CALVERT C~LIFFS NUCLEAR POWER PLANT 2012 …NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERA TOR...

APPLICANT: ___

CALVERT C~LIFFS

NUCLEAR POWER PLANT

2012 NRC

INITIAL LICENSED

OPERA TOR ]~XAM

JPM #: SRO-A~DMIN-1

Appendix C Job Perfonnance Measure Form ES-C-l Worksheet

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-I

Task Title: Detennine Status of Safety Functions for the FRP

Task Number: 201.078

KIA Reference: 2.1.20 - Ability to interpret and execute procedure steps (4.6, 4.6).

Method of testing:

Simulated Perfonnance: D Actual Performance: ~ Classroom: D Simulator: ~ Plant: D

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job perfonnance measure will be satisfied.

Initial Conditions:

1. Both Units were operating at 100% power

2. The OC DG is OOS for scheduled maintenance

3. AOP-2A was implemented for a SGTR and a Rapid downpower is commenced

4. When the reactor is tripped, lAW AOP-2A, the following complication(s) occur:

a. Oflsite Power is lost

b. The lA DG experiences a start failure

5. EOP-O has been completed

6. EOP-6 has been implemented

7. The affected S/G has been isolated

8. A fault occurs on 14 4KV Bus causing its loss

9. EOP-8 has just been implemented.

10. You are perfonning in the role ofthe STA

Initiating Cue:

The CRS has directed you to:

1. Determine status of safety functions per EOP-8, Step IV.E.

Determine the priority for implementation of the Safety Function Recovery Actions per EOP-8, Step IV.F.3. Are there any questions? You may begin.

Task Standard:

Candidate refers to the Resource Assessment Table and correctly determines the success path available to satisfy each safety function.

Appendix C Job Performance Measure Form ES-C-l Worksheet

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time:.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

EOP-8, Section VI, Resource Assessment Table

Completed EOP-O Safety Function Status Check

Completed EOP-6 Safety Function Status Check

General References:

Procedures and manuals normally available in the Control Room

Time critical task:

No

Validation Time:

15 minutes

Simulator Setup:

See next page


Simulator Setup:

1. Reset to IC-24.

2. Perform switch check.

3. Place simulator in CONTINUE, advance charts and clear alarm display.

4. Place simulator in FREEZE.

5. Enter Malfunctions:

a. OC DG Start Failure, DG002_01 at time zero

b. lA DG Start Failure, DG002_02 at time zero

c. 11 SG Tube Rupture, ms002_01 at 1.0 with no ramp time at time zero

d. Loss of Off-Site Power, swyd002 on Event 1

e. IB DG Start Failure, dg001_02 on Event 2

6. Enter Panel Overrides

a. None

7. Enter Remote Functions I Administrative

a. Caution tag OC DG output bkr HS in PTL and red dot alarms.

b. Caution tag on OC DG start pushbuttons.

8. Drive simulator to desired condition:

a. Set simulator time to real time, then place simulator in CONTINUE.

b. Perform a rapid downpower and trip the n!actor per AOP-2A, Section VI.

c. Commensurate with the trip, insert Event 1, Loss of Off-Site Power

d. Complete the required actions ofEOP-O

e. Implement EOP-6 and proceed thru isolation of 11 S/G

f. Insert Event 2, lA DG Start Failure

__ g. Initiate AFW flow with 11 AFW Pump

9. Place simulator in FREEZE.

----


ELEMENT (shaded + * = CRITICAL STEP) STANDARD

TIME START:

CUE. Provide operator with a filled out copy of the EOP-O Safety Function Status as an aid in . determining correct priority for addressing Safety Functions.

o Identifies and locates EOP-8, Functional Recovery Same as element

Procedure, Section IV, Step IV.E.

o IV.E. - DETERMINE STATUS OF SAFETY FUNCTIONS (STA).

o IV.E.l - Identify success paths for ALL Safety

Functions PER Section VI., RESOURCE

ASSESSMENT TABLE.

o VI. - RESOURCE ASSESSMENT TABLE

Evaluates Reactivity Control Success Paths and chooses: RC-l, Met

Evaluates Vital Auxiliaries Success Paths and chooses: V A-3, Not Met

Evaluates RCS Pressure and Inventory Control Success Paths and chooses: PIC-4, Not Met

Evaluates Core and RCS Heat Removal Success Paths and chooses: HR-2, Not Met

Evaluates Containment Environment Success Paths and chooses: CE-l, Met

Evaluates Radiation Levels o VI.RLEC - Radiation Levels External to External to Containment Success

Containment Success Path Paths and chooses:

RLEC-2, Met

Appendix C Job Performance Measure Fonn ES-C-l Worksheet


Acknowledge report of recommended Success Paths

Reports results of Safety Function assessment to the CRS:

0 RC-l, Met

0 V A-3, Not Met

0 PIC-4, Not Met

0 HR-2, Not Met

0 CE-l, Met

0 RLEC-2, Met

o IV.F. - PERFORM RECOVERY ACTIONS

NOTE

Safety Functions are presented in order of importance. Selected success paths should be commenced in accordance with the Safety Function hierarchy.

Reports results of Safety Function priority assessment to the CRS:

o 1st priority - V A-3 o 2nd priority - PIC-4 o 3 rd priority - HR-2 o 4th priority - RLEC-2 o 5th priority - RC-l o 6th priority - CE-l

TERMINATING CUE: This JPM is complete when the selected success paths and their priorities have been continned with the CRS. No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP: ___

-----------


Verification of Completion

Job Performance Measure Number: SRO-ADMIN-l

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _________._______

Time to Complete:

Follow up Question: _________________________

Applicant Response: _________________________

Result: SAT ______ UNSAT

Examiner's Signature and Date: _______________________


EXAMINEE'S CUE SHEET

Initial Conditions:

1. Both Units were operating at 100% power

2. The OC DG is OOS for scheduled maintenance

3. The IB DG is removed from service due to SRW Hx fouling (per AOP-7A, Att (1))

4. AOP-2A was implemented for a SGTR and a Rapid downpower is commenced

5. When the reactor is tripped, lAW AOP-2A, the following complication(s) occur:

a. Offsite Power is lost

b. The lA DG experiences a start failure

6. EOP-O has been completed

7. EOP-6 has been implemented

8. The affected S/G has been isolated

9. A fault occurs on 14 4KV Bus causing its loss

10. EOP-8 has just been implemented.

11. You are performing in the role of the ST A

Initiating Cue:

The CRS has directed you to:

1. Determine status of safety functions per EOP-8, Step rv.E. 2. Determine the priority for implementation of the Safety Function Recovery Actions per

EOP-8, Step IV.F.3.

3. Are there any questions? You may begin.

EOP-O Rev 12/Unit 1 Page 24 of 27

VI. SAFETY FUNCTION STATUS CHECK

A. The STA (or person designated by the CRS) will perform the safety function status checks

on entry into this procedure.

B. Record value/status for all safety function parameters. Circle any value/status that does not

meet acceptance criteria.

C. Notify the Control Room Supervisor if any safety function acceptance criteria is not being

satisfied, promptly upon full completion of the safety function status check.

SAFETY PARAMETERS ACCEPTANCE CRITERIA REACTIVITY

CONTROL ACCEPTANCE

PARAMETERS VALUE/STATUSCRITERIA

a. WRNI lowering 5 X 10-3

b. SUR negative (-)1/3 dpm

Unable to NO more than ONE

determine due to c. CEA status CEA NOT fully

loss ofpowerinserted

effects

OR

RCS Boration in d. Boration status

progress



VITAL AUXILIARIES PARAMETERS

a. 4KV Vital buses 11 OR 14

b. 125V DC buses 11, 12, 21 and 22

c. 120V AC buses 11, 12, 13,14

d. lY09 or lYlO

RCS PRESSURE

AND

INVENTORY

PARAMETERS

a. Pressurizer Pressure

b. Pressurizer level

c. RCS subcooling

SAFETY FUNCTION ACCEPTANCE CRITERIA

ACCEPTANCE VALUE/STATUSCRITERIA

At least ONE energized 4KV Bus 11 energized

ALL greater than 105 volts

All I25V DC buses greater than 105V

At least THREE energized

All 120V AC Buses energized

At least ONE energized 1Y09 energized


ACCEPTANCE VALUE/STATUS

CRITERIA

1850 PSIA to 1270 PSIA and 2300 PSIA slowly lowering

80 inches to empty

180 inches

21°F and slowly Greater than 30°F

nsmg

EOP-O Rev 12/U nit 1 Page 26 of 27


COREANDRCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT

REMOVAL ACCEPTANCE VALUE/STATUSPARAMETERS CRITERIA

a. RCS TCOLD 52YF to 535°F 532°F

b. THOT minus less than 10°F TcoLD Loop flT(s) = ~26°F

c. RCPs operating per lOR2 loop 0

d. S/G level (-)170 inches 11 S/G, (-)57 inches 11 OR 12 to (+)30 inches 12 S/G, (-)90 inches

CONTAINMENT _____S_A_F_E_T_Y_F_U_N_C__T_I_O_N_A_C_C_E_PT_A_N_C_E_C_R_I_T_E_R_I_A____

ENVIRONMENT ACCEPTANCEPARAMETERS VALUE/STATUSCRITERIA

a. Containment Pressure

less than 0.7 PSIG 0.1 PSIG & steady

b. Containment Temperature less than 120°F 100°F & steady

c. Containment Radiation Monitors

Alarm clear with NO unexplained rise



RADIATION LEVELS

EXTERNAL TO

CONTAINMENT

PARAMETERS

e. Noble Gas Monitor (1-RIC-5415)

f. Condenser Off-Gas RMS (1-RI-1752)

S/G BID RMS (l-RI-4014)

h. Main Vent Gaseous RMS (l-RI-5415)


ACCEPTANCE CRITERIA

alarm clear with NO unexplained rise




VALUE/STATUS

In alarm prior to loss of power

In alarm prior to loss of power

EOP-6 Rev 17/Unit 1

Page 102 of 108


A. The ST A (or person designated by the CRS) will perform the safety function status checks on entry into this procedure.

B. Record value/status for all safety function parameters. Circle any value/status that does not meet acceptance criteria.

C. Notify the Control Room Supervisor if any safety function acceptance criteria is not being satisfied, promptly upon full completion of the safety funchon status check.

SAFETY FUNCTION ACCEPTANCE CRITERIAREACTIVITY

CONTROL INTERMEDIATE FINAL

PARAMETERS CRITERIA CRITERIACHECK CHECK

..J less a. WRNI lowering than 10.4%

..J negativeb. SUR negative

or zero

NO more than NO more than c. CEA status ONECEANOT ONECEA

fully inserted NOT fully inserted

OR

greater than or greater than Boration status equal to 40 GPM 2300 PPM

EOP-6 Rev 17/Unit 1

Page 103 of 108


VITAL AUXILIARIES PARAMETERS

a. 4KV Vital buses 11 or 14

b. 125V DC buses 11, 12, 21 and 22

e. 120V AC buses 11, 12, 13,14

d. 1 Y09 or 1 Y 10


CRITERIA INTERMEDIATE

CHECK CRITERIA

FINAL CHECK

At least ONE energized

At least ONE energized

ALL greater than 105 volts ALL greater

than 105 volts

at least THREE energized

at least THREE energized

At least ONE energized At least ONE

energized

EOP-6 Rev 17/Unit 1

Page 104 of 108


RCS PRESSURE

AND

INVENTORY

PARAMETERS

a. Pressurizer Pressure

b. Pressurizer level

c. RCS subcooling

d. Reactor Vessel Level


INTERMEDIATE FINALCRITERIA CRITERIA

CHECK CHECK

Less than the less than the upper limits of upper limits of Att. (1) Att. (1)

Greater than 30 101 inches to inches 180 inches

OR

At least One Charging Pump operating and SIS injecting PER 101 inches to Atts. (10) and (11) 180 inches

less than 140°F

greater than greater than 25°F

25°F

OR

At least One ICharging Pump • greater than operating and SIS

2YFinjecting PER Atts. (10) and (11)

•

above the top core covered

of the hot leg

EOP-6 Rev 17/Unit 1

Page 105 of 108


CORE AND SAFETY FUNCTION ACCEPTANCE CRITERIA RCSHEAT

INTERMEDIATE FINALREMOVAL CRITERIA CRITERIACHECK CHECKPARAMETERS

a. CET less than less than 600°F Temperatures 600°Fl=

constant or constant or b. RCS TCOLD lowering loweringl= OR

c. Unaffected (-)170 inches to ( -)24 inches to S/G level (+)30 inches (+)30 inches l=

trending to ( -)24 inches to (+ )30 inches N/A N/AC

EOP-6 Rev 17/Unit 1

Page 106 of 108


SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT INTERMEDIATE FINAL

CRITERIA CRITERIAPARAMETERS CHECK CHECK

,j I

a. Containment less than 0.7 less than 0.7

Pressure PSIG PSIGI I I

N/A Ib. Containment constant or

Temperature (1) less than 15WF lowering

j •

NO NOc. Containment unexplained unexplainedRadiation nse riseMonitors (2) I

,jalarm clear

alarm clear I I

NOd. Containment

unexplained unexplainedSump level

rIse rise±CL NO (1) NOT available if 1Yl 0 is de~energized

(2) NOT applicable ifOOS due to loss of power

EOP-6 Rev 17/Unit 1

Page 107 of 108


RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS

EXTERNAL TO INTERMEDIATE FINALCRITERIA CRITERIACONTAINMENT CHECK CHECK

PARAMETERS

a. Noble Gas

Monitor

(l-RIC-5415) N/A N/A alarm clear

b. Condenser Off-

Gas RMS

(l-RI-1752)(l) N/A N/A alarm clear

c. S/G BID

RMS

(l-RI-4014)(1) N/A N/A alarm clear

d. Main Vent

Gaseous RMS

(l-RI-5415)(1) N/A N/A alarm clear

e. Affected S/G Less than 920 Less than 920 pressure PSIA PSIA=+±J=

(1) NOT applicable ifOOS due to loss of power

APPLICANT: ___

CALVERT C~LIFFS

NUCLEAR POWER PLANT

2012 NRC

INITIAL LICENSED

OPERATOR I~XAM

JPM #: SRO-ADMIN-2


Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-2

Task Title: Evaluate the need for plant cooldown.


KIA Reference: 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9,4.2)

Method of testing:

Simulated Performance: D Actual Performance: [2J

Classroom: [2J Simulator: D Plant:


I will explain the initial conditions, which steps to simulate or discuss, and provide initiating

cues. When you complete the task successfully, the objective for this job performance measure

will be satisfied.

,-------------------------------_........_-------,

Initial Conditions:

1. Unit-l is in Mode 6 preparing to enter Mode 5

2. SMECO is unavailable due to maintenance.

3. 11 CST is empty for maintenance

4. Unit-2 is operating at 100% reactor power.

5. A loss of offsite power occurs at 0845.

6. The 1 A DO fails to start

7. 14 4kv Bus is deenergized due to a ground fault.

8. The OC DO is unavailable

9. The plant has been stabilized per EOP-7 with the following-parameters:

a. Unit-l RCS Temperature is 110" F and slowly rising.

b. Unit-2 RCS temperature is 532" F and steady.

c. 12 CST level is 24.5 feet

d. 21 CST level is 30 feet

10. You are performing the duties of an extra SRO.

Initiating Cue:

At 1045, the Unit-2 CRS requests you perform EOP-7, Step AC, EVALUATE THE NEED FOR PLANT COOLDOWN.

Task Standard:

The candidate will assess condensate inventory using EOP Att. (9) and determine there is

insufficient water to cooldown to < 3000 F, the plant must b(~ maintained in hot standby, and the

plant can be maintained in hot standby for approximately 76 hours. The evaluator is expected to

end the lPM.





3. All time-critical steps completed within allotted time.


Required Materials:

1. EOP-7, Station Blackout (Unit-2)

2. EOP Attachments (Unit-2)

General References:


Time critical task:

No

Validation Time:

25 minutes

Simulator Setup:

None



TIME START: ___

D Locates EOP-7, Step AC, Evaluate the Need for Plant Same as element

Cooldown.

D IV.AC.I. - WHEN the RCS parameters have been stabilized, THEN evaluate the need for a plant cooldown based on:

D Plant Status Candidate will determine Att (9) completion is required D Auxiliary systems availability

D Condensate inventory PER ATTACHMENT (9),

MAKEUP WATER REQUIRED FOR RCS

COOLDOWN

Locates UNIT-2 EOP ATTACHMENTS, Attachment (9), Same as element.

Makeup Water Required For RCS Cooldown

D 1. - Determine the amount of makeup water required to perform an ADV cooldown and a TBV cooldown, Same as element. based on the time after shutdown:

Candidate uses table "INVENTORY REQUIRED TO COOL DOWN TO 3000 F" to determine 614,531 gallons are required to cool the Unit down to 3000 F two hours following the shutdown.

Candidate enters uses table "Inventory Required to Cool Down to 3000 F" and determines 88,490 gallons are required to cool the Unit

D *l.b. - TBV cooldown and time after shutdown , down to 300 0 F two hours ,

following the shutdown. Candidate may NIA this step due to condenser unavailability.

D 2. Determine the amount of makeup water available in The candidate determines the tank the CSTs: levels from the initiating cue.

JKecords 21 CST level as 30 feet


ELEMENT (shaded + * = CRITICAL STEP)

Records 12 CST level as 24.5 feet

Records 11 CST level as 0 feet

o 2.d. - Determine the status of Unit-l (check one): Same as element. o 2.d.(1) Mode 1,2 or 3 and does NOT

require AFW operation. Determines step is NOT applicable

o 2.d.(2) __ Mode 1, 2 or 3 and does require AFW operation.

Determines step is NOT applicable

Determines step IS applicable based on stated conditions

NOTE: Calculated negative values should be entered as zero.

o 2.e. - Determine the amount ofmakeup water available to Unit 1 using one of the following

Same as element. formulas, based on the status checked in step 2.d above:

o 2.e.( 1) - IF step d.( 1) is checked, THEN correct Determines step is NOT applicableCST levels for usable volume:

o 2.e.(2) - IF step d.(2) is checked, THEN correct Determines step is NOT applicable

CST levels for usable volume:

o 2.e.(3) - IF step d.(3) is checked, THEN correct Determines step IS applicable

CST levels for usable volume:

Records 21 CST usable volume as: 27.25 feet

Records 12 CST usable volume as: 22 feet

Records 11 CST usable volume as: ofeet

Records total usable volume as: 49.25 feet

Performs calculation determining approximately 474,611 gallons of CST inventory are available



NOTE

The nominal capacity of a Well Water pump is 300 GPM. The nominal capacity of a

Demineralized Water Transfer pump is 300 GPM. The Fire System can fill the CST via fire

hoses at greater than 500 GPM.

CAUTION

The status of both units should be considered when evaluating a makeup source.

Candidate determines there is NOT 3. IF adequate inventory exists to perform cooldown, adequate inventory to perform a

THEN determine if an adequate makeup source exists cooldown. to maintain hot standby. Water required is 614,531,

inventory available is 474,611

The Shift Manager requests the candidate to determine how long hot standby canCUE:

be maintained with the current inventory. Supply examinee with Cue Sheet #2.

The candidate uses ATT (9), Makeup Water Required to Maintain Hot Standby.

If the chart is NOT interpolated, the value would be 72 hours of hot standby. If chart is interpolated, the value would be 76 ± 1 hours

Acceptable answer is 72 - 77 hours

Returns to EOP-7, Step AC.2.2 Same as element.

o IV.AC.2. - IF a plant cooldown is NOT desired, THEN perform the following: Same as element. Crew focus

would be on restoration of powero IV.AC.2.a. - Maintain stabilized plant conditions. and a makeup source

o IV.AC.2.b. - PROCEED to step AG.

TERMINATING CUE: This lPM is complete when it is determined there is NOT adequate inventory to perform a cooldown and how long hot standby can be maintained. No further actions are required. The evaluator is expected to end the lPM.

[iIME STOP: ___

Appendix C Job Performance Measure Form Worksheet


Job Performance Measure Number: SRO-ADMIN-2

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _________________

Time to Complete:

Follow up Question: _________________________

Applicant Response: ________________________

Result: SAT ______ UNSAT ________

Examiner's Signature and Date: _____________________

Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet

EXAMINEE'S CUE SHEET #2

Initiating Cue:

Given the same initial conditions provided in Cue Sheet # 1, you have completed a detennination of whether or not adequate makeup water inventory exists to perfonn a cooldown.

The Shift Manager now requests you detennine how long hot standby can be maintained with the current makeup water inventory.


EXAMINEE'S CUE SHEET #1

Initial Conditions:

1. Unit-I is in Mode 6 preparing to enter Mode 5

2. SMECO is unavailable due to maintenance.

3. 11 CST is empty for maintenance

4. Unit-2 is operating at 100% reactor power.

5. A loss of offsite power occurs at 0845.

6. The IA DG fails to start

7. 14 4kv Bus is deenergized due to a ground fault.

8. The OC DG is unavailable

9. The plant has been stabilized per EOP-7 with the following parameters:

a. Unit-l RCS Temperature is 110 0 F and slowly rising.

b. Unit-2 RCS temperature is 532 0 F and steady.

c. 12 CST level is 24.5 feet

d. 21 CST level is 30 feet


Initiating Cue:

At 1045, the Unit-2 CRS requests you to determine if adequate inventory exists to perform a cool down per EOP-7, Step IV.AC.l.

:

APPLICANT: ___

CALVERT CLIFFS

NUCLEAR POWER PLANT

2012 NRC

INITIAL LICENSED

OPERATOR EXAM

JPM #: SRO-ADMIN-3

I


Facility: Calvert Cliffs 1 & 2 Job Performanc€~ Measure No.: SRO-ADMIN-3

Task Title: Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation


KIA Reference: 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications (3.9, 4.6)

Method of testing:

Simulated Performance: D Actual Performance: ~ Classroom: C8J Simulator: 0 Plant: D



cues. When you complete the task successfully, the objective for this job performance measure

will be satisfied.

Initial Conditions:

1. Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.

2. CEAs are currently inserted to 108 inches on Group 5.

3. Channel "A" LRNI Lower Sub-Channel is out of service and Channel "D" LRNI Upper Sub-Channel is out of service. Applicable T.S. LCO 3.3.1 conditions have been entered.

4. The plant computer has "crashed" and is inoperable.

5. DAS has been determined to be operable.

6. Last good value for FrT 1.66.

7. OPS CALC is not available.


9. LRNI Sub-Channel readings are as follows:

Channel Upper Lower

A 70.7 0

B 68.0 69.7

C 69.4 67.5

D 0 68.7

Initiating Cue:

AOP-7H, LOSS OF PLANT COMPUTER, has been implemented and the Shift Manager has

directed you to perform Section IV.E, to monitor Tq.

Task Standard:

. Calculate and determine whether or not Tq is in spec. Evaluates administrative requirements to I determine if any additional action is necessary.

Appendix C Job Perfonnance MeasuH~ Fonn ES-C-l Worksheet






Required Materials:

1. AOP-7H, Loss of Plant Computer in Mode One or Two.

2. NEOP-30I, Operator Surveillance Procedure

3. T.S. 3.2.3 Total Integrated Radial Peaking Factor (FRT)

4. T.S. 3.2.4 Azimuthal Power Tilt (Tq)

1. Unit-I, Cycle 20, Core Operating Limits Report

General References:

1. AOP-7H, Loss of Plant Computer in Mode One or Two.

2. NEOP-30l, Operator Surveillance Procedure

3. Tech Specs

4. Unit-I, Cycle 20, Core Operating Limits Report

Time critical task:

No

Validation Time:

20 minutes

Simulator Setup:

None



I TIME START:

i CUE: The Shift Manager directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E.

(J Locates AOP-7H, Section IV.E. - IF Greater than Same as element.

50% Rated Thennal Power, Monitor Tq.

AOP-7H, Section IV.E. - IF Greater than 50% Rated Thermal Power, Monitor Tq.

(J IV.E.1. - IF ALL four Linear Power Channels are I operable, THEN perfonn EITHER of the following Detennines Step is NIA to calculate upper and lower Tq:

NOTE

For the purposes of Tq monitoring, a total of 3 upper and 3 lower RPS power range detectors are required to be operable. The failed detectors can be on different channels.

(J IV.E.2. - IF ONLY three upper AND three lower

RPS power range detectors are operable, THEN Detennines Step is applicable

perfonn the following:

(J IV.E.2.a. - IF greater than 75% Rated Thennal Power, THEN reduce power to less than or equal Detennines Step is NIA to 75% Rated Thennal Power within 12 hours.

(J IV.E.2.b. - Perfonn either of the following to

calculate upper and lower Tq:

i

(J Calculate Tq using Opscalc function Tq Calculator.

(J Record the readings on ATTACHMENT Detennines Step is NIA(2), Tq CALCULATION USING

EXCORE DETECTORS

OR

(J Calculate Tq using the method in Records Readings on Att (2) ATTACHMENT (2), Tg CALCULATION

Perfonns calculations per Att (2) USING EXCORE DETECTORS. • Calculates Upper Tq .03070*

(J Record the readings on ATTACHMENT • Calculates Lower Tq .02561 * (2), Tq CALCULATION USING EXCORE DETECTORS * with a Tolerance of± .0006



0 IV.E.3. - IF less than three upper OR three lower RPS power range detectors are operable, THEN

Determines Step is NIAreduce power to less than or equal to 50% Rated

Thermal Power within four hours, AND exit Step E.

0 IV.E.4. - Ensure that Tq is within limits of LCO Candidate proceeds to NEOP-301,

3.2.4, as directed by NEOP-301, OPERATOR Section 6.6

SURVEILLANCE PROCEDURE.

NEOP·301, Section 6.6 Azimuthal Power Tilt (T q) Monitoring (MODE 1, >50% Power)

0 6.6.1. - IF incore monitoring ofTq is available, Determines step is N/A

THEN:

0 6.6.2. - IF incore monitoring ofTq is not available, Determines step is applicable THEN

0 6.6.2.1. - IF the DAS is unavailable ... Determines step is NIA

0 6.6.2.2. - IF the plant computer is unavailable,

THEN PERFORM the actions of IF GREATER

Determines step is applicable and in THAN 50% RATED THERMAL POWER,

progressMONITOR Tq for LOSS OF PLANT

COMPUTER in AOP-07H.

0 6.6.2.3 - IF incore monitoring is unavailable for Determines step is NIA I

any other reason

0 6.6.2.4. - PROCEED to Step 6.6.3. Determines step is applicable

0 6.6.3. - ENSURE that Tq is within limits PER LCO Determines step is applicable

3.2.4

0 6.6.3.1. - IF Azimuthal Power Tilt (Tq) is less

than or equal to 0.03, then the surveillance is Determines step is NIA

complete and satisfactory.



Detennines T.S. 3.2.4 limits have been exceeded.

• Detennines Tq must be restored to within limits within 4 hours.

OR

[J 6.6.3.2. - IF Azimuthal Power Tilt (Tq) is greater • Verify F/ is within the limit of than 0.03 but less than or equal to 0.10 THEN: LCO 3.2.3, "Total Integrated

Radial Peaking Factor" within 4 hours.

Per COLR Figure 3.2.3, verifies CEAs withdrawn to or above the Long Term Steady State Insertion Limits of Figure 3.1.6 (Not critical)

Acknowledge notification, as Reactor Engineering and the as-Operations, that CUE:

indicated T Q is greater than 0.03 but less than or equal to 0.10.

[J 6.6.3.2.a. - NOTIFY Reactor Engineering

and the as-Operations that indicated T q is

Same as element greater than 0.03 but less than or equal to 0.10.

Shift Manager directs documenting the Total Integrated Radial Peaking Factor (FRT) is CUE: within the limits ofTS 3.2.3, using Att (5) while Reactor Engineering fonnulates a

recovery plan

[J 6.6.3.2.b. - PERFORM EITHER of the

following: Completes Att (5) supplying the [J DETERMINE AND CORRECT (if following data:

possible) TQ within four hours so that Tq • Tq - .03070 (not critical) is less than or equal to 0.03. • FRT limit -1.74 ± .01

OR • FRT measured - 1.66 (not critical) FRT within limits - yes [J DETERMINE AND DOCUMENT on • Max allowable pwr - 98% ± 1%Attachment 5 within four hours AND at •

least once per subsequent eight hours that • Reactor power - 70% (not critical)the Total Integrated Radial Peaking Factor

(FRT) is within the limits ofTS 3.2.3.



CUE: I Acknowledge request for an independent review of the information on Att. (5)

0 6.6.3.2.c. - INDEPENDENTLY REVIEW Requests independent review of the information on Attachment 5. completed Att (5)

0 6.6.3.2.d. - IF neither condition of 6.6.3.2.b

can be satisfied THEN REDUCE power to

Determines step is NIAless than or equal to 50% within the following

4 hours.

0 6.6.3.3. - IF Azimuthal Power Tilt (Tq) is greater Determines step is N/A

than 0.10 THEN:

AOP-7H, Section IV.E. - IF Greater than 50%. Rated Thermal Power, Monitor Tq.

I

0 IV.E.5. - Once every 12 hours, recalculate the Azimuthal power Tilt using the Excore Detectors Determines step is NIA at this time PER Step E, Page 10.

.

TERMINATING CUE: This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits with T.S. components appropriately addressed and the NEOP-30l Attachment (5) completed. No further actions arie required.

ITIME STOP: ___

Appendix C Job Perfoffi1ance Measure FOffi1 ES-C-l Worksheet


Job Perfoffi1ance Measure Number: SRO-ADMIN-3

Applicant:

NRC Examiner:

Date Perfoffi1ed:

Facility Evaluator:

Number of Attempts: __________________

Time to Complete:

Follow up Question: ____


Result: SAT ______ UNSAT _________

Examiner's Signature and Date: ______________________



Initial Conditions:

1. Unit-1 power was recently reduced to 70% power to facilitate repairs to 11 SGFP.

2. CEAs are currently inserted to 108 inches on Group 5.

3. Channel "A" LRNI Lower Sub-Channel is out of service and Channel "D" LRNI Upper Sub-Channel is out of service. Applicable T.S. LCO 3.3.1 conditions have been entered.

4. The plant computer has "crashed" and is inoperable.

5. DAS has been detennined to be operable.

6. Last good value for F/ = 1.66

7. OPS CALC is not available

8. You are perfonning the duties of an extra SRO.

9. NI Readings are as follows:

Channel Upper Lower I IA 70.7 0 i

B 68.0 69.7

C 69.4 67.5 I

D 0 68.7

Initiating Cue:

AOP-7H, LOSS OF PLANT COMPUTER, has been impleme:nted and the Shift Manager has directed you to perfonn Section IV.E, to monitor Tq.

APPLICANT: ___

CALVERT CLIFFS

NUCLEAR POWER PLANT

2012 NRC

INITIAL LICENSED

OPERATOR EXAM

JPM #: SRO-ADMIN-4

--...--------------------------------------- Appendix C Job Perfonnance Measure Fonn ES-C-I

Worksheet

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-4

Task Title: Respond to a contaminated injured person

Task Nnmber: 204.025, 204.098

2.3.14 - Knowledge of radiation or contamination hazards that may arise during KJA Reference:

normal, abnormal, or emergency conditions or activities. (3.4, 3.8)

Method of testing:

Simulated Performance: Actual Performance: I:8J

Classroom: I:8J Simulator: D Plant: D


I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When

you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-l is operating at 100% power.

2. The FASW calls the Control Room on 911, and informs you of the following:

• A Chemistry Technician received serious steam bums while performing RCS sampling activities at the RCS Sample Sink.

• The sampling system has been stabilized and no radioactive releases are in progress.

• The Chemistry Technician is located on the 45' of the Unit-l Aux Buildingjust outside the elevator doors

• The Chemistry Technician is radioactively contaminated and requires transport to Calvert Memorial Hospital.

• He can be reached at 495-4586

Initiating Cue:

Determine and write down on the paper provided the following information for the event described in the Initial Conditions:

1. All onsite and offsite notifications required by the Control Room during and after the event. Include

any time limitations associated with the notification(s), if applicable.

2. All announcements that must be made during and after the event, including termination of the event.

Include personnel that must be dispatched by the Control Room to ensure the Chemistry Technician

receives prompt first aid and appropriate medical attention. For announcements that must be made,

include all information required in the announcement.

Task Standard:

identifies all required on site and offsite notifications and associated time limits. I I

Appendix C Job Performance Measure Fonn ES-C-l Worksheet






Required Materials:

None

General References:

ERPIP 3.0, Attachment 15, Personnel Emergency

Time critical task:

No

Validation Time:

15 minutes

Simulator Setup:

None



TIME START: ___

EXAMINER NOTE

When the Candidate determines the need for any procedure, provide them with a copy. At your discretion you may have them describe how to obtain the current revision of the

procedure prior to handing them a copy.

I 0 Candidate performs the following:

0 Locates ERPIP 3.0, Attachment 15, Personnel i Same as element

Emergency

o 1. RECORD the following information:

No announcements, onsite o Caller's Name:

notifications or offsite notifications o Location of injured person:

requiredo Nature of injury:

o Phone number to call to reach the scene:

NOTE

If based on the report the injury is minor in nature (small cut with little bleeding, small contusion or minor sprain with person able to easily walk), then sounding the Emergency Alarm is

unwarranted.

o 2. IF initial assessment by the Control Room is that

sounding the Emergency Alarm is unwarranted, Determines step is NIA

THEN: ...

Announcements, onsite notifications or offsite notifications required and associated time limits are:

Announcement

"A personnel emergency exists on the 45' elevation of the Auxiliary Bldg outside the elevator doors." "First Aid Team and Radiation Protection Technician respond." (wording may be slightly different but must convey the same basic message)

Repeat twice (not critical)



No announcements, on site 4. CONFIRM and MONITOR response. notifications or offsite notifications

required

5. DETERMINE contamination and hospitalization Same as element

status.

o 5.a. IF the injured person is suspected to be contaminated, THEN HAVE an RPT determine AND report the person's contamination status. Contamination status provided by

o 5 .a.( 1) IF unknown whether the injured person . the F ASW in his initial report is contaminated or not, THEN TREAT as contaminated.

NOTE

First Aid Team Leader can directly communicate with offsite responding units on Radio Channel 1

Announcements, on site notifications or offsite notifications required and associated time limits are:

.Notification - Notify CAS/SAS to call for offsite assistance. Transport of a contaminated individual to CMH is required.


Notification - Notify CMH that one injured/contaminated person suffering steam burns will be transported to CMH

ETA not a critical task



o 6. CONTINUE to monitor the event and direct assistance to the scene as requested by the First Aid Team Leader.

o 7. WHEN notified by the First Aid Team Leader that the event may be tenninated, THEN ANNOUNCE a brief update on status of personnel emergency.

STANDARD


Notification - Notify RP supervision by activating ERONS.


!~otification - An 8-hour ENS Report is required to the NRC for "Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment."

No announcements, onsite notifications or offsite notifications

required


l\.nnouncement - Now secure from ]:>ersonnel Emergency, injured person is being transported to hospital (wording may be slightly different but must convey the same basic message)

Repeat twice (not critical)

TERMINATING CUE: The task is complete when the applicant has determined content for announcement notifying the Site that we are securing from the personnel emergency.

Appendix C Job Performance Measure Form ES-C-I Worksheet



Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: ______________.

Time to Complete:

Follow up Question: ___________________________

Applicant Response: __________________________

Result: SAT ______ UNSAT _______

Examiner's Signature and Date: ___________.



Initial Conditions:

3. Unit-I is operating at 100% power.

4. The FASW calls the Control Room on 911, and informs you of the following:

• A Chemistry Technician received serious steam bums while performing RCS sampling activities at the RCS Sample Sink.

• The sampling system has been stabilized and no radioactive releases are in progress.

• The Chemistry Technician is located on the 45' of the Unit-l Aux Building just outside the elevator doors

• The Chemistry Technician is radioactively contaminated and requires transport to Calvert Memorial HospitaL

• He can be reached at 495-4586

Initiating Cue:

Determine and write down on the paper provided the following information for the event described in the Initial Conditions:

1. All onsite and offsite notifications required by the Control Room during and after the event. Include any time limitations associated with the notification(s), if applicable.

2. All announcements that must be made during and after the event, including termination of the event. Include personnel that must be dispatched by the Control Room to ensure the Chemistry Technician receives prompt first aid and appropriate medical attention. For announcements that must be made, include all information required in the I


CANDIDATE NAME:

List all onsite and offsite notifications required by the Control Room during and after the event. Include any time limitations associated with the notification( s), if applicable.

Describe all announcements that must be made and personnel that must be dispatched by the Control Room to ensure the Chemistry Technician receives prompt first aid and appropriate medical attention. For announcements that must be made, include all information required in the announcement.

APPLICANT: ___

CALVERT CJLIFFS

NUCLEAR POWER PLANT

2012 NRC

INITIAL LICENSED

OPERATOR EXAM

JPM #: SRO-A])MIN-5


Facility: Calvert Cliffs 1 & 2 Job Performanc,e Measure No.: SRO-ADMIN-5

Task Title: Determine Appropriate Emergency Response Actions


KIA Reference: 2.4.41 (2.9,4.6)

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom: ~ Simulator: D Plant: D


I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-2 was at 100% power when an event occurred, causing a Reactor trip.

2. SIAS failed to automatically actuate and required manual actuation.

3. RCS subcooling is O°F.

4. Containment pressure was 30 PSIG and rising when it suddenly lowered to 1 PSIG.

5. Containment High Range Radiation Monitors are currently reading 4000 RlHr.

6. The Meteorological Data Screen (DRDT) indicates the following:

a. DIRlO 3090

b. DIR60 = 300°

7. You are performing the duties of the Shift Manager.

8. This JPM is TIME CRITICAL.

Initiating Cue:

You have been requested to determine appropriate Emergency Response Actions, per the ERPIP, based on the current plant conditions provided.

Task Standard:

Determines EAL classification, Protective Action Recommendations and completes the initial notification form within prescribed time limits.

i







Required Materials:

1. ERPIP 3.0, "Immediate Actions"

2. ERPIP 3.0 Attachment 1, "EMERGENCY ACTION LEVEL (EAL) CRITERIA"

3. ERPIP 3.0 Attachment 2, "EMERGENCY CLASSIFICATION"

4. A blank copy ofERPIP 3.0, Attachment 3, "INITIAL NOTIFICATION FORM"

5. ERPIP 3.0 Attachment 4, "GENERAL EMERGENCY ACTIONS"

6. ERPIP 3.0 Attachment 5, "GENERAL EMERGENCY PROTECTIVE ACTION

RECOMMENDATIONS"

General References:


Time critical task:

Yes

Validation Time:

12 minutes

Simulator Setup:

None

Appendix C Job Performance Measure Form ES-C-1 Worksheet


EVALUATOR NOTE:

The "EAL CLOCK" starts after candidate reads "Initial Conditions" CUE sheet.

TIME START:

EAL CLOCK TIME START:

0 Identify and locate ERPIP 3.0 Same as element

0 Refers to Immediate Actions, identifies the category Determines A TT ACHMENT 2 is

from the listing and goes to the appropriate applicable.

Attachment.

ATTACHMENT 2, EMERGENCY CLASSIFICATION

0 A. - CLASSIFY the Event

A.I. - WHEN an event is in progress potentially requiring emergency response, THEN Determines step is applicable. CONDUCT the following actions in parallel:

· CUE: I The Unit-2 CRS will perform step A.I.a

0 A.l.a. - DETERMINE if existing conditions

warrant implementation of one of emergency

response attachments:

• Personnel Emergency, Att 15 • Fire,Att 16,17,18 • Radiological Event, Att 19 • Severe Weather, Att 20,21 The Unit-2 CRS will evaluate • Hazardous Material Release, Att 22 existing conditions to determine if • Containment Evacuation, Att 23 implementation of any of the listed

attachments is necessary• Security, Att 24 • Large Area Loss, Att 25

Large Steam Leak, Att 26 • • Extensive Damage Mitigation Guidelines,

Att27

• S/G Level Monitoring During Extensive

Damage Mitigation, Att 28 i



o A.I.b. - EVALUATE the existing conditions against Attachment 1, Emergency Action Level (EAL) Criteria, to determine if an EAL threshold has been met.

STANDARD

Evaluates Attachment 1 and determines a GENERAL EMERGENCY classification is warranted, under EAL H.G.5.1.4, in the Fission Product Barrier Category, based on the loss of all 3

• fission product barriers.

Fuel Clad Barrier-Containment Radiation reading> 3500 remlhr

RCS Barrier- RCS subcooling <

25°F due to RCS leakage.

Containment Barrier-Rapid unexplained CNTMT pressure decrease following initial increase.

Inform candidate the Unit-2 CRS will implement emergency response attachments as CUE:

necessary

o B. - IMPLEMENT Emergency Response Actions o B.1. - IF existing conditions warrant

implementation of an emergency response attachment, in parallel, THEN GO TO that attachment AND begin response actions.

o B.2. - IF an EAL condition is met, THEN OBTAIN an Attachment 3, Initial Notification Form, AND GO TO the appropriate EAL Declaration attachment:

o General Emergency Actions, Att 4 o Site Area Emergency Actions, Att 9 o Alert Actions, Att 11 o Unusual Event Actions, Att 13

ERPIP 3.0, ATTACHMENT 4, General Emergency Actions

o A.I - COMPLETE Attachment 3, Initial Notification Form.

The Unit-2 CRS will implement emergency response attachments as necessary

Determines from previous evaluation that an EAL is satisfied and obtains an Initial Notification form. Identifies General Emergency as the appropriate declaration. Goes to Attachment 4, General Emergency Actions.

Refers to Attachment Initial iC:ltlon

Appendix C Job Performance Measure Fonn ES-C-I Worksheet


ERPIP 3.0, ATTACHMENT 3, Initial Notification Form

NOTE TO EVALUATOR

Page 2 ofA TT ACHMENT 3 contains instructions for completing the form and should be referred to as the applicant comple:tes page 1.

Checks "is" a drill

Checks "Unit-2"

Checks "General Emergency"

Enters "H.G.S.l.4"

Checks "Yes"

o Complete Item A.S.a Checks "No"

o Complete Item ASb Checks "Airborne"

NOTE TO EVALUATOR

Attachment 5, GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS, should be used to determine the correct Protective Action Recommendations

Checks box for "A.6.e", "Evacuate PAZ 1 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 3 to take KI,

;C~:§~~lij'!'i'Y;;"1 shelter remainder of the 1 0 mile EPZ."

When a Peer Check of the EAL call is requested, acknowledge the request.

o Requests a Peer Check upon completion of items A.I. Same as element

thru A.6.

NOTE TO EVALUATOR

EAL Clock should be stopped when candidate completes item A.7 (date and time of EAL Declaration)



Completes A.7 only after items 1 6 are completed, and a Peer check has been obtained.

::s 15 minutes

Selects blocks for:

o Drill o General Emergency

o B. - Complete Section B, Personnel Notification o StaffNornlal Emergency Determination. Response Facilities (May staff

alternate ERF s based on radiological hazard)

o Prints name and signs (only after Section A is completed)

ERPIP 3.0, ATTACHMENT 4, General Emergency Actions

Acknowledge request(s) to recall the Emergency Response Organization according to CUE: Step B.l of this attachment and to transmit the Initial Notification Form to the offsite

agencies according to Step C.I of this attachment.

Same as element

(within 15 minutes ofEAL Clock

Time Stop)

Same as element

(within 15 minutes ofEAL Clock

Time Stop)

TERMINATING CUE: This JPM is complete when an EAL classification is determined based on given plant conditions, the initial notification form is completed and the CR Communicator has been requested to recall the ERO and to notify offsite agencies. No further actions are required. The evaluator is expected to end the JPM.

TIME STOP: ___


Verification of Completilon


Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Follow up Question:

Applicant Response:

Result: D SAT D UNSAT

Examiner's Signature and Date:


APPLICANT'S CUE SHEET

Initial Conditions:

1. Unit-2 was at 100% power when an event occurred, causing a Reactor trip.

2. SIAS failed to automatically actuate and required manual actuation.

3. RCS subcooling is O°F.

4. Containment pressure was 30 PSIG and rising when it suddenly lowered to 1 PSIG.

5. Containment High Range Radiation Monitors are: currently reading 4000 RlHr.

6. The Meteorological Data Screen (DRDT) indicates the following:

a. DIRIO = 309°

b. DIR60 = 300°

7. You are performing the duties of the Shift Manager.

8. This JPM is TIME CRITICAL.

Initiating Cue:

You have been requested to determine appropriate Emergency Response Actions per the ERPIP based on the current plant conditions provided.

..

APPLICANT: ___

CALVERT CJLIFFS

NUCLEAR POWI~R PLANT

2012 NRC

INITIAL LICENSED

OPERATOR I~XAM

JPM #: RO-ADMIN-1


Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-1

Task Title: Respond to a complete loss of SDC (Estimate Time to Boiling & Core Uncovery)


KIA Reference: 2.1.20 (4.6, 4.6)

Method of testing:

Simulated Performance: 0 Actual Performance: ~ Classroom: ~ Simulator: 0 Plant: 0


I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective: for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-l RCS is drained to 38.6 feet in preparation for Vacuum Fill of the RCS.

2. RCS temperature is 100° F.

3. The reactor was shut down 25 days ago after an extended period of full power operation.

4. Refueling operations have been completed. 88 fresh fuel assemblies were loaded in the core.

5. A loss of shutdown cooling has occurred.

6. You are performing the duties of an extra CRO.

Initiating Cue:

The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, Step IV.B.S.

Task Standard:

Determines Time to Boil and Time to Core Uncovery.







Required Materials:

AOP-3B, Abnormal Shutdown Cooling Conditions

General References:

AOP-3B, Abnormal Shutdown Cooling Conditions

Time critical task:

No

Validation Time:

20 minutes

Simulator Setup:

None



Locates AOP-3B, Step IV.B.5 Same as element

o IV.B.S. - IF the RCS in NOT capable of being pressurized, THEN estimate the time to boiling AND core uncovery using A TTACHMENT(ll), Same as element CALCULATION OF TIME TO BOIL OR CORE UNCOVERY.

o Locates AOP-3B, Attachment (11) Same as element

Note to evaluator:

Completion of this JPM requires interpreting graphs lthat have the potential to induce minor variations in calculated results. For that reason, calculated results are given an

"acceptable" band.

o 1. - Calculate Time To Boil

Determines Attachment (8), Time o l.a. - Determine the Time To Boil at 24 hours after to Start Boiling (TTB) After

shutdown from the appropriate figure, based on LOSDC 24 Hours After Shutdown, RCS level and RCS temperature: is the correct Attachment for stated

• conditions

U sing Attachment (8), determines TTB @ 24 hrs is approximately 13.5 minutes

Using A TT (10), determines multiplier of3.39

Determines post refueling multiplier is applicable. Uses ATT (10), to determine the Post Refueling multiplier is 1.36

PerfOlIDs TTB calculation

13.5 X 3.39 X 1.36 62.2 mins

(Answers in the range of 58 to 63.5 minutes are acceptable)

-----



CUE: Acknowledge request for independent verification of the TTB calculation

o I.d. - Independently verify the calculation. . Requests independent verification

o 2. - Calculate Time To Core Uncovery:

Determines Attachment(12), Time to Core Uncovery After LOSDC 24 o 2.a. - Determine the Time To Core Uncovery at 24 Hours After Shutdown No Nozzle

hours after shutdown from the appropriate figure, Dams, No Injection, No Cold Leg

based on RCS level and RCS temperature: Hole, is the correct Attaclunent for stated conditions

Using Att (12), determines Time To Core Uncovery @ 24 hrs is approximately 129 minutes (127 133 mins)

Using ATTACHMENT (10), determines multiplier of 3.39

Determines post refueling multiplier is applicable. Uses Att (10), to determine the Post Refueling multiplier is 1.36

Performs Time To Core Uncovery calculation

129 X 3.39 X 1.36 = 595 mins or

9 Hours 55 Minutes

(Answers in the range of 585 Mins

to 613 Mins are acceptable)

Acknowledge request for independent veritication of the TTB calculation

o 2.d. - Independently verify the calculation. Requests independent verification

ITERMINATING CUE: This JPM is complete when the ~OP-3B, Att (11), Calculation of Time i iLto Boil or Core Uncovery, worksheet has been completed. No further actions are required. ..____________________________________________________________________~

STOP:

---------

-------------------------



Job Performance Measure Number: RO-ADMIN-l

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: ______________

Time to Complete:

Follow up Question: _______________.


Result: SAT ______ UNSAT

Examiner's Signature and Date:



Initial Conditions:

1. Unit-l RCS is drained to 38.6 feet in preparation for Vacuum Fill of the RCS.

2. RCS temperature is 100° F.

3. The reactor was shut down 2S days ago after an extended period of full power operation.

4. Refueling operations have been completed. 88 fresh fuel assemblies were loaded in the core.

5. A loss of shutdown cooling has occurred.

6. You are performing the duties ofan extra CRO.

Initiating Cue:

The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, I Step IV.B.S.

APPLICANT: ___

CALVERT C~LIFFS

NUCLEAR POWI~R PLANT

2012 NRIC

INITIAL LICE~NSED

OPERA TOR I~XAM

JPM #: RO-AI)MIN-2



Task Title: Calculate BAST volume required to raise RWT to refueling boron concentration

Task Number: 041.011 - Borate the RWT

KIA Reference: 2.1.25 (3.9,4.2)

Method of testing:

Simulated Performance: D Actual Performance: [ZJ Classroom: [ZJ Simulator: D Plant:



Initial Conditions:

1. Unit-2 RWT parameters are:

a. Boron Concentration = 2550 PPM

b. Temperature = 80· F

c. Level = 460 inches

2. 21 & 22 BAST Boron Concentrations are 7.25 %

3. CEAs will NOT be credited

4. You are performing the duties of the Unit-2 RO

Initiating Cue:

In preparation for the upcoming Unit-2 Refueling Outage, the CRS directs you to calculate BAST volume required to raise the RWT boron concentration to 25 PPM above the Refueling Boron Concentration per OI-2B, Step 6.7







Required Materials:

1. OI-2B, CVCS Boration, Dilution and Makeup Operations

2. NEOP-23, Technical Data Book (Unit 2)

3. U-2 Technical Specifications Core Operating Limits Report

4. Calculator

General References:

Procedures and manuals normally available in the control room

Time critical task:

No

Validation Time:

15 minutes

Simulator Setup:

None



TIME START: ___

o Locates NEOP-23, Figure 2-11-A-6 or Unit-2 Core Operating Limits Report for Cycle 19 (3.9.1)

6.7.B.2. - DETERNIINE the volume (gallons) of boric acid needed to achieve the desired Refueling Water Tank boron concentration by using one of the following:

CUE: The Ops Calc Program is ,not available

OOps Cales Program - R WT Boration under the BORIC ACID MENU

o The following formula: (842.15) (LlB) (L+ 18)

STANDARD

Same as element

Determines required Refueling Boron Concentration is ~ 2634

PPM for the

Same as element

Same as element.

Calculation ([2634 + 25] - 2550)

should yield a LlB of 109 PPM

Determines manual calculation must be performed

Determines following values for input to manual calculation:

• LlB = 109 PPM • L = 460 inches

• CB 12676 PPM

• I 2550 PPM • VRWT = 0.01607

(from Table 1)

• V I40 0.01629 ft3/lb

Determines volume of Boric Acid required is: 4456 ± 1 (4455 to 4457

I



CUE: I Acknowledge request for independent verification of the calculation

o 6.7 .B.3. - INDEPENDENTLY VERIFY the proper Requests an independent volume of boric acid for the desired R WT boron verification of the calculation be concentration. [80270] performed

TERMINATING CUE: This JPM is complete when the proper volume of boric acid to raise the RWT boron concentration to the desired value has been determined. No further actions are required.

ISTUl": ___



Job Perfonnance Measure Number: RO-ADMIN-2

Applicant:

NRC Examiner:

Date Perfonned:

Facility Evaluator:

Number of Attempts: _____________.

Time to Complete:

Follow up Question: _-'--___________.

Applicant Response: _____________


Examiner's Signature and Date: __________.__________

,



Initial Conditions:

5. Unit-2 RWT parameters are:

a. Boron Concentration 2550 PPM

b. Temperature = 80° F

c. Level 460 inches

6. 21 & 22 BAST Boron Concentrations are 7.25 %

7. CEAs will NOT be credited

8. You are performing the duties of the Unit-2 RO

Initiating Cue:

In preparation for the upcoming Unit-2 Refueling Outage, the CRS directs you to calculate BAST volume required to raise the R WT boron concentration to 25 PPM above the Refueling

i Boron Concentration per OI-2B, Step 6.7

APPLICANT: ___

CALVERT CLIFFS

NUCLEAR POWE~R PLANT

2012 NRC

INITIAL LICENSED

OPERATOR EXAM

JPM #: RO-ADMIN-3



Determine protective clothing requirements and dose limits associated with Task Title:

performance of a task in the RCA


KIA Reference: 2.3.7 - Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5, 3.6)

Method of testing:

Simulated Performance: Actual Performance: IZl

Classroom: [gJ Simulator: D Plant:



Initial Conditions:

1. Both Units are at 100% power.

2. Spent Fuel Pool Cooling is being aligned to provide cooling using 12 SFP Clg Pp - 12 SFP Cooler - Suction from 21 SFP and discharging to 11 SFP.

Initiating Cue:

You have been directed to throttle 12 SFP PP Disch, O-SFP-l 07, two turns open and then stand by to slowly open 12 SFP PP Disch, 0-SFP-107.

State the radiological requirements for entering this area. Include in your discussion:

1. Expected radiological protective clothing for valve operation

2. Highest radiation level in the work area

3. Expected dose for this assignment (assuming a ten minute job duration)

4. Dose rate alarm

5. Low dose waiting area

Task Standard:

Determine radiological conditions for personnel exposure:

Appendix C Job Perfonnance Measure Fonn ES-C-1 Worksheet






Required Materials:

1. Survey Map for the affected area 2. RWP-2, "Operations Activities, including Fuel Shuffle, in Non-High Radiation Areas

(Low Risk)"

General References:

RP-1-100, Radiation Protection

Time critical task:

No

Validation Time:

10 minutes

Simulator Setup:

None



TIME START: ___

Once candidate detennines the need for a survey map and an SWP, provide them with CUE:

the Survey Map and a copy of R WP 2

o Candidate perfonns the following:

Detennines RWP 2, Task 2 o Locates and reviews Survey Map and RWP. requirements are applicable

Candidate states partial anti-Cs (gloves and booties) or full anti-Cs.

Detennines that highest radiation level in the area is 60 mRlhr at the north end of 12 SFP Clg Pp

Detennines that expected dose in 10 minutes is 116 * 25mRlhr = 4.2 ± 0.1 mR

Detennines from R WP that dose rate alarm will be set at 80 mRlhr.

Identifies from R WP room low dose waiting area is by the room door, or identifies lowest general area is by the door (.4 mRlhr), or states would wait outside of the room in the hallway.

TERMINATING CUE: The task is complete when the applicant has provided requested radiological infonnation.

------- ------



Job Performance Measure Number: RO-ADMIN-3

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: ____________

Time to Complete:

Follow up Question: _______________________"__

Applicant Response: _____________

Result: SAT UNSAT

Examiner's Signature and Date: _________.

i



Initial Conditions:

1. Both Units are at 100% power.

2. Spent Fuel Pool Cooling is being aligned to provide cooling using 12 SFP Clg Pp 12 SFP Cooler- Suction from 21 SFP and discharging to 11 SFP.

Initiating Cue:

You have been directed to throttle 12 SFP PP Disch, 0-SFP-107, two turns open and then stand

by to slowly open 12 SFP PP Disch, 0-SFP-I07.

State the radiological requirements for entering this area. Include in your discussion:

1. Expected radiological protective clothing for valve operation

2. Highest radiation level in the work area

3. Expected dose for this assignment (assuming a ten minute job duration)

4. Dose rate alarm

5. Low dose waiting area .

APPLICANT: ___

CALVERT CLIFFS

NUCLEAR POWER PLANT

2012 NR~C

INITIAL LICENSED

OPERATOR EXAM

JPM #: RO-ADMIN-4


Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: RO-ADMIN-4

Perform an Independent Assessment of an Event Using the EOP-O DiagnosticTask Title:

Flowchart and Recommend the Correct Recovery Procedure

Task Number: 204.l24

KIA Reference: 2.4.21 (4.0,4.6)

Method of testing:

Simulated Perfoffilance: D Actual Performance: IS] Classroom: D Simulator: IS] Plant:


I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectiv(;~ for this job performance measure will be satisfied.

Initial Conditions:

1. A Reactor Trip and Safety Injection has occurred on Unit-I.

2. EOP-O is in progress.

3. You are the extra CRO performing the duties of the interim STA.

Initiating Cue:

The Shift Manager directs you to perform the Safety Function Status Check(s) and determine the proper course of action using EOP-O, Post Trip Immediate Actions, Sections V and VI.

Task Standard:

Use plant parameters & the EOP-O Diagnostic Flowchart to Select the Appropriate Recovery Procedure.

L _____________________________________________________________________~





3. All time-critical steps completed within allotted tllme..


Required Materials:

EOP-O, Post Trip Immediate Actions

General References:

EOP-O, Post Trip Immediate Actions

Time critical task:

No

Validation Time:

10 minutes

Simulator Setup:

1. Reset to IC-24, Both Units at 100% power.

Insert Malfunctions, Remotes, Overrides:

a. ms003_0l, MS-MS-4043 (11 MSIV) at 90% open at time zero.

__ b. msOll_Ol, 11 SG Steam Line Rupture outside CNTMT with a value of75% at time zero.

__ 3. Place Simulator in RUN and complete the following:

a. When reactor trips, perfonn immediate and alternate actions ofEOP-O (as required) for HR and PIC safety functions.

4. Place Simulator in FREEZE.

__ 5. Acknowledge all panel and plant computer alanns.

6. Select "Hom ON" for annunciators and "Clock" for time.



TIME START: ___

• 0 Locate EOP-O Diagnostic Flowchart.


o Reactivity Control Safety Function.

o Vital Auxiliaries Safety Function.

o Containment Environment Safety Function.

o Radiation Levels External to Containment Safety Function.

STANDARD

Same as element

Completes SFSC for RC. Determines RC Safety Function met.

Completes SFSC for V A. Detennines VA Safety Function met.

Completes SFSC for PIC. Detennines PIC Safety Function not met due to low Pressurizer pressure and Pressurizer level.

Completes SFSC for HR. Detennines HR Safety Function not met due to low T COLD.

Completes SFSC for CEo Detennines CE Safety Function is met.

Completes SFSC for RLEC. Detennines RLEC Safety Function met.

CUE: Acknowledges report out on status of Safety Functions

o results of SFSC to CRS

Reports RCS Pressure and Inventory Control Safety Function is not met due to low Pressurizer pressure and level, and Heat Removal Safety Function is not met due to low



CUE: I Post-trip immediate actions have been completed

V. DIAGNOSTIC FLOWCHART

0 REACTIVITY SAFETY FUNCTION MET?

i

I

0

0

VITAL AUXILIARIES SAFETY FUNCTION MET?

RCS PRESS/INV SAFETY FUNCTION MET?

I 0 EITHER S/G PRESSURE LESS THAN 800 PSIA?

0 RCS SUB COOLING LESS THAN 30° F?

I

I

0 CORE/RCS HEAT REMOVAL SAFETY FUNCTION MET?

o AT LEAST ONE S/G HAS FEED FLOW?

I

I

0 ANY RCPs TRIPPED DUE TO TRIP STRATEGY?

0 S/G B/D OR COND OFF-GAS RMS ALARMS OR RISE?

STANDARD

Selects "YES" flowpath. Proceeds

to "VITAL AUXILIARIES

SAFETY FUNCTION MET?"


to "RCS PRESSIINV SAFETY

FUNCTION MET?"

Selects "NO" flowpath. Proceeds to

"EITHER S/G PRESSURE LESS

THAN 800 PSIA?"


to "RCS SUBCOOLING LESS

THAN 30° F?"

Selects "NO" flowpath. Consider

EOP-4 (ESDE). Proceeds to

"CORE/RCS HEAT REMOV AL


Selects "NO" flowpath. Proceeds

to "AT LEAST ONE S/G HAS

FEED FLOW?"

Selects "YES". Proceeds to "ANY

RCPs TRIPPED DUE TO TRIP

STRATEGY?"

Selects "YES". Proceeds to "S/G

B/D OR COND OFF-GAS RMS

ALARMS OR RISE?"

Selects "NO" flowpath. Proceeds

to "RCS SUB COOLING LESS

THAN 30° F"?



ORCS SUB COOLING LESS THAN

30° F?

o CONTAINMENT ENVIRONMENT SAFETY FUNCTION MET?

o RADIATION LEVELS EXTERNAL TO CONTAINMENT SAFETY FUNCTION MET?

o ALL SAFETY FUNCTIONS MET?

o SINGLE EVENT DIAGNOSIS POSSIBLE?

STANDARD

Selects "NO" tlowpath. Consider

EOP-4 (ESDE). Proceeds to

"CONTAINMENT

ENVIRONMENT SAFETY

FUNCTION MET?"

Selects "YES" tlowpath. Proceeds

to "RADIATION LEVELS

EXTERNAL TO CONTAINMENT



to "ALL SAFETY FUNCTIONS

MET?"

Selects "NO" tlowpath. Proceeds to

"SINGLE EVENT DIAGNOSIS

POSSIBLE?"

Selects "YES" tlowpath". Proceeds

to "IMPLEMENT THE

APPROPRIATE EOP".

Recommends implementation of

EOP-4, EXCESS STEAM

DEMAND EVENT.

TERMINATING CUE: This JPM is complete when EOP-4, Excess Steam Demand Event, is recommended. No further actions are required.



Job Performance Measure Number: RO-ADMIN-4

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _________________

Time to Complete:

Follow up Question: ____________

Applicant Response: ____________


Examiner's Signature and Date: ----------~------------



Initial Conditions:

1. A Reactor Trip and Safety Injection have occurred on Unit-I.

2. EOP-O is in progress.

3. You are the extra CRO performing the duties of the interim STA.

Initiating Cue:

The Shift Manager directs you to perform the Safety Function Status Check(s) and determine the proper course of action using EOP-O, Post Trip Immediate Actions, Sections V and VI.

APPLICANT: ___

CALVERT CLIFFS

NUCLEAR POWER PLANT

2012 NRC

INITIAL LICE,NSED

OPERATOR EXAM

JPM #: SIM-1


Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-l

Task Title: Respond to a loss of Shutdown Cooling V\ith the RCS open (Alt Path)


KIA Reference: 025AA207 (3.4, 3.7)

Method of testing:

Simulated Performance: D Actual Perforrnance: [gJ Classroom: D Simulator: [gJ Plant: D



cues. When you complete the task successfully, the objective for this job perfonnance measure

will be satisfied.

Initial Conditions:

1. Unit-l is in Mode 5 for maintenance with the PZR manway removed.

2. The RCS is being maintained at approximately 42.7 feet.

3. SDC is aligned for service and RCS temperature is 1000 F.

4. The Reactor has been shut down for 10 days.

5. Time-To-Boil is approximately 38 minutes

6. The "12 LPSI PP SUCT PRESS LO" annunciator is in alann.

7. You are perfonning the duties of the Unit 1 CRO.

Initiating Cue:

The CRS has directed you to respond to these conditions using the appropriate procedure(s).

Task Standard:

I Restore Shutdown Cooling in accordance with AOP-3B, Abnormal Shutdown Cooling

- - --------.. Appendix C Job Performance Measure Form ES-C-l

Worksheet






Required Materials:

1. AOP-3B, Abnormal Shutdown Cooling Conditions

2. lC09-ALM, ESFAS 12 Alarm Manual

General References:

1. Procedures and manuals normally available in the Control Room

Time critical task:

No

Validation Time:

25 minutes

Simulator Setup:

1. Reset the simulator IC-3 (Shutdown, RX Vessel level- 42.7 feet)

__ 2. Refueling cart available, connected for service, and SDC flow alarm setpoints set at 2900 (low flow) and 3100 GPM (high flow).

3. Ensure 12 LPSI pump is running and 11 LPSI is in PTL

4. Place the following keys in their respective keyswitches:

__ a. SDC Return Header MOV keys, 29 & 30

__ b. LPSI Pp RAS Override keys, 38 & 39

__ c. MPT Protection keys 47 & 48

5. Set up conditions for LPSI cavitation indications

a. Place the simulator in "Run"

b. Use the keyswitch for 1-SI-651-MOV to position it to 20% open

c. Run Simulator until "LPSI PUMP SUCTION PRESS LO" alarm is received.

6. Place the Simulator in FREEZE

__ 7. Bring candidate into the simulator, brief the initial conditions.

8. Place the Simulator in RUN when the candidate is ready.



Applicant should observe fluctuations in motor amps, discharge pressure and pump CUE: discharge flow. When applicant notes off-normal indications, inform applicant, as the

ABO, that excessive noise is corning from the area of 12 LPSI pump.

a Locates 1 C09-ALM. Same as element

a Investigates cause of alarm using guidance provided by lC09-ALM for Window H-28 "12 LPSI SUCT PRESS LO". Recommends

Same as element

implementing AOP-3B.

CUE: Once the RO has recommended AOP-3B be implemented, direct him, as the SRO, to implement section IV.A.4 of AOP-3B

EXAMINER's NOTE

Once applicant has located the correct section of the AOP, then give them a working copy of the

procedure section.

o Locates AOP-3B, Section IV.A.4 Same as element

a IV.A:4:2!:IF'a LPSI~PPis determined to be cavitating/gas bOmld by considering the following:

a FluctUations in!motor amps ;dFluc~uations i~ di~charge pressure Determines step is applicable.

Monitors 12 LPSI pump indications D-FIK~~tions in pump discharge flow

Determines that indications are a Excessfve 'PiurlP noise consistent with cavitation [j '~LPSFPUMP SUCTION PRESS LO" alarm

aCtuation :f THEN complete the following actions:

a IV.A.4.a. - IF the RCS is in reduced inventory, Determines step is Not Applicable

THEN perform the following actions:

CUE: Report RCS level is 42.7' and steady

o IV.A.4.a.(1) -IF ReS level is less than 37.6 feet, OR 1L£4138 is being used, THEN verify flow is less than or equal to 1800 gpm.



0 IV.A.4.a.(2) - IF RCS level is greater than 37.6 feet, THEN verify t10w is less than or equal to 3000 gpm.

0 IV.A.4.a.(3) - IF the appropriate SDC Flow is Restored AND LPSI PP cavitation/gas binding stops, THEN IMPLEMENT the appropriate Operating Procedure.

~" :.'i~~~' O· IV.A{'t.b. - Stop the operating LPSI PP(s)

0 IV.A.4.c. - Place BOTH LPSI PP handswitches in PULL TO LOCK

CAUTION

STANDARD

elem

Determines step is Not Applicable

element I

Same as element I

Isolation of the LPSI PP suction flow path can cause pump damage if the LPSI PPs are allowed to operate.

0 IV.A.S. - Check that the SDC HDR RETURN ISOL valves are open

0 1-S1-651-MOV

0 1-S1-652-MOV

0 IV.A.S.I. - IF ANY of the SDC HDRRETURN ISOL valves are open: valves are NOT fully open, THEN complete the following:

0 IV.A.S.I.a. - Stop the operating LPSI PP(s).

0 IV.A.S.1.b. - Place BOTH LPSI PP handswitches in PULL TO LOCK.

0 IV.A.S.l.c. - Initiate Aux Spray as necessary PER Step C.S.b.1, to maintain RCS

pressure less than 260 PSIA.

Determines that 1-S1-651-MOV is

NOT fully open

Same as element




I



When the candidate attempts to open I-SI-651 from the control room, it opens.

CUE:

When requested, ABO reports that I-SI -651-MOV is opening.

i 0 I . O5.I.d. -Attempt to open the affected

·S HOR RETURN ISOL valve(s) from the

/(;ontr01 Room:

Same as element r::J Fsl=651-Mbv

'.' r::J -652-MOV

r::J IV.AS.l.e. - IF BOTH SDC HDR RETURN

ISOL valves are open, THEN attempt to

Observes that both valves are open restore SDC PER ATTACHMENT (3),

and refers to attachment 3 RETURNING SHUTDOWN COOLING TO

SERVICE.

r::J Locates AOP-3B, Attachment (3) Same as element ~~_ ....---____ __________L_____

EXAMINER's NOTE:

When the applicant has located Atl. (3), then give him a working copy ofAtt. (3)

~.. --------------------.-.-----------------~

r::J 1. - Ensure RCS pressure is less than 260 PSIA Same as element

r::J 2. - Ensure RCS temperature is less than 300°F. Same as element

! r::J 3. - Ensure the SDC HDR RETURN ISOL valves are open:

Same as element r::J I-SI-651-MOV

r::J 1-SI-652-MOV

CUE: When asked: I-SI-444 and I-SI

CALVERT C~LIFFS NUCLEAR POWER PLANT 2012 …NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERA TOR...

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Transcript of CALVERT C~LIFFS NUCLEAR POWER PLANT 2012 …NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERA TOR...