ML12278A404
| ML12278A404 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/12/2012 |
| From: | Moore R Constellation Energy Nuclear Group |
| To: | D'Antonio J Operations Branch I |
| Jackson D | |
| Shared Package | |
| ML12067A049 | List: |
| References | |
| TAC U01849 | |
| Download: ML12278A404 (244) | |
Text
APPLICANT: _ __
CALVERT C~LIFFS NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR ]~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
- 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
Appendix C Job Performance Measure Form ES-C-l Worksheet 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
- 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.
Appendix C Job Performance Measure Form ES-C-l Worksheet 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:
VA-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 ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 - VA-3 o 2 nd priority - PIC-4 o 3 rd priority - HR-2 o 4th priority - RLEC-2 o 5 th priority - RC-l o 6 th 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: _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet 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: _______________________
Appendix C Job Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. Both Units were operating at 100% power
- 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 STA 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/STATUS CRITERIA
- a. WRNI lowering 5 X 10-3
- b. SUR negative
(-)1/3 dpm Unable to NO more than ONE determine due to
- d. Boration status progress
EOP-O Rev 12/Unit 1 Page 25 of 27 VI. SAFETY FUNCTION STATUS CHECK SAFETY FUNCTION ACCEPTANCE CRITERIA VITAL AUXILIARIES ACCEPTANCE PARAMETERS VALUE/STATUS CRITERIA
- d. lY09 or lYlO At least ONE energized 1Y09 energized RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY ACCEPTANCE VALUE/STATUS PARAMETERS CRITERIA
- a. Pressurizer 1850 PSIA to 1270 PSIA and Pressure 2300 PSIA slowly lowering
- b. Pressurizer 80 inches to empty level 180 inches
- c. RCS 21°F and slowly Greater than 30°F subcooling nsmg
EOP-O Rev 12/U nit 1 Page 26 of 27 VI. SAFETY FUNCTION STATUS CHECK COREANDRCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL ACCEPTANCE VALUE/STATUS PARAMETERS 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 ACCEPTANCE PARAMETERS VALUE/STATUS CRITERIA
- b. Containment Temperature less than 120°F 100°F & steady
- c. Containment Alarm clear with NO Radiation unexplained rise Monitors
EOP-O Rev 12/Unit 1 Page 27 of 27 VI. SAFETY FUNCTION STATUS CHECK RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO ACCEPTANCE CONTAINMENT VALUE/STATUS CRITERIA PARAMETERS
- e. Noble Gas alarm clear with Monitor NO unexplained rise (1-RIC-5415)
- f. Condenser alarm clear with Off-Gas RMS In alarm prior to NO unexplained rise (1-RI-1752) loss of power S/G BID alarm clear with RMS In alarm prior to NO unexplained rise (l-RI-4014) loss of power
- h. Main Vent alarm clear with Gaseous RMS NO unexplained rise (l-RI-5415)
EOP-6 Rev 17/Unit 1 Page 102 of 108 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 funchon status check.
SAFETY FUNCTION ACCEPTANCE CRITERIA REACTIVITY CONTROL INTERMEDIATE FINAL PARAMETERS CRITERIA CRITERIA CHECK CHECK
..J less
- a. WRNI lowering than 10.4%
..J negative
- b. 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 VI. SAFETY FUNCTION STATUS CHECK SAFETY FUNCTION ACCEPTANCE CRITERIA VITAL AUXILIARIES INTERMEDIATE FINAL PARAMETERS CRITERIA CRITERIA CHECK CHECK
- a. 4KV Vital buses At least ONE At least ONE 11 or 14 energized energized
- b. 125V DC ALL greater than buses 11, 12, 105 volts ALL greater 21 and 22 than 105 volts
- e. 120V AC buses 11, 12, at least 13,14 at least THREE THREE energized energized At least ONE
- d. 1Y09 or 1Y 10 At least ONE energized energized
EOP-6 Rev 17/Unit 1 Page 104 of 108 VI. SAFETY FUNCTION STATUS CHECK RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY INTERMEDIATE FINAL CRITERIA CRITERIA PARAMETERS CHECK CHECK Less than the less than the
- a. Pressurizer upper limits of upper limits of Pressure Att. (1) Att. (1)
- b. Pressurizer Greater than 30 101 inches to level inches 180 inches OR At least One Charging Pump operating and SIS injecting PER 101 inches to Atts. (10) and (11) 180 inches
Charging Pump
- greater than operating and SIS 2YF injecting PER Atts. (10) and (11)
- d. Reactor Vessel above the top core covered Level of the hot leg
EOP-6 Rev 17/Unit 1 Page 105 of 108 VI. SAFETY FUNCTION STATUS CHECK CORE AND SAFETY FUNCTION ACCEPTANCE CRITERIA RCSHEAT REMOVAL INTERMEDIATE FINAL CRITERIA CRITERIA PARAMETERS CHECK CHECK
- a. CET Temperatures less than 600°F l= less than 600°F
- c. Unaffected S/G level
(-)170 inches to
(+)30 inches l= (-)24 inches to
(+)30 inches trending to
(-)24 inches to
(+ )30 inches C N/A N/A
EOP-6 Rev 17/Unit 1 Page 106 of 108 VI. SAFETY FUNCTION STATUS CHECK CONTAINMENT SAFETY FUNCTION ACCEPTANCE CRITERIA ENVIRONMENT INTERMEDIATE FINAL PARAMETERS CRITERIA CRITERIA CHECK CHECK I
,j
- b. Containment N/A I constant or Temperature (1) less than 15WF lowering
- c. Containment Radiation Monitors (2)
NO unexplained nse j I NO unexplained rise alarm clear ,j alarm clear I I
+/-CL NO NO
- d. Containment unexplained unexplained Sump level rIse rise (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 VI. SAFETY FUNCTION STATUS CHECK RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO INTERMEDIATE FINAL CONTAINMENT CRITERIA CRITERIA 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
++/-J
- e. Affected S/G Less than 920 Less than 920 pressure PSIA PSIA (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
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-2 Task
Title:
Evaluate the need for plant cooldown.
Task Number: 201.005 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:
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 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 1A 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 < 300 F, the plant must b(~ maintained in hot standby, and the 0
plant can be maintained in hot standby for approximately 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br />. The evaluator is expected to end the lPM.
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:
- 1. EOP-7, Station Blackout (Unit-2)
- 2. EOP Attachments (Unit-2)
General
References:
Procedures and manuals normally available in the Control Room Time critical task:
No Validation Time:
25 minutes Simulator Setup:
None
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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)
D Auxiliary systems availability completion is required 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 0
COOL DOWN TO 300 F" to determine 614,531 gallons are required to cool the Unit down to 0
300 F two hours following the shutdown.
Candidate enters uses table "Inventory Required to Cool Down 0
to 300 F" and determines 88,490 gallons are required to cool the Unit D
- l.b. - TBV cooldown and time after shutdown 0
,, down to 300 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
Appendix C Job Performance Measure Form ES-C-l Worksheet 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 Determines step is NOT applicable require AFW operation.
o 2.d.(2) __ Mode 1, 2 or 3 and does require Determines step is NOT applicable AFW operation.
Determines step IS applicable based on stated conditions NOTE: Calculated negative values should be entered as zero.
o 2.e. - Determine the amount of makeup 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 applicable CST 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
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 can CUE:
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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of hot standby. If chart is interpolated, the value would be 76 +/- 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Acceptable answer is 72 - 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> 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 power o 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 Verification of Completion 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.
Appendix C Job Performance Measure Form ES-C-l Worksheet 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.
- 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:
0
- a. Unit-l RCS Temperature is 110 F and slowly rising.
0
- 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 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
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performanc~ Measure No.: SRO-ADMIN-3 Task
Title:
Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation Task Number: 204.129 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 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 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.
- 6. Last good value for FrT 1.66.
- 7. OPS CALC is not available.
- 8. You are performing the duties of an extra SRO.
- 9. LRNI Sub-Channel readings are as follows:
Channel Upper Lower I
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 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:
- 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
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(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 USING EXCORE DETECTORS. Perfonns calculations per Att (2)
(J Record the readings on ATTACHMENT
- Calculates Upper Tq .03070*
(2), Tq CALCULATION USING
- Calculates Lower Tq .02561
- EXCORE DETECTORS
- with a Tolerance of +/- .0006
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 0 IV.E.3. - IF less than three upper OR three lower RPS power range detectors are operable, THEN Determines Step is NIA reduce 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 (Tq) 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, progress MONITOR 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.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Detennines T.S. 3.2.4 limits have been exceeded.
- Detennines Tq must be restored to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
[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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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 is less than or equal to 0.03.
- Tq - .03070 (not critical)
- FRT limit -1.74 +/- .01 OR
- FRT measured - 1.66 (not critical)
[J DETERMINE AND DOCUMENT on
- FRT within limits - yes Attachment 5 within four hours AND at
- Max allowable pwr - 98% +/- 1%
least once per subsequent eight hours that
- Reactor power - 70% (not the Total Integrated Radial Peaking Factor critical)
(FRT) is within the limits ofTS 3.2.3.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 NIA less than or equal to 50% within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, recalculate the Azimuthal power Tilt using the Excore Detectors Determines step is NI A 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.
I TIME STOP: _ __
Appendix C Job Perfoffi1ance Measure FOffi1 ES-C-l Worksheet Verification of Completion Job Perfoffi1ance Measure Number: SRO-ADMIN-3 Applicant:
NRC Examiner:
Date Perfoffi1ed:
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 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.
- 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 A 70.7 0 I 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 KJ A
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 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 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 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:
None General
References:
ERPIP 3.0, Attachment 15, Personnel Emergency Time critical task:
No Validation Time:
15 minutes Simulator Setup:
None
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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:
i 0 Locates ERPIP 3.0, Attachment 15, Personnel Same as element Emergency o 1. RECORD the following information:
o Caller's Name: No announcements, onsite o Location of injured person: notifications or offsite notifications o Nature of injury: required 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)
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 FASW 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.
Announcements, onsite notifications or offsite notifications required and associated time limits are:
Notification - Notify CMH that one injured/contaminated person suffering steam burns will be transported to CMH ETA not a critical task
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Announcements, onsite notifications or offsite notifications required and associated time limits are:
Notification - Notify RP supervision by activating ERONS.
Announcements, on site notifications or offsite notifications required and associated time limits are:
!~ 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."
o 6. CONTINUE to monitor the event and direct No announcements, onsite assistance to the scene as requested by the First Aid notifications or offsite notifications Team Leader. required Announcements, on site notifications or offsite notifications required and associated time limits are:
l\.nnouncement - Now secure from o 7. WHEN notified by the First Aid Team Leader that
]:>ersonnel Emergency, injured the event may be tenninated, THEN ANNOUNCE a person is being transported to brief update on status of personnel emergency.
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 Verification of Completion Job Performance Measure Number: SRO-ADMIN-4 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 Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET 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
Appendix C Job Performance Measure Form ES-C-l Worksheet 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
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performanc,e Measure No.: SRO-ADMIN-5 Task
Title:
Determine Appropriate Emergency Response Actions Task Number: 204.097 KIA
Reference:
2.4.41 (2.9,4.6)
Method of testing:
Simulated Performance: D Actual Performance: ~
Classroom: ~ Simulator: D 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 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.
- 5. Containment High Range Radiation Monitors are currently reading 4000 RlHr.
- 6. The Meteorological Data Screen (DRDT) indicates the following:
- a. DIRlO 309 0
- 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
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:
- 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:
Procedures and manuals normally available in the Control Room Time critical task:
Yes Validation Time:
12 minutes Simulator Setup:
None
Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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
Appendix C Job Performance Measure Form ES-C-I Worksheet ELEMENT (shaded + * = CRITICAL STEP) 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 o A.I.b. - EVALUATE the existing conditions
- fission product barriers.
against Attachment 1, Emergency Action Level (EAL) Criteria, to determine if an EAL Fuel Clad Barrier-Containment threshold has been met. 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 The Unit-2 CRS will implement implementation of an emergency response emergency response attachments as attachment, in parallel, THEN GO TO that necessary attachment AND begin response actions.
o B.2. - IF an EAL condition is met, THEN OBTAIN an Attachment 3, Initial Notification Determines from previous Form, AND GO TO the appropriate EAL evaluation that an EAL is satisfied Declaration attachment: and obtains an Initial Notification o General Emergency Actions, Att 4 form. Identifies General Emergency as the appropriate o Site Area Emergency Actions, Att 9 declaration. Goes to Attachment 4, o Alert Actions, Att 11 General Emergency Actions.
o Unusual Event Actions, Att 13 ERPIP 3.0, ATTACHMENT 4, General Emergency Actions o A.I - COMPLETE Attachment 3, Initial Refers to Attachment Initial Notification Form. i C:ltlon
Appendix C Job Performance Measure Fonn ES-C-I Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD ERPIP 3.0, ATTACHMENT 3, Initial Notification Form NOTE TO EVALUATOR Page 2 of A TTACHMENT 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 10 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)
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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: _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completilon Job Performance Measure Number: SRO-ADMIN-5 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:
Appendix C Job Performance Measure Form ES-C-l Worksheet 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.
- 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
Appendix C Job Performance Measure Form ES-C-l Worksheet 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)
Task Number: 202.023 KIA
Reference:
2.1.20 (4.6, 4.6)
Method of testing:
Simulated Performance: 0 Actual Performance: ~
Classroom: ~ Simulator: 0 Plant: 0 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 performance measure will be satisfied.
Initial Conditions:
- 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.
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:
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
Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 ATTACHMENT(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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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)
Appendix C Job Performance Measure Form ES-C-I Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 I TERMINATING CUE: This JPM is complete when the ~OP-3B, Att (11), Calculation of Time i ito Boil or Core Uncovery, worksheet has been completed. No further actions are required.
L ..____________________________________________________________________ ~
STOP: -----
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: RO-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:
Appendix C Job Performance Measure Form ES-C-I Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 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 of an 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 OPERATOR I~XAM JPM #: RO-AI)MIN-2
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-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:
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 performance measure will be satisfied.
Initial Conditions:
- 1. Unit-2 RWT parameters are:
- 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
Appendix C Job Performance Measure Form ES-C-1 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:
- 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
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START: _ __
o Locates NEOP-23, Figure 2-11-A-6 or Unit-2 Core Same as element Operating Limits Report for Cycle 19 (3.9.1)
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 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 Determines manual calculation BORIC ACID MENU must be performed o The following formula: Determines following values for input to manual calculation:
(842.15) (LlB) (L+ 18)
- 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
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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": _ __
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet Verification of Completion 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: _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 5. Unit-2 RWT parameters are:
- 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
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-3 Determine protective clothing requirements and dose limits associated with Task
Title:
performance of a task in the RCA Task Number: 204.138 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:
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 performance measure will be satisfied.
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 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:
- 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
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion 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: _ _ _ _ _ _ _ _ _.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet EXAMINEE'S CUE SHEET 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 i
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2012 NR~C INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-4
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: RO-ADMIN-4 Perform an Independent Assessment of an Event Using the EOP-O Diagnostic Task
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:
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 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 _____________________________________________________________________ ~
Appendix C Job Perfonnance 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 tllme..
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
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.
Appendix C Job Perfonnance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START: _ __
- 0 Locate EOP-O Diagnostic Flowchart. Same as element VI. SAFETY FUNCTION STATUS CHECK Completes SFSC for RC.
o Reactivity Control Safety Function. Determines RC Safety Function met.
o Vital Auxiliaries Safety Function. Detennines VA Safety Function met.
Detennines PIC Safety Function not met due to low Pressurizer pressure and Pressurizer level.
Detennines HR Safety Function not met due to low TCOLD.
Completes SFSC for CEo o Containment Environment Safety Function. Detennines CE Safety Function is met.
Completes SFSC for RLEC.
o Radiation Levels External to Containment Safety Detennines RLEC Safety Function Function.
met.
CUE: Acknowledges report out on status of Safety Functions Reports RCS Pressure and Inventory Control Safety Function is not met due to low Pressurizer o results of SFSC to CRS pressure and level, and Heat Removal Safety Function is not met due to low
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: I Post-trip immediate actions have been completed V. DIAGNOSTIC FLOWCHART Selects "YES" flowpath. Proceeds 0 REACTIVITY SAFETY FUNCTION MET? to "VITAL AUXILIARIES SAFETY FUNCTION MET?"
Selects "YES" flowpath. Proceeds 0 VITAL AUXILIARIES SAFETY FUNCTION to "RCS PRESSIINV SAFETY MET?
FUNCTION MET?"
i I Selects "NO" flowpath. Proceeds to 0 RCS PRESS/INV SAFETY FUNCTION MET? "EITHER S/G PRESSURE LESS THAN 800 PSIA?"
I Selects "YES" flowpath. Proceeds 0 EITHER S/G PRESSURE LESS THAN 800 to "RCS SUBCOOLING LESS PSIA?
THAN 30° F?"
Selects "NO" flowpath. Consider 0 RCS SUB COOLING LESS THAN EOP-4 (ESDE). Proceeds to 30° F? "CORE/RCS HEAT REMOV AL SAFETY FUNCTION MET?"
I I
Selects "NO" flowpath. Proceeds 0 CORE/RCS HEAT REMOVAL SAFETY to "AT LEAST ONE S/G HAS FUNCTION MET?
FEED FLOW?"
Selects "YES". Proceeds to "ANY o AT LEAST ONE S/G HAS FEED FLOW? RCPs TRIPPED DUE TO TRIP STRATEGY?"
I Selects "YES". Proceeds to "S/G 0 ANY RCPs TRIPPED DUE TO TRIP B/D OR COND OFF-GAS RMS STRATEGY?
ALARMS OR RISE?"
I Selects "NO" flowpath. Proceeds 0 S/G B/D OR COND OFF-GAS RMS ALARMS to "RCS SUB COOLING LESS OR RISE?
THAN 30° F"?
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Selects "NO" tlowpath. Consider EOP-4 (ESDE). Proceeds to ORCS SUB COOLING LESS THAN "CONTAINMENT 30° F?
ENVIRONMENT SAFETY FUNCTION MET?"
Selects "YES" tlowpath. Proceeds o CONTAINMENT ENVIRONMENT SAFETY to "RADIATION LEVELS FUNCTION MET? EXTERNAL TO CONTAINMENT SAFETY FUNCTION MET?"
Selects "YES" flowpath. Proceeds o RADIATION LEVELS EXTERNAL TO to "ALL SAFETY FUNCTIONS CONTAINMENT SAFETY FUNCTION MET?
MET?"
Selects "NO" tlowpath. Proceeds to o ALL SAFETY FUNCTIONS MET? "SINGLE EVENT DIAGNOSIS POSSIBLE?"
Selects "YES" tlowpath". Proceeds o SINGLE EVENT DIAGNOSIS POSSIBLE? 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.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion 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: _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date:
~------------
Appendix C Job Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET 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
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet 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)
Task Number: 202.024 KIA
Reference:
025AA207 (3.4, 3.7)
Method of testing:
Simulated Performance: D Actual Perforrnance: [gJ Classroom: D Simulator: [gJ 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. Unit-l is in Mode 5 for maintenance with the PZR manway removed.
- 2. The RCS is being maintained at approximately 42.7 feet.
- 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 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:
- 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).
- 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
- 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.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 1C09-ALM. Same as element a Investigates cause of alarm using guidance provided by lC09-ALM for Window H-28 "12 Same as element LPSI SUCT PRESS LO". Recommends 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 1 L£4138 is being used, THEN verify flow is less than or equal to 1800 gpm.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 0 IV.A.4.a.(2) - IF RCS level is greater than 37.6 feet, THEN verify t10w is less than or elem equal to 3000 gpm.
0 IV.A.4.a.(3) - IF the appropriate SDC Flow is Restored AND LPSI PP cavitation/gas Determines step is Not Applicable binding stops, THEN IMPLEMENT the appropriate Operating Procedure.
i~~~' O* IV.A{'t.b.
~" :.'
- Stop the operating LPSI PP(s) element I
0 IV.A.4.c. - Place BOTH LPSI PP handswitches Same as element in PULL TO LOCK I
CAUTION Isolation of the LPSI PP suction flow path can cause pump damage if the LPSI PPs are I allowed to operate.
0 IV.A.S. - Check that the SDC HDR RETURN ISOL valves are open Determines that 1-S1-651-MOV is 0 1-S1-651-MOV NOT fully open 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, Same as element THEN complete the following:
0 IV.A.S.I.a. - Stop the operating LPSI PP(s). Determines step is Not Applicable 0 IV.A.S.1.b. - Place BOTH LPSI PP Determines step is Not Applicable 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 Determines step is Not Applicable pressure less than 260 PSIA.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD 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 of Att. (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-432 are locked shut r::J 4. - Ensure the LPSI PP NORM SUCT ISOL valves are Locked Shut: Calls Auxiliary Building operator to t:msure valves are correctly r::J (11 LPSI PP) I-SI -444 positioned r::J (12 LPSI PP) I-SI-432
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: When asked: I-SI-441 and I-S1-440 are locked open 0 5. - Ensure the LPSI PP SDC SUCT ISOL valves are Locked Open: Calls Auxiliary Building operator to
,ensure valves are correctly o (11 LPSI PP) I-S1 -441 positioned o (12 LPSI PP) I-S1-440 CUE: When asked: I-S1-447 and I-S1-435 are locked open o 6. - Ensure the LPSI PP DISCH ISOL valves are Locked Open: Calls Auxiliary Building operator to ensure valves are correctly o (11 LPSI PP) I-S1-447 positioned o (12 LPSI PP) I-S1-435 I
CUE: When asked: air is not suspected of being trapped in the SDC return header 0 7. - IF air is suspecled of being trapped in Ihe SDC D I . I
- N I A r bl Return Header THEN vent the SDC Return Header. e ermmes s ep IS 0 pp lca e WARNING Venting the SDC System may release high temperature, highly radioactive gasses.
The applicant should recognize that venting of the LPSI pumps is necessary. When he calls the ABO to vent the pumps have Booth Operator use remote function to vent 11 &
CUE: 12 LPSI pumps.
When asked: inform candidate that Rad Safety has been notified and ABO has vented pumps 0 8. - IF air is suspected in the LPSI PPs, THEN vent Determines pumps have been vented the LPSI PP casings:
Verifies output of HIC-657 is zero D::i~. -Slltif\tl1e SIDCOOEING TEMP CONrR valve, or HS-3657 is in CLOSE. Checks I-SI-657-CV.
position indication for SI-657 0 10. - Partially open the SDC FLOW CONTR valve, Same as element 1-SI-306-CV, as follows:
0 10.a. - Place the SDC FLOW CONTR, I-FIC-306, Same as element to MANUAL.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD I
Note to EvaluatOl[
Candidate should note that controller output must be increased to throttle I-SI-306-CV closed o 1O.h. - Adjust the SDC FLOW CONTR~ I-FIC-Same as element 306, to 95% output.
0 11. - Verify LPSI HDR flowpath Same as element 0 II.a. - IF the RCS level is at or below the 37.6 foot Determines step is Not Applicable elevation, OR ...
0 11.b. - IF the RCS level is between the 41 foot and Determines step is Not Applicable the 37.6 foot elevation, AND ...
0 II.c. - IF the RCS level is between the 41 foot and Determines step is Not Applicable the 37.6 foot elevation, THEN ...
0 II.d. - IF the RCS level is above the 41 foot elevation, THEN verify ALL LPSI HDR valves are open:
0 I-SI-615-MOV Same as element 0 I-S1-625-MOV 0 I-SI-635-MOV 0 I-SI-645-MOV CAUTION Do NOT operate the LPSI PPs at shutoff head.
Same as element 0 12. - Start aC,LPSI PP.
Either LPSI PP is acceptable 0 13. - IF the RCS level is at or below the 37.6 foot Determines step is Not Applicable elevation, OR ...
0 14. -lEthe RCSle~el is greater than the 37.6 foot
" ,}; ,4
, elevation,.ANDJL~4138 is NOT being used, Same as element THEN slowly ad.just the SDC FLOW CONTR, Adjusts flow to 2950 -3050 GPM I-FIC-306, to .raise SDC flow to 3000 GPM.
Appendix C Job Performance Measure F01111 ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD I CUE: I The CRS directs FIC-306 be placed in Auto.
~ . /, ..*
~~~~.~ .~ ~. Places FIC-306 in AUTO after o I5.:-Place,tl1e Sl)C FLOW CONTR, I-FIC-306, in
'i\UTO if desired} ~~:~~ing setpoint to actual SDC TERMINATING CUE: This JPM is complete when SDC flow has been restored. The evaluator is expected to end the JPM. No further actions are required.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-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:
Appendix C Job Perfonnance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET 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.
- 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 performing the duties ofthe Unit 1 CRO.
Initiating Cue:
The CRS has directed you to respond to these conditions using the appropriate procedure(s).
.' r-------------------,
APPLICANT: _ __
CALVERT <:LIFFS NUCLEAR POWI~R PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-2
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performancle Measure No.: SIM-2 Task
Title:
Respond to a Pressurizer Spray Valve FaiLure (Alternate Path)
Task Number: 064.036 KIA
Reference:
008 AA2.19 (3.4,3.6)
Method of testing:
Simulated Performance: 0 Actual Performance: ~
Classroom: 0 Simulator: I2J Plant: 0 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 performance measure will be satisfied.
Initial Conditions:
- 1. Unit-l is at 100% power.
- 2. Pressurizer pressure control and safety channels indicate low Pressurizer pressure
- 3. Proportional heaters indicate maximum current
- 4. All available backup heaters are energized
- 5. The "PZR PRESS CH 100" alarm is currently in
- 1. You are performing the duties of the Unit-l RO.
Initiating Cue:
You are directed to respond to the alarms in accordance with plant procedures.
Task Standard:
Responds to the alarms and abnormal conditions in accordance with Alarm manual, recommends and trips the reactor, secures IlA RCP
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:
1C06-ALM, RCS Control Alarm Manual General
References:
Procedures and manuals normally available in the control room Time critical task:
No Validation Time:
12 minutes Simulator Setup:
- 1. Reset the simulator to IC-24 (100% MOC).
- 2. Insert Malfunction rcs016, RCS-Przr Spray Valve l-RC-IOOE Fails Open.
- 3. Place the Simulator in RUN
_ _ 4. Run the simulator until 1C06 annunciator window E-29, "PZR Press CH 100", alarms
(- 11 Minutes).
- 5. Pressurizer Pressure should be approximately 2125 PSIA.
- 6. Acknowledge alarms.
- 7. FREEZE the simulator.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: I Have simulator driver place simulator in RUN TIME START:
Examiner Note Applicant may refer to other alanns associated with the low Pressurizer pressure condition as welL Candidate may note spray valve open initially and att(~mpt to close before referring to the Alann ManuaL 0 Locates 1C06-ALM. Same as element 0 Investigates cause of alann using guidance provided by 1C06-ALM for Window E-29 "PZR Press CH Same as element 100".
0 Notes that Pressurizer pressure is LOW, and enters the CONDITION/RESPONSE table (2) for Same as element Pressurizer low pressure 0 2. - Perfonn the following Same as element o 2.a. - CHECK Pressurizer spray valves shut.
0 l-RC-IOOE Identifies l-RC-IOOE is Open 0 l-RC-IOOF 0 2.b. - CHECK Pressurizer heaters energized. Same as element 0 2.c. - IF required, THEN PERFORM any of Same as element the following:
0 ENERGIZE Pressurizer heaters Same as element 0 SHIFT Pressurizer pressure control Detemlines step is NOT applicable channels 0 SHUT Pressurizer spray valves using Same as element I-HIe-l00 in manual 0 IF one Pressurizer spray valve has failed OPEN, THEN attempt to SHUT Pressurizer spray valve by swapping 1- Same as element HS-IOO-8 to the opposite Pressurizer spray valve.
I
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o IF Pressurizer spray valves can NOT be Detennines that l-RC-IOOE cannot shut, THEN PERFORM the following: be shut Acknowledge RO report of tripping the reactor Same as element o (2) - IMPLEMENT Reactivity Control Completes reactivity portion of the section ofEOP-O, Post-Trip Immediate EOP-O plaque Actions.
Leave lC06-ALM procedure and enter EOP-O Reactivity Control Safety Function o 1. Depress Manual Reactor Trip Pushbutton on 1COS o Verify Dl Water Makeup is secured o Check 11 & 12 RC makeup Pumps secured on lC07 o Check VCT MIU l-CVC-S12-CV is shut on lC07 Same as element o If aligned for direct makeup to RCS then shut RWT Charging Pump Suction l-CVC-S04-MOV on IC07 Reports Reactivity Control Safety Function Complete.
o 2. Check Reactor has tripped by the following:
o Prompt drop in NI power Same as element o Negative SUR o 3. Check that NO more than ONE CEA is NOT fully Same as element inserted.
o Verify DI Water Makeup to the RCS is secured as follows:
o Check 11 & 12 RC makeup Pumps secured on lC07 Same as element o Check VCT MIU l-CVC-S12-CV is shut on lC07 o If aligned for direct makeup to RCS then shut RWT Charging Pump Suction l-CVC-504-MOV on IC07
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Leave EOP-O Reactivity Control Safety Function and return to 1C06-ALM procedure Secures 11 A RCP TERMINATING CUE: This task is complete when the applicant has tripped the secured I1A RCP.
TIME STOP: _ __
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet Verification of Completion Job Perfonnance Measure Number: SIM~2 Applicant:
NRC Examiner:
Date Perfonned:
Facility Evaluator:
Number of Attempts: _________________
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response:
Result: SAT _ _ _ _ __ UNSAT - - - - - -
Examiner's Signature and Date: _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-I Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 6. Unit-I is at 100% power.
- 7. Pressurizer pressure control and safety channels indicate low Pressurizer pressure
- 8. Proportional heaters indicate maximum current
- 9. All available backup heaters are energized
- 10. The "PZR PRESS CH 100" alarm is currently in
- 11. You are performing the duties of the Unit-I RO.
- Initiating Cue:
I You are directed to respond to the alarms in accordance with plant procedures.
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POW~F~R PLANT 2012 NRC INITIAL LICE:NSED OPERATOR EXAM JPM #: SIM-3
Appendix C Job Perfonnance Measure Fonn ES-C-I Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-3 Task
Title:
Respond to a FRV or FRV controller malfunction Task Number: 202.040 KIA
Reference:
054 AA2.05 (3.5, 3.7)
Method of testing:
Simulated Perfonnance: 0 Actual Perfonnance: ~
Classroom: 0 Simulator: ~ Plant:
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. Unit-l is operating at -100 % power.
- 3. A report from the TBO indicates that there is an excessive air leak on the in-service positioner for 12 MFRV.
- 4. You are perfonning the duties of the Unit-l CRO.
Initiating Cue:
The CRS directs you to respond to the 12 MFRV positioner issue using AOP-3G, Malfunction of Main Feedwater System.
Task Standard:
Operator shifts from the in service MFRV positioner to the off service MFRV positioner from the Control Room.
Appendix C Job Performance Measure Form ES-C-I 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:
AOP-3G, Malfunction of Main Feedwater System General
References:
Procedures and manuals normally available in the control room Time critical task:
No Validation Time:
10 minutes Simulator Setup:
_ _ 1. UI at ~ 100% (IC-24).
- 2. Plasma display at 1C36 verified operable.
- - 3. Place Simulator in RUN.
. _ _ 4. Place 12 MFRV Controller in manual and lower controller output approximately 5%.
- 6. Place 12 MFRV Controller back in automatic.
_ _ 7. Allow Feedwater Regulating System to stabilize with SIG levels slowly recovering.
- 8. Place Simulator in "FREEZE"
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START:
EXAMINER'S This JPM is written to be performed with either positioner in service. The off-service positioner will be placed in service to facilitate repairing a problem with the on-service positioner.
CUE I Have Booth Operator place Simulator in "RUN" 0 Identifies and locates AOP-3G, Main Feedwater Malfunction 0 IV - PRELIMINARY I Same as element.
o IV.A. - DETERMINE THE PROPER SECTION.
0 IV.A.I. - IF a pump trips with Reactor power greater than or equal to 5%, THEN PROCEEI) Determines step is NOT applicable 0 IV.A.2. - IF a pump trips with Reactor power Determines step is NOT applicable less than 5%, THEN PROCEED ...
Determines step IS applicable.
0 IV.A.3. - IF a malfunction of the Feedwater Exits Sect IV, Preliminary, to Regulating System occurs, THEN PROCEED Section VII, Response to a to Section VII., Response to a Malfunction of Malfunction of the Feedwater the Feedwater Regulating System, Page 35.
Regulating System 0 VII - RESPONSE TO A MALFUNCTION OF THE FEED WATER REGULATING SYSTEM o VILA. - DETERMINE IF A REACTOR TRIP IS REQUIRED.
o VILA. I. - IF the Reactor is critical, ANI) ANY of the following:
0 SG level is approaching (+)50 inches 0 SG level is approaching (-)40 inches 0 TcoLD lowers to 515 F 0 Determines a Reactor trip is NOT THEN, with the approval of the SM/CRS, perform required the following actions:
o VIl.A.I.a. - Trip the Reactor.
o VILA.I.b. - IMPLEMENT EOP-O, POST TRIP IMMEDIATE ACTIONS.
I
Appendix C Job Perfomlance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o VILB. - DETERMINE IF A REACTOR TRIP IS REQUIRED.
o VII.B.l - IF a SGFP Speed Controller has Determines step is NOT applicable failed, OR is erratic, THEN PROCEED ...
o VII.B.2 - IF a FRV/FRV BYP OR FRV/FRV Determines step IS applicable.
BYP Controller malfunctions, THEN Exits Sect VII.B, proceeds to PROCEED to Step D, Page 42. Section VII.D o VII.D. - RESPOND TO A FRV/FRV BYP OR FRV/FRV BYP CONTROLLER MALFUNCTION.
o VII.D.l - IF a SG FW REG CONTROL MAIN Determines step is NOT applicable has failed ...
NOTE A differential between the output from SG FW REG CONTROL MAIN and FRV position may indicate FRV binding.
o VII.D.2. - IF there is a differential between the output from SG FW REG CONTROL MAIN Determines step IS applicable and FRV position, THEN, if desired, manually shift FRV positioners as follows:
o VII.D.2.a. - Shift FRV positioners from the Same as element Control Room NOTE Only the CPU in service (Main OR Backup) can shift Positioners.
Locates 1C36 and activates the screen for the Main CPU by touching the screen. Once screen is activated, touches the word MENU.
T ouches the selection 7 on the monitor on 1C36.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Touches the word OFF on the monitor on 1C36.
EXAMINER'S NOTE The in-service positioner will be indicated by arrows beneath the corresponding positioner letter "A" or "B".
o VILD.2.a.(4) - Check that the word OFF Verifies the word OFF changes to a changes to a flashing ON. flashing ON indication.
AND check that the positioner Control letters'A" and "B" are flashing. Verifies the letter A or B is flashing.
NOTE IF the screen is touched anywhere other than "A" OR "B", THEN the Manual Main FRV Positioner Selector will tum off.
Touches the flashing letter "A" OR"B" o VILD.2.a.(6) - Check that the FRV V erifies the position switches to the position responds. "A" OR"B" positioner.
TERMINATING CUE: This JPM will be complete whe:n the oncoming positioner has been placed in service for 12 MFRV.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-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: _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-I Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. Unit-l is operating at ~ 100 % power.
- 3. A report from the TBO indicates that there is an excessive air leak on the in-service positioner for 12 MFRV.
- 4. You are performing the duties of the Unit-l CRO.
Initiating Cue:
The CRS directs you to respond to the 12 MFRV positioner issue using AOP-3G, Malfunction of 'I' Main Feedwater System. .
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POW~ER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-4
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIMA Task
Title:
Verify RAS (Alt Path)
Task Number: 201.063 KIA
Reference:
006 A3.08 (4.2, 4.3)
Method of testing:
Simulated Performance: 0 Actual Perfoffitance: ~
Classroom: 0 Simulator: ~ Plant: 0 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 performance measure will be satisfied.
Initial Conditions:
- 1. Unit-l Tripped from 100% power due to a LOCA.
- 2. RWT Level ~ 1.0 foot and decreasing.
- 3. You are performing the duties of the Unit-l CRO.
Initiating Cue:
The CRS directs you to verify RAS Actuation per EOP-5, Stlep IV.S.
Task Standard:
This JPM is complete when the operator stops 12 LPSI Pump and aligns ECCS for RAS operation.
Appendix C Job Perfonnance Measure Fonn 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:
Procedures and manuals nonnally available in the control room General
References:
EOP-5, Loss of Coolant Accident EOP Attachments, Attachment (10)
Time critical task:
No Validation Time:
20 minutes Simulator Setup:
~_ 1. Reset the Simulator to IC-24, both Units at 100% power
- 2. Place Simulator in RUN
- 3. Set controller for I-SW-5208 to 0% output
- 4. Insert Malfunction RCS002 at 10000 GPM.
- 5. Insert override PIC09 1 HS302YA to OVERRIDE.
- - 6. Insert override PIC09_H23_LTON (LPSI PI' RAS OVERRIDE) to OFF.
- - 7. Place simulator in RUN until RAS actuates.
- 8. Place Simulator in FREEZE.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START: _ __
. 0 Identifies and locates EOP-5, Block Step "IV.S" Same as element IV.S,! - WHEN RWT level drops to 0.75 feet OR the "ACTUATION SYS RAS TRIP" alann is received, THEN perfonn the following actions:
NOTE TO EVALUATOR Applicant must perfonn critical task of securing 12 LPSI Pump due to its failure to stop automatically upon receipt of RAS. If applicant does not secure 12 LPSI during RAS verification in step IV.S.I.a, then it must be secured during verification ofRAS lineup per Attachment (6) in step IV.S.l.e.1 ALTERNATE ACTION Verifies RAS actuation:
"ACTUATION SYS RAS TRIP" alann actuated, LPSI pumps stopped & Cntmt sump valves opening. Secures 12 LPSI Pump due to receipt of RAS o IV.S.1.b. - Check a minimum containment sump Monitors containment sump level level of at least 28 inches is indicated on the on l-LI-4146 or l-LI-4147, on CNTMT WR WATER LVL indication, 1-LI-4146 IC08 and lC09.
or l-LI-4147.
o IV.S.1.c. - Place the CNTMT SUMP DISCH valve handswitches in open:
Same as element o I-SI-4144-MOV o I-S1-4145-MOV o IV.S.1.d. - Shut the RWT OUT valves:
o I-SI-4142-MOV Same as element o I-SI-4143-MOV
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o IV.S.1.e. - Verify RAS lineup PER ATTACHMENT (6), RAS VERIFICATION Same as element CHECKLIST.
ATTACHMENT (6), RAS VERIFICATION CHECKLIST On Panels IC08, IC09, ICIO:
o a. - 11 and 12 LPSI PPs - Off Same as element ALTERNATE ACTION Secures 12 LPSI Pump due to receipt ofRAS (if not secured in step IV.S.l.a - see previous note to
,evaluator)
END OF ALTERNATE o b. - MIN FLOW RETURN TO RWT ISOL MOVs:
o I-SI-659-MOV - Shut Same as element o I-SI-660-MOV - Shut o c. - CNTMT SUMNP DISCH valves:
o I-SI-4144-MOV - Open Same as element o I-S1-4145-MOV - Open On PaneIIC13:
o a. - CAC SRW INL valves o I-SRW-lS81-CV - Open o I-SRW-1584-CV - Open Same as element o I-SRW-1589-CV - Open o I-SRW-1592-CV - Open I Returns to EOP-5, Block Step "IV.S.1.f" o IV.S.1.f. - Verify Component Cooling in service as follows:
Appendix C Job Performance Measure Form ES-C-I Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Same as element (Only throttling I-HIC-5208 open is a Critical Task. I-HIC-5206 was already throttled open. Output of 1 HIC-5208 should approximate that of I-HIC-5206) o IV.S.1.f.(2) - Verify BOTH CCHX OUT valves are open:
Same as element o l-CC-3824-CV o 1- CC-3826-CV o IV.S.1.f.(3) - Verify TWO CC PPs in operation. Same as element NOTE TO EVALUATOR The candidate must end up with HPSI Pp flow split such that minimum flow requirements of 90 GPM per PP are met for running HPSI Pumps.
Main and Aux HPSI Hdr MOVs must be placed in Pull-TO-Override to throttle HPSI flow.
Applicant throttles HPSI flow to 250 +/- 25 GPM, per header, ensuring operating HPSI PP mini flow requirements are met o IV.S.l.h - IF one HPSI PPs is running, THEN throttle HPSI flow to achieve ISO GPM through Determines this step is NIA each of the four headers.
Determines HPSI header flow is o IV.S.l.i - Check HPSI MOVs with flow are at least being maintained at the required 30% open.
value I
- TERMINATING CUE: This JPM is complete when the operator has secured 12 LPSI Pump, verified the post-RAS alignment and, throttled the Main and AUX HPSI Loop flows to I approximately 250 GPM per loop. No further actions are required.
~
Appendix C Job Performance Measun~ Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-4 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ _~ l~SAT _______________
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-I Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. Unit-l Tripped from 100% power due to a LOCA.
- 2. R WT Level ~ 1.0 foot and decreasing.
- 3. You are performing the duties of the Unit-l CRO.
Initiating Cue:
The CRS directs you to verify RAS Actuation per EOP-5,
APPLICANT: _ __
CALVERT CTuIFFS NUCLEAR POW-ER PLANT 2012 NRC INITIAL LICENSED OPERATOR I~XAM JPM #: SIM-5
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performanc.~ Measure No.: SIM-5 Task
Title:
Verify the Containment Environment Safc:ty Function is satisfied (ALT Path).
Task Number: 201.016 KIA
Reference:
069 AA2.02 (3.94.4)
Method of testing:
Simulated Performance: Actual Performance: [2J Classroom: Simulator: [2J 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 performance measure will be satisfied.
Initial Conditions:
- 1. A transient resulting in a Reactor trip has occurred OIl Unit-I.
- 2. You are performing the duties of the Unit-I CRO.
Initiating Cue:
The CRS directs you to verify the Containment Environment Safety Function is satisfied. Are there any questions? You may begin Task Standard:
Verifies the Containment Environment Safety Function per EOP-O. Performs Alternate Actions Associated With the Containment Environment 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:
Procedures and manuals normally available in the control room General
References:
OP-2, Plant Startup From Hot Standby To Minimum Load 01-30, Nuclear Instrumentation Time critical task:
No Validation Time:
10 minutes Simulator Setup:
See next page
Appendix C Job Performance Measure Form ES-C-l Worksheet Simulator Setup:
-- 1. Reset to IC-24 with both units at 100% in FREEZE.
_ _ 2. Override the following on panels lC09/1ClO:
- a. PIC09_1PI5308_MT (1-PI-5308 CNTMT PRESS IND5308 MT) to final value of three (3) at time zero.
_ _ b. PICIO_IHS5297A(I-HS-5297ABVSll CHARFLTR Vl3 SWOP) to OPEN at time zero.
- c. PIC09_1HS5293 (l-HS-5293 l1CNTMT FLTR V SWPVLL) to TRIP at time zero
- 3. Insert the following malfunctions:
- a. 480vOOl_Ol (Loss of 480 VAC Bus IlA) at time zero
- b. esfa004_0l (ESFA-CSAS Channel A Auto Failure) at time zero.
_ _ c. esfa004_02 (ESFA-CSAS Channel B Auto Failure) at time zero.
_ _ d. rcsOOl (RCS Cold Leg 12B Rupture) at time zero.
_ _ 4. Place in RUN until the "CNTMT RAD LVL HI" alarm comes in (happens fairly quickly), THEN GO TO FREEZE.
- 5. Acknowledge all panel alarms and ensure "Hom On" for annunciators.
_ _ 6. Select "Clock" time.
_ _ 7. WHEN cued go to RUN.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: I Have simulator driver place Simulator in RUN TIME START: _ _
Identifies and locates EOP-O, Step o Implements EOP-O, Step IV.F.
IV.F. or uses the plaque on 1C09.
EXAMINER'S NOTE Containment Narrow Range Pressure Indication on IC09 (I-PI-5308) is failed to 3 PSIG.
Actual Containment pressure, as indicated on the Containment Wide Range Pressure indicator (l-PI-5307, to the left of I-PI-5308), is approximately 25 PSIG.
o IV.F. - VERIFY THE CONTAINMENT ENVIRONMENT SAFETY FUNCTION IS SATISFIED.
Checks containment pressure indication on I C09 and detennines that containment pressure is greater than 0.7 PSIG based on WR indication.
o IV.F.l. - Check containment pressure is less than 0.7 PSIG. Though not critical, identifies that NR pressure indicator may be suspect and makes report to CRS that Alternate Actions are being taken for Containment Environment due to high Containment pressure.
EXAMINER'S NOTE _
- The report of taking Alternate Actions can be made at the discretion of the operator but I should be reported as soon as practical. .
- The operator may manually initiate CSAS early if it is recognized that it has not automatically actuated. Equipment may already be in its desired condition when Containment Environment is checked.
BEGIN ALTERNATE ACTIONS o IV.F.1.1 - IF containment pressure exceeds 0.7 Same as element PSIG, THEN perfonn the following:
o IV.F.1. l.a. - Verify ALL available Same as element CNTMT AIR CLRs are operating.
I
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o IV.F.1.1.b. - Open the CNTMT CLR EMER OUT valves for the operating Same as element CNTMT AIR CLRs o IV.F.1.2 -IF containment pressure exceeds 2.S PSIG, THEN verify ESF AS actuation of the Same as element following:
Uses Operator Aid plaque on 1COS/l C09 to verify SIAS actions:
- 11 & 13 HPSI pumps are operating, and
- f1ACTUATION SYS CIS o CIS TRIPPED" has actuated and
- Containment CCW isolation valves are shut.
Trips all RCPs at 1C06.
Determines that CSAS has failed to actuate t by checking the annunciator, Spray Valves, Spray flow or CBPs Manually actuates CSAS "A" & "B" using pushbuttons on 1C09/1 O.
Uses Operator Aid plaque on 1COSI1 C09 to verify CSAS actions:
- "ACTUA TION SYS CSAS TRIPPED" has actuated
- Cntmt Spray valves are open
- Cntmt Spray Header flow
- Cond Booster Pps tripped.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o IV.F .2.1. - IF containment temperature Same as element exceeds 120°F, THEN perform the following:
Checks all four containment air o IV.F.2.l.a. - Verify ALL available CNTMT coolers on IC09/10 to determine that AIR CLRs are operating. all available coolers are operating.
o IV.F.2.1.b. - Open the CNTMT CLR Checks valve indication at 1C 10 to EMER OUT valves for the operating ensure they are open.
CNTMT AIR CLRs.
Verifies alarms clear on I C 10 and o IV.F.3 - Check containment radiation monitor uses indications at 1C22 to identify alarms are clear with NO unexplained rise. that
. the. containment RMS are mcreasmg.
o IV.F.3.1.a. - IF ANY valid containment Notes only 12 Iodine Filter Fan is radiation alarm is received, THEN start ALL running.
available IODINE FILT FANs.
Aligns 13 Iodine Filter Fan disconnect to 480V Bus 14 and verifies fan starts.
Reports to the CRS that the Containment Environment Safety o Reports to the Unit CRS the status of the Function cannot be met due to high Containment Environment Safety Function. containment pressure and temperature, and high Containment radiation monitor alarms.
END ALTERNATE ACTIONS TERMINATING CUE: The lPM is complete when the CRS is informed of the status of the Containment Environment Safety Function. No further actions are required. The examinee is expected to end the lPM.
TIME STOP: _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-S 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 Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
I
- 1. A transient resulting in a Reactor trip has occurred on Unit-I.
- 2. You are performing the duties of the Unit-l CRO.
Initiating Cue:
- 1. The CRS has directed you to verify the Containment Environment Function is satisfied. Are there any questions? You may begin
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-6
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-6 Task
Title:
Nulling NI Pots to L\T Pots Task Number: 078.010 KJA
Reference:
015 A3.03 (3.9,3.9)
Method of testing:
Simulated Performance: 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 performance measure will be satisfied.
Initial Conditions:
- 1. A Unit-l startup is in progress.
- 2. Power is approximately 11 % and holding.
- 3. ICOS Annunciator Window D-43, "NUCLEAR L\T CH DEVIATION" is in.
- 4. You are performing the duties of the U-I CRO.
Initiating Cue:
The CRS directs you Null the NI Pots per OP-2, Step 6.9.G.2. Are there any questions? You may begin.
Task Standard:
Nulls RPS Channel "A" NI Pot to the L\ T Pot and clears the "NUCLEAR L\ T CH DEVIATION" alarm.
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:
Procedures and manuals normally available in the control room General
References:
OP-2, Plant Startup From Hot Standby To Minimum Load 01-30, Nuclear Instrumentation Time critical task:
No Validation Time:
10 minutes Simulator Setup:
- 1. Reset the simulator to IC-20 (11 % power)
_ _ 2. Adjust NI power pots:
- - a. Channel A: 9.45 - 8.4%
- b. Channel B: null to match LlT power
- - c. Channel C: null to match LlT power
_ _ d. Channel D: null to match LlT power
_ _ 3. Adjust RPS Channel "A" ,~T power calibrate potentiometer until the "NUCLEAR LlT POWER CH DEVIATION" annunciates on lC05
_ _ 4. Verify NI-Oelta-T power alarm on IC05 caused by CH A only
_ _ 5. Borate CEAs out as required to clear primary POlL and PPOIL alarms when pots are adjusted.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START: _ __
I 0 Identify and locate OP-2, Step 6.9.G.2 Same as element NOTE
- When nulling NI pots, the possibility exists that the pot may reach its hard stop before the I NUCLEAR POWER-~T POWER deviation meter reaches zero.
- Tech Spec 3.3.1 requires the Axial Power Distribution Trip and the Loss of Load Trip to be active when NUCLEAR INSTRUMENT POWER is > 15% RTP.
o 6.9.G.2 - WHEN Reactor power is between 10 and 12%, THEN NULL the NI pot for each channel that Determines step is applicable.
NI power is reading less than Delta-T power PER 01-30, section titled, NULLING NI POTS TO Refers to 01-30, Step 6.1 ° DELT A T POTS. [B0412]
o Identify and locate 01-30, Section 6.10 Same as element NOTE
- Tech Spec 3.3.1 requires the Axial Power Distribution Trip and the Loss of Load Trip to be active when NUCLEAR INSTRUMENT POWER is > 15% RTP.
- Excore NI Power Range Safety Channels are adjusted one entire channel at a time, with the channels selected in any order.
CAUTION:
Adjustment of an Excore NI Power Range Safety Channel renders the channel inoperable AND requires entry into Technical Specification Action Statement 3.3.1.
o 6.10.B.1 - NULL the NI pot for each channel that NI Determines Channel A is causing the power is reading less than Delta-T power, by NI-DeltaT alarm performing Steps a. through i. For a specific channeL At RPS Channel "A":
Inserts and rotates keys, checks channel trip bypass lights on
- t;+'4/LOr
- :~S
.(. *.J
. . . ,.. :r.;OSS. . . . E. *. .* .O~
~O!* AXIALPWR~\
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE. Acknowledge request for independent verification that correct RPS Channel "A" Trip
. Units 1,2,7,8 & 10 are bypassed.
o 6.l0.B.l.b. -INDEPENDENTLY VERIFY that Requests independent verification RPS Trip Units 1,2, 7, 8 & 10 are bypassed.
Same as element NOTE
- Counterclockwise rotation raises the reading.
- When nulling NI pots, the possibility exists that the pot may reach its hard stop before the NUCLEAR POWER-AT POWER deviation meter reaches zero. During a plant startup, this is acceptable as long as the NUCLEAR AT CH DEVIATION alarm is clear.
CAUTION Potentiometer adjustments must be stopped immediately if 1(2)C05 annunciator "POWER LEVEL HIGH CHANNEL PRE-TRIP" alarms while adjusting a potentiometer.
Adjusts NI cal pot and verifies Nuclear Power Delta T power is zero.
Lowers locking lever on Pot 6.1 O.B.l.f. - IF tripped, THEN RESET VOPT AND RPS Trip Units 1, 7 and 10 AND associated Same as element Control Room annunciators.
Rotates and removes keys, verifies Bypass lights are otT CUE: Acknowledge request for independent verification that correct Trip Bypass Keys have been removed from RPS Channel "A" Trip Units 1,2, 7, 8 & 10.
o 6.1 O.B.l.h. - INDEPENDENTLY CHECK that Trip Bypass Keys are removed from Trip Units 1, Requests independent verification 2,7,8& 10.
o 6.10.B.l.i. - PLACE the DVM METER INPUT Same as element
Appendix C Job Perfonnance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD I 0 6.10.B.l.j. - REPEAT Steps a. through i. for the i Detennines process is NOT required next NI channel until all desired channels are for RPS Channels "B", "C" or "D" nulled.
i NOTE The "POWER ON" LED illuminated indicates the HV for the neutron chamber is within the proper voltage.
0 6.1O.B.2. - CHECK the POWER ON LED is illuminated for ALL four channels.
0 IF the POWER ON LED is NOT illuminated, Same as element i
THEN INITIATE a CR to investigate and repair.
I TERMINATING CUE: This JPM is complete when RPS Channel "A" has been nulled and it is detennined no other channels require being nulled. No further actions are required.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-6 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 Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:
- 1. A Unit-l startup is in progress.
- 2. Power is approximately 11 % and holding.
- 3. IC05 Annunciator Window D-43, "NUCLEAR ~T CH DEVIATION" is in.
- 4. You are perfonning the duties of the U-I CRO.
Initiating Cue:
. The CRS directs you Null the NI Pots per OP-2, Step 6.9.G.2. Are there any questions? You I may begin.
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-7
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-7 Task
Title:
Respond to Inadvertent Dilution During Reactor Startup Task Number: 202.005 KIA
Reference:
015 A3.03 (3.9,3.9)
Method of testing:
Simulated Performance: 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 performance measure will be satisfied.
Initial Conditions:
- 1. A reactor startup is in progress on Unit-I, OP-2 at step 6.6.G.
- 2. Shutdown CEAs are fully withdrawn
- 3. Regulating group CEAs are being withdrawn per OP-2 (There has been no rod motion for several minutes)
- 5. Neutron counts unexpectedly begin to rise (30 CPS over the last five minutes)
- 6. The "SID MON HI" annunciator (lC05, window D-33) alarms
- 7. 11 Purification Ion Exchanger has been in service for three weeks
- 8. You are performing the duties of the Unit-l CRO Initiating Cue:
The CRS directs you to respond to the reactivity excursion per the appropriate procedure. Are there any questions? You may begin.
Task Standard:
Terminates an Inadvertent Dilution During Reactor Startup and Restores Required Shutdown Margin
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:
Procedures and manuals normally available in the control room General
References:
OP-2, Plant Startup From Hot Standby To Minimum Load AOP-IA, Inadvertent Boron Dilution Time critical task:
No Validation Time:
10 minutes Simulator Setup:
- 1. IC-8, with reactor subcritical, a startup in progress with only the shutdown CEAs withdrawn, and power in the CPS range.
- 2. Connect SDM and reset alarms.
- 3. Set up the 11M trending plot, on the Plant Computer, using OI-50A.
- 4. Use System Lineup to change VCT concentration to O. Modify the file to change the VCT concentration back to 897, but don't execute the file. It is not needed during the AOP to stop the dilution since the operator will fast borate. But changing the file back to 897 restores the simulator to its normal setup.
- 5. Run simulator until count rate begins to increase and a SDM alarm comes in, then freeze.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: Have simulator driver place Simulator in RUN TIME START: _ __
o Identify and locate AOP-IA,Section VI Same as element Directs RO to stop any CEA o VLA.I. - Stop any outward CEA motion.
withdrawal.
Verifies CVC-512 is shut and RC o VLB.l. - Stop any makeup to the RCS.
MfU Pps are stopped.
Places HS-2520 in BYPASS and checks position indication for CVC-520.
o VI.C.l. - IF the rate of power rise can NOT be stopped, THEN perfonn the following actions: Checks WRNI indications to detennine rate of power rise, at o VI.C.1.a. - Trip the Reactor.
1C05. Detennines Reactor trip not o VI.C.l.b. - IMPLEMENT EOP-O, POST TRIP required.
IMMEDIATE ACTIONS.
o VLC.2. - IF, due to dilution, the Reactor approaches Monitors WRNI power, SUR, SDM, criticality below Zero Power Transient Insertion 11M to determine status of criticality Limit, 54A inches on Group 3, THEN perfonn the and determines step is NIA.
following actions ...
o VI.C.3. - IF, due to dilution, the Reactor approaches Monitors WRNI power, SUR, SDM, criticality above the Zero Power Transient Insertion 11M to detennine status of criticality Limit, 54 A inches on Group 3, and detennines step is N/A.
THEN perform the following ...
o VI.CA. - IF count rate is slowly increasing, due to the dilution, THEN perfonn the following actions to Determines step is applicable.
control the count rate:
CUE: CRS directs that CEAs not be o VI.CA.a. - Insert CEAs as necessary.
CUE: After BA Pumps run for ~ 1 minute, CPS start to decrease.
o VI.CA.b. - Borate the RCS as necessary. Detennines step is applicable.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o VLC.4.b.(1) - Shut the VCT MIU valve, Same as element l-CVC-S12-CV.
Same as element Same as element (Must start at least one)
Same as element o VI.C.4.b.(4) - Start CHG PPs as necessary. (Must ensure at least 1 Charging Pump operating)
Sorates until CPS indication on o VI.C.4.b.(S) - WHEN boration is complete, 1COS starts to lower or the dilution THEN stop borating: source has been isolated per step VLD.2.c.
o VLC.4.b.(S)(a) - Stop the SA PPs. Same as element o VLC.4.b.(S)(b) - Shut the BA DIRECT MIU Same as element valve,1-CVC-S14-MOV.
o VLC.4.b.(5)(c) - Stop CHG PPs as desired. Same as element Note to OP-2 specifies RCS Boron sampling, by Plant Chemistry, every 30 minutes during Evaluator: the approach to criticality The STA has determined required SID boron concentration is adequate per NEOP-30l.
CUE:
Chemistry'S latest grab sample indicates current RCS boron concentration is 1590 PPM.
No action required. May elect to continue boration of the RCS, per o VLC.5. - Verify SDM is adequate ...
step VLC.4, until the dilution source is isolated o VLD.l. - Verify correct lineup of the CVCS: Same as element o VI.D.l.a. - Ensure MIU WTR FLO and CONC SA FLO controllers are in MANUAL and 0% Checks FIC-21 OX and Y operating output. mode in manual with output at "0".
Checks CVC-210X and Y indicate o I-FIC-21OX shut.
o I-FIC-210Y
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: When dispatched, ABO reports 12 and 13 IX isolated and 11 IX is in service.
D VI.D.1.b. - Ensure that any CVCS IXs with deborating resin or unborated resin are removed Dispatches ABO to check IX lineup.
from service PER OI-2D, PURIFICATION Determines lineup is correct.
SYSTEM OPERATION.
CUE: When dispatched, ABO reports DW-190 was found shut.
D VI.D.l.c. - Ensure IX FLUSH ISOL valve, Dispatches ABO to verify D W-190 0-DW-190, is shut. is shut.
When dispatched, PO reports Metering Pumps are off. CVC-258, 266 and 338 were CUE:
found shut, eVe-308 was found partially open and has been shut.
Dispatches ABO to perform Steps a, D VLD.2 - Isolate any chemical additions.
b, c, d & e.
D VLD.2.a. - Verify the following Pumps are secured:
Same as element.
D 11 A Metering Pump D 11 B Metering Pump D VLD.2.b. - Verify shut CHEM ADD MTRG SKID Same as element.
OUTLET ISOL VL V, l-CVC-266.
D VLD.2.c. - Verify shut RCMW TO CHG PP Same as element.
SUCT, l-CVC-308.
D VLD.2.d. - Verify shut CHEM ADD SKID &
Same as element.
CHEM ADD TK INLET VLV, l-CVC-258.
D VLD.2.e~ - Verify shut CHEM ADD & MTRG TK Same as element.
COMB DISCH, l-CVC-338.
D VLD.3 - If necessary, notify Plant Chemistry that Same as element.
chemical additions have been secured.
TERMINATING CUE: This JPM is complete when boration takes place to lower count rate and the dilution has been secured. The evaluator is expected to end the JPM.
Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SIM-7 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 Performance Measure FOfm ES-C-I Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. A reactor startup is in progress on Unit-I, OP-2 at step 6.6.G.
- 2. Shutdown CEAs are fully withdrawn
- 3. Regulating group CEAs are being withdrawn per OP-2 (There has been no rod motion for several minutes)
- 4. RCS Boron Concentration after completion last CEA withdrawal was 1690 PPM S. Neutron counts unexpectedly begin to rise (30 CPS over the last five minutes)
- 6. The "SID MON HI" annunciator (l COS, window D-33) alarms
- 7. 11 Purification Ion Exchanger has been in service for three weeks
- 8. You are performing the duties of the Unit-l CRO Initiating Cue:
The CRS directs you to respond to the reactivity excursion per the appropriate procedure. Are there any questions? You may begin.
CALVERT CLIFFS NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-8
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-8 Task
Title:
Perform a normal shutdown, from the Control Room, of the OC DG Task Number: 024.001,024.005 KIA
Reference:
064 A4.07 (3.4, 3.4)
Method of testing:
Simulated Performance: D Actual Performance: I:8J Classroom: D Simulator: I:8J 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 performance measure will be satisfied.
Initial Conditions:
- 1. Both Units are at 100% power
- 3. Testing has been completed.
- 4. You are performing the duties of an extra Licensed Operator.
Initiating Cue:
The Unit-2 CRS directs you to perform a normal shutdown, from the Control Room, of the OC DG, per the appropriate 0 I.
Task Standard:
Removes OC DG from 24 4KV Bus, energizes the 07 4KV Service Bus from site power, and shuts down the OC DG.
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:
Procedures and manuals normally available in the control room General
References:
OI-2IC, OC Diesel Generator Time critical task:
No Validation Time:
15 minutes Simulator Setup:
- 1. Reset to IC-24, both units at 100% power
- 2. Place simulator in RUN.
- 5. Acknowledge all panel and plant computer alarms.
- 6. Ensure the "HORN ON" is selected for annunciators.
- 7. Place in FREEZE.
S. When cued by evaluator, go to RUN.
Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CUE: I Have simulator driver place Simulator in RUN i
TIME START:
iD Identifies OI-2IC, Section 6.12 Step. B as starting I Same as element.
point.
D 6.12.B.1. - IF OC DG is in parallel operation with a Safety Related 4KV Bus, THEN REMOVE OC DG Determines step is applicable.
from the 4KV Bus by performing the following:
CAUTION MW load should NOT be reduced below 0.3 MW to preclude tripping OC DO OUT BKR, 152 I 0703, on reverse power.
D 6.12.B.l.a. - LOWER MW AND KVAR loads concurrently to approximately 0.45 MW AND zero KV ARs PER the following:
D 6.12.B.l.a.(I) - LOWER MW load . Locates and lowers OC DG Speed approximately 1.0 MW using OC DG SPEED Control, 0-CS-0705, while CONTR, 0-CS-0705 [B0254] monitoring OC DG MW load.
D 6.l2.B.1.a.(2) - MAINTAIN 0 to 500 KVARs Locates and lowers OC DG Auto using OC DG AUTO VOLT CONTR, O-CS- Volt Controller, 0-CS-0704, and 0704 AND FIGURE 1, OC DIESEL
- monitors OC DG reactive load GENERATOR ELECTRICAL LIMITS. (KVARs).
D 6.12.B.l.a.(3) - MONITOR the selected 4KV Locates and monitors voltmeter for Bus voltage between 4.1 KV and 4.35 KV.
24 4KV bus.
[B0120]
CUE: Five (5) minute wait period is met.
Continues lowering OC DG MW D 6.l2.B.l.a.(4) - WAIT approximately 5 load and KV ARS OR verifies that minutes, THEN REPEAT Steps l.a.! through
~0.45 MW and zero KV ARS are 1.a.4 until OC DG reaches the desired load.
indicated prior to Step b.
Using table in 01-21 C, operator identifies handswitch, 2-CS-152 2406, and places to TRIP position.
~~~,'H~"~~ Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD CAUTION OC DG OUT BKR, 152-0703, trips on Underfrequency at 59.5 Hz when in the parallel OR transfer modes, unless bypassed.
o 6.12.B.l.c. - VERIFY OC DG frequency AND voltage are stable AND 07 4KV Bus is energized at approximately 60 Hz:
Monitors OC DG voltage 07 4Kv o OC DG FREQUENCY, 0-SI-0701 Bus Volts, and frequency.
o OC DG VOLTS, 0-EI-0701 o 07 4KV BUS VOLTS, 0-EI-0702 Places breaker handswitch, 0-CS-152-0701, to TRIP position.
CUE: Five (5) minute engine cooldown period is met.
o 6.12.B.l.e. - IF OC DG is being stopped, THEN NOTE the time AND BEGIN a 5 minute engine Operator notes time.
cooldown period prior to OC DG stop.
o 6.12.B.l.f. - IF OC DO governor mode change from i transfer mode to parallel mode is desired for loaded Determines step is NIA.
operation ...
NOTE OC DO should be stopped within approximately 5 minutes after load is 0.5 MW OR less.
o 6.12.B.2. - IF OC DO is powering 07 4KV Bus AND a parallel transfer to 07 4KV BUS FDR, 152-0704, Determines step is applicable is desired, THEN PERFORM the following:
o 6.12.B.2.a. - VERIFY 07 4KV BUS TIE, 152- Recognizes breaker opened in 0701, is OPEN. previous step.
Frequency can NOT be adjusted when the governor is in the RESET MODE.
CAUTION OC DO OUT BKR, 152-0703, trips on Underfrequency at 59.5 Hz when in the parallel OR L transfer modes.
Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD o 6.l2.B.2.b. - IF the OC DG governor is in the Determines step is NIA.
RESET MODE ...
o 6.l2.B.2.c. - INSERT the Sync Stick for 07 4KV Same as element.
BUS FDR, 0-CS-152-0704.
o 6.12.B.2.d. - CHECK the Synchroscope AND Sync Same as element.
Lights are operating on 1C 18B.
Same as element.
Same as element.
NOTE OC DG OUT BKR, 152-0703, should be tripped as soon as 07 4KV BUS FDR, 152-0704, is closed.
CAUTION Do NOT exceed 0.5 MW while paralleled with 07 4KV BUS FDR, 152-0704, to preclude tripping the feeder breaker on excess reverse power. [B0248]
Same as element.
Same as element.
6.12.B.2.i. - REMOVE the Sync Stick AND Same as element.
RETURN to Home Base.
NOTE:
OC DG should be stopped within approximately 5 minutes after load is 0.5 MW OR less.
o 6.12.B.3. - IF OC DG is powering 07 4KV Bus AND a dead bus transfer of 07 4KV Bus loads to 07 4KV Determines step is NIA.
BUS FDR, 152-0704, is desired ...
t'erronmalllCe Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD
!0 6.l2.B.4. - CHECK 07 4KV Bus voltage is 4.16KV I Same as element.
(4.1 to 4.35 KV) on 07 4KV BUS VOLTS, 0-EI-0702.
Monitors OC DO voltmeter o 6.12.B.S. - VERIFY OC DO voltage is 4.16KV and adjusts Auto Volt Control, (4.16KV to 4.30KV) on OC DO VOLTS, 0-EI-0701.
0-CS-0704, as necessary.
o 6.12.B.6. - CHECK OC DO frequency is approximately 60 Hz on OC DO FREQUENCY, Same as element.
0-SI-0701.
o 6.12.B.7. - VERIFY IC19C annunciator Locates panel 1C 19C and "OC DO.POTVOLT.FREQ LO" is CLEAR. checks alann window is clear.
When 5 minutes has elapsed depresses OC DO STOP, O-HS-0709, pushbutton.
I0 6.12.B.9. - VERIFY exciter shutdown as indicated by Operator monitors OC DO zero volts on OC DO VOLTS, 0-EI-0701. voltmeter.
I TERMINATING CUE: This JPM is complete when the OC DO has been shutdown. No
. further actions are required. The evaluator is expected to end the JPM.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-8 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:
Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. Both Units are at 100% power
- 3. Testing has been completed.
- 4. You are performing the duties of an extra Licensed Operator.
. Initiating Cue:
I The Unit-2 CRS directs you to perform a normal shutdown, from the Control Room, of the OC DO, per the appropriate OJ.
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-1
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-I Task TitJe: Obtain Safe Shutdown Equipment Then Strip MCC 114R Task Number: 202.098 KJA
Reference:
068 AA1.10 (3.7, 3.9)
Method of Testing:
Simulated Performance: f2J Actual Performance: D Classroom: Simulator: D Plant: f2J 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 performance measure will be satisfied.
Initial Conditions:
- 1. A severe fire has resulted in a Control Room evacuation.
- 2. You are performing the duties of the Unit-l ABO
- 3. You have obtained the Safe Shutdown key ring and equipment from the Safe Shutdown Key and Equipment Lockers.
Initiating Cue:
The CRO at 1C43 has directed you to strip MCC Loads per AOP-9A, Step Y. Are there any questions? You may begin.
Task Standard:
Locates and simulates manual operation of plant components to Strip MCC 114R, per AOP-9A-I.
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:
AOP-9A-l, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Fire General
References:
AOP-9A-l, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Time critical task:
No Validation Time:
20 minutes Simulator Setup:
None
Appendix C Job Performance Measure Form ES-C-I Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START: _ __
CUE: I Provide examinee with a copy of the correct Section/Step of AOP-9A-l o Identifies AOP-9A-l, Step Y, Obtain Safe Shutdown I sarn-e-a-s-el-e-m-e-nt-------;
Equipment Then Strip MCC 114R .
NOTE This procedure has parallel operations assigned to specific watchstations. When a boxed function is completed, it shall be reported to 1C43 and the next boxed function specific to that Operator shall be implemented. Where it is necessary to ensure supporting evolutions are completed before execution of another, a conditional statement is used.
o 1. Obtain designated key ring and equipment Determines step is met based on (including headlamp) at Safe Shutdown Key and Initial Conditions.
Equipment Lockers.
o 2. GO TO MCC 114R in the Auxiliary Building. Same as element CUE: I When operated, all breakers indicated OFF.
NOTE TO EVALUATOR Candidate should determine PPE requirements using the copy of Industrial Safety Manual Chapter 12, Electrical Safety that is staged in the MCC Room.
For Operating circuit breakers with enclosure doors closed (opening and closing) the following are required:
- No Minimum Arc Rating Required for FR Clothing 100% Cotton Long Sleeve Shirt and Pants, OR 100% cotton short sleeve shirt and pants under FR Lab Coat
- Safety Glasses NOTE Chemistry does NOT have to be notified for placing MAIN VENT PARTICULATE/TRITIUM SAMPLE SKID Breaker, 52-11451 in OFF.
CAUTION Do NOT place ANY breakers on the P-Panel to OFF Same as element
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + *= CRITICAL STEP) STANDARD NOTE The following breakers are arranged from left to right, facing MCC.
- 4. Place the following Breakers to on: Same as element i Breaker is in the "ON" position, no breaker position lights are illuminated Positions to ON Positions to ON Positions to ON Positions to ON Positions to ON Positions to ON I
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD EXAMINER NOTE Breaker 52-11427 is labeled "DISTRIBUTION XFMR 114480 - 2081120V" in the plant CUE: Breaker is in the "ON" position, red light is illuminated Positions to ON Same as elementlinfonns examiner
- 4. GO TO the MSIV Room to perfonn Step AC they will proceed to the MSIV Room TERMINATING CUE: This JPM is complete when MCC-114 is stripped per AOP-9A Step IV.Y. No other actions are required. The student is expected to this JPM.
Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: PLANT-1 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT - - - - - - - UN SAT - - - - - - - -
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. A severe fire has resulted in a Control Room evacuation.
- 2. You are performing the duties of the Unit-l ABO
- 3. You have obtained the Safe Shutdown key ring and equipment from the Safe Shutdown Key and Equipment Lockers.
Initiating Cue:
The CRO at 1C43 has directed you to strip MCC Loads per AOP-9A, Step Y. Are there any questions? You may begin.
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR .POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-2
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-2 Task
Title:
Isolate DI Water and Condensate MlU to the SRW and CCW Head Tanks Task Number: 202.066, 202.068 KIA
Reference:
026AAl.05 (3.1, 3.1), 062AA1.05 (3.1, 3.1)
Method of testing:
Simulated Performance: C8J Actual Performance: 0 Classroom: 0 Simulator: 0 Plant: C8J 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 performance measure will be satisfied.
Initial Conditions:
- 1. A severe fire has resulted in a Control Room evacuation.
- 2. You are performing the duties of the Unit-2 TBO
- 3. You have obtained the Safe Shutdown key ring and equipment from the Safe Shutdown Key and Equipment Lockers.
Initiating Cue:
The CRO at 2C43 has directed you to isolate DJ water and Condensate makeup to the Service Water and Component Cooling head tanks per AOP-9A-2, Step CF. Are there any questions?
You may begin.
Task Standard:
Aligns the Fire Main to supply makeup water to the Service Water and Component Cooling head tanks.
I
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:
AOP-9A-2, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Fire Key to Safe Shutdown hose locker General
References:
AOP-9A-2, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Fire Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START: _ __
CUE: Provide examinee with a copy ofthe correct Section/Step of AOP-9A-2 o Identify & locate AOP-9A-2, Step CF, Same as element NOTE Valve 2-CD-154 is located near the Gland Sea) Exhaust Condenser on the Turbine Building 27' Level.
Same as element.
o CF.2. - GO TO the Unit 1 Turbine Building Sample Same as element.
Sink area.
NOTE Valve O-DW-247 is located outside of Unit 1 AFW Pump Room on the South side.
Same as element.
NOTE
. Valve 2-CD-152 is located near the 12' Unit 2 Sample Sink on South side of Stanchion J203.
EXAMINER NOTE When applicant locates AOP-9 Equipment Locker containing required hoses, provide candidate with key to the AOP-9 Equipment Locker. Ask candidate to open the AOP-9 Equipment Locker and point out articles they would acquire.
A fire hose has been connected between HS-12-18 and 2-CD-lS2 Same as element.
Same as element.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Same as element.
Same as element.
CF.9. - GO TO 2C43 to provide additional assistance where needed, for example, to assist the ABO in Containment.
TERMINATING CUE: This JPM is complete when the Fire Main has been aligned as a makeup source for the Service Water and Component Cooling Head Tanks and 2C43 has been notified and instructed to have the ABO restore makeup to the Service Water and Component Cooling Head Tanks. No further actions are required.
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet Verification of Completion Job Performance Measure Number: PLANT-2 Applicant:
NRC Examiner:
Date Perfonned:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet EXAMINEE'S CUE SHEET Initia1 Conditions:
- 1. A severe fire has resulted in a Control Room evacuation.
- 2. You are performing the duties of the Unit-2 TBO
- 3. You have obtained the Safe Shutdown key ring and equipment from the Safe Shutdown Key and Equipment Lockers.
Initiating Cue:
The CRO at 2C43 has directed you to isolate DI water and Condensate makeup to the Service i Water and Component Cooling head tanks per AOP-9A-2, Step CF. Are there any questions?
I You may begin.
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-3
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-3 Task
Title:
Align AFW Pump Speed Control to 1C43 (Alt Path)
Task Number: 202.113 KIA
Reference:
068 AAl.02 (4.3,4.5)
Method of testing:
Simulated Performance: [gJ Actual Performance: D Classroom: D Simulator: D Plant: [gJ 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 performance measure will be satisfied.
Initial Conditions:
- 1. A severe fire has resulted in a control room evacuation.
- 2. AOP-9A, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire, has been implemented.
- 3. The Main turbines and SGFPs have been tripped and condenser makeup has been isolated.
- 4. The controllers on 1C43 have been initialized.
- 5. You are performing the duties of the Unit-l TBO.
Initiating Cue:
You have been notified by lC43 to Align AFW Pump Speed Control to lC43 per AOP-9A, Step AD.
Task Standard:
Locally aligns AFW Pump Speed Control to lC43 and resets the Throttle/Stop Valve for 11
. AFWPump i i
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:
AOP-9A, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Fire Unit-I)
Key to the Unit-l Safe Shutdown Equipment Locker General
References:
AOP-9A, Control Room Evacuation And Safe Shutdown Due To A Severe Control Room Fire (Unit-I)
Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START:
EXAMINER NOTE Ask the candidate to demonstrate how they would obtain the designated key ring and equipment at the Safe Shutdown Equipment and Key Lockers for the applicable Unit.
DO NOT allow the candidate to open the ADV enclosure or the Safe Shutdown Key Locker.
Once Safe Shutdown Equipment Locker is identified, provide candidate with key to the
. CUE: Safe Shutdown Equipment Locker. Ask candidate to open the Safe Shutdown Equipment Locker and point out articles they would acquire.
Candidate proceeds to the Unit-l 45' Switchgear Room and identifies the Safe Shutdown Equipment and o Obtain the designated key ring and equipment at the Key Lockers Safe Shutdown Equipment and Key Lockers. Key ring is obtained from the Key Locker. Procedure and tools are obtained from the Equipment Locker CUE: Once candidate identifies copy of AOP-9 in the Safe Shutdown Equipment Locker, provide the candidate with a copy of the applicable portion of AOP-9A.
EXAMINER NOTE Opening AFW pump speed control enclosures will cause AF AS status panel alarm in the control room. DO NOT allow the examinee to open the enclosure. Have the examinee describe the transfer process using the provided picture(s).
- 1. WHEN notified to align AFW Pump Speed Determines step is applicable.
Control to 1C43, THEN:
Locates Handvalve station and rotates valve to "Position 2" Locates Handvalve station and rotates valve to "Position 2" Loeates keys witch and inserts key.
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD Rotates key to DISABLE position Locates keyswitch and inserts key.
Rotates key to DISABLE position BEGIN ALTERNATE PATH
- CUE: The Trip Solenoid for 11 AFW Pp has actuated.
o 6. IF the in-service AFW Pump Trip Solenoid has actuated, THEN reset the ThrottletStop Determines step is NtA.
Valve.
Same as element Same as element END ALTERNATE PATH CUE: lC43 is notified that AFW Speed Control is aligned to lC43.
o 7. NotifY lC43 that AFW Speed Control is Calls 1C43 to report AFW Speed aligned to 1C43. Control is aligned to lC43.
- 8. GO TO Unit 1 SRW Pump Room to I Transits to the U-I SRW Pump Room or informs evaluator of need to proceed to the perform Step AE. U-I SRW Pump Room.
TERMINATING CUE: This JPM is complete when AOP-9A Step AD is complete. No further actions are required. The operator is expected to end the JPM per their Initiating CUE.
Appendix C Job Performance Measure Form ES-C-l
. Worksheet Verification of Completion Job Performance Measure Number: PLANT-3 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ ill~SAT ______________
Examiner's Signature and Date:
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet EXAMINEE'S CUE SHEET Initial Conditions:
- 1. A severe fire has resulted in a control room evacuation.
- 2. AOP-9A, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire, has been implemented.
- 3. The Main turbines and SGFPs have been tripped and condenser makeup has been isolated.
- 4. The controllers on 1C43 have been initialized.
- 5. You are perfonning the duties of the Unit-1 TBO.
Initiating Cue:
IYOll have been directed by the CRO at I C43 to align Auxiliary Feedwater Pump Speed Control to 1C43 per AOP-9A, Step AD.
Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #:1 OP- Test #: CCNPP 2012 Examiners: Operators:
Initial Conditions: Unit-1 is at 65% Power with a core burn up of 10,885 MWDIMTU. Unit-2 is in Mode 5. 12 CS pump is OOS for repairs. 23 Auxiliary Feedwater Pump is out of service for overhaul of the coupling (expected back in three shifts).
Turnover: Place 12 SGFP in parallel operation with 11 SGFP and return power to 100%.
i Event Malfunction # Event Type* Event Description' None N -BOP/SRO Aligns 12 SGFP for parallel operation will SGFP I-ATC 2 rcs026 01 Failure ofLT-llOX T-SRO R-ATC 3 None Commences power escalation N - BOP/SRO C - BOP/SRO 4 srw003 01 11 Service Water Pump Bkr Failure T-SRO 5 cd005 01 C - BOP/SRO Condensate Booster Pump trip Condensate Booster Pump discharge header rupture cd008, (25%). Reactor will not trip automatically or with I 6 M-ALL rps005, rps006 Rx Trip pushbuttons. CEDM MG Sets must be de- .
i energized to trip the reactor.
7 Various C-ALL Loss of All Feedwater I Once-Thru-Cooling
- (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
'~:-"-:~:~'-__:_i ' _ _,<<(__ ______ __ -~:~::: "','"',, - _->- ",/ :-<": !: - :~ ~>/<_:0~-_ -~ :i~ ,:._ ,i, "_ ,._ '-:';-,,-. . ," _ : ;":< - ->:\~--__~_ _ c. _, _, ,', " __ :-:C:<~_ - . -_:-;~ ~": ". ":>-:\:;:::0>-- '*-~"-~'~ ~ : ?~:;- - :,'.:~:;: t: : ?;: -:_ ',', '" _' _ -: : i:!i!: : ~r- '- - :
12~~'~~~nei§.i.~~s.*.~ED~~G~~~s~ithin.1 minute QfaIl,;existingl~.f!f.lR1,QrJ:ripCo~d~tio~:~ . * , :.
,i*~s R*~rts<Rj~ctivity.ControIcQmplete. (report not*critical). 'NlA if:RBSsetpoint nof3'r~a¢liea.
- '
- ;<,~ <~;>-:> ':~:-., <~~~>": .,' ~----:-,-:', ",:\:; _:' :'.:i:,;:.:::",,<:/~;:,_:_ ': ': ',': ,_:_';'\,,> :->: ,-/:':-' ': " " ,: "", -<--:>__ ,",. - --'< '_.--- -':-<-.." - . -:- - - --'-:-'-:r:/::: _ :,:,~
,~;;'2'."~:ri~;~~\~~l1io~t~~ommenCing RCS ~ooldown~;,...
-'_co:::
3;' ~tJliti~t~s.9ICC yyben bothS/GJevels are ~ -350" or Tcowrises >~5°F uncQntr~ll~b1Yimust be cOJDple#c~dpriprio CETtempenltures reaching 560°F)
Appendix D Scenario Outline Form ES-D-l OP-Test #: 2012 Scenario #: 1 SCENARIO OVERVIEW PARALLEL SGFP/COND HDR RUPTURE/ATWSILOSS OF ALL FEEDWATER Unit-l is operating at 65% power. 12 CS pump is OOS for repairs. 23 Auxiliary Feedwater Pump is out of service for overhaul of the coupling (expected back in three shifts). Instructions for the shift are to place 12 SGFP in parallel operation with 11 SGFP and return power to 100%.
First, the crew will use 01 -12A, Section 6.12, to align 12 SGFP for parallel operation with 11 SGFP.
While the CRO is paralleling 12 SGFP to 11 SGFP, Pressurizer Pressure transmitter LT -11OX will fail low. The RO will respond per the Alarm Manual. The crew may use the NO-I-200, Common Tap Analysis (AU. 12) to aid in determining affected equipment. Applicable Tech Spec LCOs will be identified.
Following parallel of 12 SGFP, the crew will begin raising reactor power in accordance with the supplied reactivity plan. The power ascension will continue until the Lead Examiner is satisfied he has seen the crew manipulate the plant controls to the extent desired.
Once the power increase has begun, 11 SRW Pump Breaker will trip. The crew will implement AOP-7B, Loss of Service Water, which will direct their actions in protecting plant equipment and aligning and starting 13 SR W Pp Next, a trip of 11 Condensate Booster Pump occurs. The crew will implement AOP-3G, Malfunction of Main Feedwater System. When the standby Condensate Booster Pump starts a Condensate header rupture results in a loss of feed requiringlresulting in a reactor trip. The reactor fails to automatically and manually trip. The crew will be required to deenergize the CEDM Motor Generator Sets to trip the reactor.
Following the reactor trip, 11 AFW Pump will trip as a result of a steam leak in the AFW Pump Room. 13 AFW Pump will not start, resulting in a total loss of all feed water. The crew is expected to enter EOP-O, Post-Trip Immediate Actions, and transition to EOP-3, Loss of All Feedwater.
In EOP-3, the crew will secure the Reactor Coolant Pumps and commence a rapid cooldown to less than 465°F while attempting to restore AFW flow. The crew will initiate Once-Thru Cooling, prior to CET temperatures reaching 560°F, due to inability to align a source of Main or Auxiliary Feedwater for S/G heat removal.
When the crew has initiated Once-Through-Cooling, 23 AFW Pump will be made available to restore feedwater flow to a S/G. Once Auxiliary Feedwater flow has been established to one (l)
S/O, and a positive level trend identified, the scenario will be terminated
Appendix D Scenario Outline Form ES-D-l INSTRUCTOR SCENARIO INFORMATION
- - 1. Reset to IC-I7
- 2. Perfonn "Switch Check"
_ _ 3. Place simulator in CONTINUE, advance charts and clear alann display.
- - 4. Place simulator in FREEZE
_ _ 5. Enter Triggers
- 6. Enter Malfunctions
_ _ a. Auto Reactor Trip Relay Failure (ATWS): rps005 at time zero.
_ _ b. Manual Reactor Trip Failure: rps006 at time zero.
_ _ c. 13 AFW Pump Trip: afw005 at time zero.
_ _ d. Pressurizer Level Channell-LT-IlOX Fails Low: rcs026_01, to LOW, on Event 1.
_ _ e. 11 SRW Pp Breaker failure: snv003_010n Event 2.
_ _ f. 11 Condensate Booster Pp Breaker failure: cd005_01 on Event 3.
_~ g. Condensate Booster Pp Common Disch Hdr Rupture: cd008 from 0% to 50% over a 2 min ramp time on Event 4.
_ _ h. 11 AFW Pump Trip: afw001_01 on Event 5.
_ _ i. Fire System Alann: fireOOI on Event 5.
- 7. Enter Panel Overrides:
a.IC03 Alarm window C-53 "Steam Line Drain Panel": PIC03- C53- LTON to ON, on Event 4, with a I minute delay time.
_ _ b.IC09 AIm window H-30 "12 CS Pp SIAS Blocked/Auto Start":
PIC09- H30- LTON to OFF at time zero.
_ _ c.ICI7 Alann window L-2 "Electric Fire Pp Operating": PICI7_L02_LTON to ON, on Event 5.
_ _ d.ICI7 Alann window L-6 "Diesel Fire Pump Operating": PICI7_L06_LTON to ON, on Event 5.
Appendix 0 Scenario Outline Form ES-D-l
- 8. Enter Remote Functions I Administrative:
- a. 12 CS Pp Breaker racked out 152-1407_B, to racked out, at time zero
- b. Place 12 CS Pp in <<PTL" and yellow tag HS
- c. Place protected equipment tag on 11 CS Pp HS
- d. Place red dot on lC09 alarm window H-30
- f. Have note made up stating "Window SP-9, U-I AFW PP RM 603, on 1C24 B, is in alarm'" ready to stage when directed by Step 15.c, Instructions for Booth Operator
- 9. Ensure all magnetic plaques are in place and correct for the scenario
- 10. Select "Clock" time
- 11. Acknowledge all alarms and ensure "Horn On" selected
- 12. Place in RUN
_ _ 13. Ensure 12 SGFP is in standby at 2600 - 2800 RPM per OI-12A (drain MOVs open and speed control in HIC Manual)
- 14. Dilute CEAs in to approximately 80 inches
- 15. Brief the Crew:
I .
load at 10,885 MWD/MTU
- 1. Present plant conditions: Unit 2 is in Mode 5.
- 2. Power history: 65% for the previous 5 days.
i
- 12 CS pump OOS for last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for bearing
- 3. Equipment out of repair lAS 3.6.6.A i service:
- 23 Aux Feed Pump is out of service for overhaul of the coupling expected back in three shifts.
I
- 4. Abnormal conditions: None
- 5. Surveillances due: None Parallel 12 SGFP with 11 SGFP and return the unit to
- 6. Instructions for shift:
full power
- 16. Allow crew 3-5 minutes to acclimate themselves with their positions.
Appendix D Scenario Outline Form ES-D-l
_ _ 17. Instructions for the Booth Operator:
- a. Activate Event 1, PZR level channel failure, on Lead Examiner's cue.
- b. Activate Event 2, 11 SRW Pp Breaker failure, after Tech Specs are addressed for the Pressurizer Level Control Channel failure, on Lead Examiner's cue (should occur sometime after power increase has been started).
- c. Activate Event 3, 11 Cond Booster Pp Failure, on lead examiner's cue.
_ _ d. After the Cond Booster Pp Failure has been dealt with, ensure Booth Operator has staged a conspicuous note stating "Window SP-9, U-l AFW PP RM 603, on lC24B, is in alarm".
_ _ e. Approximately 1 minute after the standby CBP picks up or is started activate Event 4, Cond Booster Pp Disch Hdr Rupture.
- f. Approximately 2 minutes after inserting Event 4, call the control room on the radio and report "This is the U-l TBO, there's a leak on the Condensate Header with water spraying everywhere. It looks like the pipe will come apart any second. The leak appears to be on the Condensate Booster Pump common discharge header."
--g. After the condenser Pit Hi Level alarm is received, modify the Condensate Booster Pp Common Disch Hdr Rupture leak rate, cd008, from 25% to 75% with no ramp time ifMFW is not secured after the reactor trip.
- h. Once OTCC has been initiated call, as the OWC, and report actual work had not commenced on 23 AFW Pump. Tags have been cleared and 23 AFW Pump is aligned and ready for use.
Appendix D Scenario Outline Form ES-D-l Responses to Crew Requests If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.
Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.
- 1. IIC investigate failure of Pressurizer Level Acknowledge request.
Controller, 1- LT-IIOX.
Acknowledge request. Use RF l-CVC 256 to shut l-CVC-256, useRF l-CVC
- 2. ABO line up for Direct Makeup to the RCS 254 to open l-CVC-2S4. 3 minutes later report Direct LIU has been completed.
(Booth Operator - use camera or Thunderview to obtain instrument reading from 1C03 indicator l-LI-4404).
- 4. TBO investigate Hotwell level locally 3 minutes later report a local level indication value that is consistent with l-LI-4404 Acknowledge request. 5 minutes later
- 5. OWC have Electricians investigate trip of 11 report 11 SRW Pp Breaker tripped on SRWPp.
overcurrent Acknowledge request. After 3 minutes Activate Event 6 to align 13 SRW Pp to
- 6. TBO align 13 SRW Pp to II SRW subsystem 11 SRW subsystem. 1 minute later report 13 SRW Pp is aligned to 11 SRW subsystem Acknowledge request. 3 minutes later actuate Event 7 to reset and restart IA
- 7. TBO reset IA/P A Compressor high temperature and PA systems. 1 minute later report trips IA/PA Compressor high temperature trips have been reset Acknowledge request. After 1-2
- 8. TBO investigate cause of trip of 11 Condensate minutes make TBO report outlined in Booster Pump. Instructions to Booth Operator, Step 15.f.
Appendix D Scenario Outline Form ES-D-l After several minutes report Condensate
- 9. PWS/PPO/TBO report on size, location and Booster pump common discharge header whether or not leak can be isolated. piping is cracked more than halfway around and is unisolable (at power).
After three minutes report unable to access AFW Pump room due to steam in the AFW Pump Room and sprinkler is
- 10. Operator andlor maintenance report status of actuated AFW Pumps 11, 12, and 13. Report 13 AFW Pump breaker appears to have tripped on overcurrent. There are black marks coming out of the motor terminal connection box.
- 11. Unit 2 inquiry about availability of23 AFW Tagged out for motor change out - job Pump. duration is one day.
After 15 minutes, report CBP discharge
- 12. PWS isolate condensate booster pump common and SGFP suction isolation valves have discharge header leak.
been shut and the leak is isolated.
Acknowledge request. 3 minutes later use RF SIAS-A6 to actuate SIAS A6,
cabinets Report SIAS A6 and SIAS B6 have been manually actuated.
Acknowledge request. 15 minutes later, report steam has dissipated and sprinkler isolation has been shut. Report the
- 14. TBO check AFW Pump Room now that steam is steam leak was a result of 11 AFW isolated (If crew shuts MS-4070 and 4071).
Pump Mud Drum drains being left open.
I-MS-225 and I-MS-228 are stuck open, perhaps thermally bound.
Acknowledge request. 5 minutes later use RF I-MS-I09 to isolate Main Steam to 11 AFW Pump. Report Main Steam
- 15. TBO Isolate Main Steam to 11 AFW Pump and to 11 AFW Pump has been isolated reset 12 AFW Pump using I-MS-I09 and that attempts to reset 12 AFW Pp have been unsuccessful.
Appendix D Scenario Outline Form ES-D-l
- 16. Machine Shop determine repair of AFW mud Acknowledge request.
drum drain.
Acknowledge request. Report U-2
- 17. U-2 CRS shut the Motor Driven Train AFW Train Motor Driven Train AFW Train Block Block valves valves have been shut Acknowledge request. Use RF 2-CV 4550 to open the U-2 to U-l AFW
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 1 Page 1 of 18 Event
Description:
Parallel 12 SGFP w/llSGFP Event Type: N - BOP/SRO i Time Position Applicant's Actions or Behavior Places 12 SGFP in OCS Manual:
- Ensures 12 SGFP HIC controller is in manual.
- Adjusts 12 SGFPT SPD CONTR, I-HIC-4517 until the XFER PERM indicator is lit on the OCS.
- When the XFER PERM indicator illuminates, depresses the HIC pushbutton on the OCS.
BOP Returns the BIAS setting for 12 SGFP to 5.0.
BOP Places 12 SGFP Miniflow Controller, I-FIC-4485 in manual.
Raises 12 SGFP speed to match the MANUAL signal with the AUTO BOP signal.
BOP Adjusts the BIAS on 11 SGFP as necessary I BOP PLACE 12 SGFPT SPD CONTR, I-HIC-4517 in AUTO.
Monitors SGFP for proper automatic operation by checking: SGFP BOP speed, S/G level, SGFP discharge pressure, steam flow and feed flow Slowly shuts 12 SGFP Miniflow using I-FIC-4485, until valve is shut or BOP miniflow controller is at setpoint while adjusting the BIAS to the ideal setting of 5.0 on 11 SGFP Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test 2012 Scenario #: I Event #: 1 (continued) Page 2 of 18 Event
Description:
Parallel 12 SGFP w/llSGFP Event Type: N - BOP/SRO Position Applicant's Actions or Behavior BOP Places 12 SGFP Miniflow Controller, I-FIC-4485 in AUTO.
BOP Places 12 SGFP DRNS handswitch, I-HS-5092 in CLOSE.
BOP When drains indicate shut, places handswitch, in OFF.
Places desired SGFP in LEAD by adjusting the SGFP BIAS pots to BOP maintain the desired SGFP speed between 75 and 125 RPM greater than the other SGFP speed.
Examiner notes:
Event concludes when the standby SGFP is paralleled with the operating SGFP NOTE TO EXAMINER Cue Booth Operator to insert next malfunction when desired. Consideration should be given to where the crew is in their effort to raise power
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 2 Page 3 of 18 Event
Description:
LIC-llOX fails low Event Type: I - ATC, T - SRO Time Position Applicant's Actions or Behavior I
ATCIBOP Recognizes multiple alarms and reports to SRO ATC Determines l-LI e-l1 OX has failed.
Directs RO to shift Pressurizer level control channel and Pzr Heater Low SRO Level Cut-off selector switch to receive their inputs from I-LIC-II OY SRO Refers to NO-I-200 for common tap instrumentation and applicable T.S.
ATe Shifts Pressurizer level control channel to l-LIe-llOY using I-HS-I10.
Shifts Pzr Heater Low Level Cut-off selector switch, I-HS-l 00-3, to the ATC Channel "Y" position.
ATC/BOP References Alarm Manual to verify correct response SRO Identifies T.S. LCO 3.3.1 O.A as applicable SRO Directs E&C to investigate failure ofLT-llOX.
Examiner notes:
Event concludes when Pressurizer Level and Heater control hand switches have been aligned to the unaffected Pressurizer Level Controller.
IfSRO's understanding ofT.S. implicatious is not clearly observable, follow-up questiouing may be required upon completion of the scenario.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 3 Page 4 ofl8 Event
Description:
Power increase Event Type: R - ATC, N - BOP/SRO Time Position Applicant's Actions or Behavior SRO Direct power escalation to 100% power SRO Contacts Chemistry to sample the RCS per CP-204 Add DI water to RCS using 01-2B section 6.2 via direct lineup:
- Calculate DI volume, independently verify calculation
- Adjust MIU Water Flow Integrator for desired DI flow rate
- Adjust MIU Batching Switch FQIS-21OX for desired DI volume
- Place M/U Flow Controller in Auto
- Place M/U Mode Selector Switch to Dilute Adjust Main Turbine load using Load set Handswitch to maintain TCOLD BOP/ATC within 2° F of program Withdraw GP 5 CEA's lAW 01-42
- Select Group 5 pushbutton on CEDS Panel ATC
- Select Manual Sequential on CEDS Panel
- Withdraw CEA's using the Raise/Lower switch
- When withdraw complete, wait 5 seconds before selecting Off on CEDS Panel Examiner notes:
Event concludes when power and load have been raised sufficiently to satisfy the Lead Examiner and the LEAD Examiner directs insertion of the next malfunction.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 4 Page 5 of 18 I
Event
Description:
11 SRW Pump Failure Event Type: C - BOP/SRO, T - SRO Time Position Applicant's Actions or Behavior ATC/BOP Recognizes multiple alarms and reports to SRO ATC/BOP Determines 11 SRW Pump has tripped, reports to SRO SRO Directs crew to implement AOP-7B, Loss of Service Water BOP Coordinates with SO-TSO, reduces Main Generator MV ARS to zero.
BOP Places 11 SRW Pp in pull-to-Iock BOP Directs TBO to mechanically align 13 SRW Pp to 11 SRW Header BOP Starts 13 SRW Pump Evaluates Tech Specs. Detennines T.S. LCO 3.7.6.B is applicable, with SRO a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time, due to both SRW Pumps being powered from 14 4KV Bus.
Examiner notes:
Event concludes when 13 SRW Pp is started and Tech Specs have been evaluated.
If SRO's understanding of T .S. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
NOTE TO EXAMINER Hang prepared note "Window SP-9, U-l AFW PP RM 603, on lC24B, is in alarm" on 1C24B, Fire Alann Panel, prior to initiation of the next malfunction NOTE TO EXAMINER Cue Booth Operator to insert next malfunction when desired
AppendixD Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 5 Page 6 of 18 Event
Description:
Condensate Booster Pp trip Event Type: C - BOP/SRO I ' T'Jl'i' me* I IPosition Applicant's Actions or Behavior Acknowledges alarm. Diagnoses the loss of 11 Condensate Booster BOP Pump.
Dispatches TBO/PWS to investigate loss of 11 Condensate Booster BOP Pump.
SRO Implements AOP-3G, Malfunction of Main Feedwater System.
BOP ! Starts 13 Condensate Booster Pump.
SRO Requests E/C to investigate trip of 11 Condensate Booster Pump Examiner notes:
Event concludes once a backup Condensate Booster Pp is started or upon report of Condensate header rupture,
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event#:6 Page 7 of 18 Event
Description:
CBP trip/Cond Hdr rupturelReactor trip Event Type: M - ALL I
rro' Position Applicant's Actions or Behavior Upon report of Condensate header rupture, refers to AOP-3G for actions BOP/SRO for feedwater rupture.
Directs reactor trip when it is detennined the Condensate header rupture SRO will cause a loss of nonnal feedwater.
Attempts to trip the reactor by depressing the manual Reactor Trip ATC pushbuttons located on 1COS Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 6 (continued) Page 8 of 18 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Applicant's Actions or Behavior Performs Reactivity Control Safety Function Depresses one set of manual Reactor Trip pushbuttons on lC05.
ATC Checks reactor tripped using NI power indications on lC05.
- Notes reactor did not trip. Reports taking alternate actions to trip the reactor.
Verifies all CEAs fully inserted Verifies DI Water Makeup is secured Checks 11 & 12 RC makeup Pumps secured on 1CO?
ATC Checks VCT M/U l-CVC-512-CV is shut on 1CO?
If aligned for direct makeup to RCS then shuts RWT Charging Pump Suction I-CVC-504-MOV on IC07 Reports Reactivity Control Safety Function is Complete Examiner Notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 6 (continued) Page 9 of 18 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL I Time Position Applicant's Actions or Behavior Takes actions to secure feedwater in response to Condensate rupture per AOP-3G.
- 1. Trips both Steam Generator Feed Pumps
- 2. Secures Condensate Booster Pumps, Condensate Pumps & Heater BOP Drain Pumps by placing their handswitches in pull-to-Iock
- 3. Shuts the S/G Feedwater Isolation Valves
- 4. Starts an AFW Pp
- a. IF 13 AFW Pp is started, notes trip, reports to CRS and starts Steam driven AFW Pp Performs Turbine Trip
- 1. Checks Reactor tripped then:
- 2. Ensures turbine has tripped:
- a. Depresses both Turbine Trip Pushbuttons on I C02
- b. Checks Main Turbine stop Valves shut on MK VI screen
- c. Checks Turbine Speed drops on MK VI screen BOP d. Checks Turbine Generator Output Breakers open
- 11 GEN BUS BKR O-CS-552-22 on lCOI
- 11 GEN TIE BKR O-CS-552-23 on 1COl
- e. Checks Generator Field Breaker open on 1CO 1
- f. Checks Generator Exciter Field breaker open on 1CO 1
- 3. Ensures MSR 2nd Stage Steam source Valves are shut Reports Turbine Trip Complete Examiner notes:
Appendix D Scenario OutJine Form ES-D-2 II Op-Test #: 2012 Scenario #: I Event #: 6 (continued) Page 10 of 18 i Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Time Position Applicant's Actions or Behavior Performs Vital Auxiliaries Safety Function
- Checks ALL 125V DC BUS VOLTS greater than 105 volts on IC24 (all are energized):
D 11 D 12 D 21 D 22 BOP
- Checks at least THREE 120V AC Vital Buses are energized on lC24:
D 11 D 12 D 21 D 22
- Checks EITHER 1Y09 OR 1Yl 0 energized on 1C24. (both are energized)
- Verifies Component Cooling Flow to the RCP's Reports Vital Auxiliaries Safety Function is Complete Performs Pressure & Inventory Control Safety Function including verifying alt actions
- 1. Checks Pressurizer pressure stabilizes between 1850 PSIA & 2300 PSIA, trending to 2250 PSIA.
- 2. Checks Pressurizer level stabilizes between 80 & 180 inches, ATC trending to 160 inches.
- 3. Verifies CVCS letdown isolations CVC-5I5 and 516 shut and all Charging Pumps operating on 1C06
- 4. Checks subcooling is greater than 30°F by PAMs display on 1C05 Reports Press & Inventory Control Safety Function is Complete Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 6 (continued) Page 11 of 18 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL
~ .. Applicant's Actions or Behavior Performs Pressure & Inventory Control Safety Function including verifying alt actions
- 5. Checks Pressurizer pressure stabilizes between 1850 PSJA & 2300 PSIA, trending to 2250 PSIA.
- 6. Checks Pressurizer level stabilizes between 80 & 180 inches, ATC trending to 160 inches.
- 7. Verifies CVCS letdown isolations CVC-515 and 516 shut and all Charging Pumps operating on 1C06
- 8. Checks subcooling is greater than 30°F by PAMs display on 1COS Reports Press & Inventory Control Safety Function is Complete Performs Core & RCS Heat Removal Safety Function
- 1. Checks TBV's controlling S/G pressure 850-920 PSIA on 1C03 and TCOLD 525-535°F on IC05.
- 2. Verifies at least one S/G available for controlled heat removal
- a. Checks S/G level (-) 170" to (+) 50" on 1C03
- Notes trip of 11 and 13 AFW Pps (no flow)
- Contacts TBO to investigate 11 & 13 AFW Pps
- Reports condition to CRS 0
- c. TCOLD> 525 F
- 3. Checks RCP operating red lights illuminated on 1C06
! 4. Checks T HOT minus TCOLD is less than 10°F by checking indicators on lC06 I Reports Core & RCS Heat Removal Safety Function Cannot Be Met
- due to no source of feedwater currently available.
Examiner notes:
Appendix D Scenario OutJine Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 6 (continued) Page 12 of 18 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL 1I'T'1.'.*Jme Position Applicant's Actions or Behavior Performs Containment Environment Safety Function including verifying alternate actions
- 1. Checks Containment Pressure < 0.7 PSIG using narrow range pressure on 1ClO.
BOP 2. Checks Containment Temperature < 120°F using cavity and dome temperature indicators on 1C 1O.
- 3. Checks Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend Reports Containment Environment Safety Function is Complete Perform Rad Levds External to Containment Safety Function
- 1. Check the following RMS alarms are clear with no unexplained rise:
- V-I Wide Range Noble Gas Monitor BOP
- V-I Condenser Off Gas @ IC22
- V-I S/G Blowdown @ IC22
- V-I Main Vent Gaseous @ lC22 Reports Rad Levels External to Containment Safety Function Complete Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 6 (continued) Page 13 of 18 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL e Position Applicant's Actions or Behavior Performs EOP-O brief
- Ensures all are attentive
- Reviews Safety Functions not met
- Informs crew of ATWS (depending on timing)
- Reviews Safety system Actuations
- Chance of AFAS (depending on timing)
- Solicits Input Concludes the brief directing the crew to continue to monitor Safety Functions while the event is diagnosed.
Refers to EOP-O flowchart
- Knowing the Heat Removal Safety cannot be met due to SRO unavailability of Main and Auxiliary Feedwater, determines EOP-3, Loss of All Feedwater is the correct Optimal Recovery Procedure Implements EOP-3, Loss of All Feedwater Examiner notes:
Event conclusion is entry into EOP-3
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event#:7 Page 14 of 18 Event
Description:
EOP-3, Loss of All Feedwater Event Type: C - ALL Time Position Applicant's Actions or Behavior I uRO Conducts EOP-3 entry brief and assigns block steps to RO and CRO BOP Verifies S/G BID valves shut Commences RCS Boration
- Shuts VCT MIU valve CVC-512-CV
- Opens BA Direct M/U valve CVC-514-MOV ATC
- Opens BAST Gravity Feed valves CVC-50S & 509-CV
- Verifies M/U Mode Selector Switch HS-210 in manual
- Starts all BA pumps
- Records boration time & BAST levels Commences C/D to <465° F.
- Opens TBV's (~ 17%) or ADV's (100%) to establish a rapid RCS cooldown to TcoLD < 465°F while maintaining RCS cooldown <
lOO°F in anyone hour, subcooling between 30 and 140°F based on BOP CETs and Pzr level between 50 & 180 inches
- Blocks SGIS when Block Permitted received
- Blocks SIAS when Block Permitted received Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 7 (continued) Page 15 of 18 Event
Description:
EOP-3, Loss of All F'eedwater Event Type: C - ALL Position Applicant's Actions or Behavior Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 1 Event #: 7 (continued) Page 16 of 18 Event
Description:
EOP-3, Loss of All Feedwater Event Type: C - ALL Time Position Applicant's Actions or Behavior Directs performance of Block Step K when informed of capability to SRO restore AFW. Determines S/G with the highest remaining level should be fed.
o (11 S/G) I-FW-4516-MOV o (12 S/G) I-FW-4517-MOV
- b. Shuts the S/G AFW BLOCK valves for the S/G to be isolated by placing the handswitches in SHUT:
II S/G o I-AFW-4520-CV o l-AFW-4521-CV o l-AFW-4522-CV o l-AFW-4523-CV 12 S/G o I-AFW-4530-CV o I-AFW-4531-CV o l-AFW-4532-CV o I-AFW-4S33-CV CRO
- c. Shuts the ADV for the S/G to be isolated using the Hand Transfer Valves on the West wall of the Unit 1 45 ft Switchgear Room as follows:
(l) Verifies the ADV controller at I C43 0 (12 S/G) I-MS-104 is set at 0% output:
o (11 ADV) I-HC-4056A o (12 ADV) I-HC-4056B (2) Aligns the Hand Transfer Valves to IC43 (POSITION 2):
11 S/G o I-HV -3938A o I-HV-3938B 12 S/G o I-HY*3939A o I-HV-3939B II Examiner notes:
Appendix D Scenario Outline Form ES-D-2 lOP-Test #: 2012 Scenario #: 1 Event #: 7 (continued) Page 17 of 18
. Event
Description:
EOP-3, Loss of All Feedwater Event Type: C - ALL Time Position Applicant's Actions or Behavior Directs performance of portions of Block Step H applicable to restoring SRO feedwater flow to a S/G when informed of availability of23 AFW Pp Establishes AFW flow with 23 AFW PP as follows:
(1) Shuts the Unit 2 Motor Train S/G AFW BLOCK valves by placing the handswitches in SHUT:
21 S/G o 2-AFW-4522-CV o 2-AFW-4523-CV 22 S/G o 2-AFW-4532-CV o 2-AFW-4533-CV CRO (2) Opens the U-2 TO U-I XCONN valve, 2-AFW-4550-CV.
(3) Establishes AFW flow with 23 AFW PP as follows:
(a) Shuts the Unit 1 S/G FLOW CONTR valves:
11 S/G o l-AFW-4S25-CV 12 S/G o l-AFW-4535-CV (b) Starts 23 AFW PP by placing its handswitch in START.
Examiner notes:
Appendix D Scenario Outline Form ES-D-2 IOp-Test#:2012 Scenario #: 1 Event #: 7 (continued) Page 18 of 18 !
. Event
Description:
EOP-3, Loss of All F'eedwater Event Type: C - ALL II 'fillne r l"P~osition Applicant's Actions or Behavior Establishes feed to the selected S/G.
- a. Verifies the TURB BYP valves AND the ADVs are shut.
- b. IF AFW has been restored PER step H, THEN perfonns the following actions:
(1) Adjusts S/G FLOW CONTR valves for the S/G to be fed to approximately 150 GPM:
1] S/G 0 1-AFW-4511-CV CRO 0 l-AFW-4525-CV 12 S/G 0 l-AFW-4512-CV 0 l-AFW-4535-CV (2) WHEN S/G level response is observed OR continuous feed has been maintained for at least 5 minutes, THEN feed rate may be slowly raised while maintaining the following:
o Gradual rise in S/G level o S/G level trending towards 0 inches ORCS cooldown rate less than 100°F in anyone hour Examiner notes:
The scenario will end when AFW flow has been restored with an observed rise in S/G level After scenario ends ask SRO for ERPIP call. The correct Emergency Action Level declaration for this scenario is:
- 1. UE per A. U. 7 .1.1, Loss of all normal and auxiliary feed such that cool down to allow main feed booster pump injection is initiated
- 3. ALERT per A.A.7.1.2, Emergency Director Judgment for a "Loss of all normal and auxiliary feed such that Once Through Core Cooling (OTCC) is initiated"
Appendix D Scenario Outline Form ES-D-l Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 2 OP-Test #: CCNPP 2012 Examiners: Operators:
Initial Conditions: Unit-l is at 100% power. Core Burnup is 17,885 MWDIlVITU. Unit-2 is in Mode 5.
Turnover: 12 AFW Pump is OOS due to a governor problem (has been OOS for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is due back by end of shift). The SMECO tie breaker is open. 14 CAR is OOS due to a failed motor bearing. The 2A DG was removed from service yesterday for scheduled maintenance. 11 ADV is wisping a small amount of steam. Instructions to the crew are to
- maintain full power.
Event # Malfunction # Event Type* Event Description 1 cvcs003 01 C -ATC/SRO 11 Charging Pump coupling failure 2 rcs023 01 I-ATC PT-IOOX fails high C -BOP/SRO 3 swOOl 02 Saltwater Leak T- SRO R-ATC 4 tg024_01 C - BOP/SRO MTCV-1 Fails to mid-position T-SRO 5 swyd002 M-ALL Loss Of Offsite Power resulting in a reactor trip 6 dg002_02 C-ALL No 4KV SR Busses resulting in Station Blackout afw004 01 7 afw004-02 C-ALL AF AS "A" & "B" failure
- (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
Appendix D Scenario Outline Form ES-D-1 OP-Test #: 2012 Scenario #: 2 SCENARIO OVERVIEW SALTWATER LEAK/STATION BLACKOUT Initial Conditions: Unit-l is at 100% power. Core Burnup is 17,885 MWDIMTU. 12 AFW Pump is out-of-service due to a governor problem (has been OOS for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is due back by end of shift). 14 CAR is OOS due to a failed motor bearing. The 2A DO was removed from service yesterday due to a lube oil cooler leak. 11 ADV is wisping a small amount of stearn.
Unit-2 is in Mode 5. Instructions to the crew are to maintain full power.
First, 11 Charging Pump coupling will fail. The crew will respond per the Alarm Manual. A coupling failure is not specifically addressed by the Alarm Manual. The crew will determine the failure by observation of Charging Pump performance indication (flow, pressure, amps).
Next, a failure of the in-service Pressurizer Pressure Control Channel, I-PIC-I00X, will occur.
The crew will implement Alarm Manual procedures and will shift Pressurizer Pressure control to the alternate channel, I-PIC-IOOY. The crew may use the NO-I-200, Common Tap Analysis (Att. 12) to aid in determining affected equipment. There are no applicable Tech Spec LCOs.
Next, a saltwater header leak will occur in the Service Water Pump Room, requiring implementation of AOP-7 A, Loss of Saltwater Cooling. The crew will be required to reduce Main Generator reactive load to 0 MV AR and will stop the saltwater leak prior to the loss of Service Water Pumps on high room level. The 1B DO will be removed from service and the Service Water headers will be cross-connected. Applicable Tech Spec LCOs will be identified.
Next, MTCV-l will fail to mid-position. The crew will respond per AOP-7F, Loss of Load and AOP-7E Main Turbine Malfunctions. The crew may be required to insert CEAs to control reactor power during stabilization of the plant.
Next, a loss of offsite power occurs resulting in a reactor trip. EOP-O will be implemented. The lA DO will trip upon starting. Indication of voltage on 12 125V DC bus will fail to zero on the trip. The OC DO Output Breaker will fail to close. AF AS will fail to actuate when SO levels reach -170" and AFW flow will have to be initiated manually.
The crew will implement EOP-7, Station Blackout. They will establish an RCS heat sink and restore power to 11 or 14 4KV Bus.
When the crew has restored power to a Vital 4KV Bus, the scenario will end.
Appendix D Scenario Outline Form ES-D-l INSTRUCTOR SCENARIO INFORMATION
-- 1. Reset to IC-14
- - 2. Perform "Switch Check"
_ _ 3. Place simulator in CONTINUE, advance charts and clear alarm display.
- 4. Place simulator in FREEZE
-- 5. Enter Triggers
- - a. None
- - 6. Enter Malfunctions
_ _ a. 12 AFW Pump OOS: afw001_02 at time zero
- - b. AFAS A Failure to Actuate: afw004 01 at time zero
- - c. AF AS B Failure to Actuate: afw004 02 at time zero
_ _ d. 2A DO OOS: dg001_01 at time zero
_ _ e. 11 Charging Pump coupling failure: cvcs003_01 on Event 1
_ _ f. Pressurizer Pressure control channel input I-PT-IOOY: rcs023_02, to HIGH, on Event 2
_ _ g. Saltwater System Leak: sWOOl_02, from 3 to 30%, over a 5 minute ramp time, on Event 3
_ _ h. IB DO Failure: dgOOl_02 on Event 4
_ _ i. MTCV-l Fails mid-position: tg024_01 to on Event 5
° %, with a 5 minute ramp time,
_ _ j. Loss of Offsite Power: swyd002 on Event 6
_ _ k. IA DO Failure: dg002_02 on Event 7
-- 7. Enter Panel Overrides:
_ _ a. 12 AFW Pump trip HIS red light: PIC04_1STP3988_LTRED to OFF at time zero
_ _ b. 12 AFW Pump trip HIS white light: PIC04_1STP3988_LTWHI to OFF at time zero
_ _ c. 12 125 VDC Bus Voltage indication: PIC24A_12_MT to ° on Event 5
- - d. 07 4KV Bus Breaker: O-CS-152-0701 to TRIP at time zero
Appendix D Scenario Outline Form ES-D-l
- 8. Enter Remote Functions / Administrative:
- a. Caution Tag 12 AFW Pump Trip/Throttle Valve (1-MS-3988) as tripped.
- c. SMECO Tie Breaker: 252-2301 to OPEN (ensure SMECO Tie Breaker labeling on panels is correct)
- d. Place an off normal tag on panel indication for SMECO Tie Breaker 252 2301.
_ _ g. OC DG to 21 4KV Bus Disconnect: 189-2106 to CLOSED at time zero
- h. Place the remaining 06 breaker handswitches (152-1106, 152-1406 & 152 2406) in PTL.
- 1. Place the appropriate off normal tags on the 06 breakers.
_ _ J. Place a protected equipment green tag on 2B DG.
- k. Place an off normal tag on 11 ADV.
- 9. Select "Clock" time.
- 10. Acknowledge all alarms and ensure "Hom On" selected
- 11. Place in RUN.
- 12. Brief the Crew:
100% power at EOC (17,885 MWD/MTU). Unit 2 is in
- 1. Present plant conditions: Mode 5
- 2. Power history: 100% for the last 256 days
- 12 AFW Pump due to governor problem (OOS for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, back by end of shift)
- 3. Equipment out of
- SMECO Tie Breaker 252-2301 is open for substation work
- 4. Abnormal conditions: 11 ADV is wisping a small amount of steam.
- 5. Surveillances due: None
- 6. Instructions for shift: Maintain 100% reactor power
- 13. Allow crew 3-5 minutes to acclimate themselves with their positions.
Appendix D Scenario Outline Form ES-D-1
_ _ 14. Instructions for the Booth Operator:
_ _ a. Activate Event 1, 11 Charging Pp coupling failure, on Lead Examiner's cue
_ _ b.Activate Event 2, PZR Pressure Control channel failure, on Lead Examiner's cue.
_ _ c. Activate Event 3, SW leak, on Lead Examiner's cue. It will take approximately 4 minutes for the SRW PP RM hi level alarm to come in.
Remove malfunction swOOl 02 after the alarm comes in to allow the crew time to isolate the leak. If 12 SW Pump is not secured OR, 12A and B SRWHXs have not been isolated within 15 minutes of receiving the SR W Pump Room hi level alarm, then trip all SRW Pumps and 13 AFW Pump.
_ _ d. Activate Event 4, 1B DO failure, when directed to isolate starting air to the 1B DO Q! when 1B DO has been running for ten minutes with no cooling.
_ _ e. Activate Event 5, MTCV -1 fails closed and 12 125V DC Bus indication fails to zero, on Lead Examiner's cue.
_ _ f. Activate Event 6, loss of offsite power, when the plant is stabilized following the closure of MTCV-1 (prior to the crew commencing a rapid downpower to
< 50%), on Lead Examiner's cue.
_ _ g. Activate Event 7, lA DO failure, when the RO reports Reactivity Control complete Q! on Lead Examiner's cue.
Appendix D Scenario Outline Form ES-D-l RESPONSES TO CREW REQUESTS If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.
Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.
After 3 minutes, report 11 Charging Pp
- 1. ABO investigate 11 Charging Pump coupling has separated
- 2. Investigate failure of J-PIC-l OOY. Acknowledge request After 2 minutes, report NW Turbine Bldg
- 3. TBO investigate 1T22 alarm.
sump is overflowing.
After approximately 1 minute, report the leak is on 12 SW Hdr return from 12A and B SRW HXs, between I-SW-5212 and 1-SW-5153-CVs, and is isolable. Water is spraying on north wall and SRW Pp Rm level is rising. Potential exists for damage to SRW/AFW Pps if leak is not brought under control.
- 4. TBOIPWS attempt to locate and/or isolate Report leak is greatly reduced when 12A and the saltwater leak. B SRW HXs are isolated or 12 SW Pp is secured. Inform Control Room there is a large crack in the piping. Modify malf sw001_02 from 30% to 10% with no ramp time.
Report leak stopped if SW Pp is secured and rupture has been isolated per AOP-7 A, Step V.DA. and delete malfunction swOOl 02 from the schedule.
When requested, activate Event 4 with 3 minute delay (l B DO start failure) then
- 5. OSO isolate start air to IB DO. report start air has been isolated per AOP 7A, Attachment 1.
Report completion of task to Control Room.
Appendix D Scenario Outline Form ES-D-l Activate Event 8 system lineup for SRW_HX12_0FF to position valves as
Report completion of task to Control Room.
After 3 minutes, report MTCV -1 slowly
- 7. TBO investigate problem with MTCV-l closing with no signs ofEHC leakage.
Acknowledge request. Report an east coast
- 8. ESO investigate loss of offsite power.
grid disturbance.
No determination yet, will let you know
- 9. ESO estimate time until power is restored.
when determination is made.
After 2 minutes, position as directed using remote functions:
- 10. Take local control of ADVs.
- I-MS-3938-HV for 11 ADV
- I-MS-3939-HV for 12 ADV Report completion of task to Control Room.
After 5 minutes report electrical assistance is requested. After 15 minutes electricians
report troubleshooting is in progress. Engine will not be returned to service in near future.
When directed Activate Event 9 on 10 minute delay to shut:
- I-FW-128 to close 12 S/G MFRV
- 12. Locally shut FW isoL FW-128 and 131. Isolation Valve
- I-FW-131 to close 11 S/G MFRV Isolation Valve Report completion of task to Control Room.
- 13. Align N2 to AFW control valves and control After approximately 2 minutes, report AFW discharge pressure locally. completion of each task to Control Room.
- 14. Report on SMECO availability. Report SMECO not available.
Appendix D Scenario Outline Form ES-D-l After 3 minutes Activate Event 10 or 11 to close the requested OC DO disconnect after modifYing remote function 189-2106 to OPEN.
- Activate Event 10: 189-1106 to
- 15. PWSIPO align OC DO disconnects. CLOSED to align the OC DO to 11 4KV Bus, or
- Activate Event 11: 189-1406 to CLOSED to align the OC DO to 14 4KV Bus Report completion of task to Control Room.
Acknowledge request. After 5 minutes, request permission to locally shut breaker.
- 16. Electricians troubleshoot OC DO output When authorized to do so, modify panel breaker 152-0701. override PICI9C_KF0701 to shut 152 0701.
, Report completion of task to Control Room.
When requested wait 2 minutes and activate Event 15 or 16 to use remote function ISY09 to tie 1Y09 and 1Yl 0 (based on 4KV bus reenergized with OC DO).
Contact the Control Room just prior to
- 17. Tie 1Y09 and 1YIO. activating event key to inform them you are tying lY09 and lYlO as follows:
- Activate Event 15 to tie 1Y09 to lYlO with lY09 supplying, or
- Activate Event 16 to tie 1Y09 to 1Yl 0 with 1Yl 0 supplying.
Appendix D Scenario Outline Form ES-D-1 When requested activate Event 12 or 13:
Activate Event 12 with 5 minute delay to tie MCC-114 to MCC-I04 (MCC-I04 feeding):
- 1. Opens MCC-114 Fdr Bkr using remote function 52-11401
- 2. Closes the Tie Bkr using remote function 52-10420
- 18. Cross tie MCC-l 04 to MCC-114.
Activate Event 13 with 5 minute delay to tie MCC-I04 to MCC-114 (MCC-114 feeding):
- 1. Opens MCC-104 Fdr Bkr using remote function 52-10401
- 2. Closes the Tie Bkr using remote function 52-10420 Report completion of task to Control Room.
When requested, activate Event 14 with 5
- 19. Shut l-CC-284 (CCW supply to minute delay to shut the CCW supply to Containment manual isolation). Containment manual isolation 1-CC-2S4.
Report completion of task to Control Room.
- 20. Align N2 and control 11 AFW Pp speed Acknowledge request. Five minutes later locally report completion of task to Control Room.
- Use RF 1-CD-410 to isolate Condensate to
- 21. Shut l-CD-41O the SIG BID Hx. 5 minutes later report completion of task to Control Room.
Use RF 252-1106 to open 13KV SITE PWR
- 22. Open 252-1106 BKR 252-1106. 5 minutes later report completion of task to Control Room.
Appendix D Scenario Outline Form ES-D-2 II Op-Test #: 2012 Scenario #: 2 Event #: 1 Page 1 of 15 II Event
Description:
11 Charging Pp coupling failure Event Type: C - ATC/SRO Time Position Applicant's Actions or Behavior ATC/BOP Recognizes alarm(s) and reports to SRO ATC Determines 11 Charging Pumps is not pumping forward SRO Directs RO to shift Charging Pumps ATC Start 12 or 13 Charging Pump and places 11 Charging Pump in PTL ATC/BOP References Alarm Manual to verify correct response May refer to TRM, (lNC 15.1.2) for Boration Flowpaths - Operating, to I
SRO determine applicability. No action is required.
SRO Directs OWC to gather resources to investigate failure of 11 Chg Pp.
Examiner notes:
I Event concludes when a standby Charging Pump is started.
If SRO's understanding of Technical Requirements Manual applicability is not clearly i observable, follow-up questioning may be required upon completion of the scenario.
I NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, PIC-IOOY failure, when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 2 Page 2 of 15 Event
Description:
PIC-IOOY fails high Event Type: 1- ATC
'Y" Position Applicant's Actions or Behavior ATC/BOP Recognizes multiple alarms and reports to SRO ATC Determines I-PIC-I00Y has failed high.
May direct RO to shift Pressurizer Pressure control channel selector SRO switch to place I-PIC-IOOX in service Shifts Pressurizer Pressure control channel to I-PIC-lOOX using I-HS ATC 100. May do so prior to CRS directing.
ATC/BOP References Alarm Manual to verify correct response SRO Refers to NO-I-200 for common tap instrumentation and applicable T~
SRO Directs E&C to investigate failure of I-PIC-lOOY.
Refers to Tech Specs. If RCS pressure decreases to less than 2200 PSIA, SRO determines Tech Spec 3.4.1 limit for Pressurizer pressure has been exceeded and enters LCO 3.4.1.A.
Examiner notes:
Event concludes when Pressurizer Pressure control hand switch has been aligned to the unaffected Pressurizer Pressure controller. If SRO's understanding ofT.S. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 12 SW Header Leak, when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event 3 Page 3 of 15 Event
Description:
12 Saltwater Header Leak Event Type: C - BOP/SRO, T - SRO Time Position Applicant's Actions or Behavior Acknowledges 1T22 and SRW Pump Room Hi Level alarms. Refers BOP to the Alarm Manual and dispatches operators to investigate.
SRO Directs implementation of AOP-7 A, Loss of Saltwater.
Monitors Main Generator temperatures. Trips reactor if any Main ATC/SRO Generator temperature limits are exceeded and cooling flow is not being restored.
Reduces Main Generator MVARs to zero and monitors Main BOP Generator temperatures.
BOP Verifies 11 CC HX is in service Removes the 1B DG from service by shutting the Air Start Header BOP Isolation valves per AOP-7 A, Attachment (1)
Crossconnects turbine building SRW subsystems with 11 SRW Hdr BOP supplying.
Refers to Tech Specs:
- Enters LCO 3.5.2.A
- Enters LCOs 3.6.6.A & C SRO
- Enters LCO 3.7.5.A
- Enters LCO 3.7.6.B
- Enters LCO 3.7.7.A
- Enters LCOs 3.8.1.A & C Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 3 (continued) Page 4 of 15 Event
Description:
12 Saltwater Header Leak Event Type: C - BOP/SRO, T - SRO Iii: Position Applicant's Actions or Behavior SRO Directs owe to have maintenance investigate the SW Header rupture Examiner notes:
Event concludes when MTCV-1 begins to fail closed.
If SRO's understanding of T.s. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, failure of MTCV-l, when desired
AppendixD Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 4 Page 5 of 15 I
Event
Description:
MTCV-1 fails closed Event Type: R - ATC, C - SROIBOP Time Position Applicant's Actions or Behavior ATC Notes TcoLD rising and turbine load lowering. Informs SRO I
BOP/ATC Determines MTCV -1 is slowly closing i Directs implementation of AOP-7F, Loss of Load. Implements AOP SRO 7E, Main Turbine Malfunctions, in parallel Verifies proper operation of the TBVs. Adjusts I-PIC-4056 to BOP maintain S/G pressure and TCOLD Inserts CEAs as necessary while maintaining the CEAs above the ATC Transient Insertion Limit.
ATC Borates RCS as necessary Verifies Pressurizer Level and Pressure control systems are functioning ATC to return parameters to normal range BOP Ensures Feed Reg system is restoring S/G/ levels to zero inches BOP Dispatches OSO to verify S/G Safety valves are seated Adjusts TBV auto-setpoint to slightly above Main Steam Header BOP pressure but not less than 830 PSIA Determines turbine load must be reduced to < 50% within one hour.
SRO Directs crew to perform a rapid downpower to < 50% per OP-3 Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event#:4 Page 6 of IS Event
Description:
MTCV-1 fails closed Event Type: R - ATC, C - SRO/BOP II;; Position Applicant's Actions or Behavior Commences Rapid Power Reduction, as directed by AOP-7E, per OP 3, Normal Power Operation
- 2. Borates the RCS
- a. Opens the RWT CHG PP Suct Valve, l-CVC-S04-MOV.
- b. Shuts the VCT Outlet Valve, l-CVC-SOI-MOV.
Adjusts turbine load to maintain TCOLD within SOF of program, not to RO/CRO exceed 548°F, using manual adjust switch, l-CS-80, or using auto on Mk6 Turbine Control Computer flat panel display on 1C02 Insert CEA's as needed by selecting Manual Sequential control at 1COS and operating the In-Hold-Out switch to the insert direction.
RO CEA's should be operated in ;::;:10-1S inch increments not to exceed transient insertion limits.
Refers to Tech Specs. Determines Tech Spec 3.4.1 limit for TCOLD has SRO been exceeded. Enters LCO 3.4. 1. A.
Examiner notes:
Event concludes when a Loss of Off-site power occurs reSUlting in a reactor trip.
If SRO's understanding of T.S. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 5 Page 7 of 15 Event
Description:
LOOP I Rx trip I EOP-O Event Type: M - ALL Position Applicant's Actions or Behavior SRO Announces reactor trip and directs crew to implement EOP-O Performs Reactivity Control Safety Function Depress Reactor trip pushbuttons on 1C05 and perform EOP-O, Reactivity Control
- Depress Manual Reactor Trip Pushbutton on 1C05
- Check Reactor tripped using NI power indications on 1C05
- Verify DI Water Makeup is secured
- Check 11 & 12 RC makeup Pumps secured on 1C07
- Check VCT MIU I-CVC-512-CV is shut on IC07
- If aligned for direct makeup to RCS then shut R WT Charging Pump Suction l-CVC-504-MOV on 1C07 Reports Reactivity Control Safety Function Complete.
Examiners notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 5 (continued) Page 8 of 15 Event
Description:
LOOP / Rx trip / EOP-O Event Type: M - ALL
~,
~ JUlio: Position Applicant's Actions or Behavior Performs Turbine Trip
- Checks Reactor tripped then:
- Depresses both Turbine Trip Pushbuttons on 1C02
- Checks Main Turbine stop Valves shut on MK VI screen
- Checks Turbine Speed drops on MK VI screen
- Checks Turbine Generator Output Breakers open BOP
- 11 GEN BUS BKR O-CS-552-22 on ICOI
- 11 GEN TIE BKR O-CS-552-23 on ICOI
- Checks Generator Field Breaker open on 1COl
- Checks Generator Exciter Field breaker open on 1CO 1
- Ensures MSR 2nd Stage Steam source Valves are shut Takes Alternate Action to shut both MSIV s due to loss of power to the MSR 2nd Stage Steam Source MOVs. Reports Turbine Trip Complete (or Cannot Be Met due to loss of power effects).
Examiner's notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 5 (continued) Page 9 of 15 Event
Description:
LOOP / Rx trip / EOP-O Event Type: M - ALL Position Applicant's Actions or Behavior Performs Vital Auxiliaries Safety Function
- Checks 11 or 14 4KV bus energized. (initially notes 11 4KV Bus energized. Notes trip of IA DO resulting in 11 and 14 4KV Buses being deenergized)
- Checks ALL 125V DC BUS VOLTS greater than 105 volts on lC24: (notes failed voltmeter for 11 125V DC Bus)
D 11 12 D 21 D 22
- Checks at least THREE 120V AC Vital Buses are energized on lC24:
BOP D 11 [J 12 D 21 22
- Checks EITHER lY09 OR lYI0 energized on lC24. (initially notes 1Yl 0 is energized. Notes trip of lA DO resulting in 1Y09 and 1YlO being de-energized)
Takes Alternate Actions to align and start the OC DG. Notes OC DO output breaker fails to shut when attempted. Reports Vital Auxiliaries Safety Function Cannot Be Met due to 11 and 14 4KV busses being deenergized.
NOTE TO EXAMINER If the IB DO was not isolated during the loss of 12 SW Header, it will start and continue to run for approximately 10 minutes before tripping out on high temperature due. If this occurs, the initial call for Vital Auxiliaries will be "Met" Examiner notes:
Appendix 0 Scenario Outline Form ES-O-2 Op-Test #: 2012 Scenario #: 2 Event #: 5 (continued) Page 10 of15 Event
Description:
LOOP I Rx trip I EOP-O Event Type: M - ALL Position Applicant's Actions or Behavior Performs Pressure & Inventory Control Safety Function. including alternate actions
- Checks Pressurizer pressure at 1C06. Determines that it is trending to 2250 PSIA.
- Checks Pressurizer level at 1C06. Determines it is trending to 160 inches.
- Checks RCS subcooling is greater than 30°F.
Reports Press & Inventory Control Safety Function Complete Performs Core & RCS Heat Removal Safety Function
- Directs ABO to manually open ADVs or aligns ADV control to 1C43 and operates ADV s to control S/G pressure 850-920 PSIA and TCOLD 525-535°F.
- Checks S/G level (-) 170" to (+) 50" on 1C03 BOP
- Checks T HOT minus T COLD is less than 10°F by checking indicators on 1C06 (notes RCPs are de-energized)
Reports Core & RCS Heat Removal Safety Function Cannot Be Met due to RCPs not running.
Examiner's notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 5 (continued) Page 11 of 15 Event
Description:
LOOP I Rx trip I EOP-O Event Type: M - ALL Position Applicant's Actions or Behavior Performs Containment Environment Safety Function
- Checks Containment Pressure < 0.7 PSIG using narrow range pressure on IClO.
- Checks Containment Temperature < 120°F using cavity and dome BOP temperature indicators on 1C 1O.
- Checks Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend Reports Containment Environment Safety Function Cannot Be Met due to loss of power effects Perform Rad Levels External to Containment Safety Function
- Check the following RMS alarms are clear with no unexplained rise:
- U-I Wide Range Noble Gas Monitor
- U-I Condenser Off Gas @ IC22 BOP
- U-I S/G Blowdown @ I C22
- U-I Main Vent Gaseous @ lC22 Takes alt action to secure BID. Reports Rad Levels External to Containment Safety Function CANNOT BE MET due to loss of power effects Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event #: 5 (continued) Page 12 of 15 Event
Description:
LOOP / Rx trip / EOP-O Event Type: M - ALL Position Applicant's Actions or Behavior Perform EOP-O brief
- Ensures all are attentive
- Reviews Safety Functions not met
- RC not met due to loss of power effects
- V A not met not met due to loss of power effects
- HR not met due to loss of power effects
- RLEC not met not met due to loss of power effects
- Reviews Safety system Actuations
- D/V
- Chance of AFAS (depending on timing)
- Solicits Input Concludes the brief directing the crew to continue to monitor Safety Functions while the event is diagnosed.
Refers to EOP-O flowchart
- Reactivity Control not met due to loss of power effects
- Vital Auxiliaries not met not met due to loss of power effects
- Containment Environment not met not met due to loss of power effects
- Radiation Levels External to Containment not met not met due to loss of power effects Recognizes a SBO is in progress and implements EOP-7 Examiner notes:
Event conclusion is implementation of EOP-7, Station Blackout
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 2 Event#:6 Page 13 of 15 Event
Description:
EOP-7 imp1ementation Event Type: C - ALL Position Applicant's Actions or Behavior BOP Shuts both MSIV s (if not shut in EOP-O)
Shuts S/G BID valves, I-BD-4010-CV, I-BD-4011-CV, BOP I-BD-4012-CV, I-BD-4013-CV Shuts Letdown Containment Isolation valves l-CVC-515-cv and ATC l-CVC-S16-CV Maintains an RCP Bleedoff flowpath:
- Verifies Rep BleedoffRV isolation, I-CVC-S07, open ATC
- Shuts Rep BleedoffIsolation valves l-CVC-SOS-CV and I-CVC-S06-CV
- Opens 11 RCDT Drain to the Cntmt floor, l-RCW-42S8-SV.
ATC Shuts RCS Sample Isolation valve, I-PS-5464-CV.
Verifies Reactor Vessel and Pressurizer Vent valves are shut:
- l-RC-I03-SV ATC
- l-RC-104-SV
- l-RC-I05-SV
Event 7
Appendix D Scenario Outline Form ES-D-2 Examiner notes:
Op-Test #: 2012 Scenario #: 2 Event #: 6 (continued) Page 14 of 15 Event
Description:
EOP-7 implementation Event Type: C - ALL Secures the Main Feedwater System:
- Trips Both SGFPs
- Places all COND BSTR PPs in PULL TO LOCK.
- Places ALL COND PPs in PULL TO LOCK.
- Places BOTH HTR DRN PPs in PULL TO LOCK.
- Protects against blowdown related waterhammer by verifying the S/G BID valves are shut and directing 11 BID H/X be manually isolated Verifies the Turbine EMERG OIL PP, EMERG H2 SEAL OIL PP and BOP SGFP EMERG OIL PPs are operating:
BOP Shuts CCW Containment Supply isolation l-CC-3832-CV Aligns the electrical system for power restoration by opening or BOP verifying open selected 13 KV and 4KV breakers (steps IV.H.l thru IV.H.30fEOP-7 Places 4KV Bus LOCI/SD Sequencer Manual Initiate Keyswitches for BOP 11 and 14 4KV Busses in on
Appendix D Scenario Outline Form ES-D-2 Examiner notes:
The scenario will terminate when power is restored in EOP-7 Op-Test #: 2012 Scenario #: 2 Event #: 6 (continued) Page 15 of 15 Event
Description:
EOP-7 implementation Event Type: C - ALL After scenario ends ask SRO for ERPIP call. The correct Emergency Action Level declaration for this scenario is:
- 1. UNUSUAL EVENT, per A.U.6.4.3, in Event 3, due to potential to lose SR equipment in the SRW Pp Room if actions are not taken or if the leakrate is not being kept up with by the floor drains
- 2. ALERT, per A.A.6.4.6, in Event 3, if the crew fails to secure the leak and the SRW Pumps and AFW Pump are lost.
- 3. ALERT, per H.A.2.1.2, briefly in Event 5/6 (prior to the loss of the lA DG)
- 4. SITE AREA EMERGENCY, per H.S.2.1.3, in Event 5/6, for loss of all AC power to BOTH 4KV vital buses on Unit-l for >15 minutes.
Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #:3 OP-Test #: CCNPP 2012 Examiners: Operators:
Initial Conditions: Unit-1 is at 100% with a core burnup of 10,885 MWDIMTU. Unit-2 is in Mode 5.
Turnover: 11 4 KV Bus alternate feed is tagged out for breaker PMs. The crew is instructed to maintain 100% power.
Event # Maifunctiull ent Type* Event Description C-RO 1 rcs027 01 PORV-4021eakby T-SRO C - BOP/SRO 2 cntmOOI 01 11 Containment Air Cooler (CAC) trips T-SRO 3 ms015 I -ALL ADV Controller, 1-HIC-4056, fails in automatic R-ATC msOOI 02 11 S/G Tube leak (0 - 65 GPM over 2 minutes) 4 C - BOP/SRO Downpower Reduce T AVE to less than 53TF T-SRO 5 ms002 02 M-ALL 11 S/G Tube rupture - one tube 6 afwOOI 01 C - BOP/SRO 11 AFW Pp trip I 11 4KV Bus loss
- (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
Appendix D Scenario Outline Form ES-D-l OP-Test #: 2012 Scenario #: 3 SCENARIO OVERVIEW STEAM GENERATOR TUBE RUPTURE Initial Conditions: Unit-I is at 100% with a core burnup of 10,885 MWD/MTU. Unit-2 is in Mode 5. PORV-402 is isolated due to leakby and 11 4 KV Bus alternate feed is tagged out for breaker PMs.
PORV-402 will start leaking by with the leakrate ramping from 0% to 5% over a 5 minute period. The crew will implement the Alarm response procedure for Control Room panellCl9, Window "E-Ol ", which will direct them to refer to the appropriate Technical Specification(s) and isolate the leaking PORV by closing the Block Valve, l-RC-403-MOV.
II Containment Air Cooler (CAC) will trip off. The crew will implement the Alarm response procedure for Control Room panel 1C 19, Window "R-04", which will direct them to refer to the appropriate Technical Specification(s) and utilize alternate equipment (start 13 CAC) as necessary.
Next, the ADV Controller, I-HIC-4056, will fail to a 100% output signal causing both ADVs to open. The crew will implement AOP-7K, Overcooling Event In Mode One or Two, which will direct them to take manual control of I-HIC-4056 and close the Atmospheric Dump Valves.
Next, 11 S/G will begin to experience tube leakage ramping in from 0 GPM to 65 GPM over a two minute period. The crew will respond using AOP-2A, Excessive Reactor Coolant Leakage, and will reduce power to reduce TAvE to less than 53TF at which point the reactor will be tripped. EOP-O, Post-Trip Immediate Actions will be implemented During EOP-O, 11 AFW Pump will trip when it is started, the S/G tube leak will increase to a rupture of 1 S/G tube and 11 4KV Bus normal feeder will be accidentally tripped. The 1A DG will start but not load due to an MJ switch sticking resulting in a loss of 11 4KV Bus. 11 AFW Pump will trip on overspeed when started requiring aligning 12 AFW for service or restoring 11 4KV Bus to service and using 13 AFW Pump.
The crew is expected to implement EOP-6. Ifplant conditions degrade or the crew is unsure of the diagnosis it is acceptable for them to enter EOP-8 directly from EOP-O. IfEOP-8 is entered all critical tasks still apply unless individual tasks are invalidated by the exam team.
The scenario will end when 11 S/G has been isolated and RCS depressurization has been commenced.
Appendix 0 Scenario Outline Form ES-D-l Instructor scenario information
-- L Reset to IC-13
- - 2. Perform "Switch Check"
- - 3. Place simulator in CONTINUE, advance charts and clear alarm display.
- 4. Place simulator in FREEZE
_ _ 5. Enter Triggers
- - a. CEA 01 on Bottom as Event 4
- 6. Enter Malfunctions
_ _ a. PORV-4021eakage: rcs027_01 from 0% to 5% over 5 minutes on Event 11
- b. 11 CAe failure: cntmOOl 01 on Event 1
_ _ c. I-HIC-4056 (ADV Controller) fails in auto: ms015 to 100% on Event 2
_ _ d. 11 S/G tube leak: ms001_01 ramp from Event 3
° to 65 GPM over 2 minutes on
_ _ e. 11 SG tube rupture: ms002_01 at 1 tube on Event 4
_ _ f. 11 AFW Pump trip: afw001_01 on Event 5
- 7. Enter Panel Overrides:
- - a. 11 4 KV Bus normal feeder breaker: P1C18 KF1115 to TRIP on Event 4
- - b. IA DG output breaker: PIC18A_KF1703 in PTL at time zero.
_ _ c. lA DG output breaker green light: P1C18A_KF1703_LTGRN to ON at time zero.
- 8. Enter Remote Functions I Administrative:
- - a. Tie 1Y09 to 1YIO: lSY09 to TO lY10 on Event 6
- - b. Shift 11 ADV to IC43: I-MS-3938-HV to 1C43 on Event 7
- - c. Tie MCC-114 to MCC-104:
_ _ I. MCC-114 Fdr Bkr: 52-11401 to OPEN with a delay of3 minutes on Event 8.
_ _ 2. MCC Tie 104R to 114R Interlock: 52-10420 to CLOSED, with a delay of 3 minutes 30 seconds on Event 8
- d. Caution tag Breaker 152-1101 in PTL.
_ _ e. Line up 13 Chg Pp to 14 Bus: "SystemLineUp\CVCS_chgpp13_bus14.sch" on Event 9
_ _ f. 12 AFW Pp reset: I-MS-3988 to 1.0 on Event 10
- 9. Select "Clock" time.
_ _ 10. Acknowledge all alarms and ensure "Hom On" selected
-- 11. Place in RUN.
Appendix D Scenario Outline Form ES-D-1
- 12. Brief the Crew:
- 1. Present plant conditions: 100% load at MOC 8,400 MWD/MTU
- 2. Power history: 100% power for previous 180 days i
- 3. Equipment out of 152-1101 (11 Bus Alt Feeder) OOS for maintenance serVIce:
I
- 4. Abnormal conditions: None
- 5. Surveillances due: None
- 6. Instructions for shift: Maintain 100% power.
- 13. Allow crew 3-5 minutes to acclimate themselves with their positions.
~_ 14. Instructions for the Booth Operator:
- - b. Activate Event 1, 11 CAC failure, on Lead Examiners' cue.
_ _ c. Activate Event 2, I-HIC-4056 failure, (AD V Controller), on Lead Examiners' cue.
- d. Activate Event 3, 11 S/G Tube leak, on Lead Examiners' cue.
- e. When the reactor trips, verify Event 4 activates (SGTR, 11 4KV Bus loss),
then delete Event 3.
_ _ g. Delete the override for 11 4KV Bus normal feeder breaker (P1C18_KF1115) from the schedule before the crew attempts to reenergize the bus.
Appendix D Scenario Outline Form ES-D-l Responses to Crew Requests If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.
Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.
- 1. OWC contact EM I Systems Engineering to Acknowledge request investigate PORV-4021eakage After 3 minutes report breaker was
- 2. TBO investigate loss of 11 CAC found tripped on overcurrent.
- 3. OWC contact EM to investigate loss of 11 CAC Acknowledge request After 15 minutes report activity present
- 4. Chemistry sample both S/Gs for activity.
in 11 S/G and none in 12 S/G.
Technicians mistakenly opened 11 4KV Bus Normal feeder breaker. After 15 minutes report "looks like a problem with MJ switch on Breaker 1703 (1 A
- 5. OWC contact EM to investigate loss of 11 4 KV Output Breaker), should be able to use bus, and failure of the lA DG Output Breaker, normal or alternate feeder to re-energize 152-1703, to close. bus".
Delete the override for 11 4KV Bus normal feeder breaker (PIC18_KFll15) from the schedule before the crew attempts to reenergize the bus.
After 2-3 minutes Activate Event 7 to
- 6. TBO shift 11112 ADV control to lC43. shift 11 ADV control to 1C43.
After 3 minutes Activate Event 6 to tie
- 7. PWS Tie 1Y09 to 1YlO.
1Y09 to 1Y 10 witll 1YlO supplying.
Acknowledge and Activate Event 8 to open MCC-114 feeder and shut MCC tie
- 8. PWS Tie MCC 114 to 104. (occurs after 3 minute delay). Inform the control room when the task is completed.
After 3 minutes Activate Event 9 to align 13 Charging Pp to 14 Bus. Inform
- 9. Align 13 Charging pump to 14 480 V bus. the control room when the task is completed.
Appendix D Scenario Outline Form ES-D-1 After 3 minutes initiate Event 10 to reset
After 3 minutes use remote functions
- 11. Manually open 11 & 12 ADVs. 1-MS-3938-CVand I-MS-3939-CV to position valve as requested.
- 12. Verify no stearn from safeties on Aux Building After 2-3 minutes report no stearn roof. corning from any safeties.
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 1 Page 1 of 15 I Event
Description:
PORV-402leakby Event Type: C - BOP/SRO Time Position Applicant's Actions or Behavior ATC Recognizes alarm(s) and reports to SRO Implements the Alarm response procedure for Control Room panel ATC/SRO 1C06, Window "E-O 1" Using the Acoustic Monitor, determines PORV-402 is leaking by to the RO i Quench Tank SRO Directs RO to isolate PORV-402 by shutting l-RC-403-MOV References Tech Spec 3.4.11. Determines T.S. LCO 3.4.11.A is SRO applicable Directs OWC to have E&C / Systems Engineering investigate the SRO leaking PORV.
Examiner notes:
Event concludes when standby CAC is started.
If SRO's understanding of T.S. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 11 CAC failure, when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 2 Page 2 of 15 Event
Description:
Loss of 11 CAC Event Type: C - BOP/SRO Time Position Applicant's Actions or Behavior ATCIBOP Recognizes alarm(s) and reports to SRO i Implements the Alarm response procedure for Control Room panel BOP/SRO 1C 19, Window "R-04" BOP Determines 11 CAC has failed.
SRO Directs CRO to place 13 CAC in service I
SRO References Tech Spec 3.6.6. Determines T.S. LCO 3.6.6.C is applicable SRO Directs E&C to investigate failure of 11 CAC.
Examiner notes:
Event concludes when standby CAC is started.
If SRO's understanding of T.S. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, ADVs fail open, when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event#:3 Page 3 of 15 Event
Description:
ADVs fail open Event Type: C - BOP/SRO
...,.,. D . .. Applicant's Actions or Behavior Notes effect of failed open ADV s (ReS temperature lowering, ALL megawatts lowering, etc.) I i
SRO Directs ATC to monitor the primary I i
ATCIBOP Notes ADV s indicate full open I
Implements AOP-7K, Overcooling Event on Mode One or Two. Directs SRO CRO to perform Block step IV.D.3 to terminate incident ATC Insert CEAs to control power, as necessary Places Atmospheric Steam Dump Controller, I-HIC-4056, in manual BOP and adjusts signal to 0% output, if necessary, terminating the event.
SRO Directs OWC to have 1M shop investigate failure of I-HIC-4056 Examiner notes:
Event conclusion is entry into AOP-2A, Excessive Reactor Coolant Leakage.
NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 11 S/G Tube leak, when desired
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 4 Page 4 of 15 Event
Description:
11 S/G Tube Leak Event Type: R - ATC/SRO, N - BOP Time Position Applicant's Actions or Behavior Refers to Alarm Manual for alarm and contacts Plant Chemistry to BOP sample both SGs.
SRO Implements AOP-2A, Excessive Reactor Coolant Leakage.
SRO Notifies Radiation Safety that excessive RCS leakage exists.
Directs Chemistry to perform qualitative samples on both SGs for SRO activity PER CPA36.
SRO Determines a S/G Tube Leak is indicated ATC Shuts the LID Containment Isolation valves ATC/BOP Ensures the S/G B/D valves are shut SRO Directs RO to Borate to reduce TAvE to less than 53TF Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 4 (continued) Page 5 of 15 Event
Description:
11 S/G Tube Leak Event Type: R - ATC/SRO, N - BOP Borates to reduce TAvE to < 537 0 F. Start with 1 minute fast boration with ALL available Charging Pumps then shifts suction to R WT.
Initial boration from the BASTs followed by suction from the RWT:
D Open the BA DIRECT MIU valve, l-CVC-514-MOV.
ATC/SRO D Start ALL available CHG PPs.
D Start ONE BA PP and operate it for approximately one minute.
D Shut the BA DIRECT MIU valve, l-CVC-S14-MOV.
D Open the RWT CHG PP SUCT valve, l-CVC-504-MOV.
D Shut the VCT OUT valve, l-CVC-501-MOV.
Refers to T.S. 3.4.13. Determines Tech Spec limits 3.4. 13.c, identified SRO leakage and 3.4.13.d, S/G tube leakage have been exceeded. Enters LCOs 3.4.13.A and 3.4.13.B.
Adjusts turbine load, as necessary, to maintain S/G pressure between ATC/BOP
- 800 PSIA and 825 PSIA Coordinates MSR shutdown with plant operators stationed locally at the BOP MSR panel loaders Trips reactor when TAvE is < 53TF or Pressurizer level cannot be ATC maintained > 101 inches or Pressurizer pressure reaches the TM/LP pre trip setpoint Examiner notes:
Event ends when the Reactor is tripped and EOP-O is implemented.
If SRO's understanding of T.S. implications is not clearly observable, follow-up questioning may be required upon completion of the scenario.
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 Page 6 of IS Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Position Applicant's Actions or Behavior SRO Announces reactor trip and directs crew to implement EOP-O Performs Reactivity Control Safety Function o Depress Reactor trip pushbuttons on 1COS and perform EOP-O, Reactivity Control o Depress Manual Reactor Trip Pushbutton on 1COS o Check Reactor tripped using NI power indications on 1COS o Verifies all CEAs fully inserted o Notes inability to determine status of CEAs due to loss of 1Y09 and performs alternate actions listed below:
IF more than ONE CEA fails to fully insert, THEN borate the RCS to at least 2300 ppm as follows:
o Verifies VCT MfU valve, l-CVC-S12-CV shut o Opens the BA DIRECT MfU valve, l-CVC-SI4-MOV.
ATC o Notes BAST Gravity Feed valves have no power o Verifies the MfU MODE SEL SW, I-HS-210, is in MANUAL.
o Starts 12 BA PP.
o Notes VCT OUT valve, l-CVC-SOI-MOV has no power.
o Starts ALL available CHG PPs.
Performs remainder of Reactivity Control Safety Function o Verify DI Water Makeup is secured o Check 11 & 12 RC makeup Pumps secured on 1C07 o Check VCT MlU l-CVC-S12-CV is shut on lC07 o If aligned for direct makeup to RCS then shut R WT Charging Pump Suction l-CVC-S04-MOV on 1C07 o Reports Reactivity Control Complete Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 7 of 15 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Time Position Applicant's Actions or Behavior Performs Turbine Trip o Checks Reactor tripped then:
o Depresses both Turbine Trip Pushbuttons on 1C02 o Checks Main Turbine stop Valves shut on MK VI screen o Checks Turbine Speed drops on MK VI screen o Checks Turbine Generator Output Breakers open BOP o 11 GEN BUS BKR 0-CS-552-22 on 1C01 o 11 GEN TIE BKR 0-CS-552-23 on 1C01 o Checks Generator Field Breaker open on lCOl o Checks Generator Exciter Field breaker open on 1CO 1 o Ensures MSR 2 nd Stage Steam source Valves are shut o Reports Turbine Trip Complete Performs Vital Auxiliaries Safety Function o Checks 11 or 14 4KV bus energized. (Notes 11 4KV Bus is deenergized) o Checks ALL 125V DC BUS VOLTS greater than 105 volts on 1C24:
D 11 D 12 D 21 D 22 BOP o Checks at least THREE 120V AC Vital Buses are energized on lC24:
D 11 D 12 D 21 D 22 o Checks EITHER 1Y09 OR 1Yl 0 energized on 1C24. (both are energized) o Verifies Component Cooling Flow to the RCP's (Starts 12 CCW Pump) o Reports Vital Auxiliaries Complete Contacts OWC to have EM to investigate loss of 11 4 KV bus, and SRO failure of the 1A DG Output Breaker, 152-1703, to close.
I Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 8 of 15 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL ime Position Applicant's Actions or Behavior Performs Pressure & Inventory Control Safety Function, including alternate actions o Checks Pressurizer pressure at 1C06 and determines that it is lowering and not trending to 2250 PSIA.
o Verifies main spray CV's indicate shut on lC06 ATC 0 Determines PORV's not leaking by checking Pressurizer RV Flow Monitor approximately zero volts on 1C06 o Verifies SIAS (informs SRO alternate action is being taken):
o Verifies 11 & 13 HPSI pumps running o Verifies all 8 HPSI header MOV's open o Reports SIAS verified to SRO o Checks Pressurizer level at 1C06 and determines that it is lowering and not trending to 160 inches.
o Verifies cves letdown isolations CVC-5I5 and 516 shut and all ATC Charging Pumps operating on 1C06 o Checks subcooling is greater than 30°F by PAMs display on 1COS o Reports Press & Inventory Cannot Be Met due to low PZR level &
Pressurizer pressure Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 9 of 15 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Time Position Applicant's Actions or Behavior Performs Core & RCS Heat Removal Safety Function D Directs ABO to manually open ADV s or has 1Y09 tied to 1YI 0 and BOP operates TBVs to control S/G pressure 850-920 PSIA and TCOLD 525-535°F.
D Checks S/G level (-) 170" to (+) 50" on 1C03 D Checks RCP operating red lights illuminated on 1C06 D Checks THOT minus TCOLD is less than 10°F by checking BOP indicators on 1C06 D Reports Core & RCS Heat Removal Safety Function Complete.
Performs Containment Environment Safety Function D Checks Containment Pressure < 0.7 PSIG using narrow range pressure on ICIO.
D Checks Containment Temperature < 120°F using cavity and dome BOP temperature indicators on 1Cl O.
D Checks Containment Gaseous RMS at I C22 not in alarm with no abnormal rising trend o Reports Containment Environment Complete Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 10 of 15 Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Time Position Applicant's Actions or Behavior Perform Rad Levels External to Containment Safety Function o Check the following RMS alarms are clear with no unexplained rise:
o V-I Wide Range Noble Gas Monitor o V-I Condenser Off Gas @ 1C22 BOP o U-l S/G Blowdown @ lC22 - notes S/G BID RMS alann, verifies S/G BID is secured.
o V-I Main Vent Gaseous @ tC22 o Reports Rad Levels External to Containment CANNOT BE MET due to S/G BID RMS trends Perfonn EOP-O brief o Ensures all are attentive o Reviews Safety Functions not met o Pressure and Inventory Control due to low Pressurizer level and pressure ORad Levels External to Containment due to negative trend on S/G SRO B/DRMS o Reviews Safety system Actuations o SIAS o Chance of AFAS (depending on timing) o Solicits Input o Concludes the brief directing the crew to continue to monitor Safety Functions while the event is diagnosed.
Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event 5 (continued) Page 11 of 15
! Event
Description:
Reactor trip & EOP-O Event Type: M - ALL Time Position Applicant's Actions or Behavior o Refers to EOP-O flowchart o Pressure and Inventory Control not met due to low Pressurizer level and pressure. Flowchart may lead to EOP-6 SRO ORad Levels External to Containment not met due to S/GI BID RMS trending higher or in alarm. Flowchart leads to EOP-6 o Recognizes a SGTR is in progress and implements EOP-6 Examiner notes:
Event conclusion is entry into EOP-6
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event#:5 Page 12 of 15 Event
Description:
EOP-6 entry Event Type: M - ALL Applicant's Actions or Behavior Directs RO to Perform Steps D - Monitor RCS Depressurization, SRO E - Perform the RCP Trip Strategy, and F- Commence RCS Boration SRO Directs CRO to Perform Step G - Commence Cooldown Step D, Monitor RCS Depressurization IF SIAS has actuated, THEN perform the following actions:
- a. Verifies the following pumps are running:
- 11 HPS! PP
- 13 HPSI PP
- 11 LPSI PP
- ALL available CHG PPs
- b. Verifies Safety Injection flow:
- HPSI flow PER ATTACHMENT(I 0), HIGH PRESSURE SAFETY INJECTION FLOW, when pressure is below1270 PSIA
- LPSI flow PER ATTACHMENT(ll), LOW PRESSURE SAFETY INJECTION FLOW, when pressure is below185 PSIA Step E, Perform the RCP Trip Strategy RCP Trip Strategy previously implemented in EOP-O. Monitors for ATC additional requirements as a result of CIS or not meeting NPSH requirements Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 13 of 15 Event
Description:
EOP-6 entry Event Type: M - ALL
.I.Ulle Position Applicant's Actions or Behavior SteQ F, Commence RCS Boration Boration initiated by SIAS. Verifies the following:
0 VCT MfU valve, l-CVC-512-CV, is shut.
0 BA DIRECT M/U valve, l-CVC-514-MOV, is open.
0 BAST GRAVITY FD valves are open:
ATC 0 l-CVC-508-MOV 0 l-CVC-509-MOV 0 All available BA PPs are running.
0 RWT CHG PP SUCT valve, l-CVC-504-MOV is shut.
0 VCT OUT valve, l-CVC-501-MOV, is shut.
0 All available CHG PPs are running.
Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 14 of 15 Event
Description:
EOP-6 entry Event Type: M - ALL Time Position Applicant's Actions or Behavior Step G, Commence Cooldown (1 C03 & 1C04) o Blocks SGlS, using SGIS Block keyswitches, when the SGIS Block Permitted alarms are received o Ensures ADVs are shut o Performs a rapid RCS cooldown to reach T HOT less than 51 YF using the TURB BYP valves, while maintaining less than 100'F in anyone hour.
0 If AFW flow not previously established, establishes AFW flow using 12AFWPp 0 Places handswitches for Steam Driven Train AFW Block valves in open (CVs l-AFW-4520, 21, 30 and 31) 0 Opens AFW Pp Steam supply valves (MOVs I-MS-4070, 70A, 71 and 71A) 0 Records open times for affected S/G AFW Steam Supply valves BOP for dose calculation purposes Event 5 0 Adjusts and maintains 12 AFW Pp disch pressure 100 PSI greater than S/G pressure using I-HC-3989A on lC04 0 Maintains cooldown rate by adjusting AFW flow 0 Verities AFW Pp Rm ventilation in operation 0 Secures the Main Feedwater system:
o Trips 11 and 12 SGFPs o Places Cond Booster Pps in PTL o Places one Cond Pp in PTL o Places Htr Dm Pps in PTL o Shuts S/G FW Isol valves (l-FW-4516 and 4517) o Shuts Hotwell dump to CST (places l-LIC-4405 @ 50% output) o Dispatches an operator to stand by in the 45' SWGR Rm to shut the affected ADV Examiner notes:
Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2012 Scenario #: 3 Event #: 5 (continued) Page 15 of 15 Event
Description:
EOP-6 entry Event Type: M - ALL
'me Position Applicant's Actions or Behavior Directs CRO to Perfonn Step J - Identify, Isolate and Confinn the SRO Affected S/G Examiner notes:
The scenario will end when 11 S/G has been isolated and RCS Depressurization Commenced or at the discretion of the Lead Examiner After scenario ends ask SRO for ERPIP call. The correct Emergency Action Level declaration for this scenario is:
- 2. ALERT, per lLA5.1.2, for a " loss - SOTR > available Charging Pump capacity" or "potential loss unisolable RCS leakage >50 GPM"