 7.4.2.b. STANDARD: Locates and refers to SOP-2A. _ SAT l
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COMMENTS: STEP 2' Determine blend ratio needed to supply a blend to the VCT of 1260 ppm. CRITICAL STEP STANDARQ: Using the foimula
= -SAT BAST (concentration) -1 aat of PMW PCS (concentration) - 1 gal of B.A jlfl1-1 = 9 aal of PMW to 1 aal Boric Acid _ UNSAT 1260 Critical Step is to calculate the ratio accurately enough so that inadvertent boration or dilution of tne PCS does not occur. l COMMENTS:
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r. JPM RO 1/SIM i* 1 Pagg 6 of 16 STEP 3 Ensure closed CV-2155 Boric Acid Blender Outlet Control Valve..
~ STANDARD: CV-2155 checked closed, green light on.
COMMENTS:' ,,_ UNSAT l STEP 4: Ensure P-90A or B operating in Manual. STANDARD: P-90A and B checked, in manual. Manual light lit. SAT
- COMMENTS: ___UNSAT.
STEP 5 Ensure the Boric Acid Tank recirculation CV's 100% open _ SAT STANDARD: Appropriate CV status checked: P-56A (CV-2130) P-568 (CV-2136). Valve position 100% open, red light on.- _ UNSAT COMMENTS: STEP 6 Start P-56A or P-568. CRITICAL STEP STANDARD: P 56A QB B hand switch taken to "CLOSE". Red light for selected pump on.
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Critical Step is to ensure properi!neup for subsequent operations. COMMENTS: ___ UNSAT t
p . JPM RO-1/SIM
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Pag 3 7 of 16 STEP 7: Push RESET button on FIC-0210B CRITICAL STANDARD: RESET button pushed on FIC-02108.
~ ' Critical Stop is to setup controller forproper operation.
QOMMENTS
- STEP 8 Ensure in AUTO FIC-02108.
STANDARD: AUTO light is lit on FIC-0210B. _ SAT s COMMENTS: L. _ UNSAT STEP 9: Ensure FIC-0210B output signaling full closed. STANDARD: FlC-02106 output is zero. _ SAT _ UNSAT COMMENT 8: STEP 10 ' Set batch on FIC-02108. CRITICAL STt!P STANDARD: FIC-02108 batch set to yield a 9:1 PMW: BA ratio (approximately 10 gallons of boric acid required), _ SAT Critical Step is to correctly enter value based on calculation in Step 2. NOTE: Approximately 3A gallons of boric acid required per percent based on a VCT volume
~ - UNSAT of 34 gations per percent and a 9:1 ratio.
COMMRNg[Q: 1
{E , JPM RO-1/SIM
'- Pags 8 of 16 STEP 11: Set flow limit for FIC-0210B STANDARD: FIC-0210B set to a rate < 25 gpm.
__ SAT COMMENTS: SIgf_1.2- . Push RESET button on FIC-0210A ~ CRITICAL
- STEP STANDARD: RESET button pusned on FIC-0210A Critical step is to set up subsequent operations to initiate blended flow. __, SAT COMMENTS:'
_ UNSAT STEP 13; Ensure in AUTO FIC-0210A. STANDARD: AUTO light is lit on FIC-0210A - _ SAT __UNSAT
- COMMENTS:
STEP 14: Ensure FIC-0210A output signaling full closed. STANDARD: FIC-0210A outputis zero ' _ SAT __UNSAT
@MENTS:
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r. ] :-- JPM RC ~1/SIM
. Page 9 of i6 STEP 15: Set batch on FIC-0210A. CRITICAL STEP
STANDARD: FIC-0210A batch set to yield a 9:1 PMW: BA ratio (approximately 92 gallons of PMW required).
_ SAT Critical Step is to correctly enter value based on calculation in Step 2. NOTE: Approximately 30.6 gallons of PMW required per percent based on a VCT volume 'of 34 gallons per percent and a 9:1 ratio.- _ UNSAT COMMENTS: STEP 16: Set flow limit for FIC-0210A. STANDARD: FIC-0210B set to a rate at t 30 gpm- _ SAT _ UNSAT COMMENTS: STEP 17: Open CV-2155. CRITICAL STLP STANDARD: CV-2155 handswitch to open. Red light on.
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SAT Critical Step is to ensure properlineup for blend operation. COMMENTS:- _ UNSAT STEP 18: Push START on FIC-02108. CRITICAL STEP STANDARD: FIC-0210B START button pushed. Red light lit. _ SAT Critical Step is to ensure boric acid flow is initiated. COMMENTS: _ UNSAT l j t j
f , o JPM RO-1/SIM Page 10 of 16 STEP 19: When FIC-0210B reaches end of batch, then ensure closed CV-2153 and FIC-02108 at zero output. STANDARD: . Zero flow indicated, CV-2153 green light lit, and zero output signal observed
~ AT S on FIC-02108.
_ _UNSAT COMMENTS: STEP '/Q: - Push START on FIC-0210A. CRITICAL , STEP STANDARD: ' FIC-0210A START button pushed. Critical Step is to ensure primary water flow is initiated. _ SAT l i COMMENTS: _ UNSAT STEP 21: When FlC-0210A reaches end of batch, then ensure closed CV-2165 and FIC-0210A at zero output. SAT STANDARD: Zero flow indicated, CV-2165 green light lit, and zero output signal observed ) on FlC-0210A.
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COMMENTS: STEP 22: . Close CV-2155, Boric Acid Blender Outlet Control Valve. CRITICAL STEP STANDARD: CV-2155 handswitch to close. Green light lit. __ SAT Critical Step is to ensure properlineup for subsequent operations that willlimit the possibility ofinadvertent boration or dilution events. COMMENTS: _ _UNSAT
f- 3_ ] +, ' JPM RO-1/SIM a; < Prga 11 of 16 .) j STEP 23: Stop the operating Boric Acid pump. i STANDARD: P 56A (B) handswitch taken to " TRIP" ' Green light lit.' __, SAT Y
, COMMENTS ,
___UNSAT i STEP 24: Record FIC-02108 and FIC-0210A. boric acid and PMW batch data.-
STANDARD:
FQl-02108 and 0210A values recorded or noted. __ SAT LOMMENTS ___, UNSAT - i STEP 25: Inform CRS of blend completion. STANDARD: CRS informed. _ _ SAT COMMENTS _ UNSAT END OF TASK TIME STOP: E' u i
I ~ JPM RO-1/SIM Page 12 of 16 JPM QUESTION # 1 REFERENCE ALLOWED: / NO yes no
. Question: The plant is at 100% power with PZR level control in CASCADE. 'PZR level is on program. The PCS leakrate calculation has identified a leak rate of 8 gpm, and it is identified to be through the "A" PORV. )
How long will it take for VCT level to lower from 72% to 68%7 Answer: A four percent change in VCT level equals 137.66 gallons. At a leakrate of 8 gpm, this l results in 17.21 minutes. l CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 004.K1.29 (4.3)
References:
GOP-13 and Lesson Plan ASFD section 4.8
ri s JPM RO-1/SIM Page 13 of 16 JPM QUESTION # 2 REFERENCE ALLOWED: YES / j yes no ' Question: LETDOWN TO VCT OR RWT Valve CV-2056 has failed and diverted all letdown flow to the CWRT. Actual VCT level has decreased to 6%, when CV-2056 is repaired. Without Operator action, predict the final lineup of the Charging pump suction valves. Answer: MO-2087 is clersed and MO 2160 is open. (Both valves and final positions required for full credit) i At 7.9% decreasing, VCT outlet valve MO-2067 loses and SIWRT outlet to the charging pumps suction valve MO-2160, opens. VCT actuallevel willincrease until CV-2056 is again in the divert position. (Not Required) CANDIDATE'S RESPONbE Time: 5 min. K/A Rating: 004A3.11 (3.6)
References:
Lesson Plan ASFA section VilK.2 ARP4, EKO910
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JPM RO-1/SIM
, Page 14 of 16 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES / __
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETlON OF ANSWER) Question: LETDOWN TO VCT OR RWT Valve CV-2056 has failed and diverted all letdown flow to the CWRT. Actual VCT level has decreased to 6%, when CV-2056 is repaired. Without Operator ac' on, predict the final lineup of the Charging pump suction valves. l J Il
I . JPM RO-1/SIM Paga 15 of 16 t JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: / _ NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: The pisnt is at 100% power with PZR level control in CASCADE. PZR level is on program. The PCS leakrate calculation has identified a leak rate of 8 gpm, and it is identified to be through the "A" PORV. How long will it take for VCT level to lower from 72% to 68%7 l l 1 l l l I i 1
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JPM RO-1/SIM s Page '16 of 16 CANDIDATE CUE SHEET-(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) i< INITIAL CONDITIONS: The plant is at 100% power with all systems in normal line-up. BAST concentration is 12,500 ppm and PCS boron concentration is 1260 ppm. INITIATING CUES: The Control Room Supervisor has directed you to raise VCT level 3% using the 'boration and
. dilution' method of SOP 2A section 7.4.2b.
r , A fale",iNI" REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO-2/SIM Respond to an LTOP Actuation CANDIDATE EXAMINER
{- . JPM RO-2/SIM h Pags 2 of 12 REGION lli l INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE , I fask: j
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Respond to an LTOP actuation caused by an instrument spike. Alternate Path:
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d. 1. m.m.y v v~ ~:,susJsD2 . as g.,? %
Facility JPM #:
$syv.mYLxym o :,.Lw:,v6:u+nmw any . .
w ruaris%w%w:dnac -n n :m -u u, , ., :n s x a%'Ja>vaM;4Q2 g,.; c,
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wg;, 'n w.mu . K/A Ratinals): 000027AA2.15 Task Standard: Utilizing station procedures respond to an LTOP actuation and limit loss of PCS inventory. Preferred Evaluation Location: Preferred Evaluation Method: Simulator - X in-Plant Perform X Simulate
References:
ONP-18, ARP EK13 # 73 and 74 Validation Time: 15 min. Time Critical: No
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Candidate: Time Start : NAME Time Finish:- Performance Ratino: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
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COMMENTS
JPM RO-2/SIM
, - Page 3 of 12 SIMULATOR OPERATOR (N STRUCTIONS: ; . Initialize to IC-36. l . I/O EK 1373, PORV OPEN, alarm to ON . l/O LTOP Channel'B' red trip light to ON ) . ' 1/0 PI-0105B on C-02 to 1.0 (failed high) . 1/O PRV-1043B HS to OPEN .' Place the simulator in RUN '.. As soon as all indications are verified (approximately 2 se.conds), place the simulator in FREEZE . After turnover, and with concurrence from the examiner, go to RUN l1 4
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r 4 JPM RO-2/SIM Pags 4 of 12
- Tools /Eauloment/Proced'ures Needed:
Ensure enough copies of ONP-18 are available. READ TO OPERATOR DIRECTION TO TRAINEE: i
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I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task.-To indicate that you have completed your assigned task return the . handout sheet I provided you. INITIAL CONDITIONS: The plant is shutdown and Shutdown Cooling is lined up for operation. An instrument failure has caused an LTOP actuation. INITIATING CUES: The Shift Cupervisor directs you to respond to the LTOP actuation using the guidance in ONP-18, Step 4.3.
( , JPM RO-2/S!M Pige 5 of 12 i START TIME: STEP 1: Refer to ONP-18. Step 4.3. STANDARD: ONP-18 referred to.
- SAT ]
1 1 l COMMENTS: _ UNSAT STEP 2 Determine that PCS pressure is below the actuation setpoint, and close both PORVs.- STANDARD: Close handswitch for PRV-10428. Green light lit.
' NOTE: This step is not required to be performed since the valve is already closed. Candidate _ UNSAT mayplace HSin CLOSE however.
Steps 2 and 3 may be performed in any order. COMMENTS: STEP 3: Determine that PCS pressure is below the actuation setpoint, and close both , PORVs. l SAT l STANDARD: Close handswitch for PRV-10438. Red light remains lit. 1
~ Steps 2 and 3 may be pertbrmed in any order. ?
_.,UNSAT COMMENTS:
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I JPM RO-2/SIM
. Page 6 of 12 f! STg M Depress associated Reset Push Button to Clear LTOP trip indication. ' STANDARD: Associated Reset Push Buttons are pushed. LTOP trip light remains lit.
_ SAT COMMENTS: _ UNSAT 1 STEP 5: If PORV's don't properly close when below their actuation setpoint, then close CRITICAL the associated PORV lsolation Valve. STEP STANDARD: MO-1043A HS placed in CLOSE. Green light lit.
~ SAT Critical Step to isolate failed open PORV to stop PCS leakage.
COMMENTS: _ UNSAT SJfEPj: Continuously monitors Pressurizer Pressure to ensure LTOP limits are not exceeded. _ SAT STANDARD: Monitors PCS and PZR pressure to ensure less than 310 psig. l _ UNSAT l C_OMMENTS: l STEP 7. Notifies SS or logs that PRV-10438 failed to operate as required. STANDARD: Log entry made or SS notified. _ SAT _ UNSAT COMMENTS:
r JPM RO-2/SIM Pig) 6 of 12 STEP 4r Depress associated Reset Push Button to Clear LTOP trip indication. I STANDARDi LAssociated Reset Push Buttons are pushed. LTOP trip light remains lit. _ SAT. COMMENTSf _ UNSAT STEP 5 If PORV's don't property close when below their actuation se'ipoint, then close CRITICAL the associated PORV isolation Valve. STEP STANDARD: MO-1043A HS placed in CLOSE. Green light lit.
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Critical Step to isolate failed open PORV to stop PCS leakage. COMMENTS: _ UNSAT STEP 6 Continuously monitors Pressurizer Pressure to ensure LTOP limits are not exceeded. _ SAT ] STANDARD: Monitors PCS and PZR pressure to ensure less than 310 psig. _ UNSAT COMMENTS: STEP 7 Notifies SS or logs that PRV-10438 failed to operate as required. STANDARD:' Log entry made or SS notified. _ SAT l _ UNSAT
' COMMENTS:
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JPM RO-2/SIM Pagn 7 of 12 STEP 8 Notifies the SS that the actions of ONP 18 are complete. STANDARD ' SS Notified. _ SAT _ UNSAT COMMENTS i o END OF TASK TIME STOP;. 1 6
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. . Page 8 of 12 i JPM QUESTION # 1 +
REFERENCE ALLOWED: YES / yes no Question: Given the following conditions:
. The plant is cooling down toward SDC entry conditions. . Pressurizerlevelis 42% and stable. . Pressurizer pressure is 1450 psia. . The lowest Tm in Loop 1 indicates 434*F.
e The lowest Tw in Loop 2 indicates 428*F. What is required for PCS overpressure protection? Answer: ' LTOP must be in service with both PORVs armed and operable. CANDIDATE'S RESPONSE 1 i I 1 l Time: 5 min. KIA Ratin0: 000027.AK3.04 (2.8)
References:
Lesson Plan ASFE Tech Specs
JPM RO-2/EiM
,, , Pag) 9 of 12 ,
JPM QUESTION # 2 REFERENCE ALLOWED: / NO yes no Question: In the event of an excessive plant cooldown, the operator is directed to place the LTOP system in service. What is the basis for this action? Answer: Placing the LTOP system in service protects the PCS from brittie fracture concerns CANDIDATE'S RESPONSE l l I Time: 5 min.
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KIA Rating: 010.K4.03 (3.8)
References:
EOP 6.0 Background Document Step 11 l
JPM RO-2/SIM , . . P:gs 10 of 12,- , JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: __ / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: In the event of an excessive plant cooldown, the operator is directed to place the LTOP system in service. What is the basis for this action?
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, JPM RO-2/SIM Pags 11 of 12;,
JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Given me following conditions:
. The plant is cooling down toward SDC entry conditions. . Pressurizerlevelis 42% and stable. . Pressurizer pressure is 1450 psia. . The lowest Tm in Loop 1 indicates 434*F. . The lowest Ta in Loop 2 indicates 428"F.
What is required for PCS overpressure protection?
s-.f JPM RO-2/SIM Pag 912 of 12 I CANDIDATE CUE SHEET
. (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS: The plant is shutdown and Shutdown Cooling is lined up for operation. An instrument failure has caused an LTOP actuation.
~ 1NITIATING CUES:
The Shift Supervisor directs you to respond to the LTOP actuation using the guidance in ONP-18, Step 4.3. l
.A fa7e", /,$"
R E GIO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO-3/SIM Equalize Boron Concentration between the Shutdown Cooling System and the SIRWT CANP10 ATE EXAMINER l
ii' j JPM RO-3/SIM l
. >S Pags 2 of 12 ;
REGIONlli INITIAL LIC2NSE EXAMINATION I JOB PERFORMANCE MEASURE , { Task: Equalize Boron Concentration between Shutdown Cooling System and the SIRWT. Alternate Path: t
.Ms7IIdl#& held 2Mt2EAED MI N 3 M M E E L M Q C M &i;i.jpgga c; . J3 Facility JPM #.
t WM' YNI$iMAbEG?dI2EI2EGl&Ekht::N%b) px K/A Ratinals): 005K5.09 Task Standard: l Shutdown Cooling System boron concentration has been equalized with the SIRWF. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant _._ Perform X Simulate
References:
SOP-3 Validation Time: 15 min. Time Critical: No
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Candidate: Time Start : ! NAME Time Finish: { l Performance Ratina: SAf UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
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COMMENTS I i I i
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c.. JPM RO-3/SIM
, Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS: s e initialize to IC-3 . Use the ADVs to cooldown until cold leg temperatures are all below 300*F . Maintain SG levels using AFW flow . Place simulator in FREEZE .- After turnover and with the concurrence of the examiner, place the simulator in RUN.
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4 JCM KO-3/SIM Page 4 of 12 Tools /Eauipment/ Procedures Needed: Insure enough copies of SOP-3, Section 7.3.1, are available.
. READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indie'.s to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: The plant is shutdown and lined up for Shutdown Cooling. INITIATING CUES: The Shift Supervisor has directed you to equalize boron concentration of the SDC and the SIRWT using SOP-3, section 7.3.1, and BOTH LPSI pumps. The procedure is complete up to and including step 7.3.1.f.
m # g 1.< q, JPM RO-3/SIM Pags 5 of 12 START TIME: STEP 1 Start both LPSI pumps. CRITICAL STANDARD: STEP P-67A & B handswitch taken to start. Red lights lit. Crldcal Step is to provide flow so that baron concentrations can be equalized. _ SAT COMMENTS: _ UNSAT STEP 2 Open LPSI Injection valves. CRITICAL STANDARD: STEP Places HS's to OPEN for. .
. MO-3008 _,_, SAT - . MO-3010 e MO-3012 . MO-3014 - Red lights lit. UNSAT Crldcal Step is to properly align the systern so that boron concentradons can be equalized.
COMMENTE: i STEP 3 Open SIT Pressure Control Valves.- CRITICAL STANDAP,D: STEP PIC's placed in " MANUAL OPEN":
. PIC-0342 e PIC-0346 .__. SAT
} e PIC-0347 1 e PIC-0338 Valves indicate open on PIC.
~ UNSAT Cridcal Step is to property align the system so that boron concentradons can be equalized. l COMMENTS:-
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JPM RO-3/SIM l ,;,_ Pag 2 6 cf 12 f 1 STEP 4: After each LPSI pump has run for at least 10 minutes request Chr.mistry to sample the Safeity frjection System.
~ SAT SIANDARD- LPSI pumpe run until sample is taken and analyzed by Chemistry.
{ i CUE: The SS informs you that Chemistry reports the sampfe snalyred indicates boron concentration is greater than Shutdown Boron concentration. _ UNSAT NOTE: it is not necessary for the pumps to run the full time. Tno examiner may use time compression and inform the candidate that 10 minutes have elapsed. COMMENTS: SIEP,5: Stop LPSI pumps. CRITICAL STANDARD: STEP P-67A & B handswitch taken to stop. Green lights lit. Critical Step is to propetty align the system. _ SAT COMMENIS
,_.,UNSAT $TEP 6 Close and lock SIT Recirculation Containment isolation valves, STANDARD: Communicates with dedicated AO to close and lock: _ SAT e MV-ES3234 e MV-ES3234A e MV-ES3237 UNSAT l e MV-ES3235 CUE: AO reports that the SlT Recirculation Conta!nmont Isolation valves are closed and locked.
QQMMEN15
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JPM RO-3/SIM Prgs 7 of 12 STEP 7: Close LPSI Injection valves.' CRITICAL STEP STANDARD: Places HS's to CLOSE for:
. MO-3008 e MO-3010 e MO-3012
_ SAT e MO-3014 Green lights lit. _ UNSAT Critical Step !s to properly silgn the system. QQMMENTS:
$IEP$ Close SIT pressure control valves by placing the associated PIC in " MANUAL CRITICAL CLOSE." STEP STANDARD: PlC's placed in " MANUAL CLOSE": ,_ SAT.
e PIC-0342 ' e PIC-0346 e PIC-0347
PIC-0338 ___.UNSAT
' Valves indicate closed on PIC.
Critical Step is to properly align the system. COMMENTS END OF TAS\j l TIME STOP: I I i l
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JPM RO 3/SIM Pag) 8 of 12 JPM QUESTION # 1 REFERENCE ALLOWED: / NO yes no Question: During Refueling Operations a loss of Shutdown Cooling has occurred.
1) What are the immediate actions?

2) Why are these immediate actions taken?
Answer: 1) Suspend Refueling Operations.
2) Ensure adequate heat removalis available while performing refueling operations CANDIDATE'S RESPONSE Time: 5 min. '
K/A Rating: 000025.AK3.03 (3.9)
References:
ONP 17 and T/S 3.8.1
JPM RO-3/SIM Page 9 of 12 JPM QUESTION # 2 REFERENCE ALLOWED: YES / yes no j Question: During a plant cooldown, preparations are being made to place the Shutdown Cooling System in operation. One of the preparations. includes equalizing the boron concentration between the SIRWT and the SDC System. { i Why must PCS pressure be maintained above 300 psia during this evolution? Answer: Prevent injecting potentially diluted SDC water into the PCS. (Ensure injection check valves remain closed). CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 005K4.02 (3.2)
References:
ASCC Lesson Plan i I l
JPM RO-3/SIM -+ Paga 10 of 12 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETlON OF ANSWER) Question: During a plant cooldown, preparations are being made to place the Shutdown Cooling System in operation. One of the preparations includes equalizing the boron concentration between the S!RWT and the SDC System. Why must PCS pressure be maintained above 300 psia during this evolution? 1 1
JPM RO-3/SIM Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON CObPLETION OF ANSW Question: During Refueling Operations a loss of Shutdown Cooling has occurred.
1) What are the immediate actions?

2) Why are these immediate actions taken?
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4 JPM RO 3/SIM' l Prgs 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS 1 The plant is shutdown and lined up for Shutdown Cooling. INITIATING CUES:
i The Shift Supervisor has directed you to equalize boron concentration of the SDC and the SIRWT i using SOP-3, section 7.3.1, and BOTH LPSI pumps. The procedure is complete.up.to and including step 7.3.1.f.
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. faIe"SA?" R E G IO N 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO-4/SIM Verify Containment Spray Response to Recirculation Actuation Signal 1
' CANDIDATE EXAMINER 8
JPM RO-4/SIM Paga 2 of 12 REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE
~ Task: I l
Verify Containment Spray Response to a Recirculation Actuation Signal Alternate Path- l 1
'}Q.: l' } ,
I'f:f Facility JPM #,1 - ENRXP.N;M.MMENRE23f!2122i?R!.LinN'SdS?WissrindM?M i K/A Ratinals): 026.A3.01 Task Standard: Respond to a RAS and take actons to place Containment Spray in the correct lineup. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate
References:
EOP-4 Validation Time: 15 min. Time Critical: No
==-- ======-----=========-----====_________=======-=========---=================
Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: _ . I NAME SIGNATURE DATE
==----====.________=.___ =========____e_s26=========________=============____======
COMMENTS i i i A- - i
e JPM RO4/SIM Page 3 of 12 fB&lLATOR OPERATOR INSTRUCTIONS: e Initialize the simulator to IC-11, e MALF RC-04 to value = 1.0 e Trip both MFPs and ramp controllers to MIN speed e Stop al.' PCPs e Close CV-2001 and 2009 e When SIRWT level reaches 2%, stop all Containment Spray Pumps and close discharge isolation valves o' Enter MALF to prevent start of Spray Pump P-54A e When previous step performed, place simulator in FREEZE 1 l l I ___ )
c:;. 4.. JPM RO4/SIM Paga 4 of 12 Tools /Eauipment/ Procedures Needed: Ensure enough copies of EOP4.0 are available. READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, factuding any required communications. I will provide initiating cues and reports on other actions when directed by you. Enswe you indicate to me when you understand your assigried task. To indicats that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: - A LOCA has occurred. RAS has initiated as designed. EOP 4.0 is in use at step 47. HPSI pumps P-66 A & B are operating. INITIATING CUES:
. The Shift Supemisor directs you to ensure Containment Spray is properly aligned for RAS operation. The Shift Supervisor has determined that two Containment Spray pumps are required for spray and to provide subcooled water to the HPSI pumps. You are to start by placing the right channel pump in service first.
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JPM RO-4/SIM Paga 5 of 12 h START TIME: STEP 1. Refer to EOP-4.0 Step 47. STANDARD: __ SAT COMMENTS: __,UNSAT STEP 2 Open one Containment Spray valve. CRITICAL STEP STANDARD: Opens CV-3002, red light lit. _ SAT Critical step is aligning system forproper operation. NOTE: EOP 4.0 step 47 is in table format. The candidate may operate the CS valves and pumps by starting with either the A or B set of pumps and valves. __,UNSAT NOTE: Alarm EK-1377, CONTAINMENT SPRAY VALVE OPEN, is an expected alarm. v0MMENTS: STEP 3 Attempts to start Containment' Spray Pump P-54A. __, SAT STANDARD: Places P-54A HS to Start. Green light remains lit. CUE: If notified, the Shift Supervisor directs the candidate to start the other two CS Pumps. ,__UNSAT COMMENTS: l
JPM RO-4'SIM Pcg3 6 cf 12 STEP 4:- Start a Containment Spray Pump CRITICAL STANDARD: Starts P-54B or P-54C Red light lit.
.___ SAT Critical step is providing subcooled water for the HPSIpumps.
COMMENTS: __ UNSAT SJffj: Start a second Containment Spray Pump. CRITICAL STANDARD: Starts remaining CS Pump. Red light lit.
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Critical step is providing subcooled water for the HPSIpumps. COMMEN.IS: ___.UNSAT STEP 6 Open second Containment Spray valve. CRITICAL STEP STANDARD: Opens CV-3001. Red light lit. Critical step is sligning system for proper operation. __ SAT COMMENTS:
,__UNSAT STEP 7: Open the first HPSI Subcooling Valve CRITICAL STEP STANDARD: Obtains Key 152 or 153. Opens CV-3070 or 3071. Red light lit.
Critical step is providing subcooled water for the HPSIpumps.
~ SAT COMMENTS:
__UNSAT i
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4
JPM RO-4/SIM Pegg 7 of12 1 STEP 8 Open the second HPSI Subcooling vt Ive.
CRITICAL
- STANDARD: STEP Obtains key 152 or 153._ Opens remaining HPSI Subcooling valve Red light lit. ,__ SAT Critical step is pmviding subcooled water for the HPSIpumps.
___UNSAT COMMENTS: STEP 9 Report the completion of step 47. STANDARD: Shift supervisor notified of completion and, if not done at step 4, that P-54 A inpped. - SAT _ UNSAT COMMENTS: END OF TASK l TIME STOP: I l l l
1 JPM RO-4/SIM 1 Page 8 of 12 JPM QUESTION # 1 ItEFERENCE ALLOWED: / NO yes no Question: Containment Press,tre is 5.2 psig and increasing.
1) What automatic avion enhances the spray water's ability to remove heat in the Containment atmospt.ere?

2) What signal (s) must be present for this feature to activate?
Answer: 1) CV-0937 and CV-0938 (Service Water) open to the Shutdown Cooling Heat Exchangers. - (Service Water aligned to SDC Heat Exchangers required for full credit. Valve numbers are not required)
2) SIAS and CHP CANDIDATE'S RESPONSE Time: 5 min.
K/A Rating: 026 K4.04 (3.7)
References:
Lesson Plan ASCA section 6.6
JPM RO-4/SIM
, Page 9 of 12
JPM QUESTION # 2 REFERENCE ALLOWED: YES /
yes no Question: Given the following conditions:
A Main Steam Line Break has occurred inside containment.

Left channel power has been lost.
What combination of Containment Spray Pumps and/or Containment Air Coolers is available to limit Containment pressure below design limits? Answer: Three (3) Containment Air Coolers AND one (1) Containment Spray Pump CANDIDATE'S RESPONSE i Time: 5 min. K/A Rating: 0026.K1.02 (4.1)
References:
ONP-7.1 Attachment 2, page 2, EOP 4.0 step 47, and Lesson Plan ASHC 4.5
JPM RO-4/SIM
g. , Page 10 gf 12 s-
- o JPM QUESTION # 2 CANDIDATE COPY /.
REFERENCE ALLOWED: YES / i yes no .I (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Given the following conditions:
.. A Main Steam Line Break has occurred inside containment.
Left channel power has been lost.
What combination of Containment Spray Pumps and/or Containment Air Coolers is available to limit Containment pressure below design limits?
1 JPM RO-4/SIM Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) I Question: Containment Pressure is 5.2 psig and increasing.
1) What automatic action enhances the spray water's ability to remove heat in the Containment atmosphere?

2) 'What signal (s) must be present for this feature to activate?
JPM RO-4/SIM Page 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS: A LOCA has occurred. RAS has initiated as designed. EOP 4.0 is in use at step 47. HPSI pumps P-66 A & B are operating. INITIATING CUES: The Shift Supervisor directs you to ensure Containment Spray is properly aligned for RAS operation. The Shift Supervisor has determined that two Containment Spray pumps are required for spray and to provide subcooled water to the HPSI pumps. You are to start by placing the right channel pump in service first.
s' fa e*1Sr$$" R E GIO N 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO-5/SIM l insert and Remove a Reactor Protection Channel Trip Bypass CANDIDATE EXAMINER i l { I l h A
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% JPM RO-5/SIM Pagn 2 of 12 1
REGION 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l Task: l Irisert hi'd remove a Reactor Protection Trip bypass ) l Alternate Path: i I fl624M7x03W2?adgE&aIHK012:sR!Et#s$iin6Enfsagh22 _chnSgra l Facility JPM #: IE7ATMWEE@@Wh$@ilRifE%7258I: 3dit EEERj55GIMik L C*?CCyM4F}4 ) K/A Ratinals): 004A2.18 Task Standard: A Reactor Protection Channelis placed in bypass and retumed to service. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate
References:
Validation Time: 15 min. Time Critical: No
========================._ __ _====================================================
l ( Candidate: Time Start : NAME Time Finish: 1 Performance Ratino: SAT UNSAT Question Grade _ Performance Time l 1 ( E.xaminer: / i NAME SIGNATURE DATE {
=============================s..__ ___ _===========================================
COMMENTS 1
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4. JPM RO-5/SIM i Pag) 3 of 12 j l
SIMULATOR OPERATOR INSTRUCTIONS: e initialize to IC-11 i t.
*4 JPM RO-5/SIM f Paga 4 of 12 1 Tools /Eauipment! Procedures Needed:
Ensure enough copies of SOP-36 are available. READ TO OPERATOR DIRECTION TO TRAINEE:
-u I will explain the initial conditions, and state the task to be performed. All control room steps shall be performcd for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indL ate to me when you i
understand your assigned task. To indicate that you have completed your assigned task return the handout sheet i provided you. INITIAL CONDITIONS: The plant is stable at 100% power. I & C has requested that Channel A of the Pressurizer High Pressure Reactor Trip be placed in bypass and then retumed to service for observation to verify as found values in a Tech Spec Test. INITIATING CUES: The Shift Supervisor directs you to utilize SOP-36, section 7.4.2, place Channel A ef the Pressurizer High Pressure Reactor Trip in bypass and after I & C has gathered data, retum it to service. i I i
s-JPM RO-5/SIM Paga 5 of 12 START TIME: STEP if Locate and refer to SOP-36, section 7.4.2
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STANDARD: SOP-36 section 7.4.2 referenced. MMEN_T3: . __,. UNSAT STEP 2 - Obtain proper.RPS Trip Unit Bypass key from Shift Supervisor. STANDARD: Bypass key obtained from Shift Supervisor for High Pressurizer Pressure Trip channel. _ SAT _,_ UNSAT COMMENTS STEP 3 Insert Bypass Key above affected RPS Trip Unit. CRITICAL , STEP l STANDARD Bypass Key inserted above "A" Channel High Pressurizer Pressure Trip (PA-0102 AH). _ SAT Critical step is to select the correct channel. The key must be Inserted to accompIlsh ' task.
- UNSAT COMMENTS .
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'4.
JPM RO-5/SIM
% ~ Paga 6 of12 - -.. 3 STEP 4: Turn key 90' c.ockwise. CRITICA1.
STEP STANDARD Key turned 90' clockwisch Criticalstep is to rotate the key to bypass the channel. .__ SAT COMMENTS _,UNSAT ! f STEP 5 Verify that yellow light above Bypass Keyswitch illuminates. STANDARD Verify yellowlight lit. __ SAT COMMENTS __UNSAT STEP 6 Notify Shift Supervisor that RPS Trip Unit has been bypassed and log evolution in the Control Room logbooks __ SAT STANDARD Shift Superviser notified and evolution logged in appropriate logbook, CUE: Acknowledge report and inform candidate that I & C has completed data collection, and _,,,,, UNSAT directs the candidate to retum the channel to service. COMMENTS STEP 7: - When bypass is no longer required, tum affected RPS Unit Bypass Keyswitch CRITICAL '
- 90' counterclockwise. STEP STANDARD Keyswitch for "A" Channel High Pressurizer Pressure Trip Bypass turned . counterclockwise. ,__. SAT Critical step is to select the correct channel. The key must be inserted to accompIlsh task. __UNSAT COMMENTS'
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' 4 T JPM RO-5/SIM Pags 7 of 12 . I ,
STEP 8 ' Verify that yellow light above Bypass Keyswitc.. extinguishes. STANDARD: - Verify yellow light not lit. _ SAT COMMENTS:
- ^
ST P 9 Remove key and return to Shift Supervisor. STANDARD: Key removed and returned to Shift Supervisor. _ SAT COMMENTS:
-UNSAT-STEP 10: Notify Shift Supervisor that RPS Trip Unit has been retumed to' service and log evolubon in Control Room logbook.
STANDARD: _ SAT Shift Supervisor notified and proper log entiy made. _ UNSAT COMMENTS: END OF TASK TIME STOP: i
JPM RO-5/SIM Page 8 of 12 JPM QUESTION # 1 REFERENCE ALLOWED: YES _ / yes no Question: The plant is operating at 50% power. RP3 'A' channel Variable High Power Trip unit is bypassed due to a failed power supply.
. A channel functional check of RPS 'D' channel VHP indicates a failure to trip at the setpoint.
What action (s) is(are) required by Tech Specs within the next hour? l l 1 Answer: Place the 'A' or 'D' trip unit in a tripped condition after assuring that the other trip unit is in bypass j CANDIDATE'S RESPONSE i I I Time: 5 min. K/A Rating: 012.K4.02 (3.9)
References:
Tech Spec Table 3.17.1
)
r JPM RO-5/SIM Pags 9 of 12 i JPM QUESTION # 2 REFERENCE ALLOWED: / NO yes no Question: With the plant at full power, a fault in the grid results in the main generator breakers opening The turbine protection system fails to generate a RPS trip.
1) What RPS actuation is designed to protect for this event?

2) Whatis the setpoint?
Answer: 1) Pressurizer High Pressure.
2) 2235 psia CANDIDATE'S RESPONSE s- ,
Time: 5 min. KIA Rating: 012.K4.04 (3.1) Re'erences: FSAR chapter 7.0, Tech Spec Table 3.17.1 Basis, ARP-21 Rack B-4 i
JPM RO-5/SIM Pago 10 of 12 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED,TO EXAMINER UPON COMPLETION OF ANSWER) i 1 Question: With the plant at full power, a fault in the grid results in the main generator breakers opening. The j turbine protection system fails to generate a RPS trip.
1) What RPS actuation is designed to protect for this event?

2) What is the setpoint?
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JPM RO-5/SIM Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: _YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: The plant is operating at 50% power, i e RPS 'A' channel Variable High Power Trip unit is bypassed due to a failed power supply. A channel functional check of RPS 'D' channel VHP indicates a failure to trip at the setpoint. What action (s) is(are) required by Tech Specs witNo the next hour? l i
JPM RO 5/SIM = Pags 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS: The plant is stable at 100% power. l&C has requested that Channel A of the Pressurizer High Pressure Reactor Trip be placed in bypass and then returned to service for observation to verify as found values in a Tech Spec Test. INITIATING CUES:'
' The Shift Supervisor directs you to utilize' SOP-36, section i.4.2, place Channel A of the Pressurizer High Pressure Reactor Trip in bypass and after I&C has gathered data, return it to service.
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a g JPM RO-6/SIM
g Page 1 of 13 R E GIO N lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE <
JPM RO-6/SIM l1 Shift Operating CCW Pumps ! I l CANDIDATE EXAMINER 4 1
0 4 O JPM RO-6/SIM Page 2 of 13 REGIONlli INITIAL' LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Shift operating CCW pumps. Alternate Path:
@5ECMAdimNjBldithdMvhili"startedkThs third CCW pump must be started, Facility JPM #:
Yh W W hi13 W W 6C M ER M 72 5J?bTii&:Did?ti2i"5$nW%23' W: lll- . , , K/A Ratinafs): 008 Task Standard: Two CCW pumps will be operating per ONP-6.2 and SOP-16. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate
References:
Validation Time: 15 min. Time Critical: No
---- ============--- - ._;;========================================================
Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time gxaminer; / i NAME SIGNATURE DA'E i
=============s_____-- -________================.-- ===============================
l 1 i COMMENTS l l
e:
4 JPM RO-6/SIM
, Paga 3 of 13 SIMULATOR OPERATOR INSTRUOTIONS:
1
. . Initialize to IC-11 : . S6 cure a running CCW Pump so only P-52A is running e
Place CCW Pump P-52C in STANDBY (leave P-52B off and NOT in standby) e MALF CCO2 for CCW Pump P-528 to active
-e Place simulatorin FREEZE l )
L. - , . . . . . _ . . . . . .
g ;: ) JPM RO-6/SIM _ Pagm 4 of 13 Tools /Eauipment/ Procedures Needed: g 1 Ensure enough copies of SOP-16 and ONP-6.2 is available. READ TO OPERATOli DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task retum the handout sheet I provided you. INITIAL CONDITIONS: CCW Pump P-52A is running with P-52C in standby. P-52A has indications of a high vibration and is to be secured. INITIATING CUES: The Shift Supervisor directs you to shift operating CCW pumps per SOP 16, section 7.3.3. P-528 is to be started and P-52C is to be left in standby, P-52A is to be used for emergency use only.
p-- 4 4 JPM RO-6/SIM , , Pags 5 of 13 START TIME: STEP 1: Refer to SOP-16, section 7.3.3 to shift operating CCW pumps.
. fiTANDARD: SOP-16 referred to. _._, SAT ' COMMENTS:
_ UNSAT STEP 2 Ensure OPEN CCW pump P-52f3 suction and discharge valves. STANDARD: Contacts AO to ensure MV-CC920 and MV-CC942 OPEN. _ SAT CUE: AO reports MV-CC9?O and MV-CC942 OPEN _ UNSAT. QOMMENTS: STEP 3 Operate CCW Pump P-52B casing vent petcock to vent air from pump. STANDARD: Contacts AO to cycle MV-CC557 open and closed. _ SAT CUE: AO reports MV-CC557 cycled open and closed COMMENTS: _ UNSAT
JPM RO-6/SIM t* , Paga 6 of 13 STEP 4: Verify both CCW Heat Exchangers are in operation. STANDARD: Verifies from initial conditions or asks SS for report. _,_ SAT CUE: If asked, SS reports that both CCW Heat Exchangers are in operation. COMMENTS:' ,__UNSAT STEP 5 Start selected CCW pump. STANDARD: When started, P-52B fails to start. Red light out. _ SAT COMMENTS _ UNSAT STEP 6 Refers to ARP-7, Window 67 and notifies Shift Supervisor of CCW pump trip and need to reference ONP 6.2. _ SAT STANDARD SS Notified. Cue: The SS directs the candidate to start CCW pump P-52C and stop P-52B, leaving NO _ UNSAT pump in standby, utilizing SOP-16, section 7.3.3. COMMENTS: STEP 7- Ensure OPEN CCW pump P-52C suction and dischage valves. STANDARD: Contacts AO to ensure MV-CC921 and MV-CC945 OPEN. _ SAT CUE: AO reports MV-CC921 and MV-CC945 OPEN _ UNSAT COMMENTS:
JPM RO-6/SIM < Paga 7 of 13
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STEP 8 Operate CCW Pump P-52C casing vent petcock to vent air from pump. CRITICAL STEP i STANDARD: Contacts AO to cycle MV-CC558 open and closed. l SAT CUE: AO reports MV-CC558 cycled open and closed., f COMMENTS: _ UNSAT STEP 9 Verify both CCW Heat Exchangers are in operation. STANDARD:- Verifies from initial conditions or asks SS for report. _ SAT CUE: If asked, SS reports that both CCW Heat Exchangers are in operation. NOTE: This was determined previously, so it may not be performed again at this time. _ UNSAT COMMENTS: STEP 10: _ Start selected CCW pump. CRITICAL STEP-STANDARQ: P-52C starts. Red light lit.
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SAT Criticalstep to estabilsh flow with P 52C to allow stopping P-52A. COMMENTS: _,,.UNSAT STEP 11: Ensure CCW heat exchanger AP is less than or equal to the maximum allowable AP and operating at optimum HX AP. _ SAT STANDARD: Directs AO to determine that CCW Heat Exchanger AP is between 12 and 16 ) psid and less than 24 psid for E-54A and less than 20.9 psid for E-54B.
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UNSAT CUE: AO reports CCW Heat Exchanger APs are 15 psid for E-54A and 14 psid for E-548. l COMMENTS: 4
JPM RO-6/SIM Pags 8 of 13 -
, STEP 12: Stop P-52A per section 7.3.5. CRITICAL ^
STEP STANDARD: ' - P-52A tumed off. Green light lit.
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CrWcalstep to stop P-52A due to potentialfailure ofpump. . +- NOTE: If asked again, cepeat that P-52A is NOT to be placed in Standby. __.,UNSAT COMMENTS
- STEP 1'3: Ensure CCW heat exchanger AP is less than or equal to the maximum allowable AP and operating at optimum HX AP.
_,_ SAT STANDARD:' Directs AO to determine that CCW Heat Exchanger AP is between 6 and 8 paid and less than 24 paid for E-54A and less than 20.9 paid for E-548. __ UNSAT CUE: AO reports CCW Heat Exchanger APs are 7 psid for E-54A and 6.5 psid for E-548. COMMENTS END OF TASK TIME STOP: ,a
JPM RO-6/SIM Page 9 of 13 JPM QUESTION # 1 REFERENCE ALLOWED: YES / _, yes no l Question: The heat load a given component places on the CCW System varies according to the operating condition of the plant. What is the LARGEST heat load on the CCW System I when the plant is in the post DBA (post RAS) condition? Answer: Shutdown cooling heat exchangers i CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 008.K1.02 (3.3)
References:
Lesson Plan ASCA i 1
I i JPM RO-6/SIM Page 10 of 13 l JPM QUESTION # 2 l REFERENCE ALLOWED: / NO yes no Question: For each of the following loads, indicate whether a leak in the heat exchanger will result in flow into, or out of, the CCW system. a) CRDM Seals
- b) Radwaste Evaporators c) SDC Heat Exchanger during Containmerit Spray Operations d) . Letdown Heat Exchanger during refueling operations )
Answer: a) into CCW b) Out of CCW c) Into CCW d) Out of CCW (3 of 4 required for full credit) CANDIDATE'S RESPONSE l I l l Time: 5 min. K/A Rating: 008K1.02 (3.3)
References:
LP ASCA Section 6.7.b Obj. 4.8, page 23 l l i l l
E JPM RO-6/SIM Page 11 of 13 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: For each of the following loads, indicate whether a leak in the heat exchanger will result in flow into, or out of, the CCW system. a) CRDM Seals b) Radwaste Evaporators c) SDC Heat Exchanger during Containment Spray Operations d) Letdown Heat Exchanger during refueling operations m_m
JPM RO-6/SIM Page 12 of 13 { JPM QUESTION # 1 I CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: The heat load a given component places on the CCW System varies according to the operating condition of the plant. What is the LARGEST heat load on the CCW System when the plant is in the post DBA (post RAS) condition? { i 4 l l 1 l l
v: JPM RO-6/SIM
Ptge 13 of 13 CANDIDATE CUE SHEET
. (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) )
INITIAL CONDITIONS: I
' CCW Pump P-52A is running with P-52C in standby. P-52A has indications of a high vibration l and is to be secured. 1 INITIATING CUES:
The Shift Supervisor directs you to shift operating CCW pumps per SOP 16, section 7. 3.3. P-528 is to be started and P-52C is to be left in standby. P-52A is to be used for emergency use only. 1
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.> ?a"e"$!N" R E G IO N 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO-7/CR Transfer Pressurizer Level Control from Manual to Cascade CANDIDATE EXAMINER l
.>- JPM RO-7/CR
+ Page 2 of 12 REGIONlli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Transfer the Pressurizer Level Control System to the CASCADE mode of operation from MANUAL. Alternato Path:
+w . g megc;ugp;qfg,yqymy yy;y w;p9qgg g =uw.
Facility JPM #:
$$i2f E E 5f0$f15$fMWiE6EMRk KIA Ratina(s):
011 A3.03 Task Standard: The Pressurizer level Control System is operating in the CASCADE mode of operation. Preferred Evaluation Location: Preferred Evaluation Method: Simulator in-Plant X Perform Simulate X
References:
SOP-1 Validation Time: 15 min. Time Critical: No
===__________=================================-- _== -
____s;_____;;============== Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
===============sz=================,=___.__. --- __e=============== - r;=========
COMMENTS
f 9- JPM RO-7/CR Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS: 1 e.. = Initialize to IC-11
- el Pk J LIC-0101 A in MANUAL ~- +- Adjust AUTO setpoint of LIC-0101A to 42% .
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JPM RO-7/CR Page 4 of 12 Tools /Eauloment/ Procedures Needed: If Control Room procedures are marked up for this JPM ensure the candidate arranges for replacement copies to be made. READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task ic be performed. All control room steps shall be performed for this JPM, including any required commuaications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you - understand your assigned task. To indicate that you have completed your assigned task return the handout sheet i provided you. INITIAL CONDITIONS: The plant is operating at 100% power. Pressurizer Level Control is in the MANUAL mode on LIC-0101 A, with the AUTO setpoint left at 42% to allow l&C to verify controller setpoints. INITIATING CUES: The Shift Supervisor directs you to place the Pressurizer Level Control System in the CASCADE mode of operation, on LIC-0101A. -
._ + N> 0 JPM RO-7/CR l 7 Pags 5 of 12 l
- START TIME: -
STEP 1 Refers to SOP-1, section 7.3.1.e. j STANDARD: SOP-1;section 7.3.1.e referenced. _ SAT
- COMMENTS:
_ UNSAT STEP 2 Using the raise / lower pushbuttons, adjust selected controller to match a:tual
- Pressurizer level.
STANDARD: The blue pointer on LIC-0101 A is set to 57%. (Actual PZR level is 57%) _,,UNSAT COMycGNTS: STEP 3 Depress the 'A" pushbutton on the selected controller. CR;TICAL STEP STANDARD: The "A" pushbutton is pushed on LIC-0101 A. Cridcal step is to set the controller up to allow transfer to cascade. _ SAT
' COMMENTS: _ UNSAT l
l 1 l. L k
f . .

s Vl;1f .
JPM RO-7/CR Page 6 of 12 1 ! STEP 4: Ensure LIC-0101 A in auto.
- SAT
l. STANDARD:. "A" light on LIC-0101 A is verified lit.
__ UNSAT COMMENTS l
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STEP 5 . Verify expected T. signal available from selected T /Twcontroller using TYT-0100, TYT-0200, or TI-0110. STANDARD T. signal verified correct using TYT-0100, T(T-0200, or TI-0110.
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COMMENTS STEP 6 - Adjust selected controller setpoint to the Pressurizer level setpoint determined by present T. using Attachment 3, T. (F) Pressurizer Level Program. __ SAT STANDARD LIC-0101 A blue pointer set at 57%. __ UNSAT NOTE: Candidate may not consult attachment 3 since 57% is the normal 100% power setting. COMMENTS I 6 u...
((: JPM RO-7/CR Page 7 of 12 STEP 7:- Depress the "C" pushbutton on the selected cordroller. CRITICAL
~ ' STANDARD: The "C" pushbutton is depressed on LIC-0101 A. . Critical step is to s.asure cascade operation by selecting the correct mode. ~ SAT
_ UNSAT COMMENTS: EjjQ.QF TASK TIME STOP:
JPM RO-7/CR . Page 8 of 12 JPM QUESTION # 1 REFERENCE ALLOWED: YES / yes no Question: Given the following conditions:
. The plant is at 100%.
Pressurizer Level control in CASCADE from LIC-0101 A. Pressurizer Pressure control is in' AUTO using PIC-0101B (Channel 'B').
. A loss of Y-10 occurs.
Predict the response of each of the following: 1)- Pressurizer variable heaters
2) Pressurizer spray valves

3) Pressurizerlevel Answer: 1) Minimum output

2) Open to control pressure

3) Continuously rises CANDIDATE'S REfiPONSE !
Time: 5 min. K/A Rating: 011 A2.11 (3.4)
References:
Lesson Plan ASFD sections 6.3 and 6.4, Lesson Plan ASFE Objective 4.6 ONP-24.1
JPM RO-7/CR l Pag 3 9 of 12 JPM QUESTION # 2 l REFERENCE ALLOWED: / NO yes no
' Question: SOP-1 contains a note to the operator to maintain PZR level < 62.8%
What three (3) design basis does compliance with this note ensure are met? Answer: The calculated PZR level program ensures:
Sufficient steam volume to allow for an insurge that won't reach the safety valve I nozzles.
.. Overall PCS volume is minimized to reduce peak containment pressure during a LOCA e Level sufficient to prevent uncovery of the pressurizer heaters following a reactor trip. ;
i (2/3 required for full credit) ! l CANDIDATE'S RESPONSE l l I l Time: 5 min. K/A Rating: 011.K5.12 (3.3) l
References:
FSAR 4.3.7 Lesson Plan ASFD section 6.7 and objective 4.1 l
JPM RO-7/CR Page 10 0f 12 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: SOP-1 contains a note to the operator to maintain PZR level < 62.8%. What three (3) design basis does compliance with this note ensure are met? l
C JPM RO-7/CR Page 11 of 12 l I JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Given the following conditions:
. The plant is at 100%.
Pressurizer Level control in CASCADE from LIC-0101 A. Pressurizer Pressure controlis in AUTO using PIC-0101B (Channel 'B').
. A loss of Y-10 occurs.
Predict the response of each of the following:
1) Pressurizer variable heaters

2) Pressurizer spray valves

3) Pressurizerlevel
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i i
,. } ' JPM RO-7/CR Page 12 of 12 1 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS: The plant is operating at 100% power. Pressurizer Level Control is in the MANUAL mode on LIC-0101 A, with the AUTO setpoint left at 42% to allow l&C to verify controller setpoints. INITIATING CUESi The Shift Supervisor directs you to place the Pressurizer Level Control system in the CASCADE mode of operation, on LIC-0101A.
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1
.5 fylfyT REGION lli INITIAL LICENSE EXAMINATION 1 JOB PERFORMANCE MEASURE !
JPM RO-8/ PLANT , { l Manually Align Y-01 to Emergency Power Supply CANDIDATE EXAMINER i
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'. 'y - JPM RO-8/ PLT l Page 2 of 13 REGIONlil i !?nTIAL LICENSE EXAMINATION l JOB PERFORMANCE MEASURE 13thi Transfer a vital (120V) instrument power supply.
Alternate Path: M M'SI4%$))fri0iClia'cidiidil2NJ3 @B j Facility JPM #:
. Y$u? MI51$NIi?INlbEliENIEti$ikONU%l#w n,, at. . l l
K/A Ratinois): l
.062 A2.03 2.9/3.4 1
Task Standard: ' Instrument bus Y-01 is powered from it emergency power source. Preferred Evaluation Location: Preferred Evaluation Method: Simulator - In-Plant X Peiform Simulate X 1 SOP 30, Rev. 23 I 1 1 Validation Time: 10 min. Time Critical: No
============- =__=======s ========_____.___2___========================= ===
1 Candidate: Time Start: NAME Time Finish: f 1 1 Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
======_____e============ - =- =______=========================
COMMENTS l 1
4 f JPM RO-8/ PLT Pagn 3 of 13 Tools /Eauloment/ Procedures Needed: Ensure copies of SOP-30 are available. Ensure SOP 30, Attachment 1, (Attachment 1 to this JPM) is available. Stopwatch or equivalent to measure 30 seconds. READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To ind:cate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:
. Plant is in Cold Shutdown for refueling. . Work is scheduled for breaker 52-145 this shift, requiring Instrument AC Bus Y-01 to be fed from MCC-2.
The Load Connected to Normal (MCC-1) light is lit. The Load Connected to Emergency (MCC-2) lightis notlit. INITIATING CUES: The Shift Supervisor directs you to manually align Instrument AC Bus YO1 to the Emergency power supply (MCC-2) per SOP-30, Section 7.6.2. 4
4 - JPM SRO-8/ PLY .' Page 4 of 13 START TIME:
. ElfE_1:- Locate the procedure to manually align instrument AC Bus YO1 to Normal or Emergency Power Supply.
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STANDARD: SOP 30, Section 7.6.2 located. COMMENTS: _ UNSAT STEP 2 Remove screws and open door to Y-50. CRITICAL STEP STANDARD: Screws removed and door opened. Cridcal Step: The cover must be removed to access the contmis. _ SAT CAUTION: When operator simulates removing the screws and opening the door to Y-50, provide the operator Att.1 of this JPM to use to explain how to perform _UNSAT steps Do not allow operator to remove screws or open door. COMMENTS: STEP 3 Check indicating light lit for desired power source. CRITICAL STEP STANDARD: Operator checks Emergency Source Available light. Light not lit. _ SAT Critical Step: If the light is not checked the Operstor could transfer the bus to a deenergizedpowersource. CUE: Emergency Source Available light is NOT lit. __ UNSAT COMMENTS: 1 1
)
JPM RO-8/ PLT Pega 5 of 13 STEP 4: if desired power source light is NOT lighted. THEN: Do not attempt transfer. CRITICAL STEP
- SAT STANDARD: Attempting to transfer power without the emergency power source lit will result in a loss of bus YOi, Critical Step: Failure to ensure a power supply available will result in a loss of the _ UNSAT instrument bus.
COMMENTS: STEP 5 Check bulb and replace if necessary , SAT STANDARD: Operator checks bulb and determines that replacement is not necessary. CUE: The light bulb is functional. _ UNSAT COMMENTS: STEP 6 Check closed appropriate emergency source breaker 52-236. CRITICAL STEP STANDARD: Operator checks breaker 52-236, and after determining that it is open, closes it. (May call SS for permission prior to closing breaker.) _ SAT Critical Step: The breaker must be closed for successful completion of the task. CUE: When the Operator checks breaker 52-236, provide cue that the breaker is in the OFF ~ UNSAT position. If Operator calls the SS for direction regarding 52-236, direct closure of the breaker. COMMENTS:
JPM RO-8/ PLT Page 6 of 13 STEP 7: if indicating light cannot be restored, then notify Shift Supervisor. CRITICAL STEP STANDARD: Operator rechecks the Emergency Source available light and determines that it is LIT. __, SAT I Critical Step; The operator must verify power is available before continuing with the task. CUE: Emergency Source Available light is LIT. - UNSAT COMMENTS:
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STEP _6 Refer to table and determine the t - t step to perform. CRITICAL STEP STANDARD: Operator reviews steps 7.6.2.e and f and determines step 7.6.2.e as next step.
' ~
Critical Step: The Operator must determine the correct procedure flowpath to continue. COMMENTS: _ UNSAT STEP 9 Hold Transfer Test Switch to " TEST" position for 15 seconds. CRITICAL STEP STANDARD: Transfer test switch held in " TEST" for 15 seconds.
,_,_, SAT Critical Step: Fifteen seconds is required for the Y-50 to transfer.
CUE: After 5 seconds of holding transfer test switch, inform the Operator that the " LOAD CONNECTED TO EMERGENCY" light is lit and " LOAD CONNECTED TO NORMAL" _ UNSAT light is NOT lit. COMMENTS:
74 - JPM RO-8/ PLT Pagn 7 of 13 1 STEP 10: - Release Transfer Test switch CRITICAL STEP STANDARD: Transfer Test switch released. Critical Step: The transfer test switch must be released to accompIlsh the next steps in l 30 sec. .__ SAT
NOTE: For the next step the 30 second limit may be exceeded if simulated due to increased time necessary to describe actions.
_ UNSAT Note: Operator may start over at JPM Step 9 if 30 seconds is exceeded. COMMENTS: STEP 11: Operate and hold TGL-1 Lock Release Switch in the direction indicated for CRITICAL
Emergency Source Available " light. STEP STANDARD: TGL-1 Lock Release Switch operated and held toward the " Emergency SAT Source Available" light. (Must be completed within 30 seconds of completion of Step 10.)
~ UNSAT Critical Step: The Lock Release switch must be operatedin the correct direction to ensure the next stepis successful.
COMMENTS: STEP 12: Place the Bypass Handle to the position indicated for the desired power CRITICAL source. STEP STANDARD: Bypass Handle placed in the " Emergency" position whiie holding the TGL-1 Lock Release Switch toward the " Emergency Source Available" light. (Must -SAT be completed within 30 seconds of completion of step 10.) Cdtical Step: The Bypass Handle must be correctly aligned to ensure continued poweris _ UNSAT available. CUE: If 30 seconds elapse before the Bypass Hande is placed in the " EMERGENCY" position, provide the cue that the " Load Connected to Normal" light has illuminated and the
" Load Connected to Emergency" light has gone out.
COMMENTS:
JPM RO-G/ PLT Pgge 8 of 13 STEP 13: Ensure Bypass Handle is fully engaged into desired power source position. CRITICAL STEP STANDARD: Operator ensures Bypass Handle is vertical, fully engaged into the
" Emergency" position, ~
Critical Step: Ensuring the Bypass handle is in the full verticalposition verifies the handleis lockedin place. CUE: The Bypass Handle is vertical pointing to " Emergency" and engaged.
.__.UNSAT COMMENTS:
STEP 14: Release TGL-1 Lock Release Switch.
- SAT SJANDARD: TGL-1 Lock Release Switch released.
CUE: The TGL 1 Lock Release Switch has retumed to center. _ UNSAT COMMENTS: SIfP 15: Close door to Y-50 Transfer Switch Cabinet and reinstall screws. STANDARD: Y-50 Transfer Switch Cabinet door closed and screws reinstalled. _ SAT COMMENTS: _ UNSAT STEP 16: Notify the SS that instrument AC Bus YO1 is manually aligned to the Emergency (MCC-2) power supply. _ SAT STANDARD: SS notified. COMMENTS:. _ UNSAT END OF TASK TIME STOP: i
1 JPM RO-8/ PLT Pags 9 of 13 JPM QUESTION # 1 REFERENCE ALLOWED: YES - LIMITED TO P & ids Question: Instrument Bus Y-01 is a grounded system. Preferred AC Busses Y-10, Y-20, Y-30, and Y-40 are ungrounded systems. What protects the ungrounded Preferred AC Busses from sensing a ground condition when one of them is being supplied by Instrument Bus Y-01? Answer: The Bypass Regulator serves as an isolation device. CANDIDATE'S RESPONSE Time: 5 min. KIA Rating: 2.1.24 (2.8)
References:
DBD 3.02, Section 1.1 E-8, Sheet 2 e
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JPM RO-8/ PLT Page 10 of 13 I- JPM QUESTION # 2 REFERENCE ALLOWED: YES / l yes no l- - Question: The unit is at 30% power. All four PCP's are running and bus 1 A and 1B have been transferred to 4 1 l the Station Power Transformer 1-1.125VDC Bus Panel D11 1 has developed a short to ground ! and is deenergized. Due to cooling water problems, the Main Generator is tripped. 1 What is the final condition of the four PCPs?
~ Answer: PCP's A and C are deenergized.
l i NOTE: Loss of Loss of D-11-1 results in loss of control power to all breakers on bus 1 A, and the bus will not fast transfer When the Generator trips bus 1 A will be deenergized. CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 062.K1.03 (4.0) l
References:
SOP-30, ONP-2.3 l { l i
l JPM RO-8/ PLT
l. Page 11 of 13 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES /
yes no , (10 BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: The unit is at 30% power. All four PCP's are running and bus 1A and 1B have been transferred to the Station Power Transformer 1-1, 125VDC Bus Panet D11-1 has developed a short to ground and is deenergized. Due to cooling water problems, the Main Generator is tripped. What is the final condition of the four PCPs? j l 1 1 1 1 1 I l l
i JPM RO-8/ PLT Page 12 of 13 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES - LIMITED TO P & ids (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Instrument Bus Y-01 is a grounded system. Preferred AC Busses Y-10, Y-20, Y-30, and Y-40 are ungrounded systems. What protects the ungrounded Preferred AC Busses from sensing a ground condition when one of them is being supplied by Instrument Bus Y-017 i i 1
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JPM RO-8/ PLT Page 13 of 13 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:
.- Plant is in Cold Shutdown for refueling. . Work is scheduled for breaker 52-145 this shift requiring instrument AC Bus Y-01 to be fed from MCC-2. . The Load Connected to Normal (MCC-1) light is lit. The Load Connected to Emergency (MCC-2) light is not lit.
INITIATING CUES: The Shift Supervisor directs you to manually align Instrument AC Bus YO1 to the Emergency power supply (MCC-2) per SOP-30, Section 7.6.2. i 1
4
o'h JPM RO-9/ PLT Page 1 of 12 R E GIO N 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM RO-9/ PLANT Start M-69A Hydrogen Recombiner l CANDIDATE EXAMINER
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4 i i
-4 ,4 JPM RO-9/ PLT Page 2 of 12 REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE 1
Task: l i Perform lineups of the Hydrogen Recombiner System. l Alternate Path: 12Eiddd/A3fSIEEED!EUlfEE3EEEWMATH6E?EQiffbJd% . jj Facility JPM #: NIE5fE M M Dlll(0D N inMT4Ef4Bli M M Eil7,fdEEE E git 3E4 3 K/A Ratinals): 028 A2.01 3.4/3.6 Task Standard: The Hydrogen Recombiner System will be functioning correctly in a Post LOCA environment. Preferred Evaluation Location: Preferred Evaluation Method: Simulator In-Plant X Perform - Simulate X 1
References:
j 1 SOP 05 Validation Time: 10 min. Time Critical: No
;;__ ;+=- ==_=======_u____--. _ -========_========e======== =====================
Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
======================---------====================================================
COMMENTS
se l JPM SRO-9/ PLT Page 3 of 12 Tools /Eauipment/ Procedures Needed: Ensure enough copies of SOP 05 are available. READ TO OPERATOR DIRECTION TO TRAINEE: l'will explain the initial conditions, and state the task to be performed. All control room steps sha.1
.. be performed for this JPM, including any reqt."ed communications. I will provide initiating cues - and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
IMIIIALAQNDm0Mi
'e- A LOCA is in progress.
e' Containment pressure is 24 psia. e- Pre-accident containment temperature was 105*F e Two Containment Cooling Fans are in service. INITIATING CUES: During performance of EOP 4, " Loss of Coolant Accident Recovery", the Shift Supervisor directs you to start M-69A Hydrogen Recombiner, referring to SOP 5, " Containment Air Cooling and Hydrogen Recombining System", Section 7.2.1. l 1 I n J
..g JPM RO-9/ PLT Pagg 4 of 12 START TIME:
STEP.1: Locate procedure to energize M-69A.' STANDARD: Operator describes where a copy of SOP 5 would be obtained. _ SAT
CUE: Hand operator copy of SOP 5.
COMMENTS: __UNSAT STEP 2 Close breaker 52-205. CRITICAL STEP STANDARD: - Operator describes closing breaker 52-205.
,_, SAT Critical Step: The breaker must be closed to enemize the recombiner.
CUE: Breaker 52-205 indicates ON. _ UNSAT COMMENTS: STEP 3 Verify POWER AVAILABLE lamp lighted on C-124. CRITICAL STEP
$7ANDARD Operator verifies white POWER AVAILABLE la:np lit on C 124. ~ SAT Critical Step verifles that the breaker operation was successful l
CUE: POWER AVAILABLE light is lit. _ UNSAT COMMENTS: 1 I J
JPM RO-9/ PLT l
.* . Pag @ 5 of 'i2 STEP 4: Ensure POWER ADJUST knob is set at 000.
STANQA6Q: Operator verifies power ADJUST knob is set at 000. CUE: POWW.R ADJUST knob indicates 000.
- UNSAT COMMENTS:
I STEP 5 Place POW s . . UT SWITCH to ON. CRITICAL STEP STANDARD: Operator describes placing POWER OUT switch to ON. CriticalStep: The switch must be placedin on to enable the following steps. __ SAT CUE: POWER OUT SWITCH indicates ON. COMMENTS: __ UNSAT STEP 6 Verify POWER OUT SWITCH red light is lit. SAT STANDARD Operator verifies POWER OUT SWITCH red light is lit. CUE: POWER OUT SWITCH red light is lit. _ UNSAT COMMENTS: , STEP 7: Place Thennocouple Selector Switch to position 1,2 or 3. STANDARD: Operator describes placing the Thermocouple Switch in position 1,2 or 3. _ SAT CUE: Thermocouple switch is as placed in position 1,2 or 3.
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COMMENTS: _ UNSAT l l l l l l L ._ j
r 4 JPM RO-9/ PLT Page 6 of 12 STEP 8 Determine required recombiner power setting from Att 1, utilizing current - CRITICA'. Containment pressure and pre-event Containment temperature- STEP STANDARD: Recombiner power setting determined to be 55 (54 to 55.5 acceptable). _ SAT Crldcal Step: Forproper operation the graph must be correctly interpreted and the cornet a4lustment made. ' __,_UNSAT
. COMMENTS: )
l STEP 9 Adjust POWER ADJUST knob until recombiner power determined 'above is CRITICAL obtained on the Kw POWER OUT meter. STEP STANDARD ' Operator describes adjusting the POWER' ADJUST knob until 55 (54 to 55.5) indicates on the Kw POWER OUT meter. J
~ SAT l Critical Step: Forproper operadon the graph must be correctly interpreted and the l correctaglustment made.
CUE: After the candidates demonstrates the ability to adjust the knob, then, The Kw POWER _ UNSAT ) OUT meter indicates the value determined by the candidate. COMMENTS STEP 10: Monitor the POWER OUT meter. . 1 STANDARD 1 Operator locates and monitors the POWER OUT meter. _ SAT
' CUE: The POWER OUT meter indicates the value determined by the candidate.
_ UNSAT
, COMMENTS 1 j
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JPM RO-9/ PLT Pags 7 of 12 STEP 11: Adjust POWER ADJUST knob as needed to maintain the Kw POWER OUT meter at the desired setting and less than 75 Kw. SAT STANDARD: . Operator describes that he/she would adjust the POWER ADJUST knob as needed to maintain the Kw power out meter at tha desired setting and less
- than 75 Kw. ~
CUE: The Power Out meter indicates the value determined by the candidate. COMMENTS: ) i STEP 12: Notify the SS that M-69A is in service. SAT ETANDARD: SS notified that M-69A is in service.
- UNSAT COMMENTS END OF TASK TIME STOP:
f l l i i i c
JPM RO-9/ PLT l Page 8 of 12 JPM QUESTION # 1 REFERENCE ALLOWED: YES / yes no Question: How long can a Hydrogen Recombiner be inoperable prier to taking any actions to shut down the plant? Answer: 30 days. CANDIDATE'S RESPONSE Time: 5 min, K/A Rating: 028K5.02 (3.9)
References:
Tech Specs L
JPM RO-9/ PLT Page 9 of 12 JPM QUESTION # 2 REFERENCE ALLOWED: / NO yes no Question: 1) At what percent concentration during an accident are the Hydrogen Recombiners required to be placed in service?
2) Why is at least one Containment Air Cooler fan required when placing the Hydrogen Recombiners in service?
Answer: 1) Between 1% and 3%
2) To prevent " pockets" of hydrogen from accumulating CANDIDATE'S RESPONSE ;
Time: 5 min. i K/A Rating: . 028K3.01 (4.0)
References:
EOP-4.0 EOP-9.0, Success Path CA-2 4 i 1
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t-
r JPM RO-9/ PLT Pagn 10 of 12 JPM QUESTION # 2 CANDIDATE COPY REFERENCE alt. OWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: 1) At what percent concentration during an accident are the Hydrogen Recombiners required to be placed in service?
2) Why is at least one Containment Air Cooler fan required when placing the Hydrogen Recombiners in service?
JPM RO-9/ PLT Page 11 of 12 JPM QUESTION # 1 , l CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: How long can a Hydrogen Renombiner be inoperable pricr to taking any actions to shut dowri the plant? l l l I I t i 1 1 1 0 I J 1 J
JPM SRO 9/ PLT Page 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:
A LOCA is in progress, e ' Containment pressure is 24 psia.
. Pre-accident containment temperature was 105 F e' Two Containment Cooling Fans are in service.
i INITIATING CUES: During performance'of EOP 4, " Loss of Coolant Accident Recovery", the Shift Supervisor directs you to start M-69A Hydrogen Recombiner, referring to SOP 5, " Containment Air Cooling and Hydrogen Recombining System", Section 7.2.1. i
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b. JPM RO-10/ PLT
Page 1 of 12 REGION 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE I
l JPM RO-10/ PLANT Start P-8B Locally Using CV-0522A CANDIDATE EXAMINER s
E
'o # JPM RO-10/ PLT Page 2 of 12 REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Start P-8B Locatty Using CV-0522A. Alternate Path: i l 5 5 h ,i N AiiG 5hkii C }li & S u su d i k ? h h t 4 5 I s h t: :41m1 - Facility JPM #: l MEMEalM&MlE?t$MEGEL%i!TiliDHisb 22 M L , . .i43%% n k i K/A Ratinals): 061 A2.05 3.1/3.5 Task Standard: Steam pressure supply to AFW Pump P-8B is 200 to 250 psig. Preferred Evaluation Location: Preferred Evaluation Method: X Perform Simulate X Simulator in-Plant
References:
.EOP Supplement 19, and ONP 25.2 Validation Time: 15 min. Time Critical: No ================================================================================
Time Start : Candidate: NAME Time Finish: UNSAT- Question Grade Performance Time Performance Ratina: SAT
/
Examiner: DATE NAME SIGNATURE
==========================================================================
COMMENTS
n 5 29
#. JPM RO-10/ PLT l
' Page 3 of 12 ( g ' Tools /Eaulement/ Procedures Needed: Ensure copies of EOP Supplement 19, pages 10-12 and 19 (Figures 2 and 3) are available. j l 3 READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall i I be performed for this JPM, including any required communications. I will provide initiating cues - and reports on other actions when directed by you. Ensure you indicate to me when you ! understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. I INITIAL CONDITIONS: e A Control Room Evacuation has occurred.
Busses 1C and 1D are deenergized.
e No AFW Pumps are running. l INITIATING CUES: While performing ONP-25.2, Alternate Safe Shutdown Procedure, the Shift Supervisor has directed you to f perform the tasks of Operator il to start AFW Pump P-8B using the alternate method (Underground Steam Line from 'B' SG) in accordence with EOP Supplement 19, Section 5.0. Turbine Driver K-8 has been verified as latched.
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JPM RO-10/ PLT Page 4 of 12 START TIME: l l I STEP 1: Locate procedure to start AFW Pump P-8B using alternate method. SAT STANDARD: EOP Supplement 19 located.
' COMMENTS:
_ UNSAT Locate and close A/S to CV-0522A, MV-CA379. CRITICAL , STEP 2 STEP J STANDARD: Operator locates and closes A/S to CV 0522A, MV-CA379. J
~ SAT i Critical Step: Required to gain manual control of CV 0522A. \
f CUE: MV CA379 is closed. _ UNSAT COMMENTS: i Bleed off AFW Pump P-8B Steam Supply From SG B, CV-0522A. instrument CRITICAL STEP 3 STEP air pressure through either regulator blowdown valve. STANDARD: Operator opens blowdown valve on either regulator. _ SAT Critical Step: Required to gain manual control of CV-0552A. CUE: Regulator blowdown _ valve is open. _ UNSAT COMMENTS: p
E JPM RO 10/ PLT
' Page 5 of 12 ~
STEP'4:' . Manually close AFW Pump P-8B' Steam Supply From SG B, CV-0522A, CRITICAL 4 using the hand operator by unscrewing the coupling from manual override STEP shaft.
$16NDARD Operator unscrews the coupling from the manual override shafti _,_ SAT.
Critical Step: Required to gain manual control of CV-0522A. CUE: Coupling is unscrewed from manual override shaft. __.UNSAT
- EVALUATOR NOTE: Figures 2 and 3 of EOP Supplement 19 provide graphic representation of the9 components.
COMMENTS Manually close AFW Pump P-8B Steam Supply From SG B, CV-0522A, CRITICAL - STEP 5 using the hand operator by tuming the handwheel clockwise until the top of STEP the actuator shaft is exposed sufficiently to engage the coupling. STANDARD CV-0522A is closed using the hand operator sufficiently to engage the ,_ SAT coupling.- Crftical Stap: Required action to ensure system operability.
,,,_ UNSAT -
CUE: The tip of the actuator shaft is properly exposed COMMENTS Completely insert the fork of the coupling onto the actuator shaft of CRITICAL STEP 6 STEP CV-0552A. - STANDARD ' The fork of the coupling shaft is inserted on the actuator shaft. _,_ SAT CriticaLStep: Required action to ensure system operability. CUE: The fork of the coupling shaft is inserted on the actuator shaft of CV-0552A.. .___UNSAT COMMENTS
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1
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r, q 1 i JPM RO 10/ PLT Page 6 of 12 l STEP 7: Open Bonnet Air Isolation Valve, MV-FW354. CRITICAL- ] STEP i STANDARD: Operator opens Bonnet Air isolation Valve, MV-FW354. l
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Critical Step: Required to gain manual control of CV-0522A. CUE: Bonnet Air Isolation Valve, MV-FW354, is open. _ UNSAT COMMENTS: 1 STEP 6 Using the hand operator, close AFW Pump P-8B Steam Supply From SG B, CRITICAL CV-0522A, using the handwheel. STEP STANDARD: . Operator clos'es CV-0522A using the handwheel.
~
Critical Step: Required to allow manual control of CV 0522A to supply steam. CUE: CV-0522A is closed. _ UNSAT COMMENTS: Open PI-0589 root valve, MV-FW687. CRITICAL STEP 9 STEP STANDARD: Opersstor opens PI-0589 root valve, MV-FW687. SAT Critical Step: Regs tred to allow monitoring of correct steam pressure. CUE: MV-FW687 is open. _ UNSAT COMMENTS: i
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i 1
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JPM RO-10/ PLT +- Pega 7 of 12 STEP 10:. Slowly throttle open AFW Pump P-8B Steam Supply From SG B, CV-0522A, CRITICAL to maintain between 200 and 250 psig steam pressure on PI-0589. STEP ST NDARD:~ Operator establishes 200 to 250 psig steam pressure on PI-0589 by thrattling CV-0522A _ SAT Critical Step: Required to provide correct steam pressure for turbine operation. _ UNSAT CUE: PI-0589 indicates 230 psig.' COMMENTS: STEP 11: Notify SS CV-0522A is being manually controlled with steam pressure between 200 and 250 psig. _ SAT STANDARD: SS n%fied. COMMENTS:
,,_,, UNSAT ,END OF TASK 1
TIME STOP:
-4
I JPM RO-10/ PLT
Pzge 8 of 12 ]
JPM QUESTION # 1 REFERENCE ALLOWED: / NO yes no Question: List four conditions that will cause Steam Generator Blowdown to isolate. For each of the conditions, explain the reason (s) for the isolation. Answer: Any four of the following: CHP lsolates containment to isolate energy sources CHR Limits radioactive release outside containment Blowdown High Level Prevents system damage for control malfunctions Flash tank High Level Prevents system damage for control malfunctions RIA-0707 High Rad Limits radioactive release outside containment CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 061.K4.03 (2.9)
References:
Lesson Plan ISIC section 6.5 B, and ASDC, page 43 l u . .
JPM RO-10/ PLT s / Pag 3 9 of 12 JPM QUESTION # 2 REFERENCE ALLOWED: YES / yes no Question: Given the following conditions: e No Main Feedwater Pumps are available.
. Auxiliary Feedwater Pump P-8B has tripped on overspeed.
Auxiliary Feedwater Pumps P-8A and P-8C have tripped.
e ' SG 'A'is faulted with level below- 140%.
. SG 'B'is intact with level at - 135%.
The overspeed trip has been reset on Auxiliary Feedwater Pump P-8B. What restriction (s) is(are) placed on restoration of feed flow to the SGs? Answer: Flow must be < 300GPM to both SGs. CAADlDATE'S RESPONSE l l l l
)
Time: 5 min. K/A Rating: 061 K.3.02 (2.9)
References:
EOP 7.0 Background Document l 1
7 :- JPM RO-10/ PLT Page 10 of 12 ,
}
JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES /__ yes no
' (To BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: Given the following conditions:
. No Main Feedwater Pumps are available. . Auxiliary Feedwater Pump P-8B has tripped on overspeed. . Auxiliary Feedwater Pumps P-8A and P-8C have tripped. . SG 'A' is faulted with level below - 140%. . SG 'B'is intact with level at- 135%.
The overspeed trip has been reset on Auxiliary Feedwater Pump P-88. What restriction (s) is(are) placed on restoration of feed flow to the SGs? i l l
i ;. en:1 RO-10/ PLT Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no
- (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: List four conditions that will cause Steam Generator Blowdown to isolate. For each of the conditions, explain the reason (s) for the isolation. i 1 l l 1 l 1 i
JPM RO 10/ PLT 1* Page 12 of 12 l CANDIDATE CUE SHEET: (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
'lNITIAL CONDITIONS: . - A' Control Room Evacuation'has occurred. '. Busses 1C and 1D are deenergized.
No AFW Pumps are running. >
INITIATING CUES: While performing ONP-25.2, Alternate Safe , Shutdown Procedure, the Shift Supervisor has directed you to perform the tasks of Operator ll to start AFW Pump P-88 using the alternate method (Underground Steam Line from 'B' SG) in accordance with EOP Supplement 19, Section 5.0. Turbine Driver K-B has been verified as latched. l l l 4 l 1 4
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/
' ES-301 Individual Walk-through Test Outline Form ES-301-2 Facility: PALISADES Date of Examination: June 7 - 11.1999 Exam Level (Circle): SRO(l) Operating Test No.: 1 System / JPM Title / Type Codes
Safety Planned Follow-up Quostions:
Function K/A/G // Importance // Description
1. Realign a Misaligned Control Rod 1 a. 001K507 (4.0) Effects of asymmetric rod (N)(S) configuration on power distribution. i

b. 001K594 (3.6) Definition of Shutdown Margin.

2. Respond to an LTOP Actuation 3 a. 027AK304 (2.8) Reason for slow pressure i (N)(A)(L)(S) recovery following a loss oflevel. l

b. 010K403 (3.8) PRZ PCS design feature for over pressure control.

3. Equalize Boron Conc between SDC 4 a. 025AK303 (3.9) Loss of CCW actions in EOP ,
and SIRWT l (N)(L)(S) b. 005K402 (3.2) RHRS modes of operation j
4. Verify Containment Spray Response to 5 a. 026K404 (3.7) CSS design feature to reduce Recirc Actuation temperature / pressure following a LOCA (N)(A)(L)(S)

b. 026K102 (4.1) CSS interconnection with Cooling Water System

5. Respond to an Area High Radiation 7 a. 072A201 (2.9) Predict ARM response following Alarm erratic or failed power supply

b. 072K302 (3.5) Effects on fuel handling following loss of ARM

6. Shift Operating CCW Pumps 8 a. 008K301 (3.4) Effect on loads cooled by CCWS '

b. 008K102 (3.3) Loads cooled by CCWS

7. Transfer PRZ Level Control from 2 a. 011 A211 (3.4) Predict failure of PRZ level !
MANUAL to CASCADE instrument -low (N)(S) I
b. 011K512 (3.3) Purpose of PRZ level program

8. Manually Align Y 01 to Emergency 6 s. 2.1.24 (2.8) Ability to interpret plant drawings Power Supply (M)(P) b. 062K103 (4.0) DC distribution interrelations with AC sources

9. Start M-69A Hydrogen Recombiner 5 a. 028K502 (3.9) Flammable gas conc limit (M)(P) .

b. 028K301 (4.0) Hydrogen conc in containment

10. Locally Start P-8B using 4 a. 061K403 (2.9) AFW design feature for automatic CV-0522A isolation of blowdown / sampling (M)(P)(R)

b. 061K302 (2.9) AFW malfunction effect on S/Gs
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)lmulator, (L)ow Power, (P)lant, (R)CA
QSff,S*
R E GIO N 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-1/SIM Realign a Misaligned Control Rod CANDIDATE EXAMINER I
4
.7 JPM SRO-1/SIM o J' Page 2 of 12 REGION 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Realign a misaligned control rod. Alternate Path: LEMWAlsinR!J3?iitiMEEEGiMdi,MiTuC2ESX11RGLhdM: ;su= ..;a s . Facilite JPM #: EbEh M ?5ffENTIPA$ T M W M (L M M 8T6? & W M l2C& Ti T K O W $ W ,l~h K/A Ratinafs): 001 A2.17 Task Standard: Realign the rod per station procedures. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate 1
References:
j j l SOP-6 i Validation Time: 15 min. Time Critical: No
====================================== _____==-------- ============================ ;
l
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Candidate: Time Start - i NAME Time Finish: I Performance Ratina: SAT UNSAT Question Grade Performance Time ! Examiner: / NAME SIGNATURE DATE
===================================================================================
COMMENTS
4 P JPM SRO-1/SIM
.. Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:
e initialize to IC-11.
Select Group 4 rod #41.- Drive it into the core 12"
. Ensure EK-0911 and EK-0912 annunciate.
Place Rod Control Mode Select in *MS" e Place simulatorin FREEZE I
1 I m
n
JPM SRO-1/SIM Pagn 4 of 12 Tools /Eauloment/ Procedures Needed:
Ensure enough copies of SOP 6 are available. l i DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be p' erformed. All control room steps shall , be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task retum the handout sheet I provided you. INITIAL CONDITIONS: Q0-34, Control Rod Exercise, was performed 40 minutes ago. Group 4 rod # 41 slipped when exercised. Reactor Engineering has verified that the rod slipped. Technical Specification 3.10.4 has been entered. INITIATING CUES: The Shift Supervisor directs you to realign group 4 rod #41 using SOP 6, section 7.4. l a
n ;. JPM SRO 1/SIM Page 5 of 12
- START TIME:
STEP 1. Refer to SOP 6, section 7.4. 1 STANDARD:. SOP 6, section 7.4 referenced. __ SAT
. COMMENTS:
_ UNSAT STEP 2 t Rod Selector Switch for the group selected through all positions to Turn 'he verify position of all rods in the group, and/or identify the rod to be moved. STANDARD; Rod Selector Switch is positioned for Group 4 rods # 38, # 39, # 40, and #41.
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NOTE: This step may not be performed since the candidate has been informed that red #41 is misaligned. If not performed go to step 3. _ UNSAT QQhlMENTS: STEP 3 Leave the Rod Selector Switch in the position for the rod to be moved. CRITICAL STEP STANDARD: Rod Selector Switch is positioned for Group 4 rod #41. Critical step is to correctly select misaligned rod. ~ COMMENTS: _ UNSAT
JPM SRO 1/SIM Pag 3 6 of 12 STEP 4: Turn Group Selector Switch to the position for the group containing the rod to be moved. CTANDARD: '4"is selected on the Group Selector Switch. _ SAT I l COMMENTS:' STEP 4: Turn Moce Selector Switch to ' MANUAL lf!DMDUAL." CRITICAL STANDARD: ' MANUAL INDIVIDUAL is selected on the Mode Selector Switch.
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Critical step is correcdy conRguring the rod controlsystem to move only one rod. COMMENTS
.,_ UNSAT STEP 5 . To reposition the rod, operate the Raise-Lower Switch. CRITICAL STEP S.TANDARD Group 4 rod # 41 is positioned to with 2' of the other Group 4 rods. _ SAT Critical step is to correcdy aligned rod to within allowable tolerances.
COMMENTS _ UNSAT STEP 6 Place the Group Selector Switch to the desired position.
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SAT STANDARD: Group 4 is selected. l CUE: The Shift Supervisor, if asked, directs the candldate to leave the Group Selector Switch in the Group 4 position. ] _ UNSAT COMMENTS: I l
JPM SRO 1/SIM Pag 3 7 of 12 S.TEP 7 Notify Shift Supervisor that Group 4 rod #41 has been realigned to the full out position. STANDARD: Shift Supervisor notified. - _ UNSAT COMMENTS: END OF TASK TIME STOP: j 4 l
rr , JPM SRO 1/SIM Page 8 of 12 JPM QUESTION # 1 l REFERENCE ALLOWEDi YES /__ yes no Question: The plant is operating at 100% full power when annunciator EK-0924, GROUP 1 PWR DEPENDENT INSERTION LIMIT, alarms.
. Group 1 PPDIL alarm is clear.
No other alarms have annunciated. The rod matrix and C-02 LEDs indicate all rods in Group 1 fully withdrawn.
. The PPC shows no rods in Group 1 below PDIL.
What condition is likely to have caused this alarm? Answer: A loop AT input to the pip has experienced a failure. CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 001.K5.07 (4.0)
References:
EK-0924 1 l
JPM SRO-1/SIM Pags 9 of 12 JPM QUESTION # 2 REFERENCE ALLOWED: / NO yes no Question: Describe the interlocks that exist in the Rod Control System to ensure Shutdown Margin is met during rod withdrawal. Which position of the Rod Control Mode Selector Switch bypasses this interlock? Answer: The Shutdown rods must be > 122" prior to the Regulating Rods being withdrawn to >6". , 1 Manual Individual (MI) bypasses this interlock. i CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 001.K5.94 (3.6)
References:
Lesson Plan ASEE section 4.24 and TS 3.10.6 Basis i I
[.- , JPM SRO.1/SIM Pcgs 10 of 12 ; I l l JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Describe the interlocks that exist in the Rod Control System to ensure Shutdown Margin is met during rod withdrawal. { Which position of the Rod Control Mode Selector Switch bypasses this interlock? l l J l i i 1 l
c JPM SRO-1/SIM Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: The plant is operating at 100% full power when annunciator EK-0924, GROUP 1 PWR DEPENDENT INSERTION LIMIT, alarms.
. Group 1 PPDIL alarm is clear.
No other alarms have annunciated. The rod matrix and C-02 LEDs indicate all rods in Group 1 fully withdrawn.
. The PPC shows no rods in Group 1 below PDIL.
What condition is likely to have caused this alarm? 1
JPM SRO-1/SIM Page 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:
' 00-34,' Control Rod Excersize, was performed 40 minutes ago. Group 4 rod # 41 slipped when excersized. Reactor Engineering has verified that the rod slipped. Technical Specification 3.10.4 -- has been entered.
1 INITIATING CQg).;, 1 The Shift Supervisor directs you to realign group 4 rod #41 using SOP 6, section 7.4. _a
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. i ) JPM SRO-2/SIM Page 1 of 12 R E GIO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-2/SIM Respond to an LTOP Actuation CANDIDATE EXAMINER 1
4 JPM SRO-2/SIM
.f Pag 3 2 of 12 i REGION lli INITIAL LICENSE EXAMINATION -
JOB PERFORMANCE MEASURE Task: Rerspond to an LTOP actuation caused by an instrument spike. Alternate Path:
)NherPPJtV10438% J OfSCS-IfWeildDIEd83,0A %gA E T lEddt07$ddi[US D f ?!m & wIQivilf fall td:ckies MO21 Facility JPM #:
IflUMNiLii:UEul@$$W W"WTWAESIO%i55E[L$%adDLULd%:M ~' K/A Ratinals): 000027AA2.15 Task Standard: Utilizing station procedures respond to an LTOP actuation and limit loss of PCS inventory. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X in-Plant - Perform X Simulate
References:
ONP-18, ARP EK13 # 73 and 74 Validation Time: 15 min. Time Critical: No
================================.. ..= -- ====================================_____ ]
i 1 Candidate: Time Start : 1 NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
================================----=___._as======= ==============t================
COMMENTS i l i I l 1 I I
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JPM SRO-2/SIM Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS: e initialize to 10-36. e I/O EK 1373, PORV OPEN, alarm to ON e !!O LTOP Channel 'B' red trip light to ON e'- 1/O Pl-01058 on C-02 to 1.0 (failed high) e' 1/0 PRV-10438 HS to OPEN e Place the simulatorin RUN e As soon as all indications are verified (approximately 2 seconds), place the simulator in FREEZE e After turnover, and with concurrence from the examiner, go to RUN l l I
f . V JPM SRO-2/SIM Pagn 4 of 12 Tools /Eaulomen*JProced0res Needed: Ensure enough copies'of ONP-18 are available. i READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues f t-- and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the l- handuut sheet i provided you, 8NITIAL CONDITIONS: The plant is shutdown and Shutdown Cooling is lined up for operation. An instrument failure has caused an LTOP actuation. INirtATING CUES: The Shift Supervisor directs you to respond to the L1OP actuation usinw the gu! dance in ONP-18, Step 4.3. l l
)
+ JPM SRO-2/SIM Pags 5 of 12
.) - $ TART TIME:
STEP 1: Refer to ONP 18. Step 4.3. STANDARD: ONP-18 referred to.
- QOMMENTS: ___UNSAT STEP 2 Determine that PCS pressure is below the actuation setpoint, and close both PORVs.
STANDARD: Close handswitch for PRV-1042B Green light lit.
- SAT NOTE: This step is not required to be performed since the valve is already dosed. Candidate _ UNSAT mayplace HSin CLOSEhowenr.. ' Steps 2 and 3 may be performed in any order.
COMMENTS STEP 3 Determine that PCS pressure'is below the actuation setpoint, and close both ' PORVs. _ SAT SI6NOARD Close handswitch for PRV-10438. Red light remalrs lit. Steps 2 and 3 may be performed in any order. _ UNSAT COMMENTS
f .._ JPM SRO-2/SIM ! ,- Pag 3 6 cf 12 s STEP 4: Depress associated Reset Push' Button to Clear LTOP trip indication. STANDARD. Associated Reset Push Buttons are pushed. LTOP trip light remains ht.
._ SAT COMMENTS:
_,UNSAT' STEP 5 ff PORV's don't ' properly close when below their actuation setpoint, then close the associated PORV isolation Valve. STANDARD: MO-1043A HS placed in CLOSE. Green light lit. _,, SAT l Critical Step to isolate failed open PORV to stop PCS leakage. COMMENTS: __.UNSAT STEP 6 Continuously monitors Pressurizer Pressure to ensure LTOP limits are not CRITICAL exceeded. STEP STANDARD Monitors PCS and PZR pressure to ensure less than 310 psig.
.__ SAT COMMENTS:
UNSAT STEP 7. Notifies SS or logs that PRV-10438 failed to operate as required. STANDARD Log entqr made or SS notified. _ UNSAT COMMENTS l
7,. i JPM SRO-2/SIM Pigm 7 of 12 ! 1 STEP 8 Notifies the SS that the actions of ONP-18 are complete. STANDARD: SS Notified.
,__ SAT -
1 1 __UNSAT CpMMENTS: END OF TASK 1 TIME STOP: k 4 I l I 1 ll N b
- i JPM SRO-2/SIM l , ,, Page e of 12 JPM QUESTION # 1 REFERENCE ALLOWED: YES /
yes no Question: Given the following conditions: 1
. The plant is cooling down toward SDC entry conditions. . Pressu izerlevelis 42% and stable. . Pressurizer pressure is 1450 psia. . The lowest Ta in Loop 1 Indicates 434*F. . The lowest Tm in Loop 2 indicates 428 F. )
What is required for PCS overprescure protection? Answer: LTOP must be in service with both PORVs armed and operable. CANDIDATE'S RESPONSE 4 Time: 5 min.
- K/A Rating:
000027.AK3.04 (2.8)
References:
Lesson Plan ASFE Tech Specs
JPM SRO-2/SIM
. - { , ,Page 9 of 12 1 JPM QuiiCION # 2 REFERENCE ALLOWED: / NO yes no Question: In the event of an excessive plant cooldown, the operator is directed to place the LTOP system in service.
What is the basis for this action? Answer: Placing the LTOP system in service protects the PCS from brittle fracture concems CANDIDATE'S RESPONSE i Time: 5 min. K/A Rating: 010.K4.03 (3.8)
References:
EOP 6.0 Background Document Step 11 o
4 JPM SRO-2/SIM
. . . ) . Page 10 of 12 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: /_ NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: In the event of ari excessivo plant cooldown, the operator is directed to place the LTOP system in service. What is the basis for this action?
r JPM SRO-2/SIM Pig 311 of 12 ;
. :* l 4
JPM QUESTION # 1 dpNDIDATE COPY REFERENCE ALLOWED: YES / yes no i I (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) l 1 Question: Given the following conditions:
. The plant is cooling down toward SDC entry conditions.
Pressurizer levelis 42% and stable.

Pressurizer pressure is 1450 psia.

The lowest Tm in Loop 1 indicates 434 F.
. The lowest Tm in Loop 2 indicates 428 F.
What is required for PCS overpressure protection?
c .;. JPM SRO-2/SIM Pags 12 of 12 CANDIDATE CUE SHEET
. (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS: The plant is shutdown and Shutdown Cooling is lined up for operation. An instrument failure has caused an LTOP actuation. IfilTIATING CUES: - The Shift Supervisor directs you to respond to the LTOP actuation using the guidance in _ONP-18, Step 4.3, i l
r ,
.4 .P ?,le*?0??'"'
R E G IO N lli INITJAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE i JPM SRO-3/SIM Equalize Boron Concentration between the { Shutdown Cooling System and the SIRWT ' CANDIDATE EXAMINER - I
)
i 1
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7c. A-JPM SRO-3/SIM
+ -9 Page 2 of 12 REGIONlli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Equalize Boron Concentration between Shutdown Cooling System and the SIRWT. Alternate Pathj
'"iT:R lqfgify!yigggggqqqq'jgq;y[r;g:3ggg qcgmygg;gy , . ;g +
Facility JPM #: M C M e% 2 [# 2 M EGl: M;CMa%TER E %li&32?sta:2:. K/A Ratinals): 005K5.09 Task Standard: Shutdown Cooling System boron concentration has been equalized with the SIRWT. li i Preferred Evaluation Location: Preferred Evaluation Method: Simulator X in-Plant Perform X Simulate
References:
SOP-3 Validation Time: 15 min. Time Critical: No
===============================________ss==========================================
Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
==============================================____==========------- ==== -___======
COMMENTS 1 I i k-
7 l- s A
, p. JPM SRO-3/SIM -
Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:
.. Initialize to IC-3 e Use the ADVs to cooldown until cold leg temperatures are all below 300 F e Maintain SG levels using AFW flow e Place simulator in FREEZE -
After turnover and with the concurrence of the examiner, place the simulator in RUN. l l l
f l l L. JPM SRO-3/SIM Page 4 of 12 i Tools /Eauloment/ Procedures Needed: ) l Ensure enough copies of SOP-3, Section 7.3.1, are available. I READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: The plant is shutdown and lined up for Shutdown Cooling. INITIATING CUES: The Shift Supervisorhas directed you to equalize boron concentration of the SDC and the SIRWT using SOP 3, section 7.3.1, and BOTH LPSI pumps. The procedure is complete up to and including step 7.3.1.f. l l r I l l i.
e s
..- JPM SRO-3/SIM Paga 5 of 12 START TIME:
STEP 1 Start both LPSI pumps. CRITICAL STANDARD: P-67A & B handswitch taken to start. Red lights lit. STEP
. Critical Step is to provide flow so that boron concentrations can be squallied. ,,_ SAT COMMENTS:
_ UNSAT STEP 2 Open LPSIInjection valves. CRITICAL STANDARD: STEP Places HS's to OPEN for:
MO-3008
,,,,,_ SAT e MO-3010 e MO-3012 e MO-3014 Red lights lit.
_ UNSAT Critical Step is to properly align the system so that boron concentrations can be equalized. COMMENTS: STEP 3 Open SIT Pressure Control Valves. CRITICAL STEP STANDARD: PlC's placed in
MANUAL OPEN".
q e PIC-0342 e PIC-0346 _,_, SAT ! e PIC-0347
. PIC-0338 Valves indicate open on PIC. { .,_ UNSAT Critical Step is to properly align the system so that boron concentrations can be equalized.
COMMENTS: t
f-JPM SRO-3/SIM Page 6 of 12 STEP 4: After each LPSI pump has run for at least 10 minutes request Chemistry to sample the Safety injection System.
~ ' STANDARD: LPSI pumps run until sample is taken and analyzed by Chemistry.
CUE: The SS informs you that Chemistry reports the sample analyzed indicates boron concentration is greater than Shutdown Boron concentration. __ UNSAT NOTE: It is not necessary for the pumps to run the full time. The examiner may use time compression and inform the candidate that 10 minutes have elapsed. COMMENTSi 1 STEP 5 Stop LPS! pumps. CRITICAL STEP STANDARD: P-67A & B handswitch taken to stop. Green lights lit. Critical Step is to property align the system. _ SAT COMMENTS _ UNSAT STEP 6 Close and lock SIT Recirculation Containment isolation valves. STANDARD: Communicates with dedicated AO to close and lock: _, SAT e MV-ES3234
. MV-ES3234A . MV-ES3237 -
UNSAT- j e MV-ES3235 l CUE: AO reports that the SIT Recirculation Containment Isolation valves are closed and locked,
]
i i COMMENTS:. f i.
7 JPM SRO-3/SIM - Pags 7 of 12 i STEP 7: Close LPSI Injection valves. CRITICAL STEP
~ STANDARD: ' Places HS's to CLOSE for: . MO-3008 . MO-3010 . MO-3012 - .__. SAT . MO-3014 Green lights lit. ,_UNSAT Critical Step is to property align the system.
COMMENTS: STEP 8 Close SIT pressure control valves by placing the associated PIC in
MANUAL CRITICAL CLOSE."
STEP STANDARD: - PlC's placed in " MANUAL CLOSE": SAT-
. PIC-0342 . PIC-0346 . PIC-0347 . PIC-0338 .
_ UNSAT Valves indicate closed on PIC. Critical Step is to property align the system. 1 COMMENTS: l END OF TASK TIME STOP:
]
1 i l l 1 i-I p. L b
c 1
._ JPM SRO-3/SIM Pag 9 8 of 12 JPM QUESTION # 1 REFERENCE ALLOWED: / NO yes no Question: During Refueling Operations a loss of Shutdown Cooling has occurred.
1) What are the immediate actions?

2) Why are these immediate actions taken?
4 Answer: 1) Suspend Refueling Operations.
2) Ensure adequate heat removalis available while performing refueling operations CANDIDATE'S RESPONSE I I
l l I I Time: 5 min. K/A Rating: 000025.AK3.03 (3.9) l H l Referenras: ONP 17 and T/S 3.8.1 I 1 I -. .
( , JPM SRO-3/SIM Page 9 of 12 JPM QUESTION # 2 REFERENCE ALLOWED: YES / yes no Question: During a plant cooldown, preparations are being made to place the Shutdown Cooling System in operation. One of the preparations includes equalizing the boron concentration between the SIRWT and the SDC System. Why must PCS pressure be maintained above 300 psia during this evolution? Answer: Prevent injecting potentially diluted SDC water into the PCS. (Ensure injection check valves remain closed). CANDIDATE'S RESPONSE Time: 5 min. KIA Rating: 005K4.02 (3.5)
References:
ASCC Lesson Plan 1 L
( , JPM SRO-3/SIM Paga 10 or 12 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES /
)
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: During a plant cooldown, preparations are being made to place the Shutdown Cooling 1 System in operation. One of the preparations includes equalizing the boron concentration between the SIRWT and the SDC System. Why must PCS pressure be maintained above 300 psia during this evolution? I I i i t 4
r ..
a JPM SRO-3/SIM Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no
-(TO GE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
J Question: During Refueling Operations a loss of Shutdown Cooling has occurred. ! 1
1) What are the immediate actions?

2) Why are these immediate actions taken? l
{ l i 1
(;- 1 JPM SRO-3/SIM j
*- Page 12 of 12 '
CANDIDATE CUE SHEET I
. (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) l INITIAL CONDITIONS: l The plant is shutdown and lined up for Shutdown Cooling.
INITIATING CUES: The Shift Supervisor has directed you to equalize baron concentration of the SDC and the SIRWT using SOP-3, section. 7.3.1, and BOTH LPS1 pumps. The procedure is complete up to and including step 7.3.1.f. 1 i l
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JPM SRO-4/SIM
/'h Page 1 of 12 R E GIO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-4/SIM Verify Containment Spray Response to Recirculation Actuation Signal CANDIDATE EXAMINER t
l l e, o.,A_,,,,,,,__,___ m
e.- a A JPM SRO-4/SIM Page 2 of 12 REGION lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Verify Containment Spray Response to a Recirculation Actuation Signal Alternate Path:
- 3. , : - 'C6nWnment Header.' valve oped," the '
v nt. ~,,Ac, t;. .,.w w.. ; a,7. . . . . , q, , ., Lj.13i,~~,...;f.%.T,ji'fs,.,p.%...,G..,.e,,: , V- ~,n+ v %.. _ ypran,pa un.3.g; xt ,. g,g . Facility JPM #: 5EKMEZh2MEC47dNEf1EdirGs2Ei!$!Ard2EEMBEY2Jic . f!; .. ; K/A Ratinals): 026.A3.01 Task Standard: Respond to a RAS and take actions to place Containment Spray in the correct lineup. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate
References:
EOP-4 Validation Time: 15 min. Time Critical: No
===================- - _____-- =-------------======================================= =
Candidate: Time Start : NAME Time Finish: Performance Ratino: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
============____.s_=========------ ================================================
COMMENTS E
r 1
^
6 JPM SRO-4/SIM [*
' Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:
I
-e Initialize t'h e simulator to IC-11. ! . MALF RC-04 to value = 1.0 - . - Trip both MFPs and ramp controllers to MIN speed * . Stop all PCPs ;
e Close CV-2001 and 2009 1
. When SIRWT level reaches 2%, stop all Containment Spray Pumps and close discharge isolation i . valves .- Enter MALF to prevent start of Spray Pump P-54A e When previous step performed, place simulator in FREEZE I
J l i l
n -.- i
' JPM SRO-4/SIM !
Pag 3 4 of 12 ; Toc,WEauipmenUProcedures Needed: Ensure enough copies of EOP4.0 are available. READ TO OPERATOR 1 DIRECTION TO TRAINEE: 1 I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you.' Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. I INITIAL CONDITIONS: 1 A LOCA h' as occurred. RAS has initiated as designed. EOP 4.0 is in use at step 47. HPSI pumps P-66 A & B are operating.
. INITIATING CUES:
The Shift Supervisor directs you to ensure Containment Spray is properiy aligned for RAS operation. The Shift Supervisor has determined that two Containment Spray pumps are required for spray and to provide subcooled water to the HPSI pumps. You are to start by placing the right channel pump in service first. L f
~
JPM SRO-4/SIM Pagm 5 of 12 START TIME: STEP 1: Refer to EOP-4.0 Step 47. STANDARD: _ SAT-COMMENTS: _ UNSAT STEP 2 Open one Containment Spray valve. CRITICAL i STEP STANDARD: Opens CV-3002, red light lit. _ SAT CrWcal step is aligning system forproper operation. NOTE: EOP 4.0 step 47 is in table format. The candidate may operate the CS valves and pumps by starting with either the A or B set of pumps and valves. _ UNSAT NOTE: Alarm EK-1377, CONTAINMENT SPRAY VALVE OPEN, is an expected alarm. ) i COMMENTS- i i 1 STEP 3 Attempts to start Containment Spray Pump P-54A. _ SAT STANDARD: Places P-54A HS to Start. Green light remains lit. CUE: If notified, the Shift Supervisor directs the candidate to start the other two CS Pumps. _ UNSAT COMMENTS: l i
r-- JPM SRO-4/SIM i Pags 6 of 12 STEP 4: Start a Containment Spray Pump CPTICAL - 3TEP STANDARD: ' Starts P-548 or P-54C. Red light lit. _ SAT Critical step is providing subcooled water for the HPSIpumps. COMMENTS: _ UNSAT I I STEP 5 Start a second Containment Spray Pump. CRITICAL ! STANDARD: Starts remaining CS Pump.' Red light lit. STEP ) I
~ SAT Critical step is providing subcooled water for the HPSIpumps.
COMMENTS' , _ UNSAT { STEP 6 Open second Containment Spray valve. CRITICAL STEP STANDARD f Opens CV-3001. Red light lit. Critical step is aligning system forproper operation. _ SAT COMMENTS
.,_ UNSAT STEP 7 : Open the first HPSI Subcooling Valve CRITICAL STEP STANDARD Obtains Key 152 or 153. Opens CV-3070 or 3071. Red light lit. ~
SAT Critical step is providing subcooled water for the HPSIpumps. COMMENTS: ___UNSAT i l l l l 1 e
r: ,
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JPM SRO-4/SIM
.)
J Pggs 7 of 12 STEP 8 Open the second HPSI Subcooling valve. CRITICAL ! STEP l STANDARD: Obtains key 152 or 153.' Opens remaining HPSI Subcooling valve. Red light lit. ___ SAT
. Critical step is providing subcooled water for the HPSIpumps. .__ UNSAT COMMENTS:
STEP 9 Report the completion of step 47.
' STANDARD; Shift supervisor notified of completion and, if not done at step 4, that P-54 A SAT ~~~
tripped. __UNSAT COMMENTS: END OF TASK TIME STOP: 1
I .
- JPM SRO-4/SIM Page 8 of 12 JPM QUESTION # 1 REFERENCE ALLOWED: / NO yes no Question: Containment Pressure is 5.2 psig and increasing.
1)- What automatic action enhances the spray water's ability to remove heat in the Containment atmosphere?
2) What signal (s) must be present for this feature to activate? i Answer: 1) CV-0937 and CV-0938 (Service Water) open to the Shutdown Cooling. Heat Exchangers. (Service Water aligned to SDC Heat Exchangers required for full credit. Valve numbers are not required)

2) SlAS and CHP CANDIDATE'S RESPONSE
.g..-.
Time: 5 min. K/A Rating: 026.K4.04 (3.7)
References:
Lesson Plan ASCA section 6.6
r s JPM SRO-4/SIM 4 Page 9 of 12 t JPM QUESTION # 2 REFERENCE ALLOWED: YES / yes no Question: Given the following conditions: I A Main Steam Line Break has occurred inside containment. l
. Left channel power has been lost.
What combination of Containment Spray Pumps and/or Containment Air Coolers is available to limit Containment pressure below design limits? Answer: Three (3) Containment Air Coolers AND one (1) Containment Spray Pump CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 0026.K1.02 (4.1)
References:
ONP-7.1 Attachment 2, page 2, EOP 4.0 step 47, and Lesson Plan ASHC 4.5
r: l
' JPM SRO-4/SIM a? Pag 910 0f 12 1
JPl@ QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Given the following conditions: A Main Steam Line Break has occurred inside containment.
) . Left channel power has been lost.
What combination of Containment Spray Pumps and/or Containment Kr Coolers is available to limit Containment pressure below design limits? l
)
1 1 1 l 1 I
y-, - -
# l JPM SCO d/ RIM 1 Page 11 oi1 2 1 JPM QUESTION # 1 C.ANDIDATE COPY REFERENCE ALLOWED: / NO yes no - (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: Containment Pressure is 5.2 psig and increasing. l
1) What automatic action enhances the spray water's ability to remove heat in the Containment atmosphere?

2) What signal (s) must be present for this feature to activate? i l
l l 1 i i i l i
JPM SRO-4/SIM Paga 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) i INITIAL CONDITIONS:
A LOCA has occurred. RAS has initiated as designed. EOP 4.0 is in use at step 47. HPSI pumps
- P-66 A & B are operating.
INITIATING CUES: The Shift Supervisor directs you to ensure Containment Spray is properly aligned for RAS operation.. The Shift Supervisor has determined that two Containment Spray pumps are required for spray and to provide subcooled water to the HPSI pumps. You are to start by placing the right channel pump in service first. 1 i l 1 i
Pa e10 11 R E GIO N lli , INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-5/SIM Respond to an Area High Radiation Alarm 1 CANDIDATE EXAMINER 1 4 1 J 1 REGIONlli INITIAL LICENSE EXAMINATION m __
4
',.- JPM SRO-5/SIM
+ Page 2 of 11 JOB PERFORMANCE MEASURE ' Task: Respond to an Area High Radiation alarm.
.. Alternate Path: $ik$1;Mid%k18$%: MOSIbMidf$?INFfd?EIN5%X$%f@Z2:MGCClifQ&
Facility JPM #:
'2509%$?Eu21Eikk&dGEELA.63WW.TU50583?idYNildE?AMIiEMEZ?d$I?Oilk h K/A Ratinals): ' 072K1.02 Task Standard:
Respond to a High Radiation event and correctly manipulate plant equipment that failed to automatically actuate. Preferred Evaluation L? cation: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate
References:
EOP-4
- Validation T!me: 15 min. Time Critical: No ==______============================_______m ========--- ======------ =============
Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT - Question Grade Performance Time gxaminer: ~ / NAME SIGNATURE DATE
=====================___ m=============------ ===_____=___=========================
COMMENTS 1 l l I i l 1 i l J
4 JPM SRO-5/SIM Page 3 of 11 { SIMULATOR OPERATOR INSTRUCTIONS:
)
e initialize to IC-11. MALFs CH05A CH05B to ACTIVE (defeats auto CSS, defeats auto CIS, and defeats auto SIS on a
- CHP). Auto defeat of SIS c1 CHP is true, but N/A since SIAS WILL auto actuate on PZR low pressure. NOTE: This malfusiction also defeats manualinitiation of CIS/CHR.
e 10 CV-0911 keyswitch to OPEN. ,
. RC-04 to value = 1.0
Trip both MFPs and ramp controllers to MIN speed
. Stop all PCPs
y JPM SRO-5/SIM Page 4 of 11 Tools /Eauipment/ Procedures Needed: Ensure enough copies of EOP 4.0 and EOP Supplement 6 available. READ TO OPERATOR I DIRECTION TO TRAINEE:- I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: A LOCA has occurred. EOP 4.0 is in use at step 12. INITIATING CUES: The Shift Supervisor directs you to verify Containment isolation per step 12 of EOP-4.0. l 1 l c ,
JPM SRO-5/SIM Pag @ 5 of 11 START TIME:' I STEP 1: Refer to EOP 4.0 step 12.
' STANDARD: EOP 4.0 step 12 referenced..
__ SAT COMMENTS: _ UNSAT
~
STEP 2 Verify Containment Pressure greater than 4.0 psig. STANDARD: Containment pressure is < 4.0 psig. EK-1161 is dark. ___ SAT COMMENTS: __ UNSAT STEP 3 Any operable Containment Radiation Monitor rises to 1x10' R/hr. STANDARD ' RfA 1805, 1807, & 1808 all indicate < 1x10' R/hr. RfA 1806 indicates > 1x10' SAT R/hr, "" ~ __.UNSAT COMMENTS l
w JPM SRO-5/SIM P:g3 6 cf 11 1 STEP 4: Verify "CIS INITIATED * (EK-1126) is alarmed. i STANDARD: EK 1126 is dark. _ SAT COMMENTS: - ^ i STEP 5 Manually initiates CIS by pushing left or right pushbutton on EC-13. CRITICAL STEP { l STANDARD: Depresses CHRL-CS or CHRR-CS on EC-13. EK 1126 alarm lit. SAT { Criticalstep is to Initiate CIS. NOTE: Either CHRL-CS OR CHRR-CS may be pushed to initiate CIS.
._ UNSAT j COMMG_TS: T STEP 6 Verify Containment Lofation per EOP Supplement 6.
STANDARD: Each valve listed in EOP supplement 6 (Attached to this JPM) is verified in the correct position. ~ SAT 1 NSAT j COMMENTS: - i STEP 7 Place CV-2003, CV-2004, and CV-2005 handswitches in CLOSED. CRITICAL STEP STANDARD: CV-2003, CV-2004, and CV-2005 placed in CLOSED. _ SAT Criticalstep is to ensure valves remain closed.
- UNSAT 1 ' COMMENTS: I END OF TASK TIME STOP;
JPM SRO-5/SIM Page 7 of 11 JPM QUESTION # 1 REFERENCE ALLOWED: YES / yes no Question: What are the effects on the Area Radiation Monitoring System on a loss of preferred AC Bus Y-10 with the Bypass Regulator unavailable? Answer: Loss of Preferred AC Bus Y-10 (not required) results in a loss of: RfA 1805 Containment Area Monitor
. RIA 2316 Refueling Containment Area Monitor e
RlA 2321 Containment High Range Monitor I (Instrument number OR description for all three required for full credit) CANDIDATE'S RESPONSE i d Time: 5 min. KIA Rating: 072A2.01 (2.9)
References:
ONP-24.1
JPM SRO-5/SIM Pags 8 of 11 JPM QUESTION # 2 REFERENCE ALLOWED: YES /
yes no Question: While moving fuel during Refueling Operations a loss of D20R occurred. What actions are required with regard to fuel handling operations? Answer: Suspend fuel movement NOT REQUIRED: until RIA-2317 is restored to service and due to CV-3055 failing closed which results in no shutdown cooling. CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 072.K3.02 (3.5)
References:
GOP-11 Technical Specification 3.8.1 ONP-2.3 i e
\
JPM SRO-5/SIM Page 9 of 11 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: YES / i yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: While moving fuel during Refueling Operations a loss of D20R occurred. > What actions are required with regard to fuel handling operations? l I l 4 1 l 1 i 1 1 l
)
l 1
r-JPM SRO-5/SIM Page 10 of 11 JPM QUESTION # 1 CANDIDATE COPY . REFERENCE ALLOWED: YES / yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) ) Question: . What are the effects on the Area Radiation Monitoring System on a loss of preferred AC
. Bus Y-10 with the Bypass Regulator unavailable?
1 i i I
1 JPM SRO-5/SIM 1 Page 11 of 11 CANDIDATE CUE SHEET (To BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) s. INITIAL CONDITIONS: A LOCA has occurred. EOP 4.0 is in use at step 12.
-INITIATING CUES:
The Shift Supervisor directs you to verify Containment isolation per step 12 of EOP-4.0. I f l 1
3
$"9e?0?s'*'M R E G IO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-6/SIM Shift Operating CCW Pumps CANDIDATE EXAMINER i
i
T
$', JPM SRO-6/SIM Page 2 of 13 l
REGION lli INITIAL LICENSE EXAMINATION JOD PERFORMANCE MEASURE Task: Shift operating CCW pumps. l Alternate Path:
;1dsdTtiaA0urpump-M2tiW!4tirted.lA31l#@.Whoitstadul&Tiithird CCW pump must be started. j I
Facility JPM #: 1 1 ES%fk M 2hE65?fuP8E%T][t3WNEt%? M RIGIWPMRGLW2iiM % & :" L % K/A Ratinals): 1 008 i l Task Standard: ! l Two CCW pumps will be operating per ONP-6.2 and SOP-16. 1 Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant I Perform X Simulate
References:
Validation Time: 15 min. Time Critical: No
======3=======================s____=======================---- ====================
Candidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time i i Examiner: / { NAME SIGNATURE DATE !
===_____==2n__== ---=========================- - ========================.,======== l i
COMMENTS i i l
$ JPM SRO-6/SIM Prgs 3 of 13 SIMULATOR OPERATOR INSTRUCTIONS:
e initialize to 1C-11
. Secere a running CCW Pump so only P-52A is running - . Place CCW Pump P-52C in STANDBY (leave P-52B off and NOT in standby) e MALF CCO2 for CCW Pump P-52B to active e Place simulator in FREEZE l
i m j
r 4
, JPM SRO-6/SIM Page 4 of 13 Tools /Eauinment/ Procedures Needed:
Ensure enough copies of SOP-16 ano ONP-6 2 is available.
' READ TO OPERATOR' DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: CCW Pump P-52A is running with P-52C in standby. P-52A has indications of a high vibration and is to be secured. INrTIATING CUES: The Shift Supervisor directs you to shift operating CCW pumps per SOP 16, section 7.3.3. P-52B is to be started and P-520 is to be left in standby. P-52A is to be used for emergency use only. I I
t:
.. v.
JPM SRO-6/SIM Pag 3 5 of 13
' $ TART TIME:
STEP 1: Refer to SOP-16,'section 7,3.3 to shift operating CCW purnps. STANDARD SOP-16 referred 'to. _ SAT COMMENTS _ UNSAT STEP 2 ~ Ensure OPEN CCW pump P-52B' suction and discharge valves.
-g STANDARD Contacts AO to ensure MV-CC920 and MV-CC942 OPEN. _ SAT CUE: AO reports MV-CC920 a' nd MV-CC942 OPEN ,UNSAT COMMENTS STEP 3 . Operste CCW Pump P-52B casing vent petcock to vent air from pump. i 3
1 STANDARD Contacts AO to cycle MV-CC557 open and closed. ,,,,,,,,, SAT: !
. CUE: AO reports MV-CC557 cycled open and closed COMMENTS . _ UNSAT j I
a
, i i
I l. L ! p2 y , l
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@fV?u g; y W jW .p :.i; , JPM SRO-6/SIM V s
.) Pigs 6 of 13 - ' EIg,PJ ., Verify both CCW Heat Exchangers are in operation.
a ., > ' '
? STANDARD'. j. Verifies from initial conditions or asks SS for report.
_ SAT-CUEIf 83%9d, SS reports that both CCW Heat Exchangers are in operation..
b. '
iCOMMENTS- ._ ,UNSAT.- STEP 5 : Start selected CCW pump. STANDARD When started, P 52B fails to start. Red light out. _ SAT ( f4MMENTS _ UNSAT STEP 6 Refers to ARP-7, Window 67 and notifies Shift Supervisor of CCW pump trip . and need to reference ONP 6.2. __ SAT STANDARD SS Notified,
. Cue: The SS directs the candidate to start CCW pump P-52C and stop P 52B, leaving NO UNSAT pump in standby, utilizing SOPr16, section 7.3.3. - GOMMENTS STEE1:- Ensyre OPEN CCW pump P-52C suction and discharge valves. . STANDARD: Contacts AO to ensure MV-CC921 and MV-CC945 OPEN. _ SAT . CUE: AO reports MV-CC921 and MV-CC945 OPEN -
__UNSAT COMMENTS
, ,c 15i(
t 1
{-
JPM SRO4/SIM Pag 9 7 of 13 STEP 8 Operate CCW Pump P 52C casing vent petcock to vent air from pump. CRITICAL STFP
, - STANDARD: Contacts AO to cycle MV-CC558 open and closed. CUE: AO reports MV-CC558 cycled open and closed. - COMMENTS _UNSAT STEP 9: Verify both CCW Heat Exchangers are in operation.
- STANDARD: - Verifies from initial conditions or asks SS for report. ._ SAT CUE: If asked, SS reports that both CCW Heat Exchangers are in operation.-
NOTE: This was determined previously, so it may not be performed again at this time. . _ UNSAT COMMENTS: STEP 10: Start selected CCW pump. CRITICAL STEP STANDARD: P 52C starts. Red lightlit.
~~~SAT CrWcalstep to establish flow with P-52C to allow stopping P 52A.
COMMENTS: UNSAT 1 STEP 11: Ensure CCW heat exchanger AP is less than or equal to the maximum allcwat;le AP and operatireg at optimurn HX AP, _ SAT STANDARD: Directs AO to determine that CCW Heat Exchanger AP is between 12 and 16 psid and less than 24 psid for E-54A and less than 20.9 psid for E-54B. __ UNSAT i CUE: AO reports CCW Heat Exchanger APs are 15 psid for E-54A and 14 psid for E 54B. ! COMMENTS: l l i
)
x J
VF JPM SRO-6/SIM Pags 8 of 13 1 STEP 12: Stop P-52A per section 7.3.5. CRITICAL STEP
- STANDARD: . P-52A turned off. Green light litc ~
Critical step to stop P 52A due to potentialfailure ofpump. NOTE: If asked again, repeat that P-52A is NOT to be placed in Standby.- COMMENTS: STEP 13. Ensure CCW heat exchanger AP is less than or equal to the maximum allowable AP and operating at optimum HX AP. _, SAT STANDARD: Directs AO to determine that CCW Heat Exchanger AP is between 6 and 8 paid and less than 24 psid for E-54A and less than 20.9 psid for E-548. _ UNSAT CUE: AO reports CCW Heat Exchanger APs are 7 psid for E 54A and 6.5 psid for E-548. COMMENTS: END OF TASK
. TIME STOP:
O L
y. I JPM SRO-6/SIM Page 9 of 13 JPM QUESTION # 1 REFERENCE ALLOWED: YES / _ yes no Question: The heat load a given component places on the CCW System varies according to the operating condition of the plant. What is the LARGEST heat load on the CCW System l when the plant is in the post DBA (post RAS) condition? Answer: Shutdown cooling heat exchangers CANDIDATE'S RESPONSE 1 Time: 5 min. K/A Rating: 008.K3.01 (3.4) l
References:
Lesson Plan ASCA 1
g. sPM SRO-6/SIM Page 10 0f 13 '
, JPM QUESTION # 2 REFERENCE ALLOWED: / NO yes no Question: For each of the following loads, indicate whether a leak in the heat exchanger will esult in flow into, or out of, the CCW system. 3 l
l a) CRDM Seals l b) Radwaste Evaporators c) SDC Heat Exchanger during Containment Spray Operations d) Letdown Heat Exchanger during refueling operations Answer: a) into CCW b) Out of OCW c) into CCW d) Out of CCW , (3 of 4 required for full credit) i CANDIDATE'S RESPONSE 4 l Time: 5 min. K/A Rating: 008K1.02 (3.3)
References:
LP ASCA Section S.7.b Obj. 4.8, page 23 ! i i
e-JPM SRO-6/SIM l Page 11 of 13 - JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: /_ NO yes no
'(TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: For each of the following loads, indicate whether a leak in the heat exchanger will result in flow into, or out of, the CCW system, a) CRDM Seals b) Radwaste Evaporators c) SDC Heat Exchanger during Containment Spray Operations d) Letdown Heat Exchanger during refueling operations
?
l
I . JPM SRO-6/SIM l
. l Page 12 of 13 l JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES /
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: The heat load a given component places on the CCW System varies according to the operating condition of the plant. What is the LARGEST heat load on the CCW System when the plant is in the post DBA (post RAS) condition? l 1 I
p; [7
..: JPM SRO-6/SIM Page 13 of 13 ' CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK') .!NITIAL~ CONDillOEf; CCW Pump P-52A is' running with P-52C in standby. P-52A has indications of a high vibration and is to be secured.
INITIATING CUES: The Shift Supervisor directs you to shift operating CCW pumps per SOP 16, section 7. 3.3. P-528 is to be started and P-52C is to be left in standby. P-52A is to be used for emergency use only.
)
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Pa e 10 1 R E GIO N lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-7/CR Transfer Pressurizer Level Control from Manual to Cascade CANDIDATE EXAMINER I
JPM SRO-7/CR Paga 2 of 12 REGIONll! INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE
.T3tki Transfer the sssurizer Level Control System to the CASCADE mode of operation from MANUAL Alternate Path:
WEEnNIAnin&dDana;HGdMdisib!MDb w n ;s .< &;i .g Facility JPM #: Z4!JdXM2RMfTLM"EGLTfa%%EGEraisir?:2GLas: N K/A RatinoIsl: 011 A3.03 Task Standard: The Pressurizer level Control System is operating in the CASCADE mode of operation. Preferred Evaluation Location: Preferred Evaluation Method: Simulator in-Plant X Perform Simulate _,_ X
References:
SOP-1 Validation Time: 15 min. Time Critical: No
====----=================____- -5==================================================
Cardidate: Time Start : NAME Time Finish: Performance Ratina: SAT UNSAT Question Grade Performance Time Examiner: /. NAME SIGNATURE DATE z._____======------- ==============---------- -.---. =============================== COMMENTS 1
1 [7 ,<< {
'l JPM SRO 7/CR Pcge 3 of 12 ' SIMULATOR OPERATOR INSTRUCTIONS: " Initialize to 1C 11 .. .e Place LIC-0101 A in MANUAL '
e' Adjust AUTO setpoint of LIC-0101A to 42% '. s 1 f
),
i i I .. 3
.JPM SRO-7/CR Page 4 of 12 .. Tools /Eauipment/ Procedures Needed:
If Control Room procedures are marked up for this JPM ensure the candidate arranges for replacement copies to be made. READS'OOPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand yer: assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: The plant is operating at 100% power. Pressurizer Level Controlis in the MANUAL mode on LIC-0101 A, with the AUTO setpoint left at 42% to allow l&C to verify controller setpoints. INITIATING CUES: The Shift Supervisor directs you to place the Pressurizer Level Control System in the CASCADE mode of operation, on LIC-0101A. .l. l
Ei: l-g L
h. JPM BRO-7/CR .
PagG 5 of 12 4 START TIME: STEP 1! Refers to SOP-1, section 7.3.1.e T-STANDARD: : SOP-1, section 7.3.1.e referenced. _ SAT COMMENTS:
,_ UNSAT STEP 2- Using the raise / lower pushbuttons, adjust selected controller to match actual Pressurizer level.
STANDARD The blue pointer on LIC-0101A is set to 57%. (Actual PZR levelis 57%)
~
_ UNSAT
' COMMENTS:
STEP 3 Depress the 'A' pushbutton on the selected controller. CRITICAL STEP STANDARD - The "A* pushbutton is pushed on LIC-0101A. - Critical step is to set the controller up to allow transfer to cascade. _. SAT COMMENTS: _ _UNSAT i l 1 i s
r3 L
JPM SRO-7/CR Page 6 of 12 STEP 4:. Ensure LfC-0101 A in auto.
.' STANDARD: "A" light' on t.lC-0101 A is verified lit. -
_ UNSAT COMMENTS:- STEP 5 Verify expected T signal available from selected T /T,,, controller using
. TYT-0100. TYT-0200, or TI-0110.
STANDARD: T.. signal vr;rified correct using TYT-0100, TYT-0200, or TI-0110.
- ^
COMMENTS: STEP 6 Adjust selected controller setpoint to the Pressunzer level setpoint determined by present T., using Attachment 3, T., (F) Pressurizer Level Program. ,_ SAT STANDARD: . LIC-0101A blue pointer set at 57%. _ UNSAT NOTE: , Candidate may not consult attachment 3 since 57% is the normal 100% power setting. COMMENTS: t
;a 1 JPM SRO-7/CR Paga 7 cf 12 '
STEP 7: Depress the "C" pushbutton on the selected controller. CRITICAL STEP STANDARD: The "C" pushbutton is depressed on LIC-0101 A.
. Critical step is to ensure cascade operation by selecting the correct mode. ~ SAT f.; '
__UNSAT CO' MMENTS: l END OF TASK
' TIME STOP:
i 1 1 j j
JPM SRO-7/CR
, ,, Page 84of 12
~
JPM QUESTION # 1 REFERENCE ALLOWED: YES / yes no Question: Given the following conditions:
. The plant is at 100%. l Pressurizer Level controlin CASCADE from LIC-0101 A.
Pressurizer Pressure control is in AUTO using PIC-01018 (Channel 'B').
. A loss of Y-10 occurs.
Predict the response of each of the following:
1) Pressurizervariable heaters

2) Pressurizersprayvalves

3) Pressurizerlevel Answer: 1) Minimum output

2) Open to control pressure

3) Continuously rises CANDIDATE'S RESPONSE l
1 Y I i Time: 5 min. K/A Rating: 011 A2.11 (3.4)
References:
Lesson Plan ASFD sections 6.3 and 6.4, Lesson Plan ASFE Objective 4.6 I i
JPM SRO-7/CR Pag 3 9 ef 12 JPM QUESTION # 2 REFERENCE ALLOWED: / NO l yes no Question: SOP-1 contains a note to the operator to maintain PZR level < 62.8% What three (3) design basis does compliance with this note ensure are met? Answer: The calculated PZR level program ensures: Sufficient steam volume to allow for an insurge that won't reach the safety valve nozzles, e Overall PCS volume is minimized to reduce peak containment pressure during a , LOCA e i Level sufficient to prevent uncovery of the pressurizer heaters following a reactor i trip. { (2/3 rer ad for full credit) CANDIDATE'S RESPONSE i 4 i i h i Time: 5 min. { K/A Rating: 011,KS.12 (3.3)
References:
FSAR 4.3.7 Lesson Plan ASFD section 6.7 and objective 4.1 i l 1 2
+ JPM SRO-7/CR Page 10 0f 12 JPM QUESTION # 2 CANDIDATE COPY 4
- REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: SOP-1 contains a note to the operator to maintain PZR level < 62.8%. What three (3) design basis does compliance with this note ensure are met? 1 I
)
1 s
; JPM SRO.7/CR Page 11 of 12 JPM QUESTION # 1 I>
CANDIDATE COPY REFERENCE ALLOWED: ' YES / yes no P (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Given the following conditions:
. The plant is at 100%.
Pressurizer Level control in CASCADE from LIC-0101 A. Pressurizer Pressure controlis in AUTO using PIC-01018 (Channel 'B'). A loss of Y-10 occurs. Predict the response of each of the following:
1) Pressurizer variable heaters

2) Pressurizer spray valves

3) Pressurizerlevel l
l l
4 JPM SRO-7/CR Page 12 of 12 CANDIDATE CUE SHEET l (70 DE RE FURNED TO EXAMINER UPON COMPLETION OF TASK) l I INITIAL CONDITIONS: The plant is operating at 100% power, Pressurizer Level Controlis in the MANUAL mode on i LIC-0101 A, with the AUTO setpoint left at 42% to allow I&C to verify controller setpoints, l INITIATING CUES:
. The Shift Supervisor directs you to place the Pressurizer Level Control system in the CASCADE mode of operation, on LIC-0101A. )
I l
- JPM SRO-8/ PLT Page 1 of 13 REGION lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-8/ PLANT Manually Align Y-01 to Emergency Power Supply CANDIDATE EXAMINER l
r r t(' ' JPM SRO-8/ PLT Page 2 of 13 REGION lli INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Transfer a vital (120V) instrument power supply.
' Alternate Path:
dEEEf$$$ihSt4EMlW "M4DPPlyMd1hlo80d.lsad "*@ Facility JPM #: Ell 3 MDISE8Ad231ST@d80555fEMID558 x 1 , KIA Ratina(s): 062 A2.03 ' 2.9/3.4 Task Standard: Instrument bus Y-01 is powered from it emergency power source. Preferred Evaluation Location: Preferred Evaluation Method: Simulator in-Plant X Perform Simulate X
References:
SOP 30, Rev. 23 Validation Time: 10 min. Time Critical: No
==___.2._========================____ =================------ ================= ===
Candidate: Time Start: NAME Time Finish: Performance Ratino: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE DATE
===================_==================== -======---m- -----== m- - - - - - - -
COMMENTS i
N
. JPM SRO-8/ PLT l
Page 3 of 13 Tools /EauipmenUProcedures Needed: Ensure copies of SOP-30 are available. Ensure SOP-30, Attachment 1, (Attachment 1 to this JP{ is available. Stopwatch or equivalent to measure 30 seconds. j i READ TO OPERATOR
)
DIRECTION TO TRAINEE: l l will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task retum the handout sheet I provided you. , I 1 INITIAL CONDITIONS:
. Plant is in Cold Shutdown for refueling.
Wo* is scheduled for breaker 52145 this shift, requiring instrument AC Bus Y-01 to be fed from
- MCC-2, The Load Connected to Normal (MCC 1) light is lit. The Load Connected to Emergency (MCC-2) light is not lit.
f INITIATING CUES: The Shift Supervisor directs you to manually align Instrument AC Bus Y01 to the Emergency power supply (MCC-2) per SOP-30, Section 7.6.2, 1 1
1 1 JPM RO-8/ PLT l Page 4 of 13 ) l 1 START TIME: - STEP 1 Locate the procedure to manually align Instrument AC Bus Y01 to Normal or Emergency Power Supply. STANDARD: SOP 3.0, Section 7.6.2 located. ~ COMMENTS: _,UNSAT k STEP 2: Remove screws and open door to Y-50. CRITICAL STEP f STANDARD: Screws removed and door opened. Cdtical Step: The cover must be removed to access the controls. ~ CAUTION: When operator simulates rercoving the screws and opening the door to Y-50, provide the operator Att.1 of this JPM to use to explain how to perform _ UNSAT steps. Do not allow operator to remove screws or open door. COMMENTS:
-a STEP 3 Check indicating light lit for desired power source. CRITICAL STEP STANDARD: Operator checks Emergency Source Available light. Light not lit. ~
Critical Step: If the light is not checked the Operator could transfer the bus to a doenergizedpower source. CUE: Emergency Source Available light is NOT lit. _UNSAT l COMMENTS: l l i l j i q l 1
p,
JPM SRO-8/ PLT Pagt 5 of 13 STEP 4: ~ If desired power source light is NOT lighted, THEN: Do not attempt transfer.
' CRITICAL STEP SAT -STANDARD: - Attempting to transfer power without the emergency power source lit will result in a loss of bus YO1.
Critical Step: Failure to ensure a power supply available will result in a loss of the U NSAT
Instrument bus.
COMMENTS: 4 l { STEP 5 Check bulb and replace if necessary. __,,,, SAT < STANDARD:- Operator checks bulb and determines that replacement is ,ot necessary.. CUE: The light bulb is functional. _,._ UNSAT COMMENTS l
]
l [ STEP,g: Check closed appropriate emergency source breaker 52-236. CRITICAL STEP STANDARD:. Operator checks breaker 52 236, and after determining that it is open, closes it. (May call SS for permission prior to closing breaker.) __, SAT l Critical Step: The breaker must be closed for successful completion of the task. '
' CUE: When the Operator checks breaker 52-236, provide cue that the breaker is in the OFF UNSAT position.~ If Operator calls the SS for direction regarding 52 236, direct closure of the breaker.
COMMENTS: 1
1_ JPM SRO-8/ PLT Page 6 of 13 _- SlEP_.Z: ; ifindicating light cannot be restored, then notify Shift Supervisor. CRITICAL STANDARD:- Operator rechecks the Emergency Source available light and determines that it is LIT. _ SAT Critical Step; The operator must verify power is available before continuing with the rask.
- UNSAT CUE: Emergency Source Available light is LIT, COMMENTS:
STEP 8 Refer to table and determine the n6xt step to perform. CRITICAL STEP STANDARD: Operator reviews steps 7.6.2.e and f and determines step 7.6.2.e as ned step.
~
SAT Critical Step: The Operator must determine the correctprocedure flowpath to continue. COMMENTS: _ UNSAT STEP 9 Hold Transfer Test Switch to " TEST" position for 15 seconds. CRITICAL STEP STANDARD: Transfer test switch held in " TEST" for 15 seconds. _ SAT Critical Step: Fifteen seconds is required for the Y 50 to transfer. CUE: After 5 seconds of holding transfer test switch, inform the Operator that the " LOAD
' CONNECTED TO EMERGENCY" light is lit and " LOAD CONNECTED TO NORMA ' _ UNSAT light is NOT lit.
COMMENTS:
y
JPM SRO-8/ PLT Page 7 of 13 STEP 10i Release Transfer Test switch CRITICAL
. STANDARD: STEP Transfer Test switch released. . Critical Step: The transfer test switch must be released to accomplish the next steps in 30 sec. .
_ SAT NOTE: For the next step the 30 seco_nd limit may be exceeded if simulated due to increased time necessary to describe actions. _ UNSAT Note: Operator may start over at JPM Step 9 if 30 seconds is exceeded. COMMENTS: STEP 11: Operate and hold TGL-1 Lock Release Switch in the direction indicated for CRITICAL
Emergency Source Available

light. STEP STANDARD: - TGL-1 Lock Release Switch operated and held toward the " Emergency SAT Source Available" light. (Must be completed wdhin 30 seconds of completion of Step 10.)
Critical Step: The Lock Release switch must be operatedin the consct direction to
~ UNSAT ensure the nextstepis successful.
COMMENTS STEP 12: Place the Bypass Handle to the position indicated for the desired power CRITICAL source. STEP STANDARD: Bypass Handle placed in the " Emergency" position while holding the TGL-1 Lock Release Switch toward the " Emergency Source Available" light. (Must SAT be completed within 30 seconds of completion of step 10.) Critical Step: The Bypass Handle must be correctly aligned to ensure continuedpower is _ UNSAT evallable. CUE: If 30 seconds elapse before the Bypass Handle is placed in the " EMERGENCY' ped. ion, provide the cue that the " Load Cont.ected to Normal" light has illuminated and the
- Load Connected to Emergency" light has gone out.
COMMENTS:
s
. JPM SRO 8/ PLT Pag 3 8 of 13 l - l STEP 13: Ensure Bypass Handle is fully engaged into desired power source position. CRITICAL STEP STANDARD: . Operator ensures Bypass Handle is vertical, fully engaged into the J " Emergency" position. {
Critical Step: Ensuring the Bypass handle is in the full verticalposition verifles the ~ SAT handle is lockedin place. CUE: The Bypass Handle is vertical pointing to " Emergency" and engaged- _ UNSAT COMMENTS: ( STEP 14: Release TGL-1 Lock Re! ease Switch. STANDARD: _ SAT TGL-1 Lock Release Switch released. CUE: The TGL 1 Lock Release Switch has retumed to center. _ UNSAT COMMENTS: STEP 15: Close door to Y 50 Transfer Switch Cabinet and reinstall screws. STANDARD: Y-50 Transfer Switch Cabinet door closed and screws reinstalled. __ SAT COMMENTS: _.,,UNSAT STEP 16: Notify the SS that Instrument AC Bus YO1 is manually aligned to the Emergency (MCC-2) power supp).
,_ SAT STANDARD: SS notified. ' COMMENTS: __UNSAT t
END OF TASK TIME STOP: _
r JPM SRO-8/ PLT Page 9 of 13 JPM QUESTION # 1 REFERENCE ALLOWED: YES - LIMITED TO P & ids Question: Instrument Bus Y-01 is a grounded system. Preferred AC Busses Y-10, Y-20. Y-30. and Y-40 are ungrounded systems. What protects the ungrounded Preferred AC Busses from sensing e ground condition when one of them is being supplied by Instrument Bus Y-017 Answer: The Bypass Regulator serves as an isolation device. CANDIDATE'S RESPONSE i
.w .m Time: 5 min.
K/A Rating: 2.1.24 (3.1)
References:
DBD 3.02, Section 1.1 E-8, Sheet 2
r
JPM SRO-8/ PLT Pags 10 of 13 JPM QUESTION # 2 REFERENCE ALLOWED: YES /
yes no Question: The unit is at 30% power. All four PCP's are running and bus 1 A and 1B have been transferred to the Station Power Transformer 1 1.125VDC Bus Panel D11-1 has developed a short to ground and is deenergized. Due to cooling water problems, the Main Generator ir tripped. What is the final condition of the four PCPs? Answer: PCP's A and C are deenergized. NOTE: Loss of Loss of D-11-1 results in loss of control power to all breakers on bus 1A, and the bus will not fast transfer. When the Generator trips bus 1 A will be deenergized. CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 062.K1.03 (4.0)
References:
SOP-30, ONP-2.3 (
, JPM SRO-8/ PLT Page 11 of 13 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: _ YES /
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETlON OF ANSWER) 1 Question: The unit is at 30% power.- All four PCP's are running and bus 1A and 18 have been transferred to the~ Station Power Transformer 1-1, 125VDC Bus Panel D11-1 has developed a short to ground and is deenergized. Due to cooling water problems, the .i Main Generator is tripped. I What is the final condition of the four PCPs? I' 4
1 h-JPM SRO-8/ PLT Page 12 of 13 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES - LIMITED TO P & ids (r0 BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) ) Question: Instrument Bus Y-01 is a grounded system. Preferred AC Busses Y-10, Y-20, Y-30, and Y-40 are ungrounded systems. 4 What protects the ungrounded Preferred AC Busses from sensing a ground condition when one of them is being supplied by Instrument Bus Y-017 I I i ( I l l i 1 l I 1 l l
. JPM SRO-8/ PLT Page 13 of 13 CANDIDATE CUE SHEET , (TO BE RETURtJED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:
. Plant is in Cold Shutocwn for refueling. . Work is scheduled for breaker 52-145 this shift requiring Instrument AC Bus Y 01 to be fed from MCC-2.
j e The Load Connected to Normal (MCC-1) light is lit. The Load Connected to Emergency
- (MCC-2) light is not lit.
INITIATING CUES: The Shift Supervisor drects you to manually align Instrument AC Bus YO1 to the Emergency power supply (MCC-2) per SOP-30, Section 7.6.2. i i
l
~ JPM SRO-9/ PLT Page 1 of 12 R E GIO N lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-9/ PLANT Start M-69A Hydrogen Recombiner CANDIDATE EXAMINER I
JPM SRO-9/ PLT Page 2 of 12 REGION 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l Iaalc Perform lineups of t'he Hydrogen Recombiner System. Alternate Path: N/A Facility JPM #: _ ASHE-01 Rev 22 (MODIFIED) _ K/A Rating (s): 028 A2.01 3.4/3.6 Task Standard: The Hydrogen Recombiner System will be functioning correctly in a Post LOCA environment. Preferred Evaluation Location: PJeferred Evaluation Method: Simulator in-Plant X Perform _ Simulate X
References:
SOP 05 Validation Time: 10 min. Time Critical: No
===_&______=_-- -- --;r=;______ -
_____mm____=================____===== Candidate: Time Start : NAME Time Finish: P_edormance Ratina: SAT UNSAT Question Grade Performance Time Examiner: __/ NAME SIGNATURE DATE _________==u___====_---- = - -____ _ _ _ -__;==================================== COMMENTS l i i 1 l i l-
,j -,
JPM RO-9/ PLT i Page 3 of 12 Tools /Eauloment/ Procedures Needed: Ensure enough copies of SOP 05 are available. READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: e ' A LOCA is in progress.
Containment pressure is 24 psia.

Pre-accident containment temperature was 105 F e Two Containment Cooling Fans are in service.
INITIATING CUES: During performance of EOP 4. " Loss of Coolant Accident Recovery", the Shift Supervisor directs you to start M-69A Hydrogen Recombiner, referring to SOP 5, " Containment Air Cooling and Hydrogen
' Recombining System," Section 7.2.1, i
i i
)
l
A JPM SRO-9/ PLT Pags 4 of 12
' START TIME:
SIEP_1: Locate procedure to energize M-69A. SIANDARD: Operator describes where a copy of SOP 5 would be obtained. _ SAT CUE: Hand operator copy of SOP 5.' COMMENTS: _ UNSAT i l STEP 2 Close breaker 52 205. CRITICAL S*iEP SIANDABQ: Operator describes closing breaker 52-205. __ SAT Critical Etep: The breaker must be closed to enemize the recombiner. CUE: Breaker 52-205 indicates ON. __UNSAT COMMENIS: l STEP 3 Verify POWER AVAILABLE lamp lighted on C-124. CRITICAL STEP STANDA8D: Operator verifies white POWER AVAILABLE lamp lit on C-124. __ SAT Critical Step verifles that the breaker operation was successful CUE: POWER AVAILABLE light is lit. UNSAT COMMENTS- 1 l l l
r
-, .r ]
JPM SRO-9/ PLT i Page 5 of 12 ;
- SIEEL4: Ensure POWER ADJUST knob is set at 000.-
SAT STANDARQ Operator verifies power ADJUST knots is set at 000. ):
. CUE: POWER ADJUST knob indicates 000.-
COMMENTS ~ STEPS - Place POWER OUT SWITCH to ON. CRITICAL STEP STANDARD: ' Operator describes placing POWER OUT switch to ON.
. Critical Step: The switch must be placed in on to enable the following steps. _,,,, SAT CUE: POWER OUT SWITCH indicates ON.
COMMENTS __ UNSAT STEP 6 Verify POWER OUT S' WITCH 1i J h;ht is lit.
,_,,,, SAT STANDARD Operator verifies POWER OUT SWITCH red light is lit.
CUE: POWER OUT SWITCH red light is lit. _ UNSAT COMMENTS-STEP 7. ' Place Thermocouple Selector Switch to position 1,2 or 3.' STANDARD Operator describes placing the Thermocouple Switch in position 1, 2 or 3. . __ SAT CUE: Thermocouple switch is as placed in position 1, 2 or 3. } J ( COMMENTS __UNSAT d
I'
l I

JPM SRO-9/ PLT l Page 6 of 12 I 1
STEP 8, Determine required recombiner power setting from Att 1, utilizing current CRITICAL Containment pressure and pre-event Containment temperature. STEP STANDARQ:. Recombiner power setting determined to be 55 (54 to 55.5 acceptable). _ SAT Critical Step: Forproper operation the graph must be correctly interpreted and the correct adjustment made. __ UNSAT
~ COMMENTS:
I
~
STEP 9 Adjust POWER ADJUST knob until recomciner power determined above is CRITICAL obtained on the Kw POWER OUT meter. STEP 1 STANDARD l Operator describes adjusting the POWER AOJUST knob until 55 (54 to 55.5) l indicates on the Kw POWER OUT meter. ! _ SAT j Critical Step: Forproper operation the grapio must be correctly Interpreted and the correct affustment made. CUE: After the candidates demonstrates the ability to adjust the knob, then, The Kw POWER _ UNSAT ! OUT meter indicates the valde determined by the candidate. COMPdENTS I l STEP 10: Monitor the POWER OUT meter. ! l STANDARD Operator locates and monitors the POWER OUT meter. _ SAT CUE: The POWER OUT meter indicates the value determined by the candidate.
]
_ UNSAT l COMMENTS: l
JPM SRO-9/ PLT Page 7 of 12 STEP 11: Adjust POWER ADJUST knob as needed to maintain the Kw POWER OUT meter at the desired setting and less than 75 Kw. )
,_ _ S AT ~ STANDARD: Operator describes that he/she would adjust the POWER ADJUST knob as needed to maintain the Kw power out meter at the desired setting and less - ,
than 75 Kw. { _ UNSAT CUE: The Power Out meter indicates the value determined by the candidate. COMMENTS: k i
. STEP 12: Notify the SS that M-69A is in service.
STANDARD - SS notified that M-69A is in service. COMMENTS END OF TASK TIME STOP: ; 1 l { i i
c ,
. JPM SRO-9/ PLT Page 8 of 12 JPM QUESTION # 1 4
REFERENCE ALLOWED: YES / yes no Question: How long can a Hydrogen Recombiner be inoperable prior to taking any actions to shut down the plant? Answer: 30 days. CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 028K5.02 (3.9)
References:
Tech Specs i i 1 1
JPM SRO-9/ PLT Page 9 of 92 JPM QUESTION # 2 REFERENCE ALLOWED: / NO yes no j l Question: 1) At what percent concentration during an accident are the Hydrogen Recombiners required to l be placed in service?
2) .Why is at least one Containment Air Cooler fan required when placing the Hydrogen Recombiners in service? ]
j l Answer: 1) Between 1% and 3%
2) To prevent " pockets" of hydrogen from accumulating CANDIDATE'S RESPONSE I
Time: 5 min. K/A Rating: 028K3.01 (4.0)
References:
EOP 4.0 EOP-9.0, Success Path CA-2
JPM SRO-9/ PLT Page 10 0f 12
'JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER)
Question: 1) At what percent concentration dunng an accident are the Hydrogen Recombiners required to be placed in service? .
2) Why is at least one Containment Air Cooler fan required when placing the Hydrogen Recombiners in service?
I
JPM SRO 9/ PLT Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: YES /
yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: How long can a Hydrogen Recombiner be inoperable prior to taking any actions to shut down the
. plant?
l t I 1 l
JPM RO-9/ PLT Page 12 of 12 CANDIDATE CUE SHEET i (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) l
! I INITIAL CONDITIONS: '
A LOCA is in progress. l e Containment pressure is 24 psia. )

Pre-accident containment temperature was 105 F e Two Containment Cooling Fans are in service.
INITIATING CUEj; During performance of EOP 4, " Loss of ' Coolant Accident Recovery", the Shift Supervisor directs you to start M-69A Hydrogen Recombiner, referring to SOP 5, " Containment Air Cooling and Hydrogen Recombining System", Section 7.2.1. I 1 l 1
E 4 JPM SRO-10/ PLT Page 1 of 12 R E GIO N 111 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SRO-10/ PLANT Start P-8B Locally Using CV-0522A CANDIDATE EXAMINER 1 1 1 1 l l l l I
y-JPM SRO-10/ PLT PJg3 2 of 12 REGION lil INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Start P-8B Locally Using CV-0522A. Alternate Path: EEdiMEON@dE$f7SEE((ME2E$ESSENE$$[$EENPMfd5[EAi,$ Facility JPM #: MMMlOf,DVsE5M?$3EMMWb?!?iEEMW55ESI$$MT&?$$N$$$h15$?if$ K/A Ratinals): 061 A2.05 3.1/3.5 Task Standard: Steam pressure supply to AFW Pump P-8B is 200 to 250 psig. Preferred Evaluation Location: Preferred Evaluation Method: Simulator in-Plant X Perform - Simulate X
References:
EOP Supplement 19, and ONP-25.2 Validation Time: 15 min. Time Critical: No
====================-==================================================n========2==
Candidate: Time Start : NAME Time Finish: Performance Ratino: SAT UNSAT Question Grade Performance Time Examiner: / NAME SIGNATURE D
=========================================================================== ====
COMMENTS L
JPM SRO-10/ PLT ) Page 3 of 12
; Tools /Eauloment/ Procedures Needed:
Ensure cop 6es of EOP Supplement 19, pages 1012 and 19 (Figures 2 and 3) are available. READ TO OPERATOR l DIRECTION TO TRAINEE: ! I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: e-A Control Room Evacuation has occurred. Busses 1C and ID are deenergized.
. No AFW Pumps are running.
INITIATING CUES: While performing ONP-25.2, Attemate Safe Shutdown Procedure, the Shift Supervisor has directed you . to perform the tasks of Operator il to start AFW Pump P-8B using the attemate method (Underground
. Steam Line from 'B' SG) in accordance with EOP Supplement 19, Section 5.0. Turbine Driver K-8 has been verified as latched. -i l .l
r JPM SRO-10/ PLT Page 4 of 12
' START TIME:
i
' STEP 1: Locate procedure to start AFW Pump P-8B using alternate method.
STANDARD: EOP Supplement 19 located. __ SAT COMMENTS: __ UNSAT 1 J STEP 2: ! Locate and close A/S to CV-0522A, MV-CA379. CRITICAL l STANDARD: STEP I Operator locates and closes A/S to CV-0522A, MV CA379. Critical Step: Required to gain inanual control of CV-0522A. ~ CUE: MV-CA379 is closed.
,_,,,_ UNSAT -
COMMENTS: STEP 3: Bleed off AFW Pump P-8B Steam Supply From SG B, r;v.0522A, instrument CRITICAL air pressure through either regulator blowdown valve. STEP STANDARD: Operator opens blowdown valve on either regulator. _, SAT Critical Step: Required to gain snanual control of CV-0522A. CUE: Regulator blowdown valve is open. __UNSAT 1 COMMENTS: i l i 1 l l < l
l l - JPM SRO-10/ PLT Page 5 of 12 i STEP 4: . Manually close AFW Pump P-8B Steam Supply From SG B, CV-0522A. CRITICAL using the hand operator by unscrewing the coupling from manual override STEP shaft. 4 STANDARD: Operator unscrews the coupling from the manual override shaft. __ SAT Critical Step: Required to gain manual control of CV-0522A.
? CUE: Coupling is unscrewed from manual override shaft. ,,,_ UNSAT EVALUATOR NOTE: Figures 2 and 3 of EOP Supplement 19 provide graphic representation cf these components.
COMMENTS: STEP 5: Manually close AFW Pump P-8B Steam Supply From SG B, CV-0522A, CRITICAL using the hand operator by tuming the handwheel clockwise until the top of STEP the actuator shaft is exposed sufficiently to engage the coupling. STANDARD: CV-0522A is closed using the hand operator sufficiently to engage the coupling.
,_,, SAT Critical Step: Required action to ensure system operability. ' ,,,_,, UNSAT CUE: The tip of the actuator shaft is properly exposed.
COMMENTS: l STEP 6: Completely insert the fork of the coupling onto the actuator shaft of CRITICAL l CV-0552A. STEP j l STANDARD: The fork of the coupling shaft is inserted on the actuator shaft. ._,,,, SAT d Critical Step: Required action to ensure system operability. CUE: The fork of the coupling shaft is inserted on the actuator shaft of CV-0552A.. ,,_ ,_ UNSAT s COMMENTS: l 1 l l l
E .i JPM SRO-10/ PLT Pag 9 6 of 12 s. STEP 7: Open Bonnet Air Isolation Valve, MV FW354. CRITICAL - STEP STANDARD: - Operator opens Bonnet Air is,olation Valve, MV-FW354. Critical Step: Required to gain manual control of CV 0622A. ~ CUE: Bonnet Air isolation Valve, MV-FW354, is open. COMMENTS: _ UNSAT STEP 8: . Using the hand operator, close AFW Pump P-8B Steam Supply From SG B, CRITICAL CV-0522A, using the handwheel. STEP STANDARD: Operator closes CV-0522A using the handwhee!. Critical Step: Required to allow manual control of CV-0622A to supply steam.
~ SAT CUE: CV 0522A is closed.
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COMMENTS: STEP 9: Open PI-0589 root valve, MV-FW687. CRITICAL { STEP STANDARD: Operator opens PI-0589 root valve, MV-FW687. Critical Step: Required to allow monitoring of correct steam pressure.
~ SAT CUE: MV-FW687 is open. >
COMMENTS: _ UNSAT { 1 I i J
7 l JPM SRO-10/ PLT Page 7 of 12 STEP 10: Slowly throttle open AFW Pump P-8B Steam Supply From SG B, CRITICAL CV 0522A, to maintain between 200 and 250 psig steam pressure on STEP PI-0589. STANDARD: Operator establishes 200 to 250 psig steam pressure on PI 0589 by throttling CV-0522A. _ SAT Critical Step: Required to provide correct steam pressure for turbine operation. UNSAT CUE: Pl.0589 indicates 230 psig. j COMMENTS: STEP 11: Notify SS CV-0522A is being manually controlled with steam pressure between 200 and 250 psig. STANDARD: - ^ SS notified. COMMENTS: END OF TASK TIME STOP: l I l I 1 1
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r JPM SRO-10/ PLT Page 8 of 12 JPM QUESTlON # 1 REFERENCE ALLOWED: / NO yes no Question: List four conditions that will cause Steam Generator Blowdown to isolate. 4-For each of the conditions, explain the reason (s) for the isolation. Answer: Any four of the following: CHP lsolates containment to isolate energy sources CHR Limits radioactive release outside containment Blowdown High Level Prevents system damage for control malfunctions Flash tank High Level Prevents system damage for control malfunctions RIA-0707 High Rad Limits radioactive release outside containment CANDIDATE'S RESPONSE Time: 5 min. K/A Rating: 061.K4.03 (2.9)
References:
Lesson Plan ISIC section 6.5 B, and ASDC, page 43
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JPM SRO-10/ PLT Pcg39cf12 JPM QUESTION # 2 REFERENCE ALLOWED: YES / yes no Question: Given the following conditions:
. No Main Feedwater Pumps are available.- . . Auxiliary Feedwater Pump P-8B has tripped on overspeed. ,
e Auxiliary Feedwater Pumps P-8A and P-8C have tripped, i e SG 'A' is faulted with level below- 140%.
. SG 'B'is intact with leve! at - 135%.
The overspeed trip has been reset on Auxiliary Feedwater Pump P-88. What restriction (s) is(are) placed on restoration of feed flow to the SG 'B'? Andwer: Flow must be < 300GPM to SG 'B'. CANDIDATE'S RESPONSE Time: S, min. K/A Rating: 061.K.3.02 (2.9)
References:
EOP 7.0 Background Document I
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- JPM SRO-10/ PLT Page 10 0f 12 JPM QUESTION # 2 CANDIDATE COPY ~
REFERENCE ALLOWED: .YES /_ yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: Given the following conditions:
No Main Feedwater Pumps are available.
Auxiliary Feedwater Pump P-8B has tripped on overspeed.
. Auxiliary Feedwater Pumps P-8A and P-SC have tripped.
SG 'A' is faulted with level below - 140%. SG 'B'is intact with level at- 135% The overspeed trip has been reset on Auxiliary Feedwater Pump P-88. What restriction (s) is(are) placed on restoration of feed flow to the SG 'B'? l
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(-. JPM SRO-10/ PLT Page 11 of 12 JPM QUESTION # 1 CANDIDATE COPY l REFERENCE ALLOWED: / NO yes no (TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER) Question: List four conditions that will cause Steam Generator Blowdown to isolate. For each of the conditions, explain the reason (s) for the isolation.
r , ! - JPM SRO-10/ PLT Pag 312 of 12 1 CANDIDATE CUE SHEET - (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) < INITIAL CONDITIONS: A Control Room Evacuation has occurred.
. Busses 1C and 1D are deenergized. . No AFW Pumps are running.
INITIATING CUES: ivnile performing ONP-25.2, Alternate Safe Shutdown Procedure, the Shift Supervisor has directed you to perform the tasks of Operator ll to start AFW Pump P-8B using the altemate method (Underground Steam Line from 'B' SG) in accordance with EOP Supplement 19 Section 5.0. Turbine Driver K-8 has been verified as latched. i i 4 1 i
r-l- i FINAL AS-ADMINISTERED SCENARIOS FOR THE l PALISADES EXAMINATION - THE WEEK OF JUNE 7,1999 l l l 1 l
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m 3, Appendix D Scenario Outline Form ES-D-1 Facility:_, PALISADES Scenario No.: 1 Op-Test No.: g Examiners: Operators: Objectives:
1) Shift running charging pumps per SOP-2A.

2) Increase turbine, load from 75%.

3) Evaluate and respond to a trip of a running SW pump with a failure of the standbf pump to automatically start. '

4) Evaluate and respond to a low pressure in an SI Tank.

5) Evaluate and respond to a failure of the Tave control signal.

6) Evaluate and respond to a SG tube leak /SOTR.'

7) Evaluate and respond to a charging pump trip during the response to the tube leak.

8) Classify the event.
Initial Conditions / Setup:
1) IC-20 (76%).

2) Tag out AFW P 8C.
MALF FW16C-active e I/O P-8C H/S to TRIP e liO P-8C-G to OFF e I/O P-8C-R to OFF
= Caution Tag P-8C OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
Take P-7C out of STANDBY by rotating HS to TRIP (Event 2) I/O P-7C-A to ON (Event 2) Turnover: Core Age is EOL. 76% power, constant power for load control. Current boron concentration is 98 ppm. PCS pressure is 2060 psig and temperature is 553*F. Rod Position is ARO. SG Blowdown is 20K cach. ASI average is approximately 0.01. MDAFW Pump P-8C is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.5.1). EK-1316, SAFETY INJ TANK T-82A HI/LO PRESS, alarm has been coming in/out. Shift orders are to shift running charging pumps for breaker maintenance on P-55A by placing P-5SB ir. service and increase power to 85% over the next six hours per area power control. NOTE: SURROGA TE OPERA TOR WILL BE FILLING 'TURB ' POSITION DURING THISSCENAR10. S
l livent Malf. Event Event No. No. Type * ) Description i i NA (N) Shift running charging pumps to tag out previously running RX for breaker maintenance. , CRS l' 2 NA (R) I Control of reactivity during power ramp. RX { 3 SWO4A (C) Trip of SW pump P-7A with failure of P-7C to (1) RX. automatically start. 1 CRS . NA (N) Increase of p! ant power TURB CRS f 4 S!04A (C) Low pressure in an SIT. (1) RX CRS 5 RP23B (1) High failure of Tave control signal due to Thot failure (1) RX TURB CRS 6 ScalB (M) SG Tube Leak / Rupture (1) RX TURB l CRS } 7 C 03 ( Trip of charging pump during response to tube leak. CRS l 8 NA CRS Classifies event as a SITE AREA EMERGENCY. Terminate scenario when a cooldown within TS limitations toward shutdown cooling has been initiated, and the faulted S/G has been isolated. or at lead 4 examiner's discretion. l f l (1) See Attachment," Simulator Setup & Actions Required for Scenario 1," for details on setup. l
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor i ) )
n 1 y Simul ter Setup & Actions Required for Scenario 1 AFW P-8C Setup - e MALF FW16C - active e UO P-8C 17/S to TRIP e UO P-8C-G to OFF e UO P-8C-R to OFF e Caution Tag P-8C OOS for breaker maintenance Actions for Event i e UO P-55A to TRIP AFTER the pump is secured (prevents pump from restarting later if attempted) Setup Event 3 Take P-7C out of STANDBY by rotating HS to TRIP (insert prior to scenario start) e' UO P-7C-A to ON (insert prior to scenario start)- NOTE: Remove when HS taken to START.
MALF SWO4A to active Setup Event 4

Adjust "sikkmalfsiO4" from 0.001 to 0.01 MALF SIO4A to active approximately 10 minutes before alarm condition desired (when SWP-7C is started by operator in previous event)
Setup Event 5
MALF RP-23B to 1.00 Setup Event 6 MALF SG01B @ 80 gpm ramped over 5 minutes (value = 0.08) e NOTE: Increase AL4LFSG01B to 700 gym aper transition to EOP-5.0 (value = 0.7)
L Setup Event 7
MALF CV03B to active when Reactor Trip occurs
m., - --
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SHIFT TURNOVER (#1) l e~ Core Age is EOLi l 76% power, constant power for load control. Current boron concentration is 98 ppm. PCS pressure is 2060 psig and temperature is 553 F. Rod Position is ARO. e , SG Blowdown is 20K each.
. ASI average is approximately 0.01.
e l MDAFW Pump P-8C is tagged out ofservice for motor bearirig inspection and is expej back in approximately 8 hours (TS 3.5.1). e j EK-1316, SAFETY INJ TANK T-82A HI/LO PRESS, alarm has been coming in/out. e j Shift orders are to shift running charging pumps for breaker maintenance on P-55A by placing P-55B in service and increase power to 85% over the next six hours per area po control, t. i
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- Appendix D Operator Actions Form ES D-2 Op-Test No.: Scenario No.: 1 Event No.: 1 Page 1 of 1 Event
Description:
Shift Running Charging Pumps to Tag Out Previously Running for Breaker Maintenance. Time Position Applicant's Actions or Behavior Start CRS Directs RO to shift charging pumps from P-55A running to P-55B 0:00 per SOP-2A, section 7.1.7. Monitors / directs RO actions. RX IE removing P-55A from service, THEN leave SIC-0216 in CASCADE. Selects P-55B controller to man (SOP-2A) CRS/RX Directs AO to locally verify pump is ready to start. AO reports that pump is ready to run (SOP-2A)
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RX Shift pumps by starting the selected pump, when charging flow increases, stop the operating pump. Starts P-55B andstops P-55A, reports to CRS. (SOP-2A) RX Ensure that charging flow remains at approximately 40 gpm after switching pumps. (SOP 2A) RX Reports charging pumps have been shifted to B running and A secure. m-
[f , 1 Appendix D . Operator Actions Form ES-D 2 I Op Test No.: Scenario No.: 1 Event No.: 2 Page l' of 1 Event
Description:
Increase of Plant Power and Control of Reactivity During Power Escalation. Time Position Applicant's Actions or Behavior Start CRS Direct the activities of the RXmlRB during the power escalation. 15:00 15 min RX Calculate dilution using the TDM. 10 min CRS Review and approve dilution calculation. t 5 min RX Initiate dilution using section 7.5 of SOP-2A 2 min TURB Enter the load increase rate into the DEH and verify proper operation. I i
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F \ . Appendix D Operator Actions Forra ES-D-2 Op-Test No.: Scenario No.: Event No.: 1 3 Page 1 of I l Event
Description:
Trip of SW Pump P-7A with Failure of P-7C to Automatically Start. Time Position Applicant's Actions or Behavior
~
Start Diagnose Loss of Service Water using the following indications: 42:00 CREW Alarms EK-1131 SERVICE WATER PUMP P-7A OVERLOAD / TRIP EK-1163 CRITICAL SERV WATER HEADER "B" LO PRES ~ 45 psig EK-1164 CRITICAL SERV WATER HEADER "A" LO PRES - 45 Psig EK-1165 NON-CRITICAL SERV WATER LO PRESS -45 psig Indications P-7A tripped P-44 tripped on Panel C-126 5 min CRS Enter and direct the actions of ONP-6.1 NOTE: IFEK-0259, Exciter Cooler Hi Temp, and EK-1165, Non-criticalServ Water Lo Press, BOTH alarm, the crew would be directed to trip the reactor. (NOTEXPECTED TO OCCUR) RX E Service Water Pumps have tripped, THEN start available Service Water Pumps. Starts P-7C (Critical step is to restore SW) (ONP-6.1) TURB E Service Water Pumps have tripped, THEN start available Service Water Pumps. May also start P-44 (SOP-8) 5 min CRS Enter Tech Spec 3.4T2 (7 days to restore)
F' Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 4 Page 1 of 1 Event
Description:
Low Pressure in SIT 'A'. -
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. Time Position !
Applicant's Actiens or Behavior Start CREW Diagnose low pressure in Safety injection Tank A 52:00 i . EK-1316, Safety Inj TarJc T-82A Hi/Lo Press - 205.5 to 208.5 psig
EK-1318, Safety inj Tank T-82A Lo Press - 205 psig
. PI-0363, SI Tank T-82A Press i
RX CheckT-82A level normal. CRS T/S 3. 3.1 All four SITS are operable and pressurized to at least 200 psig with a tank liquid level of at least 174 inches and a maximum level of 200 inches with a boron concentration of at least 1720 ppm, but not more than 2500 ppm. Determine TechnicalSpecification operability is NOTmet. CRS T/S 3.3.2 One safety injection tank may be inoperable for a period of no more than one hour. CRS Directs RO to increase pressure in the SIT A. I NOTE: It is not intended thatpressure be increased in the SIT prior to the next event. l
s Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 5 Page 1 of 1 Event
Description:
High Failure of Tave Control Sigust Due to Thot Failure. Time Position Applicant's Actions or Behavior Start CREW Diagnose High Failure of Tave signal by the following: 62:00 ' Alarms EK0772 LOOP 2 HOT LEG HI TEMP- 610*F EK0924 GROUP 1 PWR DEPENDENT INSERTION LIMIT EK0969 LOOP 2 Tave/TrefGROSS DEVIATION- 5 F difference EK06 Rack A #5 VARIABLE H PWR LVL CHANN PRE-TRIP EK06 Rack C #1 and #5 TM/LO PRES CHANNL TRIP & PRE TRIP Digital Indication Reads 615.3 LIC 0101B output increases Second Charging Pump starts and one orifice is open CRS Refers to and directs the actions of ONP 13. CRS/RX Select Loop 1 on direction from CRS or informs CRS that loop 1 is selected. (ONP-13) lCRS Refers to ARP-21 and SOP-36 and directs actions TURB Bypass the RPS trips for failed channel (SOP-36) l CRS Refers to Technical Specification Table 3.17-1 (T/S 3.17.1.2 - 7 days) l 1 1
W . l Appendix D Operator Actions Form ES-D-2 h Op-Test No.: Scenario No.: 1 Event No.: 6 Page 1 of 6 { Event
Description:
SG Tube Leak / Rupture. l I Time Position f Applicant's Actions or Behavior i Start CREW . Diagnose a SG tube leak by the following indications: 77:00 Alarms 3 ' EK1364 GASEQUS WASTE MONITORING HI RADIATION RIA 0631 CONDENSER OFF GAS MCB PZR Level decreasing PZR Press decreasing Orifice Valves closed Main Steam gamma monitorin alarm i CRS Enter ONP-23.2 and direct actions of crew
. Secondary AO reports off-gas flow rate at 7 cfm when asked. I e Chemistry reports total PCS xenon 133 is 50 Ci/kg when asked. )
CRS Direct a Reactor Trip based on step 4.1.a.4, and table 23.1. (IfSG ' tube leak has been confirmed and chargingflow is increasing, then trip the reactor) CRS Enter and direct the actions of EOP-1 l l __ l (Cont. next page) l l I R.
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% fAppendix D 1 LOperetor'Actions Form ES-D-2 Op-Test No.: Scenario No. 1 Event No.: 6 Page 2 of. 6 Event
Description:
SG Tube Leak /Ry;,ture. Time ; Position ' Applicant's Actions or Behavior 5 min' RX RX verifies the following Critical Functions are met: (EOP1 Att 3) e Reactivity Control '
* - . PCS Inventory Control (NOTMET) e:
f PCS Pressure Control (NOTMET)
. - Core Heat Removal e Containment Isolation : * ' ConteMment Atmosphere . ' Vital Auxiliaries, Water . Vital Auxiliaries, Air.
NOTE: See event #7for loss ofCharging Pump. 5 min - -TURB- _TURB verifies the following Critical Functions are met:(EOP1 Att 2) e Feedwater System Control j y CR Radiation Environment e ~ Vital Auxiliaries, Electric 1
. PCS Heat Removal e- Containment Isolation Operator Actions-Verify at least one Condensate Pump and one Cooling Tower Pump operating. . 5 min CRS IF ANY of the following conditions exist: . ANY safety function acceptance criteria NOT met . . ANY contingency action we taken e ~ Control Room is'NOT habitable ,
THEN REFER TO Attachment 1," Event Diagnostic Flow Chart" l AND diagnose the event. l 1 (Cont. next page) L
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Page 3 of 6 Event
Description:
SG Tube Leak / Rupture. 1 Time Position Applicant's Actions or Behavior RX/TURB Commence Emergency Shutdown Checklist. Refer to GOP-10, j
" Balance of Plant Actions Following a Reactor Trip." i CRS Determines from Attachment 1 of EOP-1.0 that EOP-5.0 should be utilized. Transitions to EOP-5.0 RX When PCS pressure is < 1605 psia, ensure SIAS. PCS Pressure Controlsafety)imetion.
1 5 min CRS/RX When PZR pressure is less than 1300 psia, ; TIIEN stop PCPs as needed to establish one PCP operating in each l loop. o TURB IF an SIAS has initiated THEN perform EOP Supplement 5 " Checklist for Safeguards Equipment Following SIAS."
, (Cont, next page) l
c. Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Page 4 of 6 Event
Description:
. SG Tube Leak / Rupture. Time Position Applicant's Actions or Behavior RX- Initiate Energency boration per EOP Supplement 35 (Not required due to Siflow inprogress) 15 min TURB Cooldown the PCS to highest Tu less than 524 F using the Turbine Bypass Valve. NOTE: It is acceptable to isolate affectedSGprior to verifying throttling criteria is met. CRS Verify SI Pump throttling criteria are satisfied by ALL of the following: Based on the A,erage of Qualified CETs, PCS subcooling meets ONE of the following: At least 25 F subcooled for non-degraded Containment conditions e Corrected PZR level is greater than 20% i e At least one S/G is available for PCS heat removal with corrected level being maintained or being restored to between 60% and 70%. ' Operable RVLMS channels indicate greater than 102 inches above the bottom of fuel alignment plate (621' 8"). NOTE: Allconditions are met. (Cont, next page)
F , l i Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Page 5 of 6 Event
Description:
SG Tube Leak / Rupture. ; j Time . _ Position - Applicant's Actions or Behavior CRS/RX Depressurize the PCS l
~ CRSfrURB Determine the most affected S/G i l
1 10 min 'CRS/TURB WHEN ALL narrow range PCS Tu temperatures are less than 524 I I F, THEN isolate the most affected S/G using EOP Supplement 13 l for "B" S/G. (Critical Step is to limit radiological release) e AFW FIC-0727 to MAN CLOSE
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AFW FIC-0736A/0736 to MAN CLOSE e HS-0522B to CLOSE

HS-0744 to CLOSE

MO-0510 to CLOSE

HS-0501 and HS-0510 to CLOSE then to OPEN-CRSfrURB . Maintain the most affected S/G pressure less than 940 psia CRStrURB . Verify the most affected S/G is isolated i
G (Cont. next page) { 4
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- Appendix D i Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Pr.y v of 6 3 Event
Description:
_ SG Tube Leak / Rupture. I Time - Position Applicant's Actions or Behavior r j RX ; Maintain PCS pressure within the limits of EOP Supplement 1 CRS Ensure the least affected S/G has corrected level being maintained or being restored to between 60% and 70%. Refer to EOP Supplement 11. CRS Calculate minimum PCS cooldown rate. Refer to EOF Supplement 2. CRSrfURB Commence a controlled PCS cooldown. Refer to,EOP Supplement 33 Total NOTE: Terminate the scenario when the controlled cooldown is 122:00 started, with the concurrence ofthe lead examiner.
Appendik D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 7 Page 1 of 1 Event
Description:
Trip of Charging Pump During Response to Tube Leak. Time Position Applicant's Actions or Behavior During RX While utilizing Attachment 3 of EOP-1.0 determines that the P-55B l Event 6 pump is NOT running. Determines that the PCS Inventory safety j function is challenged. j (EOP-1) i i RX Attempts to start Charging Pump. (EOP-l) CRS Evaluates transition to EOP-9.0 IC series for loss of Charging pump. Using Attachment 1 ofEOP-9.0 determines that the safety function is met ifone Chargingpump is operating. (EOP-9.0) i i i 4 4 l I,
Appendix D Operator Actions Form ES-D-2
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Op-Test No.: Scenario No.: 1 Event No.: 8 Page 1 of 1 Event
Description:
Classifies Event as a SITE AREA EMERGENCY. Time Position Applicant's Actions or Behavior 5 min CRS Classify the event as a SITE AREA EMERGENCY using EI-1, PRIMARY COOLANT SYSTEM INTEGRITY, (Primary to secondary leak rate > charging pump capacity.) l i 1 l i 1 l l l l I W
-: .,Pi L Appendix D- Scenario Outline Form ES-D4 Facility: PALISADES Scenario No.: 2 ,Op-Test No.:
Examiners: Operators: I l i n Obje'c tives:' , ,
1) Evaluate and respond to a high failure of PRZR Pressure Control channel.

2) Evaluate and respond to a dropped control rod.

l. 3) Lower reactor power to <75% in response to the dropped rod.

4) ~ Control reactivity during load reduction.

5) . Evaluate'and respond to a failure of a steam flow channel.

6) Evaluate and respond to a loss ofoffsite power, resulting in a Rx Trip and loss of forced circulation.

7) Evaluate and respond to a failure of EDG l-1 output breaker to close.

8) . Evaluate and respond to a trip of AFW Pump P-8B following loss of offsite power

9) Respond to a loss of all feedwater following a loss of offsite power.

10) Classify the event.
Initial Conditions / Setup: 1)' IC-11 (99.7%).
2) Tag out AFW P-8C.
* : MALF FW16C -active 1/0 P-8C H/S to TRIP e- I/O P-8C-O to OFF -
I/O P-8C-R to OFF
e. Caution Tag P-8C OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
. MALF EDI1 A to active (Event 6) *~ MALF FW16B to active (Event 7)
Turnover: Core Age is NEW. 99.7% power, equilibrium conditions. Current boron concentration is 1260 ppm. PCS pressure is 2060 psig and temperature is 560 F. Red Position'is ARO. SG Blowdown is 20K each. ASI average is approximately 0.00. MDAFWP Pump P-8C is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.5.1). Shift orders are to maintain currem power level. NOTE: SURROGA TE OPERA TOR WILL BE FILLING 'CRS' POSITION DURING THISSCENM'!O. L_.
e - l,
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i Event Malf. Event h ent No. No. fype' Description j
' ; p 1 RX05B (1) High failure of PRZR Pressure Control channel '
I (1) IG CRS i
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2 RD12-35 (C) Respond to a dropped rod. I l RX
. (1)
CRS h4 2 3 NA (N) Turbine load reduction to <75o o j 3 TURB CRS J-NA (R) Reactivity control during power reduction.
RX 4 RX15A (I) High failure of a steam flow channel (1) TURB CRS
= 5 ED01 (M) Loss of offsite power, resulting in Rx Trip and loss of
. (1) RX forced circulation (Following events result in loss of all TURB feedwater.) j CRS ; ;
i . 6 EDI1A C) Failure of EDG l-1 output breaker to close. ll ) CRS b H 7 FWl6B (C) Loss of TDAFW Pump P-8B following loss of offsite d (1) TUM power (Results in loss of all feedwater) NA CRS 8 Classify the evera as General Emergency. (Note that surrogate is fil!tng role of CRS in this scenario.) f) Terminate scenario when appropriate actions taken to establish once-through core cooling during the l performance of EOP-7.0 or at lead examiner's ) l discretion. ; I (1) See Attachment. " Simulator Setup & Actions Required for Scenario 2." for details on setup j (N)ormal. (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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{. , Simul ter Setup & Actions Requ!:ed for Scenario 2 AFW P-8C Setup e MALF FW16C -active e I/O P-8C H/S to TRIP e I/O P-8C-G to OFF e I/O P-8C-R to OFF e Caution Tag P-8C OOS for breaker maintenance Setup Event 1 e- MALF RX05B to active Setup Event 2 e MALF RD12-35 to active
' Setup Event 4 e ' MALF RX15A to active at 0.65 -
Setup Event 5.
MALF ED01 to active Setup Event 6 e MALF ED11 A to active (insert prior to scenario start) -
Setup Event 7 e - MALF FW16B to active (insert prior to scenario start)
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SHIFT TURNOVER (#2).
.- Core Age is NEW 4 e 99.7% power, equilibrium conditions. -
e Current boron concentration is 1260 ppm. e' PCS pressure is 2060 psig and temperature is 560 F.
. Rod Position is ARO. j e SG Slowdown is 20K each.- . - ASI average is approximately 0.00.
MDAFWP Pump P-8C is tagg:d out of cervice for motor bearing ineection and is expected back in approximately 8 hours (TS 3.5.1).
. Shift orders are to maintain current power level. 4 i
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, .] - 1 y Appendix D Operator Actions Form ES-D-2 i
i Op-Test No.: Scenario No.: 2 Event No.: 1 Page 1 of I l l Event
Description:
High failure of PRZR Pressure Control channel. 1 I Time - Position . Applicant's Actions or Behavior CREW Diagnose malfunction in PIC-0101B by observation of:
$ EK-0754 PRZ PRESS OFF NORMAL HI/LO - 2110 psia PR-101B red pen high l
PIC-0101B red pen high Spray valves open Pzr Heaters in minimum Verify indications of PZR pressure by performing channel check. CRS Enter and direct the actions of ONP 18. RX Take manual control of PIC-0101B. (Critical task to take manual control and stabilize prior to Reactor Trip) NOTE: May choose to select PIC-0101A as the controlling controller per ONP-18 lastead of taking manual control. This is acceptable. 5 min RX Place PIC-0101 A in service as directed by CRS. RX Monitor pressure control signal CRS Contact I&C to investigate failure of PZR pressure controller
Appendix D Operator Actions Form ES-D-2 1 Op-Test No.: Scenario No.: 2 Event No.: 2 Page 1 of 2 Event
Description:
Respond to a dropped rod. Time Position Applicant's Actions or Behavior l Start CREW Diagnose dropped rod by observation of the following alarms: i 5:00 EK0905 SHUTDOWN ROD POSITION ABNORMAL EK0011 ROD POSITION 4 INCHES DEVIATION EK0912 ROD POSITION 8 INCHES DEVIATION 1 EKJ948 DROPPED ROD EK0969 LOOP 2 Tave/frefGROSS DEVIATION EK0734 CHARGING PUMPS SEAL COOLING LO PRESS ! EK06 Rack C 3,4, and 7 EK06 Rack D 3,4, and 7 Observe the following plant response: Tave decrease PZR Pressure decrease PZR Level decrease I Nuclear Power decrease 3 Charging Pumps running, one orifice open i I CRS Direct actions to be performed per ONP 5.1
Ensure turbine load lowered to match Tave/ Tref e Notify Reactor Engineer I e Notify Electrical Maintenance to troubleshoot

Direct monitoring of ASI and QPT(EM-04-02)
- Direct power reductions to be performed by boration 10 min TURB Reduce turbine load as necessary to match Tave/ Tref. See event #3.
RX Reduce power to less than 75% by boration as necessary. NOTE: Reactor Power may be less than 75% due to the dropped rod. (Cont. next page) s
l-l Appendix D Operator Actions Form ES-D-2 ) Op-Test No.: Scenario No.: 2 Event No.: 2 Page 2 of 2 Event
Description:
Respond to a dropped rod. Time Position Applicant's Actions or Behavior 5 min CRS Refer to Tech Spec 3.10.4 ( 2 hours to restore or be in Hot Shutdown within the following 12 hours) i 1 i i i
Appendix D . Operator A'/'ons Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 3 Page 1 of 1 Event
Description:
Turbine load reduction to <75% and Reactivity control during power reduction. I Time Position - Applicant's Actions or Behavior start - CRS- Direct the activities of the RX/TURB during the power reduction. 20:00 15 min RX Calculate the boron addition using the TDM. i i 10 min CRS Review and approve boron calculation. 1 I l l 5 min RX Initiate boration using section 7.5 of SOP-2A
, 2 min TURB Enter the load decrease rate into the DEH and verify proper operation.
Note: If the crew utilizes the Rapid Shutdown ONP, then they should:
. Drive Group IV Regulating Rods in =10 inches, and e Reduce turbine load at < 300%/hr as directed by CRS e Adjust rods to maintain Tave/ Tref W/I 5 F NOTE: PDIL limits do not apply during rapid load reductions.
l. I U .
3 i I i Appendix D Operator Actions. Form ES-D 2 I l Op-Test No.: Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
Low failure of a steam flow channel.
. Time Position Applicant's Actions or Behavior Start CREW . Diagnose the Steam Flow Channel low failure by observation of the 52:00 following alarm:
EK-0962 STEAM GEN E-50A LO LEVEL- 55% j Plant Indications l Steam Low Feed Flow Mismatch Lowering Steam Generator Level Lowering Feed Flow CRS Enter and direct the actions of ONP-3 l 1 5 min TURB Take manual control of LIC-0703 and raise feed flow until it matches steam flow. Gradually increase feed flow to recover steam j generator level. (Critical step to establish steam generator level l l control prior to Reactor Trip) l I \ l l ! TURB Monitor feed / steam flow, i i l l l .- CRS Contact I&C to investigate failure of feed flow channel.
m , Appendix D Operatcr Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 1 of 2 Event
Description:
Loss of offsite power, resulting in Rx Trip and loss of forced circulation (Following events result in loss of all feedwater.) Time Position Applicant's Actions or Benavior Start CREW Diagnose Loss of Offsite Power by: 57:00 Reactor Trip PCS Low Flow No Safety injection Undervoltage Alarms on Busses l A.B,C, and E CRS Enter and direct the actions of EOP-1.0 5 min RX RX verifies the following Critical Functions are met: (EOP1 Att 3) i e Reactivity Control e PCS Inventory Control e PCS Pressure Control i Core Heat Removal (NOTMET) 1 e Containment Isolation
Containment Atmosphere e Vital Auxiliaries, Water I e Vital Auxiliaries, Air (Cont. next page)
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 2 of 2 l Event
Description:
Loss of offsite power, resulting in Rx Trip and loss of forced circulation (Following events result in loss of all feedwater.) 7 min TURB TURB verifies the following Critical Functions are met:(EOPl Att i
2) i e Feedwater System Control (NOTNET)
CR Radiation Environment Vital Auxiliaries, Electric (NOTMET) e PCS Heat Removal e Containment Isolation Operator Actions-Verify at least one Condensate Pump and one Cooling Tower Pump operating. NOT met, the TURB must close the MSIV's. (Critical Step is prevent damage to plant equip) - l i l
)
CRS IF ANY of the following condition:: exist ANY safety function acceptance criteria NOT met (See above)
ANY contingency action was taken l
Control Room is NOT habitable THEN REFER TO Attachment 1," Event Diagnostic Flow Chart" AND diagnc% ihe event. I RX/TUPB Commence Emergency Shutdown Checklist. Refer to GOP-10,
" Balance of Plant Actions Following a Reactor Trip."
l 5 min CPS Refer to Diagnostic Flowchart (EOP 1.0, Attachment 1), to determine which procedure to enter. Recognize that EOP-8.0 and EOP-7.0 should be considered. CRS Transitions to EOP-7.0
' Appendix D Operator Actions Form ES-D-2 l
Op-Test No.: Scenario No.: 2 Event No.: 6 Page 1 of 1 Event
Description:
Failure of EDG 1-1 output breaker to close. l
. Time Position Applicant's Actions or Behavior During TURB Utilizing attachment 2 of EOP-1.0 determine that bus IC is not Event 5 energized TURB Determine that EDG l-1 is running with the output breaker open.
1 l i
)
TURB Report EDO l-1 status to CRS. 1 CRS Notifies Electrical Maint. of the breaker problem. :
e . l ^ Appendix D Operator Actions Pan ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 1 of 2 Event
Description:
Loss of AFW Pump P-8B following loss of offsite power (Results in loss of all feedwater). Time Position Applicant's Actions or Behavior Start CRS Give a crew brief for entry into EOP 7.0. 74:00 l CREW Dispatch AO to investigate P-8B trip. I 2 min RX Commence emergency boration. CRS Direct NCO to stop remaining PCPs. (None running) Close S/G bottom blowdown valves. Stop all secondary sampling and unnecessary steam discharge. CRS Direct RXffURB to come.ence cooldown to allow feeding S/Gs with a condensate pump. NOTE: With neither Bus 1A nor Bus 1B available, it is not possible to make a condensatepump available, so this action may not be taken. (Cont. next page) N
.. Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 2 of 2 Event
Description:
Loss of AFW Pump P-8B following loss of offsite power (Results in ' loss of all feedwater). Time Position Applicant's Actions or Behavior 5 .n RX Place LTOP in service. ! 1 TURB Block MSIV atto closure. CRS When both steam generators lower to -84%, implement EOP 9.0 HR-4 t I min RX Initiate SIAS. (Critical Step is to provide source of cooling water ' l for once through cooling). i 1 l 1 min RX Establish once-through cooling utilizing PORV's and PORV isolation valves. (Critical Step to provide exit path for heated water when utilizing once through cooling) RX Monitor CETs for effective core heat removal. Total NOTE : Terminate the scenario when once through cooling is 93:00 established and with the concurrence ofthe Lead Examiner
I[_ i
. Appendix D - Operator Actions Form ES-D-2 g
Op-Test No.: : Scenario No.: 2 Event No.: 8 Page 1 of 1 Event
Description:
Classify the event as General Emergency. Time. -- Position Applicant's Actions or Behavior (Note that surrogate isfilling role of CRS in this scenario.) 5 min CRS Classify event as a General Emergency using El-1, Attachment 1 ENGINEERED SAFETY FEATURES. (Transient initiated by loss ofFeedwater und Condensate System, followed byfailure ofthe Auxillary Feedwater Systemfor an extendedperiod) 1 l i l \
I l.
L. l 1 1
- 1
\
i Appendix D Scenario Outline Form ES-D-1 q 1 Facility: PALISADES Scenario No.: 3 Op-Test No.: Examiners: Operators: 4 Objectives:
1) Evaluate and respond to contaminants in EDG l-1 fuel oil.
1
2) Perform a plant shutdown at 12% per hour.

3) Evaluate and respond to a low failure of a SG feed flow channel. }
I
4) Evaluate and respond to a low failure of a PRZR level channel. i
~
5) Evaluate and respond to a trip of a cooling water pump with subsequent rapid power reduction in response to lowering condenser vacuum.
q
6) Control reactivity during rapid power reduction.

7) Evaluate and respond to increasing SG tube leakage requiring Rx Trip.

8) Evaluate and respond to a steamline break outside containment on the SG with tube leakage upon the Rx Trip.
l
9) Evaluate and respond to a fai:ure of HPSI discharge valve, resulting in inadequate SI flow i following actuation.

10) Classify the event.
{ i Initial Conditions / Setup: I
1) IC-11 (99.7%).

2) Tag out HPSI Pump P-66A.
. RM SI23 to RACKOUT e Caution Tag P-66A OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
I/O CV-3059 to CLOSE (Event 7) e I/O CV-3059-R to ON (Event 7) I/O CV-3059-G to OFF (Event 7) Turnover: Core Age is NEW. 99.7% power, equilibrium conditions. Current boron concentration is 1260 ppm. PCS pressure is 2060 psig and temperature is 560 F. Rod Position is ARO. SG Blowdown is 20K each. ASI average is approximately 0.00. HPSI Pump P-66A is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.3.1). Shift orders are to maintain power. I l 1
Event Malf. No. Event Event No. Type
Description l 1 NA (C) Chemistry reports contaminants found in EDG l-1 ft.el oil i CRS sample. l 2 NA (N) Lower power at 12% per hour.
TURB CRS NA (R) Control reactivity during power reduction. RX 3 RX14 (1) Low failure of SG feed flow channel. (1) TURB , CRS i RX07B (I) Low failure of a PRZR level channel. ; 4 (1) RX l CRS 5 CWOlA (C) Trip of cooling water with subsequent rapid power (1) TURB reduction in response to lowering condenser vacuum. CRS 6 SG01A (C) Increasing SG tube leakage requiring Rx Trip. (1) RX TURB CRS 7 MS06A (M) Steamline break outside containment on SG with tube (1) RX leakage upon Rx Trip. TURB CRS 8 (1) (C) Failure of HPSI discharge valve (disc separated from stem), r su!!ing in inadequate SI flow following actuation. CS 9 NA CRS Classifies event as General Emergency. NOTE: Terminate the scenario when the operators cooldown and depressurize the plant to establish LPSI flow or when they establish HPSI flow and with the lead examiners concurrence. (1) See Attachment," Simulator Setup & Actions Required for Scenario 3," for details on setup. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor f u ;
4 e Simulator Setup'& Actions Required for Scenario 3
' HPSI P-66A Setup - e ' RM S123 to RACKOUT
Caution Tag P-66A OOS for breaker maintenance Setup Event 3 .
y e MALF RX14A at 0.0001 Setup Event 4 e' MALF RXO7B to activate Setup Event 5
MALF CWOI A to activate t
Setup Event 6
MALF SG01 A at 0.06 (Enter upon Reactor Trip if a trip occurs as a result of the Cooling Tower Pump trip). .
Setup Event 7
* . .. MALF MS06A at 1,0 (Enter upon Reactor Trip)
Setup Event 8 e I/O CV-3059 to CLOSE (insert prior to scenario start) e I/O CV-3059-R to ON (insert prior to scenario start)
I/O CV-3059-G to OFF (insert prior to scenario start)
p
' SHIFT TURNOVER (#3)' ;
i .- . e . - Core Age is NEW.-
~
e 99.7% power, equilibrium conditions. , e ' Current boron concentration is 1260 ppm.
+ ' PCS pressure is 2060 psig and temperature is 560 F.
Rod P isition is ARO.- I eL. SG Blowdown is 20K each. I
, .. .. ASI average is approximately 0.00. . HPSI Ptunp P-66A is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.3.1). . . Shift orders are to maintain power.
1 i l
.1 1
ll
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t
' Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Page 1 of I Event
Description:
Chemistry reports contaminants found in EDG 1-1 fuel oil sample. Time Position Applicant's Actions or Behavior Start CRS Chemist reports that sediment in the Fuel Oil Storage tank is out of 0:00 Specification high. A second sample has been drawn and verifies the first sample. 10 min CRS Enters Technical Specification 3.7.3.C and declares both EDG's INOPERABLE. CRS Enters Technical Specification 3.7.1.E Two hours to restore one EDG to operable or Hot Shutdown within the next 12 hours and Cold Shutdown within the following 48 hours. CRS Notifies Plant Management of Technical Specification entry and required actions. NOTE: Acting asplant management, direct the crew to lower power at 12% per hour.
L Appendix D. Operator Actions Form ES-D-2 l Op-Test No.: Scenario No.: 3 . Event No.: 2 Page 1 of 1 Event
Description:
Lower power from 100% and Control reactivity during power reduction. Time Position Applicant's Actions or Behavior Start CRS Direct the activities of the RX/TURB during the power reduction. ; 10:00
]
15 min RX Calculate the boron addition using the TDM. t 10 min CRS Review and approve boron calculation. i 5 min RX Initiate boration using section 7,5 of SOP-2A l I 2 min TURB Enter the load decrease rate into the DEH and verify proper operation. i l l \
p l
- Appendix D Operator Actions Fonn ES-D-2 l
j: ) Op-Test No.: Scenario No.: 3 Event No.: 3 Page 1 of 1 Event
Description:
Low failure of SG feed flow channel. Time Position Applicant's Actions or Behavior 1 Stan CREW Diagnose Feedwater Flow Transmitter low failure by observation of ' 42:00 the Main Feed Regulating valve. The SG high level alarm at 85% may or may not come in. As the SG level increa:-s, the program , level signal will cause the MFRV to cycle full open to tull close to i limit SG level. i CRS Enter and direct action per ONP-10 I 5 min TURB Take manual control of LIC-0701. TURB Match steam and feed flow to stabilize SG level. Slowly adjust MFRV position to return SG level to program. CRS Contact I&C to investigate Feedwater Flow Transmitter failure.
l Appendix D Operator Actions Form ES-D-2 i Op-Test No.: Scr 1ario No.: 3 Event No.: 4 Page 1 of 1 Event
Description:
Low failure of a PRZR level channel. Thne Position Applicant's Actions or Behavior Start CREW Diagnose malfunction in LIC-01018 by observation of: 47:00 EK0704 LETDOWN HT EX TUBE INLET Hi-LO PRESS - 500 psig EK0741 PZR HTR TRNS #15 AND #16 BRKRS TRIP EK0761 PRESSURIZER LEVEL HI LO - 5.75% deviation l EK0764 PRESSURIZER LEVEL CH "B" LO-LO - 36% EK0770 FAILED FUEL MONITOR LOW FLOW-0.22 gpm B and C CCP's start PZR Heaters in minimum Letdown orifice isolation valves close. 1 CRS Direct RX to transfer controllers per SOP-1. 5 min RX Place LIC-0101 A in service as directed by CRS. (Critical task to stabilize prior to Reactor Trip) RX Take manual control of LIC-0101B. NOTE: This action is acceptable to perform prior to changing controllers. RX Place Heater Control selector in 'A' position. i RX Monitor level control signal
CRS Contact I&C to investigate failure of PZR level controller
~
l' Appendix D - Operator Actions Form ES-D 2 l- ! Op-Test No.: Scenario No.: 3 Event No.: 5 Page 1 of 3 Event
Description:
Trip of cooling water with subsequent rapid power reduction in response to lowering condenser vacuum and Reactivity control
during rapid power reduction.
Time Position Applicant's Actions or Bchavior Start CREW Diagnose the loss of Cooling Tower Pump by: 52:00 EK-3522 CLG TWR PUMP P-39A TRIP l P-39A Handswitch mismatch ; Cooling Tower Basin Hi/LO level Decreasing Condenser Vacuum NOTE: This event will result in a reactor trip due to rapidly lowering condenser vacuum. Candidates must have taken actions to respond in accordance wiik procedures to satisfy the intent of this event. 15 min CRS Direct RX/TURB to perform rapid shutdown to stabilize condenser backpressure utilizing ONP-26. TURB Perform rapid down power at rate specified by the CRS. RX Begin Reactor power reduction by inserting Group 4 Regulating Rods approximately 10 inches in " Manual Sequential." l TURB Commence turbine load reduction using the Setter OR Runback at a rate <300%/ hour, as ordered by the Control Room Supervisor. f I (Cont. next page)
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 2 of 3 Event
Description:
Trip of cooling water with subsequent rapid power reduction in response to lowering condenser vacuum and Reactivity control during rapid power reduction.
' Time - Position Applicant's Actions or Behavior RX Attempt to maintain T AVE within 5 F of TRtr during the rapid power reduction by regulating rod insertion. NOTE: PDIL limits do NOT apply during rapidpower reduction.
CRS Direct performance of ONP 14 for loss of P-39A. TURB Perform ONP 14 Cire Wster actions for P-39A.
* ' Reduce power to 55%
e Open the affected side Waterbox Inlet to at least 20% open P-39A is MO-5301 TURB Ensure closed Dilution Water Pump Discharge Valve to Mixing Basin on affected side: P-39A is MO-5311 TURB Ensure fully open Dilution Water Pump Discharge Valves to Cooling Towers on affected side: P-39A is MO-5313 and MO-5315 (Cont. next page) w n
I Appendix D Operator Actions Fomi ES-D-2 l Op-Test No.: Scenario No.: 3 Event No.: 5 Page 3 of 3 Event
Description:
Trip of cooling water with subsequent rapid power reduction in response to lowering condenser vacuum and Reactivity control during rapid power reduction. I 1 Time Position Applicant's Actions or Behavior TURB Ensure closed Cooling Tower Blowdown Valve on affected side 1 e P-39A is MO-5326A ' l l : CRSfrURB Direct AO to isolate condenser blowdown and start additional air j ejectors. l }
s
~ Appendix D Operator Actions Form ES-D-2 Op-Test No.i Scenario ha.: 3 Event No.: 6 Page 1 of 3 l )
Event De.,cription: SG tube leakage following Rx Trip. Time Position Applicant's Actions or Behavior Stut CREW Diagnose a SG tube leak by the following indications: 67:00 Alarms EK1364 GASEOUS WASTE MONITOluNG III RADIATION RIA 0631 CONDENSER OFF GAS MCB PZR Level decreasing PZR Press decreasing Orifice Valves closed I Main Steam gamma monitor in alarm NOTE: Reactor trip willhave occurred on Cooling Tower Pump trip. Candidates must diagnose post-trip SG tube leak. CRS Enter and di ect the actions of EOP-1 (Next Page) 1 (Cont. next page) l i 1
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 6 Page 2 of 3 Event
Description:
SG tube leakage following Rx Trip. Time Position Applicant's Actions or Behavior 8 min RX RX verifies the following Critical Functions are met: (EOP1 Att 3) e Reactivity Control e PCS Inventory Control (NOT AIET) e PCS Pressure Control (NOT AIET)
Core Heat Removal e Containment Isolation i

Containment Atmosphere e Vital Auxiliaries, Water I e Vital Auxiliaries, Air l 5 min TURB TURB verifies the following Critical Functions are met:(EOPl Att 1 2) e Feedwater System Control (Eventually NOT met) l e CR Radiation Environment
. Vital Auxiliaries, Electric + PCS Heat Removal e Containment Isolation Operator Actions-Verify at least one Condensate Pump and one Cooling Tower Pump operating.
5 min CRS IF ANY of the following conditions exist:
ANY safety function acceptance criteria NOT met

ANY contingency action was taken e Control Room is NOT habitable THEN REFER TO Attachment 1," Event Diagnostic Flow Chart" AND diagnose the event.
(Cont. next page) L
1 l Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 6 Page 3 of 3 Event
Description:
SG tube leakage following Rx Trip. r-Time Position Applicant's Actions or Behavior Commence Emergency Shutdown Checklist. Refer to GOP-10, RX/TURB " Balance ofl'lant Actions Following a Reactor Trip." CRS Determines from Attachment 1 of EOP-1.0 that EOP-9.0 should be utilized due to SGTR with a steam line break. (See next eventfor actions to respond to steam line break.) CRS Implements EOP-9.0, HR-2, SGs Available with SI 10 min TURB Isolates SG 'A' 5 min RX Place LTOP in service. CRS Implements CI-1, Containment Isolation 1 min TURB Initiate Containment Isolation
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 1 of 1 Event
Description:
Steamline break outside containment on SG with tube leakage upon Rx Trip. Time Position Applicant's Actions or Behavior During CREW Diagnose a Main Steam Line Break Outside Containment by: Event 5
Indicated Steam flow e Lew Pressurizer Pressure e Drcreasing Tave (<525 F)
TURB During performance of EOP-1.0, Attachment 2, determine that the Feedwater Systems Control safety function is NOT met. CRS/FURB When Tave is < 525 F, TRIP both Main Feed Pumps. (Critical Step to stop adding water to a faulted SG) CRS/TURB When SG pressure is < 800 psia, CLOSE both MSIV's. (Critical Step to isolate the steam break) RX When PCS pressure is < 1605 psia, ensure SIAS. PCS Pressure Controlsafe yfunction.
/
Note: Go to next event
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 1 of 2 Event
Description:
Failure of HPSI discharge valve (disc separated from stem), resulting in inadequate SI flow following actuation. Time Position Applicant's Actions or Behavior Start RX , Ensure ALL available HPSI and LPSI pumps operating with the 103:00 associated loop isolation valves CRS/RX When PZR pressure is less than 1300 psia, THEN stop PCPs as needed to establish one PCP operating in each loop. 5 min TURB IF an SIAS has initiated THEN perform EOP Supplement 5 " Checklist for Safeguards Eouipment Following SIAS." 2 min RX Verify at least minimum SI flow. REFER TO EOP Supplement 4. Determine that HPSI flow does NOT meet the requirements of Supplement 4. NOTE: May open Train 2 Valve, CV-3018, to establish HPSI flow. CRS Recognir.es that based on PCS pressure and subcooling SI Throttling criteria are NOT met. If throttling criteria are met, then no HPSI flow would be required. RX Initiate Emergency Boration. (Cont. next page)
. l 1
Appendix D
)
Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 2 of 2 Event
Description:
Failure of HPSI discharge valve (disc separated from stem), resulting in inadequate SI flow following actuation. Time Position Applicant's Actions or Behavior RX IF PCPs are operating, THEN verify PCP operating limits are satisfied. BEFER TO EOP Supplement 1. (EOP-6.0 step 9) Operating limits are satisfied. I t 5 min RX Place LTOP in service. (Critical step is to prevent PCS failure during subsequent PCS pressurization) l l 5 min TURB Stabilize PCS temperature by using the ADV and controlling SG level. CRS Verify SI Pump throttling criteria are satisfied by ALL of the l following: i e Based on the Average of Qualified CETs, PCS subcooling meets ONE of the following: ,
At least 25 F subcooled for non-degraded Containment {
conditions i e Corrected PZR level is greater than 20% (NOTMET) e At least one S/G is available for PCS heat removal with corrected level being maintained or being restored to between 60% and 70%.
Operable RVLMS channels indbate greater than 102 inches above the bottom of fuel alignn.ent plate (621' 8").
NOTE: May be met ifcrew opened CV 3018 previously. Otherwise, PZR level will not be met and a plant cooldown and depressurization would be required. Total NOTE: Terminate the scenario when the operators cooldown and 120:00 depressurize the plant to establish LPSIflow or when they establish HPSIflow and with the lead examiners concurrence. L
7-i* i
. Appendix D ~
Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 9 Page 1 of 1 Event
Description:
Classifies event ar GENERAL EMERGENCY. l l l l- Time Position Applicant's Actions or Behavior l 5 min CRS Classify the event as a GENERAL EMERGENCY using EI-1, PRIMARY COOLANT SYSTEM INTEGRITY. (Primary to secondary leak rate > 50 gym and steam break inside or outside containment) NOTE: Cand'date should not use SECONDARY SIDE chart, note requires using the Primary Coolant Integrity \ chart. l 1 1 l l I I L l l l
w g s iAppendix D L Scenario Outline Form ES-D-1 i Facility: PALISADES Scenario No.: 4 Op-Test No.: b. Examiners: Operators: I Objectives:
1) Perform Stop and Governor Valve testing per SOP-8.

2) _ Raise power to 100% to following turbine valve testing.

3) Control core reactivity during power increase.

4) Evaluate and respond to a high failure ofletdown pressure control.
.5)- Evaluate and respond to high PCS activity.-
6) . Evaluate and respond to a low failure of SG B level transmitter.

7) - Evaluate and respond to a trip of a running charging pump.

8) Evaluate and respond to a large break LOCA.
9)' Evaluate and respond to a failure of automatic actuation of CHP/CIS.
10) Classify the event.
Initial Conditions:
1) IC-20(76%).

2) Raise power to 86% to support Govemor Valve Testing.

3) Maintain power level for approximately 30 minutes.

4) Tag out HPSI Pump P-66A.
W - * ~ RM S'
.o MCKOUT e C(_ ion Tag P-66A OOS for breaker maintenance
5) Plw DEH control in Governor Single valve mode.
Scenario Event Setup Prior to Scenario Start:
~
e ' MALF CH05A to activate (Event 9) .
.. MALF CH05B to activate (Event 9) .
Tumover: Core Age is EOL. 86% power, constant power for 30 minutes following a 10% load increase over the last two hours from 76% equilibrium conditions. Current boron concentration is 83 i ppm.- PCS pressure is 2060 psig and temperature is 553 F. Rod Position is ARO. SG . I Blowdown is 20K each. ASI average is approximately 0.01. HPSI Pump P-66A is tagp; out of sesice forhetor bearing inspection and is expected back in approximately 8 hours (i S 3.3.1). DEH controller is in Governor Single valve mode. SOP-8 is in progress (step 1.1.1.c complete) to test Stop and Governor Valve #3 only. Shift orders are to test Stop and Governor j Valve #3 and then reum the unit to 100% conditions. Note: Double charging and letdown ; is to be used. l I m: J a
3 Event Malf. Event Event No. No. Type
Description 1 NA (N) Perform test of Stop and Governor Valve #3.
TURB CRS 2 NA (N) Raise power to 100%. TURB CRS NA (R) Control reactivity during power reduction. RX i 3 CV05 (I) High failure ofletdown pressure control. (1) RX l CRS 4 NA (C) Chemistry reports PCS activity at a value exceeding Tech CRS Spec limits. 1 1 5 RX10C (I) Low failure of SG B level transmitter. (1) TURB i CRS 6 C\' 3A ( Trip of running Charging Pump. CRS 7 RC04 (M) Large break Loss of Coolant Accident. RC02 RX ; (1) TURB CRS 8 CH05A (C) Failure of automatic actuation of CHP/CIS. CH05B RX (1) CRS 9 NA CRS Classifies event as Site Area Emergency. Terminate scenario when proper alignment completed following failure of CHP/CIS or at lead examiner's discretion. I (1) See Attachment, " Simulator Setup & Actions Required for Scenario 4," for details on setup.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
(
o k l
,. i Simulator Satup & Actions Required for Scenario 4 l l HPSI P-66A Setup j e RM S123 to RACKOUT l
Caution Tag P-66A OOS for breaker maintenance Setup Event 3

MALF CV05 to active Set"p Event 5 l

MALF RX10C at 0.0001-I Setup Event 6

MALF CV03A to activate Setup Event 7 I e MALF RC04, ramped over 4 minutes, at 0.7 e MALF RCO2 (insert after operators trip last 2 PCPs)
Setup Event 8
MALF CH05A to activate (insert prior to scenario start) e MALF CH05B to activate (insert prior to scenario start)
^' NOTE: These malfunctions willneed to be deleted to allow manualinitiation when the ;
operator depresses thepush buttons. i l 1 _n
7. I. SHIFT TURNOVER (#4) h e Core Age is EOL.
. 86% power, constant power for 30 minutes following a 10% load increase over the last two hours from 76% equilibrium conditions.
e ~ Current boron concentration is 83 ppm.
PCS pressure is 2060 psig and temperature is 553'F.
e'- Rod Position is ARO.
. SG Blowdown is 20K each. .. ASI average is approximately 0.01.
HPSI Pump P-66A is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.3.1).
. - DEH controller is in Govemor Single valve mode. SOP-8 is in progress (step 1.1.1.c complete) to test Stop and Governor Valve #3 ONLY. . Shift orders are to test Stop and Governor Valve #3 and then return the unit to 100%
conditions.
Double charging and letdown is to be used.
l 1 I M
4
~ "
l. l Appendi:: D Operator Actions Form ES-D-2 l Op-Test No.: Scenario No.: 4 Event No.: 1 Page 1 of 2 l Event
Description:
Perform test of Stop sud Governor Valve #3. Time Position Applicant's Actions or Behavior start CRS/TURB IAW SOP-8 attachment 2: 0:00 Set status ofIMPULSE PRESSURE LOOP to IN. TURB Raise valve limiter setting to approximately 103%. 1 TURB Station an observer at the valves to be tested j l TURB Press VALVE TEST DISPLAY on the DISPLAYS keypad. l TURB Tab the CURSOR to the Stop Valve (SV3) to be tested and press SELECT. I i l l TURB Press VALVE TEST CLOSE on the CONTROL keypad and J observe the following: ;
The CRT will display "In Progress" for valve test. l

The Governor Valve corresponding to the sclerted Stop Valve i will begin closing. l
. The Governor Valve position meter below the CRT and ttx )
graphic on the CRT will both show Goverr.or Valve closing.
After the Governor Valve is closed, the DEH Controller will !
output a five-second signal to close selected Stop Valve. Stop Valve will reopen after five seconds. (Cont. next page)
i Appendix D Operator Actions Form ES-D-2 l Op-Test No.: '. scenario No.: 4 Event No.: 1 Page 2 of 2 Event
Description:
Perform test of Governor Valve #3. Time Position Applicant's Actions or Behavior TURB To reopen the Governor Valve, press VALVE TEST OPEN on the CONTROL keypad and observe the Governor Valve returns to its pretest position. TURB Wait 5 to 10 minutes for the tested governor valve to return to its' pretest position. I l l l l t-
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 2 Page 1 of I l Event
Description:
Raise power to 100% and Control reactivity during power escalation. Time Position Applicant's Actions or Behavior Start CRS Direct the activities of the RXHURB during the power escalation. 20:00 15 min RX Calculate the dilution using the TDM. 10 min CRS Review and appcove dilution calculation. 5 min RX Initiate dilution using section 7.5 of SOP-2A 2 inin TURB Enter the load increase rate into the DEH and verify proper operation. ! i l
F Appendix D Operator Actions Form ES-D-2 i Op-Test No.: Scenario No.: 4 Event No.: 3 Page 1 of 2 Event
Description:
High failure ofletdown pressure control. 1 Time Position Applicant's Actions or Behavior l Start CREW Diagnose failure ofletdown pressure controller by observation of 52:00 the following: EK-0704 LETDOWN HT EX Hl/LO INLET PRESS Letdown flow increasing Erratic pressure caused by flashing in the letdown line. CRS Check Charging and Letdown Flows matched, and check Low Pressure Letdown Pressure controller PIC-0202 controlling at approximately 460 psig. (ARPfor EK-0704) 10 min RX Place PIC-0202 in MANUAL and maintain at 460 psia. (Critical step is to controlletdown pressure.) NOTE: Thefollowing actions are optionalactions that may be taken ifPIC-0202 is NOTplaced in MANUAL RX [E Back Pressure Regulating Valve CV 2012 or CV-2122 , malfunction is indicated, THEN shift controlling valve referring to i SOP-2A, Section 7.3. RX Determine PIC-0202 output control signal on Panel C-02. RX Place PIC-0202 in MANUAL by depressing the pushbutton. RX Begin transfer of control by simultaneously: 1
; (Cont. next page) l l
l
Appendix D Operator Actions . Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 3 Page 2 of 2 Event
Description:
High failure ofletdown pressure control. Time . Position Applicant's Actions or Behavior RX VERY SLOWLY operate HIC-2122 on Panel C-12 using the thumb wheel to obtain 'l/2 the output determined above. RX Operate PIC-0202 in the manual closed direction to maintain pressure at approximately 460 psig. RX Operate HS-0202 on C-12 to the desired position. RX Complete transfer by simultaneously:
. VERY SLOWLY operate HIC-2122 using the thumb wheel until the output signal is at 0%. . Operate PIC-0202 in the manual open direction to maintain pressure at approximately 460 psig.
i l 1 j
m Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4' Event No.: 4 Page 1 of 1 , Event
Description:
Chemistry reports PCS activity at a value exceeding Tech Spec l
' limits. ]
Time Position Applicant's Actions or Behavior Start CRS Chemist reports that specific activity of the PCS is 3.2pCi/ gram 62:00 dose equivalent I-131 l 5 min CRS - T/S3.1.4 The specific activity of the primary coolant shall be limited to:
1) < l.0 Ci/ gram dose equivalent I-131, and

2) < 100/ pCi/ gram.
t l CRS With the specific activity of primary coolant > 1.0 Ci/ gram dose equivalent I-131 but less than 40 pCi/ gram, operation may continue for up to 72 hours provided that operation under these circumstances shall not exceed 36 days per calendar year. (action b) CRS Initiates the sampling and analysis requirements ofitem I of Table 4.2.1 until the specific activity of the primary coolant is restored to within its limits. (action e) CRS Notifies Plant managen ent of T/S entry and required actions, and makes log entries, j l l t - - - - _ --
)
i . ) l Appendix D Operator Actions Fom1 ES-D-2 i Op-Test No.: Scenario No.: 4 Event No.: 5 Page 1 of 1 Event
Description:
Low failure of SG B level transmitter. Time Position Applicant's Actions or Behavior Start CREW Diagnose the level transmitter failure by observation of: l 67:00 EK-0963 STEAM GENERATOR E-50B HI LEVEL- 85% l EK-0105 TURBINE HIGH VIBRATION l High Level Override from LIA-0704 closes Feedwater l Regulating Valve CV-0703. The Feed Reg. valve cycles from full open to full closed. CRS Check Steam Generator level;IE high, THEN refer to ONP-10,
" Excessive Feedwater Increase." (ARPfor EK-0963) 5 min TURB Take manual control of Feedwater Valve (s) or Feedwater Purnp Turbine (s) to stabilize / reduce S/G level (s). (ONP-10 step 1) 5 min TURB Matches Steam and Feed flow. Slowly reduces feed flow to restore SG level to programmed level.
CRS Notifies I & C to investigate and repair Steam Generator level channel.
F Appendix D Opcrator Actions Form ES D-2 Op-Test No.: Scenario No.: 4 Event No.: 6 Page 1 of 1 Event
Description:
Trip of running Charging Pump. ! l l Time Position Applicant's Actions or Behavior ! Start CREW Diagnose loss of Charging Pump by observation of: 77:00 EK-0727 CHARGING PUMPS PSSA, P55B, P55C TRIP EK-0735 CHARGING LO FLOW j EK-0740 DHARGING PUMPS DICHARGE LO PRESS ! Charging flow indicates zero. 1 RX Reduce to single letdown. 5 min RX Adjust PIC-0202 in MANUAL and maintain at 460 psia. CRS Declare previously running pump inoperable. Refer to Technical Specification 3.2. (ARPfor EK-0735 and 40) i
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 7 Page 1 of 4 Event
Description:
Large break Loss of Coolant Accident. Time Position Applicant's Actions or Behavior Start CREW Diagnose LOCA by observation of the following: 82:00 EK-1361 CONTAINMENT HI PRESS EK-1362 CONTAINMENTPRESSURE OFF NORMAL EK-1363 CONTAINMENT HI RADIATION EK-1354 GASEOUS WASTE MONITORING HI RADIATION Reactor Trip Safetyinjection PZR level and pressure decrgasing 1 CRS Enter and direct the actions of EOP-1. l l 8 min RX RX verifies the following Critical Functions are met: (EOP1 Att 3) ; e Reactivity Control e PCS Inventory Control (NOT AIET) e PCS Pressure Control (NOTAIET)
Core Heat Removal ,
o Containment Isolation (NOT AIET) e Containment Atmosphere (NOTAfET) e Vital Auxiliaries, Water
. Vital Auxiliaries, Air (Cont. next page)
L.
t-0Appndix D L Operator Actions Form ES-D-2 Op Test No.: Scenario No.: 4 Event No.: 7 -Page 2 of 4 1 Event
Description:
. Large break Loss of Coolant Accident.
i
' Time Position . Applicant's Actions or Behavior 5 min - TURB~ TURB verifies the following Critical Functions are met:(EOPl Att
,. 2)
. . Feedwater System Control e 'CR Radiation Environment
Vital Auxiliaries, Electric '
e PCS Heat Removal e Containment Isolation Operator Actions-Verify at least one Condensate Pump and one Cooling Tower Pump operating. CRS. IF ANY of the following conditions exist:
ANY safety function acceptance criteria NOT n.et e ANY contingency action was taken e Control Room is NOT habitable THEN REFER TO Attachment 1," Event Diagnostic Flow Chart" AND diagnose the event.
RXm3RB Commence Emergency Shutdown Checklist. Refer to GOP-10,
" Balance of Plant Actions Following a Reactor Trip."
5 min - CRS Deiermines from Attachment 1 of EOP-1.0 that EOP-4.0 should be utilized. CRS. Transitions to EOP-4.0 (Cont. next page)
+
l...... .. , .
i Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 7 Page 3 of 4 Event
Description:
Large break Loss of Coolant Accident. I Time Position Applicant's Actions or Behavior RX/TURB IF PZR pressure is less than or equal to 1605 psia OR Containment pressure is greater than or equal to 4.0 psig, THEN verify " SAFETY INJ INITIATED" (EK-1342) is alarmed. (EOP-4) RX/TURB IF SIAS is present, THEN perform ALL of the following: (EOP-4) 5 min RX/rURB Ensure available safeguards equipment operated or operating. REFER TO EOP Supplement 5. (EOP-4) i 2 min RX/rURB Verify at least minimum SI flow. REFER TO EOP Supplement 4. (EOP-4) l i (Cont. next page) r
1 Appendix D Operator Actions Form ES-D-2 i Op-Test No.: Scenario No.: 4 Event No.: .7 Page 4 of 4 Event
Description:
Large break Loss of Coolant Accident. Time Position Applicant's Actions or Behavior
)
RX/TURB IF PZR pressure lowers to less than 1300 psia ) AND SIAS is initiated, THEN perform BOTH of the following:
Ensure one PCP is stopped in each loop.
. IF PCS is less than 25 F subcooled, THEN ensure ALL PCPs stopped. (Critical step due to PCP trip criteria analysis)
(EOP-4) 5 min RX Isolate the LOCA by performing ALL of the following: IF PZR pressure is less than 2185 psia, THEN verify BOTH PORVs are closed.
Ensure closed Letdown Stop Valves e Ensure < losed PCS Sample Isolation Valves
)
e Ensure c losed Reactor Vessel and PZR Vent Valves on C-11 A )
. Verify BO fH of the following conditions exist: i CCW Radiation Monitor, RIA-0915, alarm clear i " COMPONENT CLG SURGE TANK T-3 HI-LO LEVEL" l (EK-1172)is clear i Verify PZR Relief Valve (s) NOT lining (EOP-4) I i
5 min TURB Place at least one Hydrogen Monitor in operation. REFER TO SOP-38, " Gaseous Process Monitoring Syster 4." (EOP-4) CRS IF ANY of the following conditions exist: (Both exist) Containment pressure is greater than or equal to 4.0 psig Any operable Containment Radiation Monitor rises to 1 x 10' R/hr, Then perform all of the following: (EOP-4) (GO TO NEXT EVENT)
Appendix D Operator Actions ' Form ES D-2 Op Test No.: Scenario No.: 4 Event No.: 8 Page 1 of I l Event
Description:
Failure of automatic actuation of CHP/CIS. Time Position Applicant's Actions or Behavior During - RX/TURB Verify "CIS INITIATED" (EK-1126) is alarmed. (EOP-4) Event 8 NOTE: These actions may be completedduring EOP-i actions. > I min RX Manually initiate CIS by pushing left or right HIGH RADIATION INITIATE pushbutton on EC-13. (Critical step to initiate corrective action to prevent radioactive release) (EOP-4) ! RX/TURB Verify Containment isolation. REFER TO EOP Supplement 6. (EOP-4) CRS IF Containment pressure is greater than or equal to 4.0 psig, THEN perform ALL of the following: (EOP-4) 2 min RX Verify Containment Spray alignment AND at least minimal acceptable spray flow (EOP-4) 5 min TURB Verify Containment Isolation for CHP. REFER TO EOP Supplement 6. (EOP-4) Following valves are required to be closed:
. CV-1064 e CV-1044 e . CV-1045 . CV-1065 ,
e CV-0770 e CV-0771 e CV-0767 e CV-0768 e CV-1001 e CV-1037 e CV-2009 e CV-2083
. CV-2099 Total Terminate the scenario when proper alignment completed 124:00 followingfailure of WPM or at lead aaminer dhcretion.
m
c: ,. Operator Actions Form ES-D-2
=
Op-Test No.: Scenario.No.: 4 Event No.: 9 Page 1 of 1 Event
Description:
Classifies event as SITE AREA EMERGENCY. Time Position Applicant's Actions or Behavior 5 min CRS Classify the event as a SITE AREA EMERGENCY using El attachment 1, Primary Coolant Activity. PCSleak rate orprimary to secondary leak rate greater than charging pump capacity. l l l l. I i lm_
7 -- (( !.
1. ,
Appendix D Scenario Outline Form ES-D-1 l l. Facility: PALISADES Scenario No.: 5 Op-Test No.: . Examiners: Operators:
)
i
) ' Objectives:
1) - Secure a running Main Feedwater Pump.

2) Lower power from 50%.

3) Control reactivity during power reduction.

4) Evaluate and respond to a lowpressure in an SI Tank.

5) Evaluate and respond to a low failure of a Przr Pressure channel.

6) L Evaluate and respond to a low failure of a Steam Generator level charmel.

7) Evaluate and respond to a high vibration on a PCP.

8) . Evaluate and respond to a loss of offsite power with the failure 'of I-2 DG to start.

9) Evaluate and respond to a trip of SW Pump P-7B. j

10) Evaluate and respond to a Station Blackout due to the loss of 1-1 DG. i

11) Classify the event.
Initial Conditions:
1) IC-14 (51%).

2) Tag out HPSI Pump P-66A.

e. RM SI23 to RACKOUT e Caution Tag P-66A OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
MALF ED14B to activate (Event 7) Turnover: Core Age is MOL. 51% power, equilibrium conditions. Current boron concentration is 741 ppm. PCS pressure is 2060 psig and temperature is 546 F. Rod Position is ARO. SG - Blowdown is 20K each. ASI average is approximately -0.01. HPSI Pump P-66A is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours. Shift orders are to stop MFW Pump P-1 A~due to a steam leak and to continue to lower power for a mid-cycle maintenance outage. Per Reactor Engineering, control rods are to be used during the shutdown. i
)
4
]
l 5 l Event Malf. No. Event Event No. Type
Description 1 NA (N) Secure a running Main Feedwater Pump.
TURB l CRS 2 NA (N) Lower power from 50%. TURB i CRS NA (R) Control reactivity during power reduction. RX 3 SIO4A (C) Low pressure in an SIT. l (1) RO i CRS 4 RX06B (I) Low failure of a Przr Pressure channel. (1) RX CRS 5 RP27 (I) Low failure of a Steam Generator Level Channel. (1) TURB CRS 6 RC16B (C) High vibration on PCP. (Loss of offsite power occurs (1) RX before trip conditions are met.) CRS 7 ED01 (M) Loss of offsite power with the failure of I-2 DG to stan. ED14B RX (1) TURB CRS 8 SWO4B (C) Trip of SW Pump P-78. (1) RX CRS 9 NA (M) Station Blackout due to loss of 1-1 DG. RX TURB CRS 10 NA CRS Classifies event as Site Area Emergency. Terminate scenario when the preliminary actions of EOP Supphment 24 are completed or at lead examiner's discretion. (1) See Attachment," Simulator Setup & Actions Required for Scenario 5," for details on setup.
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor
7 .:.: .O
j. -
j .. Simulator Setup & Actions Required for Scenario 5 l
. . HPSI P-66A Setup '
RM S123 to RACKOUT e' Caution Tag P-66A OOS for breaker maintenance ' ,
1 Setup Event 3 - . , l- * - Adjust "sikkmalfsiO4" from 0.001 to 0.01 e MALF SIO4A to active approximately 10 minutes before alarm condition desired (initiate at same time load reduction is commenced)
- Setup Event 4 l e MALF RX06B to 1.0 ' Setup Event 5 -
e MALF RP27A to 0.0001 Setup Event 6 ; e MALF RC16B, ramped over 10 minutes, to activate (initiate at same time as Event 5) Setup Event 7 e htALF ED01 to activate e MALF ED14B to activate (insert prior to scenario start)
- Setup Event 8
MALF SWO4B to activate (insert after immediate actions are complete) l i
I A u
y ii !' I !, '[ SHIFT TURNOVER (#5) e Core Age is MOL.
.- 51% power, equilibrium conditions.
Current boron concentration is 741 ppm.

PCS pressure is 2060 psig and temperature is 546 F. ,
e Rod Position is ARO. ' I '
-e' SG Blowdown is 20K each.
l . e ASI average is approximately -0.01.
. HPSI Pump P-66A is tagged out of service for motor bearing inspection and is expected back ~
in approximately 8 hours.-
Shift orders are to stop MFW Pump P-I A due to a steam leak and to continue to lower power.
for a mid-cycle maintenance outage.
'
Per Reactor Engineering, control rods are to be used during the shutdown.
I f 1 l ) i
t. )
l l j
m l .
~ Appendix D. ' Operator Actions Form ES D-2 Op-Test No.: - Scenario No.: 5 Event No.: 1 'Page 1 of 2 Event
Description:
Secure a running Main Feedwater Pump. l
. Time Position Applicant's Actions or Behavior 3, .CRS Direct the TURB operator to shutdown the P-1 A MFP, using 0:00 section 7.4.2 of SOP-12 i
15 min ~ -TURB If one main feedwater pump is still operating, then ensure Feedwater Bypass Control Valve manual isolation valve position. :
P-1 A Operating - MV-FW707 Open and MV-FW705 Closed 1 e^ P-1B Operating - MV-FW707 Closed and MV-FW705 Open 4
1 TURB- Place HIC-0526 (HIC-0529) on Panel C-01 to " MANUAL" and ensure output setting at les's than or equal to zero TURB _ Dump the Control Oil System either with the Local " MANUAL" i' Trip or the Remote Trip pushbutton on Panel C-01. TURB Check Throttle and Trip Valves and steam admission valves closed. TURB Check closed Feed Pump Recirculating Valve CV-07.11 (CV-0710) for pump which was tripped. p (Cont. next page)
Appendix D Operator Actions Form ES-D-2 Op Test No.: Scenario No.: 5 Event No.: 1 Page 2 of 2 Event
Description:
Secure a running Main Feedwater Pump. Time Position Applicant's Actions or Behavior TURB Direct AO to OPEN Casing Drain Valves. I l TURB Direct AO that WHEN Governor Oil pressure drops to 70 psig, l THEN: l
. Ensure that the Auxiliary Oil Pump P-29B (P-29D) starts. i e After pump starts, place handswitch to " HAND" position.
j 1 TURB Direct AO that pnor to Turbine rotor coming to rest, start Turbine i Gear Oil Pump, P-30A (P-30B) at Panel C-24 (C-25). TURB Direct AO that WHEN Rotor comes to rest, THEN perform the following:
Stop the Auxiliary Oil pump P-29B (P-29D) at Panel C-24 (C-25).
. Engage the Turning Gear lever at Turbine. . Start the Turning Gear Motor at Panel C-24 (C-25).
TURB Direct AO to maintain steam seals to avoid loss of Main Condenser vacuum. TURB Direct AO to allow oil cooler outlet temperature to drop to 85 F to 90 F; Maintain this oil temperature while Turbine is on the gear TURB Report to CRS that MFP is secure.
1 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 5 Event No.: 2 Page 1 of 1 Event Der iption: Lower power frc= 50% and Control reactivity during power reduction. Time Position Applicant's Actions or Behavior Stan CRS Direct the activities of the RX/TURB during the power reduction. 32:00 15 min RX Insert control rods as needed to maintain Tavg within 3 F of Tref. 2 min TURB Enter the load decrease rate into the DEH and verify proper operation.
4 Appendix D Operator Actions Form ES D-2 Op-Test No.: Scenario No.: 5 Event No.: 3 Page 1 of 1 Event
Description:
Low Pressure in SIT 'A'. Time Position Applicant's Actions or Behavior Start Crew Diagnose low pressure in Safety Injection Tank A E00
EK-1316, Safety Inj Tank T-82A Hi/Lo Press e EK-1318, Safety Inj Tank T 82A Lo Press e PI-0363, SI Tank T-82A Press RX Check T-82A level normal.
10 min CRS T/S 3.3.1 All four SITS are operable and pressurized to at least 200 psig with a tank liquid level of at least 174 inches and a maximum level of 200 inches with a baron concentration of at least 1720 ppm, but not more than 2500 ppm. Detern:!ne TechnicalSpecification 1 operabilityis NOTmet. CRS T/S 3.3.2 One safety injection tank may be inoperable for a period of no more than one hour. CRS Directs RO to increase pressure in the SIT A. NOTE: It is not intended that pressure be increased in the SIT prior to the next event. i
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 5 Event No.: 4 Page 1 of 1 Event
Description:
Low failure of a Pzr Pressure channel. Time Position Applicant's Actions or Behavior Start CREW Diagnose malfunction in PIC-031B by observation of: 57:00 EK-0754 PZR PRESS Hl/LO OFF NORMAL - 1975 psia PR-101B blue needle low PIC-0101B blue needle low Spray valves close ; Pzr Heaters in maximum I Verify indications of PZR pressure by performing channel check. I CRS Enter and direct the actions of ONP 18, i l 5 min RX Take manual control of PIC-0101B. (Critical task to take manual l control and stabilize prior to Reactor Trip) RX Place PIC-0101 A in service as directed by CRS. NOTE: This action may be directed /taken without taking manual controlofPIC-0101B. RX Monitor pressure control signal CRS Contact I&C to investigate failure of PZR pressure controller
I l Appendix D Operator Actions Form ES-D ' l Op-Test No.: Scenario No.: 5 Event No.: 5 Page 1 of 1 Event
Description:
Steam Generator A Level Channel Low Failure. l Time Position Applicant's Actions or Behavior l Start CREW Diagnose a failure of the Steam Generator level transmitter by 62:00 observation of: EK-0137 AFAS - FOGG SUBSYSTEM TRIP EK06 Rack A #4 Low Level SGI Channel Trip SG level on LI 0751 A indicates zero 5 min CRS/TURB IF instrument is faulty, THEN bypass the Low Level SGI Trip for the alTected channel per SOP 36 and refer to Technical Specifications 3.17.1 & 3.17.2 (ARPfor EK06 Rack A #4) 5 min TURL Obtain proper RPS Trip Unit Bypass key from Shift Supervisor. Insert Bypass Key above affected RPS Trip Unit. (SOP-36) TURB Turn key 90* clockwise. Verify that yellow light above Bypass Keyswitch illuminates. fSOP-36) CRS Refers to Tech Spec 3.17.1 and 3.17.2,7 days to restore Log in Reactor Logbook (SOP-36) e
Apps..~.dir D Operator Actions Form ES-D 2 Op-Test No.: Scenario No.: 5 Event No.: 6 Page 1 of 2 Event
Description:
High vibration on PCP. (Loss of offsite power occurs before trip conditions are met ) { 1 Time Position Applicant's Actions or Behavior J Start CREW Diagnose increasing vibration on the PCP by observaIioe of the following: ] 72:00 EK-0913 PRI COOLANT PUMP VIBRATION ALERT I 1 1 i CRS/TURB Confirm increased PCP vibration by observing both vertical and j horizontal probes. E the Reactor is Critical AND imminent PCP i failure is corroborated by other indications, TliEN trip the Reactor and go to EOP-1.0, " Standard Post Trip Actions." Vibration is l increasing @ >2 mils /hr, butfailure is not imminent. Candidate shouldNOTtrip the Reactor. (ARPfor EK-0913) NOTE: Crew may determine that this is a vibration probefailure due to NO corroborating indications. 1 l CRS/TURB E either vertical or horizontal PCP vibration increases 2 mils in 24 ) hours and problems are corroborated by other indications, THEN remove PCP from service as soon as plant conditions permit per SOP-1, Section 7.2.6 or 7.2.7 as applicable. (ARPfor EK-0913) l l 5 min CRS Refer to Technical Specifications 3.1.1 and 3.10.1.b. l (ARPfor EK-0913) NOTE: Candidate may not refer to TS untilplant trip occurs. 1 p' (Cont. next page)
y .p , 1, :
' Appendix D Operator Actions- . Form ES-D Op-Tcst No.: Scenario No.: 5 Event No.: .6 Page 2 of 2 Event
Description:
High vibration on PCP. (Loss of offsite power occurs before trip conditions are met.) Time ~ Position - Applicant's Actions or Behavior CRS- T/S 3.1 Four primary coolant pumps shall be in operation whenever the reactor is operated above hot shutdown, with the following exception: Before removing a pump from service, thermal power shall be , reduced as specified in Table 2.3.1 and appropriate corrective action implemented. With one pump out of service, retum the pump to service within 12 hours (retum to four-pump operation) or be in hot shutdown'(or below) with the reactor tripped (from the C panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours. Start-up (above hot shutdown) with less than four pumps is not permitted and power operation with less than three pumps is , not permitted. Table 2.3.1 is the RPS tr'p settings. Candidate ' ' should recognize that this T/S does not apply until the PCP is trippedwith the Reactor atpower. o J CRS. Notify Plant Management of potential PCP vibration and the need to continue the plant shutdown. s-s l 1
1 Appendix D Operator Actions Form ES D-2
- i Op-Test No.: Scenario No.: 5 Event No.: 7 Page 1 of 2 Event
Description:
Loss of offsite power with the failure of I-2 DG to start.
~ Time = Position Applicant's Actions or Behavior Start CREW Diagnose Loss of Offsite Power by:
77:00 Reactor Trip PCS Low Flow No Safety Injection Undervoltage Alarms on Busses l A,B,D, and E l CRS Enter and direct the actions of EOP-1.0 i 5 min RX RX verifies the following Critical Functions are met: (EOPI Att 3) { e Reactivity Control j e PCS Inventory Control '
PCS Pressure Control e
Core Heat Removal (NOTMET) l
Containment Isolation e Containment Atmosphere e Vital Auxiliaries, Water e Vital Auxiliaries, Air i
(Cont. next page) 4-
Appendix D Operator Actions Form ES-D 2 Op-Test No.: Scenario No.: 5 Event No.: 7 Page 2 of 2 Event
Description:
Loss ok affsite power with the failure of 1-2 DG to start. Time Position Applicant's Actions or Behavior 10 min TURB TURB verifies the following Critical Functions are met:(EOP1 Att 2) e Feedwater System Control (NOTNET) e CR Radiation Environment e Vital Auxiliaries, Electric (NOTMET)
PCS Heat Removal e Containment Isolation Operator Actions-Verify at least one Condensate Pump and one CooHng Tower Pump operating. NOT met, the TURB must close the MSIV's. (Critical Step is prevent damage to plant equip)
~
CRS IF ANY of the following conditions exist:
ANY safety function acceptance criteria NOT met (See above)
. ANY contingency action was taken e Control Room is NOT habitable THEN REFER TO Attachment 1," Event Diagnostic Flow Chart" AND diagnose the event.
RX/TURB Conunence Emergency Shutdown Checklist. Refer to GOP-10, "Bahnce of Plant Actions Following a Reactor Trip." 5 min CRS . Refer to Diagnostic Flowchan (EOP 1.0, Attachment 1), to determine which procedure to enter. Recognize that EOP-8.0 should be considered. CRS Transitions to EOP-8.0
Appendix D ' Operator Actions Form ES-D-2 Op-Test No.i Scenario No.: 5 Event No.: 8 Page 1 of 2 l Event
Description:
Trip of SW Pump P-78. Time - Position Applicant's Actions or Behavior During CRS Referring to ONP-6.1 Event 8 Direct the following action (s) to restore Service Water Header pressure, as appropriate. RX E Service Water Pumps have tripped, THEN start available Service Water Pumps. None available (ONP-6.1) RX E only one Service Water Pump is available, THEN close CV-0824 I to isolate Service Water from Containment. E either Critical i Service Water Header pressure is less than 42 psig, THEN perform the following, as necessary: None available (ONP- l 6.1) RX E either Critical Service Water Header pressure is less than 42 psig, THEN perform the following, as necessary:
Close CV-1359 to isolate Non-Critical Service Water.
. Operate C-2B, Instrument Air Compressor and secure C-2A/C, Instrument Air Compressors. No power (ONP-6.1)
TURB Determine that EDG l-1 is running with no service water cochng- ~ ~ CRS Directs AO to monitor EDG l-1 locally. NOTE: After approximately 2 minutes, notify CRS as AO that EDG 1-1 JA CKET WA TER temperature is 18(fF and rising and L UBE OIL temperatureis 18TFand rising.
Appendix D Operator Actions Fomi ES D-2 Op-Test No.: Scenario No.: 5 Event No.: 8 Page 2 of 2 L Event
Description:
Trip of SW Pump P-78. Time Positicn Applicant's Actions or Behavior NOTE: After an additional 5 minutes, notify CRS as AO that EDG 1-1
.lACKET WA TER temperature is 190*F and L UBE OIL temperature is 189'F.
NOTE: After an additional 5 minutes, IF EDG 1-1 IS STILL NOT TRIPPED, notify CRS as A O that EDG l-1 JACKET WA TER temperature is 196*F and L UBE OIL temperature is 195'F and EDG 1-1 is making a " knocking" sound. CRS Direct the TURB to trip the EDG due to no high temperatures. (EOP-3.0) (Critical step is to prevent damage to EDG without Service Water) CRS Transition to EOP-3.0 I 1 M L
1-Appendix D Operator Actions Form ES-D-2 i Op-Test No.: Scenario No.: Event No.: 5 9 Page 1 of 3 Event
Description:
Station Blackout due to loss of 1-1 DG. Time Position . Applicant's Actions or Behavior Start CRS Confirm proper event diagnosis by performing ALL of the j 97:00 following: ' Verify Attachment 1," Safety Function Status Check Sheet" acceptance criteria: Are satisfied at intervals of approximately fifteen minutes. I e Corrective actions to restore Attachment 1," Safety Function Status Check Sheet," acceptance criteria are effective. (EOP-3) l l TURB IF ANY D/G is operating AND Service Water to the D/G is NOT adequate as indicated by D/G temperatures above normal running indications, THEN perform ANY of the following: Initiate actions to restore D/G cooling. REFER TO ONP-6.1, I
" Loss of Service Water."
Stop the affected D/G by tripping its Overspeed Trip Lever locally. (Critical step is to prevent damage to EDG without Service Water) (EOP-3) j l 5 min RX Minimize the loss of PCS inventory by placing the following handswitches to CLOSE:
. HS-2083, PCP Controlled BleedoffIsolation Valve, CV-2083
HS-2099, PCP Controlled BleedoffIsolation Valve, CV-2099 e HS-2003, Letdown Orifice Stop Valve, CV-2003 l e HS-2004, Letdown Orifice Stop Valve, CV-2004 !
. HS-2005, Letdown Orifice Stop Valve, CV-2005 !
e HS-1910, Primary System Sample Isolation Valve, CV-1910
HS-1911, Primary System Sample Isolation Valve, ,
CV-1911(Critical step is to minimize loss of PCS inventory) ! (EOP-3) i a I (Cont, next page)
]
l
~- Apperdix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 5 Event No.: 9 Page 2 of 3 Event
Description:
Station Blackout due to loss of1-1 DG. I Time Position Applicant's Actions or Behavior s CRS/rURB Ensure TAVE is less than 540 F AND controlled by operation of Atmospheric Steam Dump Valves. (EOP-3) CRS/TURB Ensure at least one S/G has corrected level being maintained or ' being restored to between 60% and 70%. REFER TO EOP Supplement 11. (EOP-3) CRS IF AFAS has actuated, THEN perform ALL of the following: IF BOTH S/Gs have level of at least 30% and controlled, i THEN, as resources permit, reset AFAS. REFER TO SOP-12, l "Feedwater System," Attachment 2 (AFAS is not actuated) (EOP-3) \ 1 TURB IF ANY 4160 VAC or 2400 VAC buses are NOT energized, ; THEN ensure open ALL feeder and supply breakers on the affected buses. REFER TO EOP Supplement 34. (EOP-3) ; l i l TURB WHEN at least five minutes have elapsed from the onset ofloss of all AC power, THEN verify all PCP DC Oil Lift Pumps are stopped. (EOP-3) (Cont, next page)
Appendix D Operator Actions Form ES D-2 Op-Test No.: - Scenario No.: 5 Event No.: 9 Page 3 of 3 Event
Description:
Station Blackout due to loss of 1-1 DG. . i Time ' Position Applicant's Actions or Behavior CRS IF Plant power has been lost for less than 10 minutes, THEN initiate actions to restore available D/Gs by performing AL.L of the following. Candidate shouldrecognize that the EDG 's cannot be started. (EOP-3) I i 10 min RXMRB IF Plant power has been lost for areater than or eaual to 10 minutes, THEN initiate actions to restore available D/Gs by performing ALL 1 of th: following: !
. Perform the preliminary actions of EOP Supplement 24.(EOP-3) )
NOTE: The candidates may transition to other success path, they shouldrealize that none ofthem wouldresult in success until some ACpower is restored. yog,; Terminate the scenario wIen thepreliminary actions ofEOP 117:00 SUPP l ement 24 are cowyteted or at lead aaminer dhcretion.
.4 t
I t , Appendix D - Operator Actions Form ES D-2 L Op-Test No.: Scenario No.: S ~ Event No.: 10 Page 1 of 1 Event
Description:
- Classifies event as Site Area Emergency.
Time Position Applicant's Actions or Behavior 5 min CRS Classify the event as a Site Area Emergency using El attachment 1, 4 POWER PLANT ELECTRICAL (Loss ofoffsite and onsite AC powerfor more than 15 minutes) - i l l I
f SUBMITTAL OF THE OUTLINE FOR THE PALISADES EXAMINATION THE WEEK OF JUNE 7,1999 t
*4se 4 +*
J
o ! !t i ES-201_ Examination Outline Fotm ES-201-2 j Quality Assurance Checklist Facility: PALISADES c Date of Examination: JUNE 1999 initials Item Task Description 7 a b c
a. Verify that the outime(s) fit (s) thc appropriate model per ES 401.
A )g g
b. Assess whether all six knowledge and four ability categories are appropriately sampled.

c. Assess whether the outhe over-emphasizes any systems, evolutions, or generic topics. ge T (
.g.
d. Assess whether the repetition from previous examination outlines is excessive.
[C & /
a. Using Form ES-301-5, verify that. voposed scenario sets cover the sequired number of normal

2. evolutions, instrument and compo.m
Ulures, and major transients. j d JC S b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of I applicants in accordance with the expected crew composition and rotation schedule without compromising .
M exam integrity; ensure each applicant can be tested using at least one new scenario and scenarios will not be g U repeated over successive days. L A c. To the extent possible, assess whether the outline (s) conform (s) with the qualitanvc and quantitative criteria T specified on Form ES-301-4 and described in Appendix D.
m. Venfy that the outline (s) contain(s) the required number of control roont and in-plant tasks atid verify that ,
3- no more than 30% of the test material is repeated from the last NRC exacrination. N - J b. Verify that the tasks are distributed among the safety function groupings as specified in ES-301; one task P shall require a low-power or shutdown condition, one or two shall require the applicant to implement an g g M ahernate path procedure, and one should require entry to the RCA. /
c. Verify that the required administrative topics are covered, with emphasis on performance-based activities. g g

d. Determine if there are enough different outlines to test the projected number and mix of applicants and N
ensure that no more than 30% of the items are duplicated on successive days. [
a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate 4- exam section. g M h,,
G b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. g N c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. g g R d. Check for duplication and overlap among exam sections. g g L
e. Check the entire exarn for balance of coverage. CC

f. Assess whether the exam fits the appropriate job level (RO or SRO).
4C g i Printed Name / $ignat Date
a. Author ,_
ro.,3 ! N $7/ff
b. Facility Reviewer (*) [rActI b# / / [f f

c. Chief Examiner . Afs /A 4

d. NRC Supervisor (10 6 S [ }%
(*) Not applicable for NRC-developed examinations i
2 a . .y . ES-301 Administrative Topics Outline Form ES-301-1 L Facility: PALISADES Date of Examination: _ JUNE 1999 Examination Level (circle one): RO/ Operating Test Number:
. Administrative Describe method of evaluation:
Topic / Subject - 1. ONE Aaministrative JPM, OR Description 2. TWO Administrative Questions Conduct of Admin JPM - A.1-1 (RHAA03A MODIFIED) A1 Operations - Determine Average Qualified Core Exit Thermocouple Temperatures Use of Plant Computer Conduct of. Admin JPM - Admin A.1-2 (TBAA01 A MODIFIED) Operations Determine Feedwater Reserve Inventory and Time Interval for Heat
. Interpreting Plant Removal i Reference Material Equipment AdminJPM- Admin A.2(NEW)
A2 Control Determine the tagging requirements for a LP Safety injection Pump using Tagging and plant drawings (actual development of tagout NOT required) Clearances Radiation - .-^ ' ' ^r "'r- ^/ ^. ' Q' 'NEW) A.3 Control D1.... ~ amo. luiub for in.; =el 3I C Co 1 ' I'7 A.. Q ._^*- = Ai .h A.3-Q2 (NEW) D.. ..mmi.um fu , ' ':' g-- myvrar in zer, Mi f. :d and aist== 'adial^;t e ' ::;..u Emergency Plan Admin JPM - Admin A 4-S (SEP04 MODIFIED) A.4 Protective Action Determine protective action recommendations during a General Recommendations Emergency l l L. L l
m 4 ;. , ,
. ES-301 Administrative Topics Outline Form ES-301-1 Facility:' PALISADES ' - Date of Examination: JUNE 1999 - . Examination Level (circle one): M ROOperating Test Number:
Administrative Describe method of evaluation: Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions Conduct of - Admin JPM - A.1-1 (RilAA03A MODIFIED) A.1 Operations Determine Average Qualified Core Exit Thermocouple Temperatures Use of Plant - Computer Conduct of - Admin JPM - Admin A.1-2 (TBAA01 A MODIFIED) Operations Determine Feedwater Reserve Inventory and Time Interval for Heat Interpreting Plant - Removal Reference - Material Equipment Admin JPM - Admin A.2 (NEW) - A.2 Control Determine the tagging requirements for a LP Safety Injection Pump using Tagging and plant drawings (actual development of tagout NOT required) Clearances l
^
Radiation ^ ' ' Our'r . .d" .^. ' Q ! ("E") A.3 Control h~miaa a=pa- u :- r; g,7~1 j C 1
= tim Rbb reb3 - l -AdmitrQuesnon - Admm A.3-QiW.EW) 0 .....~ .chv.6 fg : imi ing arpnenre in aren with fixed and airDorne raaiviv5.CdSources 1
Emergency Plan Admin JPM - Admin A.4-R (SEP02 MODIFIED) l AA Emergency Plan Make emergency notifications required by the site emergency plan l
' Notifications ' ]
i i l I
o, [71 7 . u j u ES-301 Individual Walk-Through Test Outline Form ES-301-2 i ) Facility: PALISADES Date of Examination: JUNE 1999 l' Exam Level: RO Operating Test No.: System / JPM Title / Type Codes Safety Planned Follow-up Questions: Function K/A/G - Importance - Description
1. 004/ Respond to a Failed VCT 1

a. 004.K1.29 (3.4) K/O cause/effect between Level Channel Transmitter / (M)- CVCS, Pzr valve leak, and VCT makeup' (S)' activity

b. 004.K4.12 (3.1) K/O CVCS design for j minimum level of VCT j

2. 000027/ Respond to an LTOP 3 a. 000027.AK3.04 (2.8) K/O reason for slow Actuation due to a Failure /(N)(A) pressure recovery following loss / restoration (L)(S) of Pzrlevel

b. 010.K4.03 (3.8) K/O Pzr PCS design which provides overpressure protection '

3. 000025/ Loss of PCS Inventory ' 4 a. 000025.AK3.03 (3.9) K/O reasons for i While on SDC/ (N)(S)(L) immediate actions forloss of SDC

b. 005.K5.03 (2.9) K/O implications of reactivMy effects of SDC fill water j

4. 026/ Verify Containment Spray - 5 a. 026.K4.04 (3.7) K/O CSS design which Response to Recirculation provides for containment temperature and Actuation Signal / (N)(A)(L)(S) pressure reduction following LOCA

b. 026.K1.02 (4.1) K/O ceuse/effect relationship between CSS and cooling water

5. 012/ insert and Remove a 7 a. 012.K4.02 (3.9) K/O RPS design which Reactor Protection Channel Trip provides trip when RPS setpoint exceeded Bypass / (M)(S) and basis for trip i

b. 012.K4.04 (3.1) K/O RPS design which provides for redundancy
+ Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA
E l '
> = . .
I . System / JPM Title / Type Codes Safety Planned Follow-up Questions: Function K/A/G -Importance - Description
6. 008/ Shift Operating CCW 8 a. 008.K4.05 (2.7) K/O CCW design which '
l Pumps /(N)(A)(S) provides for standby feature for pumps
b. 008.K1.02 (3.3) K/O cause-effect l relationship between CCW and loads

7. 011/ Transfer Pressurizer Level 2. a. 011.K1.03 (3.7) K/O cause-effect Control from Manual to Cascade / relationship between Pzr Level Control and (N)(C)- Pressure Control

b. 011.K5.12 (2.7) K/O criteria and purpose of Pzr Level program

8. OS2/ Manually Align Y-01 to 6 a. 062.K4.10 (3.1) K/O AC Distribution Emergency Power Supply / (D)(A) design which provides for Uninterruptable (P)(R). 48 power sources

b. 062.K1.03 (3.5) K/O cause-effect relationship between AC and DC Distribution

9. 028/ Start M 69A Hydrogen 5 a. 028.K5.02 (3.4) K/O implicaticns of
'Recombiner/ (D)(P)tR) 4 flammable hydrogen concentration i
b. 028.K3.01 (3.3) K/O effect of loss of hydrogen recombiner on hydrogen ;
concentration in containment 10.061/ Reset AFAS/(D)(A)(L)- 4 a. 061.K4.03 (2.7) K/O design feature which [ (P)(Rl g provides for blowdown / sample isolation
b. 061.h3.02 (4.2) K/O effect of loss of AFW on the SG !
i . Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA i l L . 1
+ l f
0.g 1 a l l ES-301 Individual Walk-Through Test Outline Form ES-301-2 Facility: PALISADES Date of Examination: JUNE 1999 ) Exam Level: SRO Operating Test No.: System / JPM Title / Type Codes Safety Planned Follow-up Questions: Function K/A/G -Importance - Description
1. 001/ Realign a misaligned 1

a. 001.K5.07 (4.0) K/O effects of an )
control rod /(N)(S) asymmetric rod configuration on power ! distribution
b. 001.KS.94 (3.6) K/O effects of rod control l system on shutdown margin
{ 1
2. 000027/ Respond to an LTOP 3 a. 000027 AK3.04 (3.3) K/O reason for slow l Actuation due to a Failure /(N)(A) pressure recovery following loss / restoration (L)(S) of Pzrlevel

b. 010.K4.03 (4.1) K/O Pzr PCS design which provides overpressure protection

3. 000025/ Loss of PCS inventory 4 a. 000025.AK3.03 (4.1) K/O reasons for immediate actions forloss of SDC j While on SDC/(N)(S)(L)

b. 005.K5.03 (3.1) K/O implications of reactivity effects of SDC fill water

4. 026Nerify Containment Spray 5 a. 026.K4.04 (4.1) K/O CSS design which Response to Recirculation provides for containment temperature and Actuation Signal /(N)(A)(L)(S) pressure reduction following LOCA

b. 026.K1.02 (4.1) K/O cause/effect relationship between CSS and cooling water

5. 072/ Respond to an Area High 7 a. 072.A2.01 (2.9) Predict the effect on the Radiation Alarm /(N)(A)(S) Area Rad Monitoring System caused by a power supply failure

b. 072.K3.02 (3.5) K/O effect of a failure of the Area Rad Monitoring System on fuel handling
. Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room,(S)imulator,(L)ow-P wer,(P)1 ant,(R)CA l
f l l l
~
n. ,,-- i f u._ w
[c t-l System / JPM Title / Type Codes Safety ' Planned Follow-up Questions: Function K/A/G - Importance - Description l 6. 008/ Shift Operating CCW 8 . a. 008.K4.05 (2.9) K/O CCW design which l Pumps / (N)(A)(S) provides for standby feature for pumps . b. 008.K1.02 (3.4) K/O cause-effect j relationship between CCW and loads
7. 011/ Transfer Pressurizer Level 2 a. 011.K1.03 (4.0) K/O cause-effect Control from Manual to Cascade / relationship between Pzr Level Control and l (N)(C) Pressure Control i
l b. 011.K5.12 (3.3) K/O criteria and purpose of Pzr Level program
8. 062/ Manually Align Y-01 to 6 a. 062.K4.10 (3.5) K/O AC Distribution Emergency Power Supply / (D)(A) design which provides for Uninterruptable (P)JJ44 power sources 1

b. 062.K1.03 (4.0) K/O cause-effect ;
relationship between AC and DC Distribution )
9. 028/ Start M-69A Hydrogen 5 a. 028.KS.02 (3.9) K/O implications of flammable hydrogen concentration Recombiner/(D)(PMQ

b. 028.K3.01 (4.0) K/O effect of loss of hydrogen recombiner on hydrogen concentration in containment

10. 061/ Reset AFAS/ (D)(A)(L) 4 a. 061.K4.03 (2.9) K/O design feature which
_(P) @ g provides for blowdown / sample isolation i b. 061.K3.02 (4.4) K/O effect of loss of AFW on the SG i' e Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol l room, (S)imulator, (L)ow-Power, (P)lant, (R)CA i i
p. I ES-301 Transient and Event Checkli t Form ES-301-5 ' OPERATING TEST NO.: Group A Applicant Evolution Minimum Scenario Number i Type Type. Number 1 1 2 2 RX TURB RX TURB Reactivity 1 3 NA NA 1 1 NA NA 3 p _ Normal i instrument 2 5 NA NA 4 RO - Component 2 27 NA NA 67 Majw 1 6 NA NA 5 l Reactivity 1 NA NA 3 NA Normal 0 NA NA NA NA NA 1 NA Instrument 1 As RO NA NA 2 NA Component 1 Majw 1 NA NA 5 NA SRO4 1 2 CRS CRS Reactivity 0 'j t NA ?",'; 'y'; fj! W Normal 1 13 ljj ' y NA , jl7 ggjj" Instrument 1 5 ' ',pyi:j, NA y;c ; gjggjg As SRO Component 1 27 ,'y} NA ',S'(,,/. ll{g$g Major 1 6 hljj'y , NA Ay gjjjy l 1 Group A consists of SRO4 and RO. Surrogate to fill TURB position in Scenario 1 and CRS ! position in Scenario 2. l
\
f Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each l evolution type. ! (2) Reactivity manipulations must be significant as defined in Appendix D. Author: N " Chief Examiner: l vuxJ l l I l
R
]
I ES-301 Transient and Event Checklist ' Form ES-30105 OPERATING TEST NO.: Group B Applicant Evolution Minimum Scenario Number Type . Type Number 1 1 2 2 RX TURB RX TURB l Reactivity' -1 3- NA NA Normal - 1 1 NA NA 3 Instrument 2 5 NA NA 4 RO Component 2 27_ NA NA 67 Major 1 6 NA NA 5 Reactivity . 1 NA NA 3 NA Normal 0 NA NA NA l Inkment 1 M M 1 NA As RO Component - 1 NA NA 2 NA Majw 1 NA NA 5 NA j SRO4 1 2 CRS - CRS Reactivity 0 !M{$ NA gf@s 44+gy Normal 1 13 'hhgj NA hNh '%[s As SRO in ment 1 5 hk NA jgg iff}' Component 1 27 hlllh$ NA [fjj{gy (;2 {~,':)j{ Major 1 6 -t[fffhhp NA $$jg ?is@ ;[ly' 8]; Group B consists of SRO4 and RO. Surrogate to fill TURB position in Scenario 1 and CRS position in Scenario 2. Instructions: (1)' Enter the operating test number a'nd Form ES-D-1 event numbers for each evolution type. (2) Reactivity manipulations must be significant as defined in Appendix D. Author: N/b ^ Chief Examiner: ( m
l~ w ..,. ES-301 Trrnsi:nt end Event Checklist Form ES-301-5 OPERATING TEST NO.: Group C Applicant Evolution Minimum Scenario Number Type Type Number 3 3 4 4 5 5 RX TURB RX TURB RX TURB Reactivity 1 3 NA NA NA Normal 1 NA NA 12 NA 12 Instrument 2 1 NA NA 5 NA RO Component 2 57 NA NA 7 NA 5 Major 1 6 NA NA 8 NA 79 Applicant Evolution Minimum Scenario Number Type Type Number l 3 3 4 4 5 5 RX TURB RX TURB RX TURB Reactivity 1 NA NA 1 NA NA NA Normal 0 NA NA NA NA NA Instrument 1 NA NA 3 NA NA NA j As RO Component 1 NA NA 69 NA NA NA Major 1 NA NA 8 NA NA NA SRO-l (1) 3 4 5 . l CRS CRS CRS Reactivity 0 f1,' NA s i, < hjf^ F Normal 1 l'"', NA JJ 'c'] 12 ;ll"':%
>iii' instrument 1 12 }gh EI ^ NA , 's 4 As SRO Component 1 457 8$@F NA s sM g 568 La[ 1.
! Major 1 6 @%.. -; NA * ^9% 79 .g, %%f
\q.
Applicant Evolution Minimum Scenario Number l Type Type Number 3 3 4 4 5 5 RX TURB RX TURB RX TURB Reactivity 1 NA NA lt^. 1 NA Normal 0 NA NA NA NA Instrument 1 NA 2 NA NA 4 NA As RO Component 1 NA 45 NA NA 68 NA Major 1 NA' 6 NA NA 79 NA l SRO-l (2) 3 4 5 CRS CRS CRS Reactivity 0 NA fjhq[ }jpg NA e ,'f Normal 1 NA jhi%g i2 $$hi@ NA y ;;;- Instrument 1 UA lf"i%$j[ 35 id$kh= NA
= '/ s>2' ' ' ^ ' ' '
As SRO , Component 1 NA jjggbgn 679 jdsjk n NA : sj s. j' Major 1' NA
'M!% 8 gjlk NA ' ' " (, } '
1 Group C consists of SRO-l(1), SRO-l(2), and RO). Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type. (2) Reactivity manipulations must be significant as defined in Appendix D. Author; b " U Chief Examiner:
/ ,3 cr /
A i J' My l l l
ES-301 Competencies Checklist F6rm ES-301-6 , I 1 l OPERATING TEST NO.: Group A RO SRO-I SCENARIO SCENARIO i 1 2 1 2 Competmeies , RX TURB CRS RX Undennand andInterpro 2567 4567 2567 125 Annunciators and Alarms Diagnose Evats 2567 4567 2567 125 and Conditions Undentand Plant 2356 3456 2356 1235 l 7 7 7 7 and System Response Comply With and 1235 3456 1235 1235 67 7 678 7 Use Pmcedures(1) Operate Control - 1235 3456 NA I235 07 7 7 i Boards (2) ALL ALL ALL ALL Communicate and Interact With the Crew Demonstrate Supavisory NA NA ALL NA Ability (3) NA NA 124 NA Comply With and > Use Tech. Specs. (3) Group A consists of RO, SRO4, and Surrogate (TURB - Scenario 1; CRS - Scenario 2). Notes: (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicableto SROs. l l Author. ChiefExaminer.
~
ES-301 Competencies Checklist Form ES-301-6 OPERATING TEST NO.: Group B RO SRO-I SCENARIO SCENARIO l' 2 1 2 Competencies RX TURB CRS RX j Understand andInterpret 2567 4567 2567 125 Annunciators ami Alarms j Diagnose Evaits 2567 4567 2567 125 and Conditions Understand Plant 2356 3456 2356 1235 7 7 7 7 and System Response Comply With and 1235 3456 1235 1235 07 7 078 7 Use Procedun:s(1) Operate Control 1235 3456 NA 1235 67 7 7 Boards (2) Communicate and
'ALL ALL ALL ALL Intaact With the Crew Demonstrate Supavisory NA NA ALL NA i
Ability (3) Comply With and NA NA 124 NA l L Use Tech. Specs.(3) l l Group B consists of RO, SRO 8, and Surrogate (TURB - Scenario 1; CRS - Scenario 2). l Notes: (1) Includes Technical Specification compliance for an RO. l (2) Optional for an SRO-U. (3) Only applicable to SROs. Author: O ChiefExaminer: M)
< ~u
s-
' ES-301 Competencies Chucklist Form ES-3016 OPERATING TEST NO.: Group C RO- SRO-I(1) SRO-1(2)
SCENARIO SCENARIO SCENARIO 3 4 5 3 4 5 3 4 5 Competecies RX TURB TURB CRS RX CRS TURB CRS RX 1567 578 579 1245 3689 4567 2456 3456 4678 Understand andlnte 67 89 789 Annunciators and Alarms Diagnosc Evats 1567 578 579 1245 3689 4567 2456 3456 4678 67 89 789 and Conditions Understand Plant 1456 1257 1257 1245 1368 1245 2456 1234 1467 0 0 0 8 and Systern Response 9 Comply With and 1456 1257 1257 1234 1368 1245 2456 1234 1467 7 8 9 5678 9 6789 5678 89 Use Pmcedures(l) 10 9 10 Operate Control 1456 1257 1257 NA 1368 NA 2456 NA 1467 7 8 9 9 89 Boanis(2) ALL ALL ALL ALL ALL ALL ALL ALL ALL Communicated Interact With the Crew DemonArcac Supervisory NA NA NA ALL NA ALL NA ALL NA Noility(3) Comply With and NA NA NA 35 NA 3 NA 46 NA UseTech. Specs.(3) ~ Group C consists of RO, SRO 4 (1), and SRO-l(2). Notes: (1) Includes Technical Specification compliance for an RO. (2) . Optional for an SRO-U. (3) Only applicable to SROs.
. Author: - /
Chief Examiner: - /?pt / v N l
'O.,.
Appendix D Scenario Outline Form ES-D-1 1 1 Facility: PALISADES Scenario No.: 1 Op-Test No.: 7- Examiners: Operators: Objectives:
1) Shift running charging pumps per SOP-2A.

2) Evaluate and respond to a trip of a running SW pump with a failure of the standby pump to automatically start.

3) Reduce turbineload from 75%.

4) Evaluate and respond to a low boron concentration in the SI accumulator.

5) Evaluate and respond to a failure of the Tave control signal.

6) Evaluate and respond to a SG tube leak /SGTR.

7) Evaluate and respond to a charging pump trip during the response to the tube leak.

8) Classifytheevent.
Initial Conditions / Setup:
1) IC-10(75%).

2) Tag out MDAFWP P-8C.
MALF FW16C-active

I/O P-8C H/S to TRIP e ' I/O P-8C-G to OFF e I/O P-8C-R to OFF e Caution Tag P-8C OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start: .

Take P-7C out of STANDBY by rotating HS to TRIP (Event 2) e I/O P-7C-A to ON (Event 2)
Turnover: Core Age is NEW.~ 75% power, constant power for 2 houn following 3%/ hour ramp from 100% equilibrium conditions. Current boron concentration is 1335 ppm. PCS pressure is 2060 psig and temperature is 552*F. Rod Position is ARO. SG Blowdown is 20K each. ASI average is approximately 0.00. MDAFW Pump P-8C is tagged out of service for motor bearing inq7ection and is expectal back in approximately 8 houn (TS 3.5.1). EK-1318, SIRWT Hl/LO PRESS ALARM has been coming in/out. Shift orders are to shift running charging pumps for breaker maintenance on P-55A and continue power reduction. NOTE: SURROGA TE OPERA TOR WILL BE FILLING 'TURB' POSITIONDURING THISSCENARIO.
o .
) )
Event Malf. Event Event No. No. Type
Description 1 NA (N) Shift running charging pumps to tag out previously running )
RX for breaker maintenance. ! CRS 2 SWO4A (C) Trip of SW pump P-7A with failure of P-7C to j (1) RX automatically start. ' CRS 3 NA (R) Control of reactivity during power ramp. RX NA (N) Reduction of plant power. TURB CRS , 4 NA (C) Chemistry reports boron concentration at value below Tech CRS Spec limit. 5 RP23B (I) High failure of Tave control signal due to Thot failure (1) RX TURB CRS 6 SG01B (M) SG Tube Leak / Rupture (1) RX TURB CRS 7 CV03 ( Trip of charging pump during response to tube leak. CRS 8 NA CRS Classifies e~ at as a Site Area Emergency Terminate scenario when a cooldown within TS limitations toward shutdown cooling has been initiated, and the faulted S/G has been isolated. or at lead examiner's discretion. (1) See Attachment," Simulator Setup & Actions Required for Scenario 1," for details on setup.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
s i~ p
- l Appendix D Scenario Outline Form ES-D-1 1
Facility: PALISADES Scenario No.: 2 Op-Test No.: Examiners: Operators: Objectives:
1) Evaluate and respond to a high failure of PRZR Pressure Control channel.

2) Evaluate and respond to a dropped control rod.
' 3) Lower reactor power to <75% in response to the dropped rod.
4) Control reactivity during load reduction.

5) Evaluate and respond to a failure of a steam flow channel.

6) Evaluate and respond to a loss of offsite power, resulting in a Rx Trip and loss of forced circulation.

7) Evaluate and respond to a failure of EDG l-1 output breaker to close.

8) Evaluate and respond to a trip of TDAFW Pump P-8B following loss of offsite power.

9) Respond to a loss of all feedwater following a loss of offsite power.

10) Classify the event.
Initial Conditions / Setup:
1) IC-11 (99.7%).

2) Tag out MDAFWP P-8C.
. MALF FW16C-active
I/O P-8C H/S to TRIP e I/O P-8C-G to OFF e I/O P-8C-R to OFF e Caution Tag P-8C OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
e MALF EDI1 A to active (Event 6) i e MALF FW16B to active (Event 7) Turnover: Core Age is NEW. 90.7% power, equilibrium conditions. Current boron concentration is l 1260 ppm. PCS pressure is 2060 psig and temperature is 560 F. Rod Position is ARO. SG l Blowdown is 20K each. ASI average is approximately 0.00. MDAFWP Pump P-8C is tagged out of service for motor bearing inspection and is expected back in approximately 8 ho-urs (TS 3.5.1). Shift orders are to maintain current power level. NOTE: SURROGA TE OPERA TOR WILL BE FILLING 'CRS' POSITIONDURING l THISSCENARIO. l
Ltd.e 4 Event Malf. Event Event No. No. Type
Description 1 RX05B (I). High failure of PRZR Pressure Control channel.
(1) RX CRS 2 RD12-16 (C) Control rod recovery following drop into core. (1) RX-CRS 3 NA (N) Turbine load reduction to <75%. TURB CRS NA (R) Reactivity control during power reduction. RX 4 RX15A (I) High failure of a steam flow channel. (1) TURB CRS 5 ED01 (M) Loss of offsite power, resulting in Rx Trip and loss of (1) RX forced circulation (Following events result in loss of all TURB feedwater.) CRS 6 EDI1A Failure of EDG l-1 output breaker to close. CRS 7- FW16B (C) Loss of TDAFW Pump P-8B following loss of offsite (1) RB power (Results in loss of all feedwater). 8 NA CRS Classify the event as General Emergency. (Note that sunogate is filling role of CRS in this scenario.) Terminate scenario when appropriate actions taken to establish once-through core cooling during the performance of EOP-7.0 or at lead examiner's discretion. (1) See Attachment," Simulator Setup & Actions Required for Scenario 2," for details on setup.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor l
, 1 o > Appendix D Scenario Outline Fonn ES-D-1 Facility: PALISADES Scenario No.: 3 Op-Test No.: Examiners: Operators: Objectives:
1) Evaluate and respond to a low failure of a PRZR level channel.

2) Evaluate and respond to a low failure of a SG feed flow channel.

3) Evaluate and respond to contaminants in EDG l-1 fuel oil.

4) Evaluate and respond to a trip of a cooling water pump with subsequent rapid power ;
reduction in response to lowering condenser vacuum.
5) Control reactivity during rapid power reduction.

6) Evaluate and respond to increasing SG tube leakage requiring Rx Trip.

7) Evaluate and respond te a steamline break outside contaimnent on the SG with tube leakage upon the Rx Trip.

8) Evaluate and respond to a failure of HPSI discharge valve, resulting in inadequate SI flow following actuation.

9) Classify the event.
Initial Conditions / Setup:
1) IC-11 (99.7%).

2) Tag out HPSI Pump P-66A.
. ..- u '3 to RACKOUT
Caw .nn Tag P-66A OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
I/O CV-3059 to CLOSE(Event 7) I/O CV-3059-R to ON (Event 7) I/O CV-3059-G to OFF(Event 7) Turnover: Core Age is NEW. 99.7% power, equilibrium conditions. Current boron concentration is 1260 ppm. PCS pressure is 2060 psig and temperature is 560*F. Rod Position is ARO. SG Blowdown is 20K each. ASI average is approximately 0.00. HPSI Pump P-66A is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.3.1). Shift orders are to reduce power at a rate of 3% per hour.
Event ' Malf. No. Event Event No. Type
Description 1 ' RX07B (I) Low failure of a PRZRlevel channel.
(1) RX CRS J 2- RX14 (I)~ low failure of SG feed flow channel.
-(1)' TURB CRS 3 NA (C). Chemistry reports contaminants found in EDG l-1 fuel oil CRS sample.
4 CWO!A (C)- Trip of cooling water with subsequent rapid power (1)- TURB reduction in response to lowering condenser vacuum. CRS NA (R) Reactivity control during rapid power reduction. RX 5 SG01A- (C) Increasing SG tube leakage requiring Rx Trip. (1) RX TURB CRS-6- MS06A (M) Steamline break outside containment on SG with tube ; (1) RX leakage upon Rx Trip. l TURB CRS 7 (1) (C) Failure of HPSI discharge valve (disc separated from stem), resulting in inadequate SI flow folloving actuation.
,8 NA CRS Classifies event as Alertc Terminate scenario when SI How is throttled and LHSI .
pumps are stopped or at lead examiner's discretion. l (1) See Attachment," Simulator Setup & Actions Required for Scenario 3," for details on setup.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 4
4. e f. . o
..l, 1
u / Appendix D: ' Scenario Outline Form ES-D-1 Facility: ' PALISADES ' Scenario No.: 4 Op-Test No.: Examiners: Operators: Objectives:
1) Lower power to 86% to per#orm turbine valve testing.
2)' Control core reactivity during power reduction.
3) Perform Governor Valve testing per SOP-8.

4) . Evaluate and respond to a high failure ofletdown pressure control.

5) Evaluate and respond to high PCS activity.

6) Evaluate and respond to a low failure of SG B level transmitter.

7) Evaluate and respond to a trip of a running charging pump.

8) Evaluate and respond to a trip of a heater drain pump.

9) Evaluate and respond to a large break LOCA.

10) Evaluate and respond to a failure of automatic actuation of CHP/CIS.
I1) Classify the event. Initial Conditions:
1) IC-11 (99.7%).

2) Lower power to 89% to begin a small change in xenon concentration.

3) Maintain power level for approximately % minutes.

4) Tag out HPSI Pump P-66A .
. RM SI23 to RACKOUT e Caution Tag P-66A OOS for breaker maintenemce
5) ' Place DEH control in Govemor Single valve mode.
Scenario Event Setup Prior to Scenario Start: e MALF CH05A to activrie(Event 9)
MALF CH05B to activate (Event 9)
Turnover: Core Age is NEW. 89% power, constant power for 30 minutes following a 2% load reduction over the last hour from 99.7% equilibrium conditions. Current boron concentration is 1260 ppm.' PCS pressure is 2%0 psig and temperature is 555'F. Rod Position is ARO. SG Blowdown is 20K each. ASI average is approximately 0.00. HPSI Pump P-66A is tagged out - of service for motor bearing inspection and is expected back in approximately 8 hours (TS 3.3.1). DEH controller is in Governor Single valve mode. SOP-8 is in progress to test Governor Valve #3 only. Shift orders are to lower power to 86%, test Governor Valve #3 and then return the unit to 100% conditions.
E' ) f, o
\
i
' Event Malf. Event Event No. No. Type
Description 1 NA.- (N) Lower power to 86%. i TURB {
CRS NA (R) Control reactivity during power reduction. ! RX - l 2 .NA (N) Verform test of Governor Valve #3. TURB CRS 3 CV05 (I) High failure ofletdown pressure control. (1) RX CRS l 4 NA: (C) Chemistry reports PCS activity at a value exceeding Tech ! CRS Spec limits. 5 RXIOC (I) Low failure of SG B level transmitter. ' (1) TURB CRS ! 6 3A ( Trip of running Charging Pump. CRS 7 FWO7B Trip of Heater Drain Pump. CRS 8 RC04 (M) Large break Loss of Coolant Accident. ; RC02 RX : l (1) TURB : CRS 9 CH05A (C) Failure of automatic actuation of CHP/CIS. CH05B RX (1) CRS 10 NA CRS Classifies event as Site Area Emergency. i Terminate scenario when proper alignment completed following failure of CHP/CIS or at lead examiner's discretion. 1 (1) See Attachment," Simulator Setup & Actions Required for Scenario 4," for details on setup.
* (N)ormal, - (R)eactivity, (I)nstrument, (C)omponent, (M)ajor t
I.. .
{ 16 . , l Appendix D'. Scenario Outline Form ES-D-1 p. l Facility: PALISADES - Scenario No.: 5 Op-Test No.: Examiners: Operators: l ., Objectives:
1) Lower power from 50%.

2) Control reactivity during power reduction.

3) Secure a running Main Feedwater Pump.

4) Evaluate and respond to a low boron concentration in the SI accumulator.

5) Evaluate and respond to a low failure of a Przr Pressure channel.

6) Evaluate and respond to a trip of a Condensate Pump.

7) Evaluate and respond to a high vibration on a PCP.

8) Evaluate and respond to a loss of offsite power with the failure of I-2 DG to start.

9) Evaluate and respond to a trip of SW Pump P-7B.

10) Evaluate and respond to a Station Blackout due to the loss of 1-1 DG.
I1) Classify the event. Initial Conditions: I
1) IC-9 (51%).

2) Tag out HPSI Pump P-66A.
RM SI23 to RACKOUT

Caution Tag P-66A OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:

MALF ED14B to activate (Event 7)-
Turnover: Core Age is MOL. 51% power, equilibrium conditions. Current boron concentration is 1260 ppm. PCS pressure is 2060 psig and temperature is 546*F. Rod Position is ARO. SG Blowdown is 20K each. ASI average is approximately 0.01. HPSI Pump'P-66A is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours. Shift orders are to continue to lower power for a mid-cycle maintenance outage.
r W , l i Event Malf. No. Event Event No. Type
Description 1 NA (N) Lower power from 50%. ,
TURB j CRS j 1 NA (R) Control reactivity during power reduction. 4 RX 2 NA (N) Secure a running Mah Feedwater Pump. TURB CRS ) 3 NA (C) Chemistry reports boron concentration at value below Tech CRS Spec limit. 4 RX06B (I) Low failure of a Przr Pressure channel. (1) RX , CRS ! 5 ~ FWO4A (C) Trip of a Condensate Pump. (1) TURB CRS l 6 RC16B (C) High vibration on PCP. (Loss of offsite power occurs (1) RX before trip conditions are met.) CRS 7 ED01 (M) Loss of offsite power with the failure of I-2 DG to start. ED14B RX ' (1) TURB , CRS l 8 SWO4B (C) Trip of SW Pump P-7B. (1) RX CRS 9 NA ( Station Blackout due to loss of 1-1 DG. TURB CRS 10 NA. CRS Classifies event as Site Area Emergency. Terminate scenario when the preliminary actions of EOP Supplement 24 are completed or at lead examiner's discretion. l l (1) See Attachment," Simulator Setup & Actions Required for Scenario 5," for details on setup.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor E
p 1 At 3
'I Appendix D . Scenario Outline Form ES-D-1 Facility: PALISADES ' Scenario No.: SPARE Op-Test No.: l Examiners: Operators:
Objectives:
1) Lower power from 75%.

2) Control reactivity during power reduction.

3) Evaluate and respond to a trip of the running Charging Pump. l

4) Evaluate ard respond to a high failure of a Pressurizer Pressure Control channel. l

5) Evaluate and respond to a trip of a Main Feedwater Pump. l

6) Evaluate and respond to a failed closed Feedwater Control Valve.

7) Evaluate and respond to a Feedwater line break inside containment.

8) Evaluate and respond to a failure of a single train of SIAS to actuate.

9) Evaluate and respond to a trip of a Containment Spray Pump.

10) Classify the event. l Initial Conditions: l

1) IC-10(75%).

2) Tag out HPSI Pump P-66A.
*- RM SI23 to RACKOUT !
Caution Tag P-66A OOS for breaker maintenance
3) Tag out MDAFWP P-8C. 1 e - MALF FW16C-active e I/O P-8C H/S to TRIP e I/O P-8C-O to OFF e' I/O P-8C-R to OFF e Caution Tag P-8C OOS for breaker maintenance Scenario Event Setup Prior to Scenario Start:
MALF ED13A to activate (Event 7) ; e MALF SIO3C to activate (Event 8) Turnover: Core Age is NEW. 75% power, constant power for 2 hours following 3%/ hour ramp from 100% equilibrium conditions. Current boron concentration is 1335 ppm. PCS pressure is 2060 psig and temperature is 552*F. Rod Position is ARO. SG Blowdown is 20K each. ASI average is approximately 0.00. MDAFW Pump P-8C is tagged out of service for motor bearing inspection and is expected back in approximately 8 hours (T." 5.1). EK-1318, SIRWT HI/LO PRESS ALARM has been coming in/out. HPSi Pump N6A is tagged out of service for motor bearing inspection and is expected back in appmxin tately 8 hours. Shift orders are to shift running charging pumps for breaker maintenance on P-55A and continue power reduction for a maintenance outage.
a ~y l t Event Malf. No. Event Event No. Type
Description 1 NA (N) . Lower power from 75%.
l TURB l CRS NA (R) Control reactivity during power reduction. RX 2 CV03B (C) Trip of a running Charging Pump. (1) RX CRS i 3 RX05B (I) High failure of a Pressurizer Pressure Control channel. (1) RX CRS 4 FWOIB (C) Trip of a Main Feedwater Pump. (1) TURB CRS 5 FWO6A (C) Failed closed Feedwater Control Valve. (1) TURB CRS 6 FWO9A (M) Feedwater line break inside containment. (1) RX TURB CRS 7 ED13A (C) Failure of a single train of SIAS to actuate. (1) RX CRS 8 S103C (C) Trip of a Containment Spray Pump. (1) RX CRS 9 NA CRS Classifies event. Terminate scenario when the actions are taken to throttle Si flow following faulted SG isolation or at lead examiner's discretion. l l (1) See Attachment," Simulator Setup & Actions Required for Scenario Spare," for details on ! l setup. l
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor l
1 i
c
\
0 fn l l ES-401 PWR RO Examination Outline Fonn ES-401-4 l l l Facility: PAIJSADES Date of Exam: JUNE 1999 Exarn Level: RO l K/A Category Points Point Tier Group Total KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
1. I 2 2 3 3 3 3 16 i Emergency & 2 3 2 3 3 17 Abnormal Plant . 3 TT 0 1 0 1 3 Evolutions Tier Totals 6 6 6 7 36

2. I 2 2 2 2 2 2 2 2 2 2 3 23 Plant 2 2 1 2 l2 ll l2 l2 2 l2 l2 l2 20 Systems 3 0 0 I l1 l0 l1 l1 I l1 l1 l1 8 Tier Totals 4 3 $ 5 3 5 5 5 5 5 6 51

3. Generic Knowledge and Abdities Cat I Cat 2 Cat 3 l Cat 4 4 3 3 3 13 Notes:
Attempt to distribute topics among all K/A categories; select at least one topic fmm every K/A category within each tier.

Actual point totals must match those specified in the table.

Select topics from many systems; avoid selecting more than two or three K/A topics fmm a given system unless they relate to plant.
specific priorities. e Systems / evolutions within each gmup are identified on the associated outline. e The shaded areas are not applicable to the ca'egory/ tier. e (PRA) in E/ APE # / Name / Safety Function (Tier I) or System # / Nanm (Tier 2) indicates K/A statement related to most important operator actions determined in the Palisades Nuclear Plant Probabilistic Risk Assessment. Note not all important operator actions are evaluated, outline only reflects those K/A items randomly selected AND related e the Probabilistic Risk Assessment.
Number in 10CFR55.41(b) indicates associated item for RO written examination.
NUREG-1021 Interim Rev. 8. January 1997
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V l.' c . , . ES-401 RO Generic Knowledge and Abilities Outline (Tier 3) 1 orm ES-4015 Facility: PALISADES Date o Exam: JUNE 1999 Exam Level: RO l Category imp. 10CFR K/A # Topic 55 41(b) I item Conduct of Operations 2.1.11 Knowledge ofless than one hour technicri specification action statements for systems. 3.0 10 2.1.20 Ability to execute procedure steps. 4.3 10 2.1.22 Ability to determine Mode of Operation. 2.8 10 2.1.28 Knowledge of the purpose and function of major system components and controls. 3.2 7 Total 4 Equipment Contml 2.2.2 Ability to manipulate the console controls as required to operate the facility between 4.0 10 shutdown and designated power levels. 2.2.23 Ability to track liiniting conditions for operations. 2.6 10 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from 3.5 13 fuel handling area, communication with fut storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation l { Total 3 j 1 Radiation Control 2.32 Knowledge of facility Al ARA program. 2.5 12 2.3.4 Knowledge of radiation exposure hmits and contamination control, including 2.5 12 permissible levels in excess of those authorized. 2.3.1 l Ability to control radiation releases. 2.7 II Total 3 Emergency Procedures and Plan 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP 3.9 7 entry conditions. 2.4.17 Knowledge of EOP terms and definitions. 3.1 10 2.4.34 Knowledge of RO tasks performed outside the main control room durmg emergency 3.8 10 operations including system geography and system implications. , I I Total 3
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Tier 3 Target Point Total 13 NUREG-1021 Interim Rev. 8, January 1997 1 l l l
i e , ES-401 PWR SRO Examination Outline Fonn ES-401-3 l Facility: PALISADES C. s m: JUNE 1999 Examlevel: SRO l K/A Category Points Point Tier Group Total Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G
1. I 4 4 4 4 4 4 24 Emergency & 2 3 3 2 3 16 Abnormal Plant 3 TT 0 1 0 1 3 Evolutions Tier Totals TT 7 8 6 8 43

2. I 2 I I 2 1 2 2 2 2 2 2 19 Plant 2 2 I I l2 l1 l2 ll 2 l1 l2 l2 17 Systems 3 0 0 I l0 l0 l1 l0 0 l0 l1 ll 4 Tier Totals 4 2 4 2 4 5 40 3 5 3 3 l5

3. Generic Knowledge and Abilities Cat I Cat 2 Cat 3 Cat 4 4 4 4 5 17 i
Notes: j e Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier. !
Actual point totals must match those specified in the table, e ' Select topics from many systems; avoid selecting more than two or three K/A tapics from a given system unless they relate to plant-specific priorities.

Systems / evolutions within each group are identified on the associated outi me.
e The shaded areas are not applicable to the category / tier, e (PRA) in E/ APE # / Name / Safety Function (Tier 1) or System W / Name (Tin 2) indicates K/A statement related to most imponant operator actions determined in the Palisades Nuclear Plant Probabilistic Risk Assessment. Note not all important operator actions are evaluated; outline only reflects those K/A items randomly selected AND related to the Protabilistic Risk Assessment.
Number in 10CFR55.43(b) indicates associated item for SRO ONLY questions on written examination. Where no number is listed tim K/A is common to both the RO and SRO candidate.
NUREG-1021 Interim Rev. 8 January 1997 j
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1 ES431 SRO Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 1 Facility: PALISADES Date of Exam: JUNE 1999 Exam level: SRO Category I,r A # Topic Imp. I FR Conduct of Operations 2.1.2 Knowledge of operator responsibihties during all modes of plant operation. 4.0 5 2.1.7 Ability to evaluate plant performance and eneke operationaljudgments based on 4.4 5 operating characteristics, reactor behavior, and instrument interpretation. 2.1.10 Knowledge of conditions and limitations in the facility license. 3.9 1 2.1.23 Abihty ta nerform specific system and integrated plant procedures during all modes of 4.0 5 plant operation. Total 4 Equipment Control 2.2.1 Abihty to perform pre-startup procedures for the facihty, including operating those 3.6 5 , controls associated with plant equipment that could affect reactivity. % 2.2.15 Ability to identify and utilize as-built design and configuration change documentation 2.9 3 to ascertain expected current plant configuration and operate the plant. 2.2.17 Knowledge of the process for managing maintenance activities during power 3.5 5 operations. 2.2.27 Knowledge of the refueling process. 3.5 6/7 Total 4 Radiation Control 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirernents. 3.0 4 2.3.7 Knowledge of the pocess for preparing a radiation work permit. 3.3 4 2.3.8 I;nowledge of the pmcess for performing a planned gaseous radioactive release. 3.2 4 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 4 personnel exposure. Total 4 Emergency Procedures and Plan 2.4.7 - Knowledge ofevent based EOP mitigatwa wategies. 3.8 5 2.4.15 Knowledge of communications pmcedures associated with EOP implementation. 3.5 5 2.4.20 Knowledge of operational implications of EOP warnings, cautions, arui notes. 4.0 5 2.4.28 Knowledge of procedures relating to emergency response to sabotage. 3.3 5 2.4.31 Knowledge of annunciators alarw . Scations, and use of the response 3.4 5 instructions. Total 5 Tier 3 Target Point Total NUREG-1021 interirn Rev. 8. January 1997 k . . b}}

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