ML15126A423
| ML15126A423 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/06/2015 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML15126A423 (144) | |
Text
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPMA
1503 NRC Sim JPM A Page 2of18 Task: Shutdown Bank Withdrawal Task#: 0010180101 Task Standard: The examinee will close the Reactor Trip Breakers and commence Shutdown Bank withdrawal.
The examinee will Trip the Reactor when continuous rod withdrawal occurs.
Alternate Path: YES: - - X - NO:
Time Critical Task: YES: ---
NO: x KIA Reference/Ratings: 001A2.11 (4.4/4.7)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator ---
x In-Plant - - - - Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 23 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
1503 NRC Sim JPM A Page 3of18 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset to IC 256
- 3. IF IC #256 is not available then reset to IC#16
- Hold FW Isolation 'reset pushbuttons' and trip the Reactor. Leave Rods in Manual.
- Select a SR and IR pen for NR45.
- Ensure Audio Count rate is audible.
- Clear and unblock HI Flux at Shutdown alarm.
- Clear 1st out.
- Insert overrides to cause either SD bank A to withdraw continuously when Rods Out Light comes on.
- {zdiflrm1 [1]} IOR ZDIFLRM1 f:1 (overrides In-Hold-Out switch to OUT)
- {zdiflrm1 [1]} IOR ZDIRBSS1 f:6 (overrides Bank Select Switch to SOB A)
- IOR AN_OV_325 f:1 (fails annunciator as is for Computer Alarm Rod Dev.)
- 4. JPM Steps 7 through 10 will require a simulator operator.
- 5. PLACE SIMULATOR IN RUN
- 6. An extra operator will be required to acknowledge alarms.
- 7. ACKNOWLEDGE ALARMS
- 8. FREEZE SIMULATOR
- 10. PLACE SIMULATOR IN RUN
- 11. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.
- 12. Tools/Equipment/Procedures Needed:
Marked up copy of O-S0-85-1, Control Rod Drive System, section 5.5 (marked through Step 10) and 6.3 Tl-28 Attachment 6
References:
Reference . Title Rev No.
- 1. O-S0-85-1 Control Rod Drive System 42
========================================================================
1503 NRC Sim JPM A Page 4of18 DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3 with Tavg at 547F and RCS pressure at 2235 psig.
- 2. Both M-G sets are in service.
- 3. All Precautions and Prerequisites of O-S0-85-1, Control Rod Drive System have been met. (Sections 3.0 and 4.0 are complete).
- 4. O-S0-85-1 Control Rod Drive System Section 5.5 is complete through Step 9.
INITIATING CUES:
- 1. You will close the "Reactor Trip" breakers and withdraw the Shutdown Banks using O-S0-85-1, Control Rod Drive System Section 5.5, beginning with step 10.
- 2. Inform the SM when the shutdown banks have been withdrawn.
1503 NRC Sim JPM A Page 5of18 Start Time STEP 1 --
SAT Obtain a copy of O-S0-85-1, Control Rod Drive System section 5.5 (and then section 6.3)
- - UNSAT Examinee obtains a copy of O-S0-85-1, Control Rod Drive System section Standard:
5.5.
Provide a marked up copy of O-S0-85-1, Control Rod Drive System section Cue:
5.5 (and then section 6.3).
Examiner Initiating conditions cover several steps in section 5.5 prior to step 10.
Note: These steps are not addressed in the JPM.
Comment
["IO] [CTS] IF unit is in Mode 3,THEN STEP 2 ENSURE requirements of Tech Spec 3.4:1.2 are met -- SAT
[ffS] IF unit is in Mode 3,THEN UNSAT ENSURE requirements of Tech Spec 3.4_5 are met Standard: Examinee ensures TS 3.4.1.2 requirements are met.
Cue: Provide the following cue: "The SRO has verified requirements are met."
Comment
1503 NRG Sim JPM A Page 6 of 18 STEP 3 SAT (nJ DEPRESS and HOLD FW !sol Reset pushbuttons [HS-3-99A] -
and [HS-3-99BJ[C.1]
UNSAT Standard: Examinee verifies both HS-3-99A and B, FW Isolation A & B Train Reset pushbuttons, are being held in the IN Reset position.
Examiner Have the simulator operator play role as CRO and depress both A& B FW Note Isolation Reset pushbuttons.
Comment STEP 4 ["i2] IF resetting Unit 1 Reactor Trip Breakers, THEN SAT CLOSE Rx Trip Breakers by placing [1-HS-99-7], in CLOSE position_ UNSAT Comment STEP 5 [B] IF resetting Unit 2 Reactor Trip Breakers, THEN - - SAT CLOSE Rx Trip Breakers by placing [2-HS-99-7], in CLOSE position. - - UNSAT Standard: Examinee determines step is N/A.
Comment
1503 NRC Sim JPM A Page 7of18
[14] VERIFY Reactor Trip Breakers CLOSED by RED indicating STEP 6 lights on M-4: - - SAT BREAKER RED LIGHT INITIALS - - UNSAT POSITION INDICATION RTA ON RTB ON Examinee verifies Red indicating lights come on and green lights go off Standard:
on Reactor Trip Breaker indicating lights on panel M 4.
Comment STEP 7 - - SAT
['15] RELEASE FY.l lsol Reset pushbuttons [HS-3-99A] and
[HS-3-998].[C.1]
- - UNSAT Standard: Examinee directs additional operator to release pushbuttons Comment STEP 8 - - SAT
["16] NOTIFY !Ms to periom1 *1,2-Pl-IFT-099-0P4.0, Verification of P4 Contacts.
- - UNSAT Examinee notifies IMs to perform 1,2-Pl-IFT-099-0P4.0, Verification ofP4 Standard:
Contacts.
Provide the following cue: "The SRO will notify the IMs to perform this Cue:
Pl."
Comment I
1503 NRC Sim JPM A Page 8of18 STEP 9 ['17] IF Shutdown or Control Rods will be withdrawn and both MG Sets are NOT in operation but are available, THEN - - SAT PERFORM one of the follo'Wing AND RETURN to this Section (Mark selection NOT made NIA): - - UNSAT
['17.'I} GO TO Section 6.1, Placing MG Set A In Service With MG Set B Operating D OR
['17-2] GO TO Section 6-2, Placing MG Set B In Service With MG Set A Operating D Standard: Examinee determines both steps are N/A Comment STEP 10 [18) IF Shutdown or Control Rods 'Will be withdrawn, THEN
- - SAT GO TO Sedion 6.3, Manual Operation of Rod Control System Below -15 Percent Power.
- - UNSAT End of Se~tion 5.5 Standard: Examinee determines Section 6.3 is applicable.
Comment STEP 11 - - SAT Obtain a copy of O-S0-85-1, Control Rod Drive System section 6.3
- - UNSAT Standard: Examinee obtains a copy of O-S0-85-1, Control Rod Drive System section 6.3.*
Cue: Provide a copy of O-S0-85-1, Control Rod Drive System section 6.3.
1503 NRC Sim JPM A Page 9of18 CAUTIONS
- 1) (CTS] TR 3.1.3.3 [ITSJ TRM 8.1.3 requires group demand position indicator capable of determining within +/-2 steps, the demand position for each rod not fully inserted. In Modes 3, 4, or 5 and greater than +/-2 steps deviation refer to AOP-C.01.
- 2) If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each. This will limit the possibility of "thennal lock-up" of the rods. Thermal lock-up is NOT a concern during unit heatup.
NOTE When RCS temperatures are greater than 350"'F, continuous rod motion shall comply with these restrictions:
CROM OUTLET ROD MOTION LIMITS TEMPERATURE
- s;190"F *10 minutes ON 20 minutes OFF
- QOO"F 6 minutes ON 24 minutes OFF STEP 12 - - SAT
[1] ENSURE Section 5_5, Reset/Close Reactor Trip Breakers has been completed_ D
- - UNSAT Standard: Examinee determines Section 5.5 is complete.
Comment STEP 13 {2] IF the shutdown and control rods were withdrmvn 5 steps to - - SAT prevent them1al lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawaL - - UNSAT Standard: Examinee determines step is N/A.
Comment I
1503 NRC Sim JPM A Page 10of18 STEP 14 [3] IF RCS temperatures are greater than 350"F,
- - SAT THEN ENSURE CROM cooling fans are aligned and in service in accordance wfth O-S0-30-6. - - UNSAT Standard: Examinee ensures that CROM cooling fans are aligned and in service per O-S0-30-6 Cue: Provide the following cue: "CROM cooling fans are aligned and in service per 0-50-30-6" Comment CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4} should never be held in STARTUP position for any extended period of time. Holding this switch in STARTUP position may cause damage to the counters.
NOTE ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) Resets:
A. All GROUP STEP COUNTERS on the Control Board.
B. The master cyder reversible coonter.
C. All slave cycler counters.
D. The bank overlap counter.
E. All internal memory and alarm circuits.
F. All pulse-to-analog converters in the Rod Position Indication System.
STEP 15 [4] MOMENTARILY PLACE [SUS], Rod Control Startup Step SAT Counter Reset to the STARTUP position to reset Control Rod Drive System. UNSAT Comment
1503 NRC Sim JPM A Page 11 of 18 CAUTION Before withdrawing any rod from the fully inserted position, all Group Step Counters and all Rod Position indicators must be at zero steps.
STEP 16 - - SAT
[5J ENSURE all Full Length Rod step counters resetto zero.
- - UNSAT Standard: Examinee verifies rod step counters have reset to zero.
Comment STEP 17 - - SAT
[6] VERIFY rod control IN-OUT direction lights are NOT UT.
- - UNSAT I
Standard: Examinee verifies both IN and OUT lights NOT lit.
Comment STEP 18
- - SAT
[7] DEPRESS [RCAS], Rod Urgent Failure Alam1 Reset
- - UNSAT Standard: Examinee depresses RCAS, Rod Urgent Failure Alarm Reset.
Comment
1503 NRC Sim JPM A Page 12of18 STEP 19 [8] RESET Window 6 (A-6), ROD CONTROL SYSTEM URGENT - - SAT FAl LURE alami on panel JXA-55-48] using (XS-55-4.AJ, Annunciator RESET/ACKffEST Switch. - - UNSAT Standard: Examinee resets ROD CONTROL SYSTEM URGENT FAILURE alarm.
Comment NOTE Window 13 (B-6) may be marked NIA if Shift Manager approval is obtained for reactor startup with Non-Urgent Failure Alarm. Risk of dropped rods (if additional failure occurs or during subsequent corrective maintenance) should be evaluated.
STEP 20 19] VERIFY the following rod control system alanns on panel
~A-55-48] are NOT LIT:
- - SAT WINDOW NUMBER NOT LIT('/} WINDOW NUMBER NOT LIT {\I) - - UNSAT 5 (A5) D 18 (C4) D 6 (A6) D 19(C5) D 11 (B4) D 27 {D6) D 12 (B5) D 34 (ES) D 13(86) D Standard: Examinee verifies that the listed annunciators are not lit Comment
1503 NRC Sim JPM A Page 13of18 STEP 21 ['IO] ENSURE Plant computer ~nts for rod bank position are ZERO using the following computer points: - - SAT UNSAT COMPUTER PT U0049 ROOBANK Control A D
U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D U0056 Shutdown D D Standard: Examinee ensures Plant computer points for rod bank position are ZERO Cue: Provide the following cue: "Another operator has verified Plant computer points for rod bank position are ZERO" Comment STEP 22 - - SAT
[HJ MONITOR Control Rod position USING Rod Position Indicators ICS screen 30 minute trend during SD & Control Banks \l!lithdrawal to aid in detecting rod misalignment - - UNSAT Standard: Examinee monitors Control Rod position using Rod Position Indicators ICS screen 30 minute trend.
Cue: Provide the following cue: "Another operator will monitor Rod Position Indicators using ICS "
Comment
1503 NRC Sim JPM A Page 14of18 STEP 23 [12] IF Individual Rod Position Indication does not indicate proper rod position during withdrawal of SD Banks, THEN - - SAT
['12.1] STOP rod withdrawal. - - UNSAT
['12-2] ENSURE subcriticality_
['12.3] CONTACTl&C ANO INITIATE t~bleshooting_
["12-4] IF troubleshooting does not resolve the problem, OR subcriticality can NOT be verified, THEN INITIATE Reactor TRIP_
Standard: Examinee addresses step Comment STEP 24 [13] IF Individual Rod Position Indication does NOT indicate proper
- - SAT rod position during withdrawal of Control Banks, THEN GO TO AOP-C.01, Rod Control System Ma/functions_ - - UNSAT Standard: Examinee addresses step Comment
1503 NRC Sim JPM A Page 15of18 CAUTION Under normal conditions control rod banks must be withdrawn and Inserted in the prescribed sequence. For withdrawal, the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, Control Bank D. The insertion sequence is the reverse of the withdrawal sequence.
NOTES
- 1) Startup rate, Source range, Intermediate range, Nuclear lnstrumentation recorders, Group Step Counters and the Rod Position Indicators should be monitored during each bank wlthdrawaL
- 2) The fol!o:wing failures will render the rod control system incapable of automatic and I or manual motion '...irlhout any annunciation or indication: *q Hand switch failure: 2) relay failure, and 3) simultaneous failure of both *1 OOv DC power supplies (PS3 and PS6)
STEP 25 SAT
["14] PLACE [HS-85-5110]. Rod Control Mode Selectorto the SBA position_
UNSAT Comment STEP 26 - - SAT
[15] VERIFY Rod Speed Indicator [Sl-412], indicates 64 Steps/minute_
- - UNSAT Standard: Examinee verifies Rod Speed Indicator reads 64 Steps/minute.
Comment
1503 NRC Sim JPM A Page 16of18 NOTE Monitor Group Step Counters, Rod Position Indicator and the ~IN-OUT' status lights to ensure anticipated motion as each bank is being withdrawn. Rod speed indicator should be reading 64 steps per minute.
STEP 27 ['16] ENSURE Shutdo\lilTl Bank A demand position counters operational by performing the following: [C.2] - - SAT
[16:1] BUMP [HS-85-5111). Rod Control Switch to withdraw --
UNSAT Shutdown Bank A one-half step at a time, for one full step.
Standard: Examinee momentarily places [HS-85-5111], Rod Control Switch to Withdraw for one-half step.
Examiner When Rod Control Switch is taken to OUT a malfunction will cause Note SOB A rods to withdraw continuously forcing ALTERNATE PATH Comment ALTERNATE PATH STEP 28 - - SAT When moving SB A out the second full step SBA begins withdrawing continuously with no command - - UNSAT
- 1. DIAGNOSE the failure:
GOTO IF ... SECTION PAGE Uncontrolled rod bank movement 2.1 4 (rod movement NOT due to actual T-avgJT-ref mismatch or change in reactor/turbine power)
Standard: Examinee recognizes continuous uncontrolled rod bank movement Comment
1503 NRC Sim JPM A Page 17of18 2.1 Uncontrolled Rod Bank Movement STEP 29 - - SAT NOTE: Step 1 is an immediate action step. - - UNSAT
- 1. STOP uncontrolled rod motion:
- a. PLACE rod control in MAN.
- b. CHECK rod motion STOPPED. b. TRIP the reactor, and GO TO E-0, Reactor Trip or Injection.
Standard: Examinee places Rod Control in MAN and determines that rods are still moving.
Comment 2.1 Uncontrolled Rod Bank Movement STEP 29 SAT NOTE: Step 1 is an immediate action step. UNSAT
- 1. STOP uncontrolled rod motion:
- a. PLACE rod control in MAN.
- b. CHECK rod motion STOPPED. b. TRIP the reactor, and GO TO E-0, Reactor Trip or Injection.
Comment Terminating Provide the following cue, "Another operator will complete the Cue: STOP remaininsteps of this procedure."
i Stop Time End of JPM
JPM BRIEFING SHEET DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3 with Tavg at 547F and RCS pressure at 2235 psig.
- 2. Both M-G sets are in service.
- 3. All Precautions and Prerequisites of O-S0-85-1, Control Rod Drive System have been met. (Sections 3.0 and 4.0 are complete).
- 4. O-S0-85-1 Control Rod Drive System Section 5.5 is complete through Step 9.
INITIATING CUES:
- 1. You will close the "Reactor Trip" breakers and withdraw the Shutdown Banks using O-S0-85-1, Control Rod Drive System Section 5.5, beginning with step 10.
- 2. Inform the SM when the shutdown banks have been withdrawn.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPM B
2015 NRC SIM JPM B Page 2 of 14 RO/SRO JOB PERFORMANCE MEASURE Task: Respond to loss of all charging per AOP-M.09.
Task#: 0040020101 Task Standard: The examinee will depressurize the RCS to facilitate SI Pump flow using AOP-M.09 LOSS OF CHARGING.
Alternate Path: YES: - - - NO: x Time Critical Task: YES: ---
NO: x KIA Reference/Ratings: APE 022 AA 1.03 (3.2/3.2)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator x In-Plant - - - - Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
2015 NRC SIM JPM B Page 3 of 14 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset to IC 275
- 3. If IC 275 is not available perform the following:
- Reset to IC 16.
- Trip the Reactor.
- Place both Charging Pump HS in PTL.
- Establish AFW flow at approx. 600 gpm.
- Place Steam Dumps in STEAM PRESSURE MODE.
- Isolate Letdown.
- Ensure Pressurizer Level is 25%.
- Ensure T Hot is less than 550 deg.
- Perform G0-12
- 4. PLACE SIMULATOR IN RUN
- 5. An extra operator will be required to acknowledge alarms.
- 6. ACKNOWLEDGE ALARMS
- 7. FREEZE SIMULATOR.
- 9. PLACE SIMULATOR IN RUN
- 10. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.
- 11. Provide an in-progress copy of AOP-M.09 LOSS OF CHARGING completed through step 29.
Tools/Equipment/Procedures Needed:
- 1. AOP-M.09 LOSS OF CHARGING completed through step 29.
References:
I Reference Title Rev No.
- 1. AOP-M.09 LOSS OF CHARGING 6 I 2.
2015 NRG SIM JPM B Page 4 of 14 DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3.
- 2. Both Charging pumps are unavailable.
- 3. ES-0.1, REACTOR TRIP RESPONSE has been completed.
- 4. AOP-M.09, LOSS OF CHARGING is in progress, completed through step 28.
INITIATING CUES:
- 2. Inform the SRO when complete.
2015 NRC SIM JPM B Page 5 of 14 Start Time STEP 1 --
SAT Obtain a copy of AOP-M.09, LOSS OF CHARGING
- - UNSAT Standard: Examinee obtains a copy of AOP-M.09, LOSS OF CHARGING Cue: Provide an in-progress copy of AOP-M.09, LOSS OF CHARGING.
Comment CAUTION If RCS temperature is less than 350°F, operating an SI pump in later steps would violate requirements of Tech Spec LCO 3.4.12 (LTOPS}.
STEP 2 - - SAT
- 29. MONITOR RCS T-cold greater than 350°F.
- - UNSAT Standard: The examinee determines RCS temperature is greater than 350 deg by observing plant instrumentation.
Comment
2015 NRG SIM JPM B Page 6 of 14 NOTE SI actuation is NOT necessary when RCS pressure is deliberately lowered to I allow SI pump injection in later steps.
I
- a. CHECK for any of the following: a. GO TO Step 31.
- - UNSAT
- containment pressure greater than 1.5 psig ~
- uncontrolled drop in S/G pressure to less than 600 psig.
Standard: The examinee determines SI is not required by observing plant instrumentation.
Comment STEP 4 31. MONITOR if SI pump injection is needed:
- - SAT
- a. CHECK for any of the following:
- - UNSAT
- RCS boratlon is required to maintain shutdown margin or to prepare for RCS cooldown OR
- pressurizer level less than 25%
- pressurizer level needs to be raised to support RCS coo Id own.
The examinee determines SI is pump injection is required by Standard:
observing Pressurizer level < 25%.
Comment
2015 NRG SIM JPM B Page 7 of 14 STEP 5 - - SAT
- 32. CHECK T-hot less than 550"F.
- - UNSAT Standard: The examinee determines RCS temperature is greater than 550 deg by observing plant instrumentation.
Comment STEP 6 33. CHECK low pzr pressure SI signal
- - SAT NOT blocked:
UNSAT
- permissive M-4A window 8-4 DARK.
Standard: The examinee determines the Low Pressure SI signal not blocked by observing permissive M-4A window 8-4 DARK.
Comment CAUTION Low pressurizer pressure SI actuation circuits will automatically unblock if pressurizer pressure rises to greater than 1970 psig.
STEP 7 34. REDUCE pzr pressure to 1920 psig SAT to allow SI block:
UNSAT
- a. DE-ENERGIZE pressurizer heaters.
Comment
2015 NRG SIM JPM B Page 8 of 14 STEP 8 34. REDUCE pzr pressure to 1920 psig SAT to allow SI block:
- - UNSAT
- b. CHECK RCPs RUNNING.
The examinee determines the RCPs running by observing red lights Standard: above HS-68-8A, 31A, 50A, and 73A Reactor Coolant Pump 1, 2, 3, and 4 ON.
Comment STEP 9 34. REDUCE pzr pressure to 1920 psig SAT to allow SI block:
UNSAT
- c. OPERATE normal spray valves as necessary to reduce pzr pressure to approximately 1920 psig.
Comment
2015 NRC SIM JPM B Page 9 of 14 STEP 10 34. REDUCE pzr pressure to 1920 psig SAT to allow SI block:
UNSAT
- d. BLOCK Low pressurizer pressure SI signal.
Comment STEP 11 34. REDUCE pzr pressure to 1920 psig SAT to allow SI block: --
- e. CHECK PRESSURIZER SI TRAINS - - UNSAT A&B BLOCKED permissive LIT
[M-4A, 84].
The examinee determines the SI Low Pressure Blocked by observing Standard: PRESSURIZER SI TRAINS A&B BLOCKED permissive LIT [M-4A, 84].
Comment CAUTION 1 Pressurizer level may rise rapidly when RCS pressure is below SI pump shutoff head.
CAUTION 2 Operation of SI pump with recirc flowpath isolated could result in pump damage.
STEP 12 SAT
- 35. ENSURE one SI pump running.
UNSAT Comment
2015 NRG SIM JPM B Page 10of14 NOTE To allow injecting with SI pump, RCS subcooling may temporarily be reduced below required value in ES-0.2 or ES-0.3 (if applicable). Manual SI actuation based upon low subcooling is NOT required as long as operators retain control over RCS pressure.
STEP 12 36. CONTINUE RCS depressurization SAT UNTIL SI pump begins to inject:
UNSAT
- a. ENSURE discharge valve OPEN for running SI pump:
- FCV-63-152 (Train A)
- FCV-63-153 (Train B)
- b. PERFORM one of the following as necessary to reduce RCS pressure:
- OPERATE normal spray valves.
Comment
2015 NRG SIM JPM B Page 11 of 14 STEP 13 36_ CONTINUE RCS depressurization SAT UNTIL SI pump begins to inject UNSAT c_ WHEN SI pump begins to inject AND pzr level is rising, THEN STOP RCS depressurization.
Cue: "The SRO directs you to fill the Pressurizer to 65%."
Comment
2015 NRC SIM JPM B Page 12of14 STEP 14 36. CONTINUE RCS depressurization SAT UNTIL SI pump begins to inject UNSAT
- d. CONTROL RCS pressure to maintain desired injection rate.
Comment
2015 NRC SIM JPM B Page 13 of 14 NOTE 1 Normal requirement for running SI pump at least 20 minutes does NOT apply in this AOP.
NOTE2 Normal motor starting limitations are NOT applicable in this AOP. However, pump stop/start cycles should be limited as much as possible to minimize potential for overheating motor windings_
STEP 15 37. WHEN pressurizer level reaches 65~10 SAT or desired value, THEN UNSAT PERFORM the following:
- a. TERMINATE SI pump injection:
- CLOSE SI pump discharge valve FCV-63--152 (Train A) or FCV-63-'153 (Train B).
Comment Terminating Provide the following cue, "Another operator will complete the STOP Cue: remaining steps of this procedure."
Stop Time - - - -
JPM BRIEFING SHEET The examiner 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 1 is in MODE 3.
- 2. Both Charging pumps are unavailable.
- 3. ES-0.1, REACTOR TRIP RESPONSE has been completed.
- 4. AOP-M.09, LOSS OF CHARGING is in progress, completed through step 28.
INITIATING CUES:
- 2. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPMC
1503 NRC Sim JPM C Page 2 of 14 RO/SRO JOB PERFORMANCE MEASURE Task: Isolate the Ruptured Steam Generator (With MSIV Failure to Close)
Task#: 0000380501 Task Standard: The examinee isolates Steam Generator #1 with a failed #1 MSIV using E-3 Steam Generator Tube Rupture Alternate Path: YES:
Time Critical Task: YES: NO: x KIA Reference/Ratings: EPE 038 EA1.32 (4.6/4.7)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator -- x - In-Plant - - - - Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
1503 NRC Sim JPM C Page 3 of 14 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset simulator to IC #265.
a) Activate malfunction IMF TH05A f:8.5 to initiate SIG tube rupture in SIG #1.
b) Activate malfunction IMF MS14A f:100, to fail open SIG Loop 1 MSIV.
c) Actuate a MANUAL reactor trip and safety injection, take all actions up through Step 3 of E-3.
d) Complete the actions of E-0 thru step 12, which will transition the crews to E-3 e) Complete any required actions in ES-0.5. Including closing the TD AFW LCVs, but do not put handswitches in pull-to-lock.
f) Complete the first three steps in E-3.
- 4. An extra operator will be required to acknowledge alarms.
- 5. ACKNOWLEDGE ALARMS
- 6. FREEZE SIMULATOR.
- 7. Provide a copy of E-3 STEAM GENERATOR TUBE RUPTURE
- 8. PLACE SIMULATOR IN RUN SPECIAL INSTRUCTIONS TO EVALUATOR:
N/A Tools/Equipment/Procedures Needed:
- 1. In progress copy of E-3, STEAM GENERATOR TUBE RUPTURE
References:
Reference Title Rev No.
- 1. E-3 STEAM GENERATOR TUBE RUPTURE 21
1503 NRC Sim JPM C Page 4 of 14 DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a Steam Generator Tube Rupture on Steam Generator #1.
- 2. A manual safety injection was initiated.
- 3. E-3, STEAM GENERATOR TUBE RUPTURE is in progress, steps 1 through 3 of E-3 have been completed INITIATING CUES:
- 1. You have been directed to continue with E-3, STEAM GENERATOR TUBE RUPTURE beginning at Step 4.
- 2. Inform the SRO when you have isolated the #1 Steam Generator.
1503 NRC Sim JPM C Page 5 of 14 Start Time Obtain a copy of E-3, STEAM GENERATOR TUBE RUPTURE STEP 1 - - SAT
- - UNSAT Examinee obtains a copy of E-3, STEAM GENERATOR TUBE Standard: RUPTURE Cue Provide a marked up copy of E-3, STEAM GENERATOR TUBE RUPTURE completed through step 3.
Comment Procedure CAUTION If the TD AFW pump is the only source of feed flow, isolating both Caution: steam supplies will result in loss of secondary heat sink.
I STEP 2 4_ ISOLATE flow from Ruptured SiG(s): SAT a_ ADJUST Ruptured S/G(s) UNSAT atmospheric relief controller setpoint to 87% in AUTO_ ('1040 psig)
Comment
1503 NRC Sim JPM C Page 6 of 14 4_ ISOLATE flow from Ruptured S/G(s):
STEP 3 - - SAT b_ CHECK Ruptured S/G{s) - - UNSAT atmospheric relief hand switch in P-AUTO and valve(s) CLOSED_
Standard: Examinee observes SIG #1 atmospheric relief handswitch, 1-HS-1-6, on 1-M-4 in P-AUTO and valve CLOSED.
Comment '
STEP 4 4_ ISOLATE flow from Ruptured S/G(s):
- - SAT c_ CHECK SIG #1 or #4 ruptured_ - - UNSAT Standard: Examinee observes steam generator #1 level rising with no feed or by referring to the initial conditions.
Comment STEP 5 4_ ISOLATE flow from Ruptured S/G(s)~ SAT d_ CLOSE TD AFVV pump steam UNSAT supply from Ruptured SIG FCV-*1-15 {S/G #1) or FCV-1-16 (SIG #4)_
Comment
1503 NRC Sim JPM C Page 7 of 14
- 4. ISOLATE flow from Ruptured S/G(s):
STEP 6 - - SAT e_ VERIFY Ruptured S/G{s) blowdown - - UNSAT isolation valves CLOSED.
Standard: Examinee observes FCV-1-7 and FCV-1-181 CLOSED green indication lights above handswitch 1-HS-1-71181on1-M-4 ON.
Comment STEP
- 4. ISOLATE flow from Ruptured SiG(s):
7 - - SAT f_ CLOSE Ruptured S/G(s) r...1s1v
- - UNSAT and IVlSIV bypass valve.
Examinee places 1-HS-1-4 SIG #1 MSIV to CLOSE. Recognizes Standard: MSIV FCV-1-4 failed to close, by the red light above 1-HS-1-4 ON, and goes to the RNO to isolate the SIG.
Comment Examiner SIG #1 MSIV will NOT close and the operator MUST go to the RNO Note column
1503 NRC Sim JPM C Page 8 of 14 Alternate path STEP 8 SAT 4_ ISOLATE flow from Ruptured S/G(s):
UNSAT f_ PERFORM the following:
(Not Critical) Examinee verifies MSIV bypasses closed by observing green lights ON above handswitch 1-HS-1-148, 1-HS-1-149, & 1-HS-1-150 MSIV bypass valves.
Comment 4_ ISOLATE flow from Ruptured SlG(s):
STEP 9 - - SAT f_ PERFORM the following:
- - UNSAT
- 2) DISPATCH operator to perform EA-1, Closing l'v1SIVs Locally, for any t\*1SIV or MSIV bypass valve which fails to close_
Standard: Examinee dispatches an operator to perform EA- 1-1, Closing MSIVs Locally, for #1 S/G MSIV.
Cue Acknowledge the direction from the examinee.
Comment
1503 NRC Sim JPM C Page 9 of 14 STEP 10
- 4. ISOLATE flow from Ruptured S/G(s): SAT
- f. PERFORM the following: UNSAT
- 3) ISOLATE steam header:
- PLACE condenser steam dumps in OFF. [M-4]
Comment STEP
- 4. ISOLATE flow from Ruptured S/G(s):
11 - - SAT
- f. PERFORM the following:
- - UNSAT
- 3) ISOLATE steam header:
- ENSURE steam dump valves CLOSED. [M-4]
Standard: Examinee verifies the steam dump valves are closed by observing green light indication on 1-XX-55-4A for all steam dump valves are ON Comment
1503 NRC Sim JPM C Page 10 of 14 4_ ISOLATE flow from Ruptured S/G(s):
STEP 12 SAT f_ PERFORM the following: UNSAT
- 3) ISOLATE steam header:
- CLOSE FCV-47-'180, HP Steam Seal Supply Isolation_ [M-2]
Comment 4_ ISOLATE flow from Ruptured S/G(s):
STEP 13 -
SAT f_ PERFORM the following: UNSAT
- 3) ISOLATE steam header:
- ENSURE FCV-47-'18'1 HP Steam Seal Suppty Bypass CLOSED_ [M-2]
Examinee verifies FCV-47-181 HP Steam Seal Supply Bypass Standard: CLOSED by observing green light indication above the handswitch to ON.
Comment
1503 NRC Sim JPM C Page 11 of 14 STEP 14
- 4. ISOLATE flow from Ruptured S/G(s):
- f. PERFORM the following: UNSAT
- 3) ISOLATE steam header:
Comment STEP 15
- 4. ISOLATE flow from Ruptured S/G(s):
- - SAT f_ PERFORM the following:
- - UNSAT
- 3) ISOLATE steam header:
- DISPATCH operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.
Standard: Examinee dispatches an operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.
Cue Acknowledge the direction from the examinee.
Comment
1503 NRC Sim JPM C Page 12 of 14 4_ ISOLATE flow from Ruptured S/G(s):
STEP 16 --
SAT f_ PERFORM the following:
- - UNSAT
- 4) USE Intact S/G(s) atmospheric relief for steam dump_
Standard: Examinee addresses the procedure step.
Comment STEP 17 5_ MONITOR Ruptured S/G(s) level:
- - SAT
- - UNSAT a_ CHECK ruptured SIG narrow range level greater than '100,'o [25~,~ ADV]_
Examinee verifies #1 S/G narrow range level greater than 10% by Standard: observing Ll-3-42, or Ll-3-39, or Ll-3-38 or other installed plant instrumentation_
Comment STEP 18 5. MONITOR Ruptured S/G(s) level: SAT
- b. ISOLATE MW to ruptured SIG:
UNSAT 1} ENSURE AFW LCVs for ruptured S/G are CLOSED_
Comment
1503 NRC Sim JPM C Page 13of14 STEP 19 5_ MONITOR Ruptured S/G(s) level: SAT
- b. ENSURE AFW isolated UNSAT to ruptured SIG:
- 2) PLACE Turbine Driven APN LCV for ruptured SIG in CLOSE PULL TO LOCK.
Comment Terminating Provide the following cue "Another operator will perform the STOP Cue: remaining steps of this procedure."
Stop Time
JPM BRIEFING SHEET The examiner 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 1 has experienced a Steam Generator Tube Rupture on Steam Generator #1.
- 2. A manual safety injection was initiated.
- 3. E-3, STEAM GENERATOR TUBE RUPTURE is in progress, steps 1 through 3 of E-3 have been completed INITIATING CUES:
- 1. You have been directed to continue with E-3, STEAM GENERATOR TUBE RUPTURE beginning at Step 4.
- 2. Inform the SRO when you have isolated the #1 Steam Generator.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPM D
1503 NRC Sim JPM D Page 2of16 RO/SRO JOB PERFORMANCE MEASURE Task: Start a Reactor Coolant Pump Task#: 0030010101 Task Standard: The Operator manually stops the #1 Reactor Coolant Pump.
Alternate Path: YES: ---
x NO:
Time Critical Task: YES: NO: x KIA Reference/Ratings: APE 015/017 AA1.03 (3.7/3.8)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator x
- - - In-Plant - - - - Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
1503 NRC Sim JPM D Page 3 of 16 SPECIAL INSTRUCTIONS:
- 1) Ensure Simulator Operator Checklist is complete
- 2) Initialize to IC 268
b) Place MODE 3 sign on Panel M-4 c) Insert AN_OV_359 to OFF (Disables Loose Parts Alarm.)
d) Close the Loop 1 Pressurizer Spray valve
- 5) An extra operator will be required to acknowledge alarms.
- 6) ACKNOWLEDGE ALARMS
- 7) FREEZE SIMULATOR.
- 8) Provide a marked up procedure 1-S0-68-2, Reactor Coolant Pumps Section 5.1 completed through step 10 (and also provide Appendix 10 if requested.)
- 9) PLACE SIMULATOR IN RUN
- 10) Booth operator standby to insert the SCN File RCPHEATUP.scn (from exams folder) during the JPM
- 11) Go to SCENS
- 12) GO Exam folder
- 13) Run SCN File RCPHEATUP when the #1 RCP is started SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'
- 2. Any UNSAT requires comments.
Tools/Equipment/Procedures Needed:
1-S0-68-2 Reactor Coolant Pumps AOP- R.04 Reactor Coolant Pump Malfunctions
References:
Reference Title Rev No.
- 1. 1-S0-68-2 Reactor Coolant Pumps 39
1503 NRC Sim JPM D Page 4 of 16 DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3
- 2. Preparations are being made to start #1 RCP.
- 3. All precautions and prerequisites are complete.
- 4. 1-S0-68-2, Reactor Coolant Pumps Section 5.1, steps 1 through 10 are complete.
- 5. All other RCPs are in service INITIATING CUES:
- 1. You have been directed to start and monitor the #1 RCP using 1-S0-68-2, Reactor Coolant Pumps starting at step 5.1.11.
- 2. Notify the SRO when you are complete.
1503 NRC Sim JPM D Page 5 of 16 Start Time Obtain a copy of 1-S0-68-2, Reactor Coolant Pumps Section 5.1 STEP 1 SAT completed through step 10. --
- - UNSAT Standard: Examinee obtains a copy of 1-S0-68-2, Reactor Coolant Pumps Section 5.1.
Cue Provide a marked up copy of 1-S0-68-2, Reactor Coolant Pumps Section 5.1 completed through step 10.
Comment STEP 2 SAT
[11] PLACE [1-HS-68-84Al #1 RCP Lift Oil Pump in the START position. UNSAT Comment Examiner REAC COOL PMPS OIL LIFT PRESS LOW annunciation will come in Note and clear during performance of the next step
1503 NRC Sim JPM D Page 6of16 STEP 3 [12] WHEN Lift Oil Pump for #1 RCP has run
- - SAT 2 2 minutes, THEN ANNOUNCE #1 RCP start on the PIA system. - - UNSAT Standard: Examinee addresses the procedure step.
Cue: Provide the following cue, "Another operator will make the PA Announcement."
Comment
[13] IF no RCPs are running AND RCP #1 is the first STEP 4 - - SAT RCP to be started, THEN MONITOR the SRMs during startup of the RCP. [C.3] --
UNSAT Standard: Examinee determines other 3 RCPs are running and marks this step as N/A.
Comment STEP 5. SAT
[14] PLACE [1-HS-68-BAJ #1 RCP in the START position.
UNSAT Comment
1503 NRC Sim JPM D Page 7 of 16 Procedure NOTE Motor and Pump Operating Parameters are listed in Appendix D. Appendix E provides vibration limits if pump is Note started after maintenance activities.
STEP 6 - - SAT
[15] ENSURE #1 RCP motor and pump are operating within the parameters listed in Appendix D. UNSAT Standard: Examinee monitors #1 RCP motor and pump parameters using installed instrumentation.
Comment Examiner Note Directthe Booth Operator to insert File RCPHEATUP.scn.
The motor will start heating up and result in the REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH alarm on 1-M-5, Window E-Examiner 1 on 1-XA-55-58 coming in during the performance of the next steps .
Note (JPM steps 6-7; procedure steps 15-17). When alarm comes in, the operator may not complete performing procedure step 15, 16 or
- 17. N/A those steps if applicable and move on to JPM step 9 if the examinee transitions to alarm procedure.
STEP 7 - - SAT
[16] ENSURE {1-TCV-67-861 RCP Motor Cooler 1A is OPEN (1-HS-67-86 red light illuminated}.
- - UNSAT Standard: Examinee verifies 1-TCV-67-86 is open on Panel M-27A by observing the red indicating light above handswitch ON.
Comment
1503 NRC Sim JPM D Page 8 of 16
[17] WHEN Lift Oil Pump has run greater than 1 minute after STEP 8 RCP start, TH EN - - SAT UNSAT PLACE [1*HS-68-84AJ #1 RCP Lift Oil Pump in --
the STOP position.
Standard: Examinee places 1-HS-68-84A #1 RCP Lift Oil Pump handswitch to STOP Comment STEP 9 I eves SEAL WATER AND RCP 1-XA-55-58 I - - SAT
- - UNSAT 29 (E-1)
REAC COOL PMPS MOTOR STATOR I
TEMPERATURE HIGH Standard: Examinee acknowledges alarm and observes rise in RCP motor stator temperatures.
Comment If the actions contained in the Annunciator Response Procedure (ARP)
Examiner are implemented, JPM steps 11-24 cover the actions directed by the Note ARP and AOP to stop the RCP. If RCP is stopped without implementing the ARP, JPM 10 step will end the JPM.
1503 NRC Sim JPM D Page 9 of 16 STEP 10 SAT STOP Loop 1 RCP UNSAT If the examinee stops the RCP now provide the following cue, Cue "Another operator will perform the remaining steps of this procedure."
Comment Examiner The following steps are from the Annunciator Response Procedure 1-Note AR-MS-B.
NOTE RCP 1-4 is known to have high winding temperature (up to Procedure approximately 303°F when running with RCS temperature below Note 400°F. (EWR 10-COM-068-057)) However, alarms on RCP 1-4 should NOT be dismissed as "expected".
Corrective (1J DETERMINE which pump is in alarm by monitoring computer STEP 11 Actions points. - - SAT Pump 1: Point T0409A, 411 A or 412A (A,B, &C Pump 2: Point T0429A, 431 A or 432A {A,B, &C UNSAT Pump 3: Point T0449A, 451A or 452A (A,B, & C 0) --
Pump 4: Point T0469A, 471A or 472A (A,B, & C 0)
Standard: Examinee determines the #1 RCP in alarm by observing the ICS display.
Comment
1503 NRC Sim JPM D Page 10 of 16 STEP 12 - - SAT
[2] CONTACT Engineering to obtain engineering assistance in determining the validity of the alarm_ UNSAT Standard: Engineering is contacted to obtain engineering assistance in determining the validity of the alarm.
Respond as Unit Supervisor "Engineering has been contacted Cue and has validated the alarm."
Comment
[3] MONITOR the following parameters for increasing trends:
STEP 13 a_ Motor Current - - SAT b_ Bearing Temperatures
- - UNSAT C. Pump/Motor Vibration
- d. Containment Air Temperatures Examinee monitors or directs monitoring parameters by observing Standard: indications on installed instrumentation and determines indications normal.
Comment
1503 NRC Sim JPM D Page 11 of 16 STEP 14 - - SAT
[4] ENSURE ERCW' aligned to pump cooler.
- - UNSAT Standard: Examinee verifies ERCW aligned to pump cooler by observing red light above 1-HS-67-86 on O-M-27A ON.
Comment Examiner Note May have been performed in JPM step 7.
STEP 15 - - SAT
[5] VERIFY ERCW system temperature and pressure normal.
- - UNSAT Standard: Examinee verifies ERCW system temperature and pressure normal by observing indications O-M-27 A.
Comment STEP 16
- - SAT f6] VERIFY lower compartment air temperature normaL
- - UNSAT Standard: Examinee verifies lower compartment air temperature normal by observing indications on ICS and other installed plant instrumentation.
Comment
1503 NRC Sim JPM D Page 12 of 16 I STEP 17 --
[7] REFER TO 1-S0-68-2 for RCP operating limifa_
- - UNSAT Standard: Examinee refers to 1-S0-68-2 , Reactor Coolant Pumps Appendix D for the operating limits.
Comment If the remaining actions contained in the Annunciator Response Examiner Procedure (ARP) are implemented, JPM steps 19-20 cover the actions Note directed by the ARP and AOP to stop the RCP. If RCP is stopped at this point, JPM 18 step will end the JPM.
STOP Loop 1 RCP STEP 18 SAT UNSAT If the examinee stops the RCP now provide the following cue, Cue "Another operator will perform the remaining steps of this procedure."
Comment
1503 NRC Sim JPM D Page 13 of 16
[8] IF Ops/Engineering determines alarm is valid, THEN STEP 19 --
SAT PERFORM the following:
[a] CHECK pump motor amps. (normal 415 amps with 608 amps - - UNSAT maximum_)
[b] IF RCP motor amps approach 608 amps, THEN GO TO AOP-R04, Reactor Coolant Pump Malfunctions.
Examinee verifies pump amps normal by observing El-68-8 less than Standard:
400 amps.
Comment
[9] IF Ops/Engineering determines alarm is valid and pump motor STEP 20 - - SAT stator temperature approaches 311°F (329"F for RCS temperature less than 540°F}, THEN
- - UNSAT GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
Standard: Examinee observes the motor winding temperature is greater than 311°F using the ICS and goes to AOP-R.04.
Cue Respond as Engineering "Alarm is valid."
Comment STEP 21 'L DIAGNOSE the failure: - - SAT
- - UNSAT II Motor Stator Temperature High on ANY RCP I 2.6 I
24 II Standard: Examinee goes to AOP-R.04 section 2.6 or 2.1 Comment
1503 NRC Sim JPM D Page 14 of 16 Procedure CAUTION: Operating the RCP with excess winding temperature will reduce the expected Caution life of the motor insulation.
NOTE: RCP motor winding temperature limits are as follows:
Procedure Note
- 329°F if RCS temperature is less than 540"'F.
- 3'! 1°F if RCS temperature is greater than or equal to 540°F .
Alternate Path STEP 22 - - SAT
- 1. MONITOR RCP Motor Stator temperature a. IF RCP Motor Stator temperature less than applicable limit by monitoring reaches applicable limit - - UNSAT the following computer points: AND indication is verified valid.
THEN
- Pump *1: T0409A, 41'1Aor412A PERFORM the following:
- Pump 2: T0429A, 431A or 432A
- 1) IF reactor power less than 20%,
- Pump 3: T0449A. 45'1A or 452A
. Pump 4: T0469A, 471A or 472A THEN GO TO Section 2. *1, ANY RCP Tripped or RCP Shutdown Required [C.1]
~
Examinee determines the motor winding temperature is greater than Standard: 311°F by observing the ICS and goes to the RNO column and ultimately to Section 2.1.
Comment 2.1 ANY RCP Tripped or RCP Shutdown Required Procedure Caution CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is stopped.
'1. CHECK unit in Mode 1 or 2. STOP affected RCP(s).
STEP 23 --
SAT Time:
UNSAT GO TO Caution prior to Step 3.
~
Standard: Examinee determines the Unit is in MODE 3 and proceeds to RNO Comment
1503 NRC Sim JPM D Pa e 15 of 16 CHECK unit in Mode -1 or 2_ STOP affected RCP(s)_
STEP 24 SAT Time: _ _ __
UNSAT GO TO Caution prior to Step 3_
Comment Terminating Provide the following cue "Another operator will perform the Cue: STOP remaining steps of this procedure."
Stop Time ____
JPM BRIEFING SHEET I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3
- 2. Preparations are being made to start #1 RCP.
- 3. All precautions and prerequisites are complete.
- 4. 1-S0-68-2, Reactor Coolant Pumps Section 5.1, steps 1 through 10 are complete.
- 5. All other RCP's are in service INITIATING CUE:
- 1. You have been directed to start and monitor the #1 RCP using 1-S0-68-2, Reactor Coolant Pumps starting at step 5.1.11.
- 2. Notify the SRO when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPM E
2015 NRG SIM JPM E Page 2 of 11 RO/SRO JOB PERFORMANCE MEASURE Task: Respond to uncontrolled depressurization of all Steam Generators per ECA-2.1.
Task#: 3310100601 Task Standard: The examinee will reduce AFW flow to all Steam Generators to less than 60 gpm but with positive flow > 30 gpm as indicated on all Steam Generators.
Alternate Path: YES: NO: x Time Critical Task: YES: - - - NO: x KIA Reference/Ratings: EPE-E12 EA-1.1 (3.8/3.8)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator x
- - - In-Plant - - - - Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 10 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
2015 NRG SIM JPM E Page 3 of 11 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset to IC 276
- 3. If IC 276 is not available perform the following:
- Reset to IC 16.
- IMF MS04A f:1
- IMF MS04B f:1
- IMF MS04C f:1
- IMF MS04D f: 1
- IMF MS01A f:100
- PLACE SIMULATOR IN RUN
- Trip the Reactor.
- When T Cold has reached 470 deg, FREEZE SIMULATOR.
- 4. PLACE SIMULATOR IN RUN
- 5. Trip the Reactor.
- 6. An extra operator will be required to acknowledge alarms.
- 7. ACKNOWLEDGE ALARMS
- 8. When T Cold has reached 470 deg, FREEZE SIMULATOR.
- 10. PLACE SIMULATOR IN RUN
- 11. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.
Tools/Equipment/Procedures Needed:
References:
Reference Title Rev No.
- 1. ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM 11 GENERATORS 2.
2015 NRG SIM JPM E Page 4 of 11 DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3.
- 2. The crew has just completed all applicable steps of E-2, Faulted Steam Generator Isolation and has transitioned to ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
INITIATING CUES:
- 1. The SRO has directed you to perform ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS starting at step 1.
- 2. Inform the SRO when complete.
2015 NRC SIM JPM E Page 5 of 11 Start Time STEP 1 - - SAT Obtain a copy of ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS
- - UNSAT Standard: Examinee obtains a copy of ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS Comment CAUTION Isolating both steam supplies to the TD AFW pump when it is the only source of feed flow will result in loss of secondary heat sink.
NOTE This procedure has a foldout page.
STEP 2 - - SAT NOTE This procedure has a foldout page.
- - UNSAT Standard: The examinee reviews the Foldout Page.
Examiner The Foldout Page items are on the next page. The Examinee should Note: not take any actions as a result of the Foldout Page.
Comment
2015 NRC SIM JPM E Page 6 of 11 FOLDOUT PAGE SI REINITIATION CRITERIA IF either of the following conditions occurs:
- Pressurizer level CANNOT be maintained greater than 10% [20% ADV],
THEN RAISE ECCS flow by performing one or both of the following:
- ESTABLISH CCPIT flow USING Appendix C
EVENT DIAGNOSTICS
- IF both trains of shutdown boards deenergized, THEN GO TO ECA-0.0, Loss of All AC Power.
- IF any SIG pressure rises at any time AND Steps 15 through 25 are NOT in progress, THEN RAISE AFW flow to intact S/G as necessary and GO TO E-2, Faulted Steam Generator Isolation.
- IF any S/G has level rising in an uncontrolled manner or has abnormal radiation, THEN
- a. RAISE ECCS flow by performing one or both of the following as necessary:
- ESTABLISH CCPIT flow USING Appendix C
- b. GO TO E-3, Steam Generator Tube Rupture.
TANK SWITCHOVER SETPOINTS
- IF CST level less than 5%,
THEN ALIGN AFW suction to ERCW.
- IF RWST level less than 27%,
THEN GO TO ES-1.3, Transfer to RHR Containment Sump.
2015 NRC SIM JPM E Page 7 of 11
- 1. CHECK secondary pressure boundary:
STEP 3 - - SAT
- a. CHECK the following: a. CLOSE valves to restore pressure boundary on at least one SIG. UNSAT
CLOSED IF valves CANNOT be closed, THEN
- MFW regulating valves and DISPATCH personnel to close valves reg bypass valves CLOSED locally, one loop at a time:
- MFW isolation valves CLOSED
- CLOSE MSIV and bypass valve as necessary USING EA-1-1,
- Atmospheric reliefs CLOSED Closing MSIVs Locally .
- SIG blowdown valves CLOSED.
- ISOLATE S/G atmospheric relief valve as necessary USING EA-1-2, Local Control of SIG PORVs.
- ISOLATE blowdown locally as necessary.
Standard: The Examinee Checks the MSIVs are OPEN and cannot be closed.
The examinee addresses the Step 1a RNO actions.
Cue When asked provide the following cue, "Time has been compressed operators report the MSIVs cannot be closed using EA-1-1."
Comment STEP 4 - - SAT
- - UNSAT The Examinee checks MD AFW pumps running as indicated by red Standard:
light above HS-3-118A and 128A AFW Pump 1A-A and 1B-B ON.
Comment
2015 NRC SIM JPM E Page 8 of 11 STEP 5 SAT c CLOSE TD AFW pump steam supply valve FCV-1-17 or FCV-1-18. UNSAT Comment NOTE Reducing total feed flow to less than 440 gpm, as directed in this procedure, does NOT require implementation of FR-H.1, Loss of Secondary Heat Sink, as long as a total feed flow capability of 440 gpm is available.
- 2. CONTROL feed flow to minimize STEP 6 RCS cooldown:
- a. CHECK T-cold cooldown rate a. REDUCE feed flow to 50 gpm UNSAT less than 1QOGF/hr. to each SIG.
OPEN MD AFW pump recirc valves FCV-3-400 and FCV-3-401 as necessary to control flow.
GO TO Substep 2.c (AER column).
Comment
2015 NRC SIM JPM E Page 9 of 11 STEP 7 c. MONITOR SIG narrow range levels c. MAINTAIN feed flow to affected S/G(s) --
SAT greater than 10% (25% ADV]. greater than or equal to 50 gpm UNTIL level greater than 10% (25% ADV]. - - UNSAT Standard: The Examinee maintains AFW flow to all Steam Generators.
Comment
- 3. MAINTAIN shutdown margin adequate:
STEP 8 - - SAT UNSAT
- a. NOTIFY Chem Lab to sample RCS --
boron concentration.
- b. CHECK shutdown margin ADEQUATE USING O-Sl-NUC-000-038.0, Shutdown Margin.
Standard: The Examinee addresses the procedure step.
Cue: Acknowledge communication steps, as required.
Comment
2015 NRC SIM JPM E Page 10of11
- 4. MONITOR if RCPs should be stopped:
STEP 9 --
- a. CHECK if the following a. GO TO Step 5.
conditions exist: - - UNSAT
- RCS subcooling based on core exit T/Cs less than 40°F
~
- b. STOP RCPs.
Standard: The examinee determines RCP's are to be left running.
Comment Terminating Provide the following cue, "Another operator will complete the Cue: STOP remaining steps of this procedure."
Stop Time _ _ __
JPM BRIEFING SHEET The examiner 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 1 is in MODE 3.
- 2. The crew has just completed all applicable steps of E-2, Faulted Steam Generator Isolation and has transitioned to ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
INITIATING CUES:
- 1. The SRO has directed you to perform ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS starting at step 1.
- 2. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPM F
1503 NRC Sim JPM F Page 2of13 RO/SRO JOB PERFORMANCE MEASURE Task: Respond to High Containment Pressure, Place RHR Spray in Service Task#: 3110160601 (RO)
Task Standard: The examinee will establish one train of RHR spray in service using FR-Z.1, HIGH CONTAINMENT PRESSURE.
Alternate Path: YES: - - x - NO:
Time Critical Task: YES: NO: x KJA Reference/Ratings: W/E14 EA1 .1 (3.7/3.7)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator x In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 8 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
1503 NRC Sim JPM F Page 3of13 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset to IC 254
- a. Activate MF# TH01A at 35%.
- b. Activate MFs # CH01 A thru D at 70% (-10.2 psid) with 240 sec ramp.
C. Stop RCPs.
- e. Activate Override ZDIHS7241A CLOSE, to prevent FCV-72-41 from opening.
- f. Activate ZAOPDl30133 f:5
- g. Activate ZAOPDIR30133 f:0.5
- 4. Activate the following, as necessary, to prevent nuisance alarms:
- h. AN:OVRN[96] to ON, prevents Turbine Zero Speed alarm
- i. AN:OVRN[304] to ON, prevents Saturation Monitor alarm
- 5. Insert Remote Function RHR14 ON, places power on FCV-63-1.
- 6. PLACE SIMULATOR IN RUN
- 7. An extra operator will be required to acknowledge alarms.
- 8. ACKNOWLEDGE ALARMS
- 9. FREEZE SIMULATOR.
- 11. PLACE SIMULATOR IN RUN
- 12. At JPM step 15, when candidate opens 1-FCV-72-40:
- j. Modify malfunction CH01A f:O r:240 k:1
- k. Modify malfunction CH01B f:O r:240 k:1 I. Modify malfunction CH01 B f:O r:240 k: 1
- m. Modify malfunction CH01 D f:O r:240 k: 1
- 13. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.
1503 NRC Sim JPM F Page 4of13
- 14. Tools/Equipment/Procedures Needed:
FR-Z.1, HIGH CONTAINMENT PRESSURE, step 13 (marked up through step 12)
References:
Reference Title Rev No.
- 1. FR-Z.1 High Containment Pressure 19
1503 NRC Sim JPM F Page 5of13 DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS;
- 1. Unit 1 has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.
- 2. The crew is monitoring step 13 of FR-Z.1, HIGH CONTAINMENT PRESSURE.
- 3. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.
INITIATING CUES:
- 1. The SRO directed you to initiate one train of RHR spray per FR-Z.1, HIGH CONTAINMENT PRESSURE starting at step 13.
1503 NRC Sim JPM F Page 6of13 Start Time 1
STEP - - SAT Obtain a copy of the FR-Z.1, HIGH CONTAINMENT PRESSURE UNSAT Standard: Examinee obtains a copy of FR-Z.1, HIGH CONTAINMENT PRESSURE Cue Provide an in-progress copy of FR-Z.1, HIGH CONTAINMENT PRESSURE complete through step 12 Comment STEP 2 n_ MONITOR if RHR spray should be placed 1n service: - - SAT a_ CHECK the following: - - UNSAT
. Containment pressure greater than 9 .5 psig AND Standard: Examinee checks 1-PDl-30-45 and 44 and determines that pressure is greater than 9.5 Comment
1503 NRC Sim JPM F Page 7of13 STEP 3 n_ MONITOR if RHR spray should be placed in seMce: - - SAT a_ CHECK the following: - - UNSAT
. At least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident Standard: Examinee determines from initiating cues (or asks US) that 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed Cue IF asked, provide the following cue, "1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident".
Comment STEP 4 n_ MONITOR if RHR spray should be placed 111 seMce: - - SAT a._ CHECK the follo*wing: - - UNSAT
. RHR suction ALIGNED to containment sump Examinee checks FCV-63-72 and 73 OPEN and FCV-74-3 and 21 Standard: CLOSED, or asks if ES-1.3, "Transfer to RHR Containment Sump,"
has been completed.
Cue IF asked, provide the following cue, "ES-1.3 has been completed."
Comment
1503 NRC Sim JPM F Page 8 of 13 STEP 5 n_ MONITOR if RHR spray should be placed SAT 1n service: --
a_ CHECK the following: - - UNSAT
. At least one CCP AND one SI pump RUNNING.
Examinee verifies at least one CCP is running as indicated by Red light on HS-62-104A or 108A ON.
Standard: AND Verifies at least one SI pump is running as indicated by Red lights on HS-63-10A or 15A ON.
Comment 6
STEP 13. MONITOR if RHR spray should be placed
- - SAT in service~
b_ CHECK both RHR pumps RUNNING. - - UNSAT Standard: Examinee checks that both RHR pumps are running as indicated by red lights on HS-74-10A and 20A "ON".
Comment 7
STEP 13. c: ESTABLISH Train B RHR spray: - - SAT
- 1) CHECK Train B RHR pump
- - UNSAT RUNNING.
Standard: Examinee checks that 1B-B RHR pump is running as indicated by red light on HS-74-20A "ON".
Comment
1503 NRC Sim JPM F Page 9of13 8
STEP n. C. ESTABLISH Train B RHR spray: - - SAT
- 2) ENSURE RHR crosstie FCV-74-35 CLOSED. - - UNSAT Standard: Examinee verifies FCV-74-35 in the CLOSED position as indicated by HS green light ON and red light OFF Comment STEP g B. c. ESTABLISH Train B RHR spray: SAT
- 3) CLOSE RHR injection UNSAT FCV-63-94.
Comment 10 Begin ALTERNATE PATH STEP - - SAT
- n. C. ESTABLISH Train B RHR spray: UNSAT
- 4) OPEN RHR spray FCV-72-41.
Examinee places handswitch for RHR injection FCV-72-41 in the Standard: OPEN position and recognizes that the green light stays ON and the red light is OFF, goes to RNO column.
Comment
1503 NRC Sim JPM F Page 10 of 13 11 ALTERNATE PATH STEP - - SAT c_ IF Train B RHR spray CANNOT be established, - - UNSAT THEN PERFORM the following:
a) ENSURE RHRspray FCV-72-41 CLOSED.
Examinee verifies FCV-72-41 closed as indicated by green light ON Standard:
and red light OFF.
Comment 12 c. IF Train B RHR spray STEP SAT CANNOT be established, THEN PERFORM the following: UNSAT b) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-94 OPEN.
Comment 13 C. IF Train B RHR spray STEP CANNOT be established, - - SAT THEN PERFORM the follmving: - - UNSAT c) ESTABLISH Train A RHR spray:
('I) ENSURE RHR crosstie FCV-74-33 CLOSED.
Examinee verifies RHR crosstie FCV-74-33 in the CLOSED position Standard:
as indicated by green light ON handswitch.
Comment
1503 NRC Sim JPM F Page 11 of 13 14 c. IF Train B RHR spray STEP SAT CANNOT be established, THEN PERFORM the following:
UNSAT c) ESTABLISH Train A RHR spray:
(2) CLOSE RHR injection FCV-63-93.
Comment 15 c. IF Train B RHRspray STEP SAT CANNOT be established, THEN PERFORM the following: UNSAT c) ESTABLISH Train A RHR spray:
(3) OPEN RHR spray FCV-72--40.
Examiner When examinee starts to open FCV-72-40, initate a 240 sec ramp on Note CH01 A thru D to reduce CNMT pressure from 10.2 to zero (0).
Comment
1503 NRC Sim JPM F Page 12 of 13 16 STEP - - SAT Examinee verifies that RHR Containment spray is effective in lowering CNMT pressure. --
UNSAT Standard: Examinee verifies that CNMT pressure is lowering by observing Lower pressure readings on CH01A thru D Comment Terminating Provide the following cue, "Another operator will complete the Cue: STOP remaining steps of this procedure."
Stop Time ----
DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.
- 2. The crew is monitoring step 13 of FR-Z.1, HIGH CONTAINMENT PRESSURE.
- 3. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.
INITIATING CUES:
- 1. The SRO directed you to initiate one train of RHR spray per FR-Z.1, HIGH CONTAINMENT PRESSURE starting at step 13.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPMG
2015 NRG SIM JPM G Page 2 of 10 RO/SRO JOB PERFORMANCE MEASURE Task: 3210430301 Task#: Respond to a loss of Shutdown Board using AOP-P.05.
Task Standard: The examinee will respond to a loss of Shutdown Board using AOP-P.05 and start the 1A Charging pump. Subsequently the examinee will place the 1B Diesel Generator in emergency stop due to a failure of the cooling water valve to open.
Alternate Path: YES: - - x - NO:
Time Critical Task: YES: NO: x KIA Reference/Ratings: 062 A2.04 (3.1/3.4)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator x In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 8 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
2015 NRG SIM JPM G Page 3 of 10 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset to IC 16
- 3. PLACE SIMULATOR IN RUN
- 4. An extra operator will be required to acknowledge alarms.
- 5. ACKNOWLEDGE ALARMS
- 6. FREEZE SIMULATOR
- 8. PLACE SIMULATOR IN RUN
- 9. De-energize the 1B 6.9 kv Shutdown Board by inserting IMF ED068
- 10. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.
Tools/Equipment/Procedures Needed:
References:
Reference Title Rev No.
- 1. AOP-P.05 LOSS OF UNIT 1 SHUTDOWN BOARDS 23 2.
2015 NRC SIM JPM G Page 4 of 10 DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 1.
INITIATING CUES:
- 1. Respond to plant conditions
2015 NRC SIM JPM G Page 5 of 10 Start Time STEP 1 - - SAT Obtain a copy of AOP-P.05 LOSS OF UNIT 1 SHUTDOWN BOARDS.
- - UNSAT Standard: Examinee obtains a copy of AOP-P.05 LOSS OF UNIT 1 SHUTDOWN BOARDS.
Comment
- 2. DETERMINE applicable section:
GOTO IF ... SECTION PAGE 1A-A 2.1 4 6900V Shutdown Board DE-ENERGIZED 18-8 2.2 20 STEP 2 --
SAT Determine applicable section.
- - UNSAT Standard: The examinee determines the 1B 6.9 kv Shutdown Board is de-energized and proceeds to section 2.2.
Comment
2015 NRC SIM JPM G Page 6 of 10 NOTE
- Loss of power to this board will result in a loss of RPls and rod bottom lights .
STEP 3 --
- 1. MONITOR 1A-A 6900V Shutdown Board ENERGIZED. - - UNSAT Standard: The examinee monitors 1A-A 6900V Shutdown Board ENERGIZED by observing plant instrumentation.
Comment CAUTION
- Restoring seal cooling to an overheated RCP seal could result in RCP seal damage or steam voiding in CCS.
- Operation of RCPs for greater than 2 minutes without CCS cooling to oil coolers will result in bearing temperatures greater than 200°F.
STEP 2. CHECK RCP seal cooling available:
- - SAT 4
- seal injection flow UNSAT OR
- thermal barrier cooling flow Standard: Addresses the procedure step.
Comment
2015 NRC SIM JPM G Page 7 of 10
- M-B ERCW Pump
- - UNSAT OR
- P-B ERCW Pump Standard: The examinee verifies B Train ERCW running by observing the red light above the respective handswitch ON.
Comment ALTERNATE PATH STEP 6 SAT
- 4. ENSURE the following: EMERGENCY STOP any running DIG with NO ERCW cooling available. UNSAT
- D/Gs RUNNING
- ERCW ALIGNED to running D/Gs.
Comment STEP 7 5. ENSURE CCS pumps RUNNING: - - SAT
- b. ENSURE 28-B or C-S CCS Pump supplying Train B.
The examinee verifies 1A CCS pump running by observing the red light above the HS-70-47A ON.
Standard:
The examinee verifies C-S CCS pump running by observing the red light above the HS-70-51A ON.
Comment
2015 NRG SIM JPM G Page 8of10 NOTE If RHR pump 1B-B was in service for shutdown cooling prior to loss of 6900V Shutdown Board 18-8, the pump will not restart automatically.
SAT for shutdown cooling, THEN ENSURE AOP-R.03, RHR System - - UNSAT Malfunctions, entered to address RHR pump trip, WHILE continuing in this procedure.
Standard: The examinee addresses the procedure step as N/A.
Comment STEP 9 - - SAT
- 7. MONITOR REACTOR COOLANT PUMPS MOTOR THRUST BEARING TEMP HIGH UNSAT alarm DARK. [1-M-58, E-3) --
Standard: The Examinee observes [1-M-58, E-3] dark.
Comment ALTERNATE PATH STEP 9 SAT
UNSAT
- a. ENSURE CCP suction path:
- LCV-62-132 and -133 OPEN with VCT level greater than 20%
- LCV-62-135 OPEN
Comment
2015 NRG SIM JPM G Page 9 of 10 Terminating Provide the following cue, "Another operator will complete the STOP Cue: remaining steps of this procedure."
Stop Time ____
JPM BRIEFING SHEET The examiner 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 1 is in MODE 1.
INITIATING CUES:
- 1. Respond to plant conditions Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT 1503 NRC SIMULATOR JPM H
2015 NRC SIM JPM H Page 2 of 16 RO/SRO JOB PERFORMANCE MEASURE Task: Respond to a loss of Essential Raw Cooling Water per AOP-M.01.
Task#: 0000620501 Task Standard: The examinee will respond to a loss of ERCW by starting the STANDBY A TRAIN ERCW Pump and the ERCW Header leak has been isolated.
Alternate Path: x YES: - - - NO:
Time Critical Task: YES: NO: x KIA Reference/Ratings: APE A07AA1.3 (3.3/3.5)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator x
- - - In-Plant - - - Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
2015 NRC SIM JPM H Page 3 of 16 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Reset to IC 16
- 3. PLACE SIMULATOR IN RUN
- 4. An extra operator will be required to acknowledge alarms.
- 5. ACKNOWLEDGE ALARMS
- 6. FREEZE SIMULATOR.
- 8. PLACE SIMULATOR IN RUN
- 9. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.
- 10. When directed insert malfunction MF RW01G (Trips Q-A ERCW Pump)
- 11. When directed insert malfunction RW138 at 90% prior to JPM step 8.
Tools/Equipment/Procedures Needed:
References:
Reference Title Rev No.
2015 NRG SIM JPM H Page 4 of 16 DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 1.
INITIATING CUES:
- 1. Respond to plant conditions
2015 NRG SIM JPM H Page 5 of 16 Start Time ERCW/CCS PUMP PUMP R-A DISH PRESS MOTOR LOW TRIP Responds to alarm using ARP O-AR-M27-A, B-2 and/or O-AR-M27-BA, STEP 1 SAT E-4 --
UNSAT
[1] IF ERCW pump motor TRIPS, THEN GO TO AOP-M_Oi, Loss of Essential Raw Cooling Water.
[2] IF CCS motor trip, THEN GO TO AOP-rvt03, Loss of Component Cooling Water.
[3] DETERMINE which motor tripped.
[4] TURN control switch to OFF position to reset alarm_
[5] DISPATCH operator to investigate cause of alarm.
[6] EVALUATE LCO 3T3 (CCS) or 3.7A (ERCW).
Standard: Examinee Places O-HS-67-460A ERCW Pump Q-A in PTL.
Comment
2015 NRC SIM JPM H Page 6 of 16 CAUTION: ERCW header rupture in Aux Bldg could fill passive sump in 15 minutes.
Prompt action may be needed to isolate rupture using this AOP.
- 1. CHECK for indlcations of ERCW rupture GO TO Step4.
STEP 2 inside Aux Building: - - SAT
- flooding from ERCW inside Aux Bldg which requires rapid isolation to protect
~ --
UNSAT equipment or personnel OR
- abnormal high flow indicated on any ERCW supptf header in conjunction with flooding alarms or other indications of ruptl.Jre.
Examinee determines no leak exists in the Aux Building based on no Standard: reports of flooding and no indications of high flow and so goes to RNO and then to STEP 4 Comment STEP 3 4. IF this procedure entered for any reason
- - SAT other than ERCW rupture in Aux Bldg, THEN GO TO applicable section: - - UNSAT Standard: The examinee determines a pump trip has occurred and goes to section 2. 1.
Comment
2015 NRC SIM JPM H Page 7 of 16 IF ... GO TO SECTION PAGE ERCW Pump(s) tripped or failed 2.1 ERCW pump failure 9 STEP 4 --
SAT 1- IDENTIFY and LOCK OUT failed ERCW pump.
- - UNSAT Standard: Examinee Places O-HS-67-460A ERCW Pump Q-A in PTL if not already performed.
Comment STEP 5 SAT
- 2. START additional ERCW pumps as required to maintain supply header pressure between 78 psig and 124 psig. UNSAT Comment STEP 6 - - SAT
- 3. CHECK two Train A ERCW Pumps AVAILABLE.
- - UNSAT Standard: Examinee verifies that 2 Train A ERCW Pumps are available based on various indications.
Comment
2015 NRG SIM JPM H Page 8 of 16
- - UNSAT
- a. Supply header pressures Ibetween 7~ psig and 124 psig]:
,. 1-Pl-67-493A
- 2-Pl-67-493A
- b. Supply header flows
[expected vatue]:
It 1-Fi-67-61
- 2-FJ-67-61 Standard: Examinee determines that A Train supply header pressures and flows are normal based on plant indicators.
Comment Examiner Direct the simulator operator to insert RW138 at 90% prior to JPM step Note: 8. Change to B Train.
ALTERNATE PATH STEP 8 - - SAT r
"* CHECK 1B am:l 2B ERCW supply header If header leak or rupture is indicated, pressures and flows NORMAL: THEN - - UNSAT RETURN TO Section 2.0 for diagnosis.
- a. Supply header pressures {between 78 psig and 124 psig]: _;1111--
- 1-PJ-67-488A If NO Train B ERCW pump ls available,
- 2-Pl-67-488A THEN GO TO Section 2.11, Loss of Train B ERGW.
- b. Supply header !lows [expected valuej:
- 1-Fl-67-62 ~
- 2-Fl-67-62 If pressure is low due to only one pump available, THEN EVALUATE isolatlcn of non-essential ERCW loads.
Examinee checks Train B header pressures and flows and determines Standard: flows are abnormal based on the listed indicators, goes to the RNO and then to Section 2.0 for diagnosis Comment
2015 NRG SIM JPM H p aqe 9 0 f 16 CAUTION: ERCW header rupture in Aux Bldg could fill passive sump in 'f5 minutes.
Prompt action may be needed to isolate rupture using this AOP.
- 1. CHECK for indications of ERCW rupture GO TO Step4.
STEP 9 inside Aux Building: - - SAT
- flooding from ERCW inside Aux Bldg which requires rapid isolation to protect
~ - - UNSAT equipment or personnel OR
- abnom1al high !low indicated on any ERON supp.ly header in conjunction with flooding a!amis or other indications of mpture.
If asked provide the following cue," There are no reports of flooding Cue from the Aux Building."
Examinee determines no leak exists in the Aux Building based on no Standard: reports of flooding and no indications of high flow and so goes to RNO and then to STEP 4 Comment STEP 10 4. If this procedure entered for any reason other lhan ERCW mpture in Aux Bldg, - - SAT THEN
- - UNSAT GO TO applicable section:
law flow ERCW supply headers 18 and 26, AND STRAINER D!FF PRESS alarms DARK
[M-27A, C-6 and 0-SJ, AND at least one of the following alarms UT:
[1-M-156, A-3] Upstream of Strainer Inlet Valves OR OR Loss of Train B ERCW
{1-M-15A, B-6]
Examinee determines Section 2.11 is applicable based on Low flow on Standard: ERCW supply headers 1B and 28 and one or more of the specified alarms.
Comment
2015 NRG SIM JPM H p age 10 0 f 16
- 1. CHECK this section entered for any STEP 11 of the following: --
- rupture known to be upstream of ERON strainer inlet valve - - UNSAT (I or 2-FCV-67-489)
- rupture which CANNOT be isolated OR
- rupture which requires stopping aH Train 8 ERCW flow.
Examinee determines that rupture is known to be upstream of due to Standard: absence of Strainer Differential Pressure alarms in combination with low flow in both 1B and 28 headers as identified in diagnosis step.
Cue: If asked provide the following cue, "The leak is upstream of the 8 Train strainer."
Comment CAUTION: If running, Train B CCP and SI Pumps may experience bearing failure 10 minutes after loss of ERCW cooling.
ALTERNATE PATH STEP 12 SAT
- 2. STOP and LOCK OUT aUTrain B ERCW Pumps. UNSAT Comment
2015 NRC SIM JPM H Page 11 of 16 CAUTION: Pipe rupture inside ERCW Pumping Station could result in safety hazards due to water spray and flooded compartments.
- 3. IF performing this section due to rupture STEP 13 Inside ERCW pumping station - - SAT OR due to rupture in unknown location, THEN UNSAT DISPATCH operators with radios to perform me following:
- PERFORM Appendix G.2, ERCWMCC Valves. [ERCW Pumping Station}
. EHSURE all pumping station watertight doors are CLOSED.
[ERCW Pumping Station]_
Standard: Examinee addresses step and dispatches personnel to perform the required appendix and close watertight doors.
Cue Role play and acknowledge the request.
Comment 4_ OPEN alternate ERCW supply to STEP 14 Train B DfGs SAT
- 1-FCV-67-65 (1B-B DIG) UNSAT
- 2-FCV-<>7-65 (2B-B O!G'.f Cue: Provide the following cue, "Unit 2 HS-67-65 has been opened."
Comment
2015 NRC SIM JPM H Page 12 of 16 STEP 15 5. DISPATCH operator to place Train B - - SAT Aux Air Compressor in SAFE STOP.
[Aux Bldg, 734' elev, Refuel Floor}
- - UNSAT Standard: Examinee addresses the procedure step.
Cue Role play and acknowledge the request.
Comment
- 6. Unit *1 Only:
STEP 16 STOP affected pumps: - - SAT
- 1) ENSURE letdown orifice valves CLOSED.
- 2) GO TO Substep 6.b.
~
Standard: Examinee identifies that 1A CCP is not running and goes to RNO.
Comment
2015 NRC SIM JPM H Page 13of16 STEP 17 a. IF RCP them1al barrier cooling is SAT in service, THEH UNSAT
- 1) ENSURE letdown orifice valves CLOSED.
- 2) GO TO Substep 6-b.
~
Comment STEP 18 SAT
UNSAT Comment STEP 19 - - SAT
- c. PLACE SI pump 18-B in PULL TO LOCK.
- - UNSAT Standard: Examinee places HS-63-1 SA SI Pump 1Bin PTL.
Comment
2015 NRC SIM JPM H Page 14 of 16
- 7. Unit2 Onty:
STEP 20 STOP affected pumps:
UNSAT
- 1) ENSURE letdown orifice valves CLOSED.
- 2) GO TO Substep 7.b.
~
IF RCP thermal barrier cooling is NOT in service, THEN PERFORM Ille folfowing:
- 1) WHEN :CCP 2A-A ls running {Step 8},
THEN PLACE CCP 26-B in PULL TO LOCK.
- 2) GO TO Substep 7.c.
~
- c. PLACE SI pump 28-B in PULL TO LOCK Standard: Examinee addresses the procedure step.
Cue: Provide the following cue, "Unit 2 will perform Step 7".
Comment STEP 21 SAT
- 8. ENSURE Train A CCPs RUNNING.
UNSAT Comment
2015 NRG SIM JPM H Page 15of16 Terminating Provide the following cue, "Another operator will complete the STOP Cue: remaining steps of this procedure."
Stop Time _ _ __
JPM BRIEFING SHEET The examiner 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 1 is in MODE 3.
INITIATING CUES:
- 1. Respond to plant conditions Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1503 NRC PLANT JPM I
1503 NRC PLANT JPM I Page 2 of 10 RO/SRO JOB PERFORMANCE MEASURE Task: Locally closing MSIV's by pulling control power fuses.
Task#: 3010030601 Task Standard: The examinee closes MSIV's for SG 2, 3, and 4 by placing its transfer control switch in the Auxiliary Control Room in the AUX position then removes the control power fuses on the associated 125 V Vital Battery Board for SG 1.
Alternate Path: YES: - - - NO: x Time Critical Task: YES: NO: x KIA Reference/Ratings: APE 040AA1.04 (4.3/4.3)
Method of Testing:
Simulated Performance: x Actual Performance:
Evaluation Method:
Simulator In-Plant x Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 8 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
1503 NRC PLANT JPM I Page 3of10 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. SM approval will be required to enter the 'Trip Hazard Zone" in backup control room.
- 2. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'
- 3. Any UNSAT requires comments.
Tools/Equipment/Procedures Needed:
References:
Reference Title Rev No.
- 1. EA-1-1 Closing MSIVs Locally 1
========================================================================
READ TO EXAMINEE HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
DIRECTIONS TO OPERATOR:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 is in MODE 3
- 2. Unit 2 has experienced faulted SG's.
- 4. All MSIV bypass valves are closed.
INITIATING CUES:
- 2. Inform the SRO when complete.
1503 NRC PLANT JPM I Page 4 of 10 Start Time STEP 1 - - SAT Obtain a copy of EA-1-1, Closing MSIVs Locally.
- - UNSAT Standard: Operator obtains a copy of EA-1-1, Closing MSIVs Locally.
Cue ProvideacopyofEA-1-1, Closing MSIVs Locally.
Comment 4.1 Section, Applicability STEP 2 - - SAT
- 1. SELECT applicable unit:
- - UNSAT
- Unit 1
- Unit2 - -
Standard: The Examinee selects Unit 2 based on the initiating cue.
Comment
1503 NRC PLANT JPM I Page 5of10 I 2. SELECT affected valve(s):
STEP 3 - - SAT SIG AFFECTED VALVE{S)
UNSAT
- 4 MSIV 0 MSIV bypass 0 Standard: The examinee selects all MSIV's based on the initiating cue Comment
~ - - UNSAT Standard: The examinee addresses the procedure step as N/A.
Comment
~ - - UNSAT Standard: The Examinee addresses the step as N/A.
Comment
1503 NRC PLANT JPM I Page 6of10 I 5. IF any Unit 2 MS!V will NOT close, STEP 6 - - SAT THEN GO TO Section 4.4. D
- - UNSAT
~
Standard: The Examinee goes to section 4.4 Comment 4.4 Unit 2 MSIV Isolation STEP 7 - - SAT
- 1. PLACE affected MSIV transfer control switch in AUX position:
- - UNSAT
[Auxiliary Control Room, Panels 2-L-11A and 2-L-118]
AUX TRANSFER AUX POSITION SIG EQUIPMENT ,/
SWITCH 1
MS!V Loop 1, Train A, 2-FCV-1-4 2-XS-1-4A D MS!V Loop 1, Train B, 2-FCV-1-4 2-XS-1-48 D Standard: The Examinee places 2-XS-1-4A & 2-XS-1-48 and to AUX.
Comment
1503 NRC PLANT JPM I Page 7 of 10 4.4 Unit 2 MSIV Isolation STEP 8 SAT
- 1. PLACE affected MSIV transfer control switch in AUX position:
[Auxiliary Control Room, Panels 2-L-11A and 2-L-11B] UNSAT AUX TRANSFER AUX POSITION S/G EQUIPMENT SWITCH '1 MSIV Loop 2, Train A, 2-FCV-1-11 2-XS-1-11A D 2
MSIV Loop 2, Train B. 2-FCV-1-11 2-XS-1-118 D 3
MSIV Loop 3, Train A, 2-FCV-1-22 2-XS-1-22A D MSIV Loop 3, Train B, 2-FCV-1-22 2-XS-1-228 D 4
MSIV Loop 4. Train A, 2-FCV-1-29 2-XS-1-29A D MSIV Loop 4, Train B. 2-FCV-1-29 2-XS-1-298 D Comment
- - UNSAT Standard: The Examinee contacts the MCR to determine status of MSIV's. CRITICAL Cue When asked provide the following cue, "The MSIV for Loop 1 is OPEN The MSIV's for Loop 2, 3 and 4 are CLOSED."
Comment
1503 NRC PLANT JPM I Page 8 of 10 NOTE1 Fuse pullers and flashlight will be needed for next step.
These may be obtained from AOP-C.04 cabinet in 6.9KV Shutdown Board Room A.
NOTE2 Fuses may be removed in any order.
- 3. IF affected MSIV still open STEP 10 OR control power fuse removal desired, SAT THEN REMOVE fuses for affected MS!V{s): UNSAT FUSES FUSE LOCATION SIG EQUIPMENT REMOVED (Two per circuit) v' 125V Vital Battery Bd !II MSIV Loop 1, Train A, 2-FCV-1-4 Circuit A-46 0 1 Circuit B-46 0 125V Vital Battery Bd IV MSIV Loop 1, Train 8, 2-FCV-1-4 Circuit A-46 0 Circuit B-46 0 Cue If asked provide the following cue, "Loop 1 MSIV is CLOSED. Steam generator #1 pressure is 450 psig and stable."
Comment
1503 NRC PLANT JPM I Page 9 of 10 STEP 11 SAT
- 4. GO TO Section 4.1, step in effect UNSAT END OF SECTION Standard: The Examinee addresses the procedure step.
Comment Terminating The JPM is complete when the Examinee returns the cue sheet to STOP Cue: the Examiner.
Stop Time
JPM BRIEFING SHEET DIRECTIONS TO OPERATOR:
All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 is in MODE 3
- 2. Unit 2 has experienced faulted SG's.
- 4. All MSIV bypass valves are closed.
INITIATING CUES:
- 2. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1503 NRC PLANT JPMJ
PLANT JPM J Page 2 of 8 RO/SRO JOB PERFORMANCE MEASURE Task: Take Local Control of the Turbine Driven AFW Level Control valve 2-LCV-3-175.
Task#: 0000140504 Task Standard: The Examinee simulates assuming local control of 2-LCV-3-175.
Alternate Path: YES: NO: x Time Critical Task: YES: ---
NO: x KIA Reference/Ratings: APE 068 AA1 .03 (4.1/4.3)
Method of Testing:
Simulated Performance: x Actual Performance:
Evaluation Method:
Simulator ---
In-Plant ---
x Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 12 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
PLANT JPM J Page 3 of 8 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'
- 2. Any UNSAT requires comments.
Tools/Equipment/Procedures Needed:
References*
Reference Title Rev No.
- 1. AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL 35 ROOM
========================================================================
READ TO EXAMINEE HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
DIRECTIONS TO OPERATOR:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 is in MODE 3.
- 3. AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM is in progress.
- 4. APPENDIX W.2 CONTROL OF UNIT 2 TURBINE DRIVEN AFW FLOW FROM OUTSIDE MCR has been completed through step 5.
INITIATING CUES:
- 1. You have been directed to locally shut Unit 2 TD AFW Loop 4 LCV (2-LCV-175) using APPENDIX W.2 CONTROL OF UNIT 2 TURBINE DRIVEN AFW FLOW FROM OUTSIDE MCR starting at step 6.
- 2. Inform the SRO when complete.
PLANT JPM J Page 4 of 8 Start Time STEP 1 --
SAT Obtain a copy of AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM. --
UNSAT Standard: Operator obtains a copy of AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM.
Cue Provide a copy of AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix W.2.
Comment
- 6. IF necessary to locally control TD AFW flow to Unit 2 SIG #1.
STEP 2 THEN - - SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm
- - UNSAT at emergency control station for 2-LCV-3-174]
Standard: The Examinee addresses the procedure step as N/A.
Comment
- 7. IF necessary to locally control TD AFW flow to Unit 2 S/G #2 or 3.
STEP 3 THEN - - SAT THROTTLE or CLOSE TD AFW valves as directed:
- - UNSAT Standard: The Examinee addresses the procedure step as N/A.
Comment
PLANT JPM J Page 5 of 8 NOTE1 Turbine-Driven AFW level control valves fail in OPEN position on loss of control air. The following step uses air from SBO air bottle to close S/G #4 TDAFW LCV from emergency control station. Approximately 45 psig (on outlet pressure indicator 2-Pl-3-1758) should be applied if necessary to close valve.
NOTE2 At minimum SBO air bottle pressure (800 psig), sufficient air supply is available for at least four full strokes (open to closed) of TD AFW LCV. Valve strokes should be minimized to conserve air supply.
- 8. IF necessary to locally control TD AFW flow to Unit 2 SIG #4, STEP 4 THEN SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm using emergency control station for 2-LCV-3-175] UNSAT
- a. CLOSE [2-VTIV-3-175EJ. Vent Valve. D Provide the following cue, "Valve handle turned 90° CW and is now snug."
Comment
- 8. IF necessary to locally control TD AFW flow to Unit 2 SIG #4.
STEP 5 THEN SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm using emergency control station for 2-LCV-3-175] UNSAT
- b. ENSURE [2-PREG-3-175), Pressure Regulator. is adjusted fully counterclockwise (lower direction). D Provide the following cue, "Regulator handle turned several turns CCW and is now snug."
Comment
PLANT JPM J Page 6 of 8
- 8. IF necessary to locally control TD AFW flow to Unit 2 SIG #4,
.STEP 6 THEN SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm using emergency control station for 2-LCV-3-175] UNSAT
- c. OPEN [2-ISIV-32-1866KJ, SBO/App. R HP Air Cy! !sol Valve. D Provide the following cue, "Valve handle turned 90° CCW and is now snug."
If asked provide the following cue point to 90 psig on pressure indicator 2-Pl-3-1750.
Comment
- 8. IF necessary to locally control TD AFW flow to Unit 2 S/G #4.
STEP 7 THEN SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm using emergency control station for 2-LCV-3-175] UNSAT Provide the following cue, "Valve handle turned 90° CCW and is now snug."
Comment
PLANT JPM J Page 7 of 8
- 8. IF necessary to locally control TD AFW flow to Unit 2 SIG #4, STEP 8 THEN SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm using emergency control station for 2-LCV-3-175} UNSAT Cue Provide the following cue, "Valve handle turned 90° CCW."
Comment
- 8. IF necessary to locally control TD AFW flow to Unit 2 S/G #4, STEP 9 THEN SAT PERFORM the following: [Aux Bldg el 714 Unit 2 Pen Rm using emergency control station for 2-LCV-3-175] UNSAT
- f. ADJUST [2-PREG-3-1751. Pressure Regulator. slowly in clockwise direction to close 2-LCV-3-175 as directed by ACR D If asked as to where to place 2-LCV-3-175, direct the Examinee to refer to the initiating cue.
After the Examinee simulates adjusting [2-PREG-3-175], Pressure Regulator, in full clockwise direction point approximately to 45 psig on outlet pressure indicator 2-Pl-3-1758.
Comment Terminating Provide the following cue "Another operator will perform the Cue: STOP remaining steps of this procedure."
Stop Time
JPM BRIEFING SHEET DIRECTIONS TO OPERATOR:
All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 is in MODE 3.
- 3. AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM is in progress.
- 4. APPENDIX W.2 CONTROL OF UNIT 2 TURBINE DRIVEN AFW FLOW FROM OUTSIDE MCR has been completed through step 5.
INITIATING CUES:
- 1. You have been directed to locally shut Unit 2 TD AFW Loop 4 LCV (2-LCV-175) using APPENDIX W.2 CONTROL OF UNIT 2 TURBINE DRIVEN AFW FLOW FROM OUTSIDE MCR starting at step 6.
- 2. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1503 NRC PLANT JPMK
PLANT JPM K Page 2 of 14 RO/SRO JOB PERFORMANCE MEASURE Task: Radiation Monitor O-RE-90-122 Flushing After Hi Radiation Signal Isolation of Release.
Task#: 0690100104 Task Standard: The examinee completes flushing of O-RE-90-122 after isolation due to high radiation.
Alternate Path: YES: - - x - NO:
Time Critical Task: YES: - - - NO: x KIA Reference/Ratings: 073 K4.02 (3.3/3.9)
Method of Testing:
Simulated Performance: Actual Performance: x Evaluation Method:
Simulator In-Plant x Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 min Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
PLANT JPM K Page 3 of 14 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'
- 2. Any UNSAT requires comments.
Tools/Equipment/Procedures Needed:
References:
Reference Title Rev No.
O-S0-77-1 Waste Disposal System 53
========================================================================
READ TO EXAMINEE DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. A release from the CDCT has just been initiated using O-S0-77-1, Waste Disposal System and O-Sl-CEM-077-400.1 Liquid Waste Effluent Batch Release.
- 2. The calculated high radiation trip setpoint for O-RM-90-122 is 8.59 E+04 cpm, using O-Sl-CEM-077-400.1, Liquid Waste Effluent Batch Release.
- 3. A high radiation signal on O-RE-90-122 occurred shortly after initiation of the release, causing an isolation of the release.
- 4. O-RCV-77-43 has been verified CLOSED.
- 5. All Prerequisite Actions are complete (Section 4.0)
INITIATING CUES:
- 1. You have been directed to perform Section 8.2 of O-S0-77-1, Waste Disposal System to flush O-RE-90-122 after the High Radiation Isolation.
- 2. Inform the SRO when complete.
PLANT JPM K Page 4 of 14 Start Time STEP 1 - - SAT Obtain a copy of O-S0-77-1, Waste Disposal System UNSAT Standard: Operator obtains a copy of O-S0-77-1, Waste Disposal System Provide an in progress copy of O-S0-77-1, Waste Disposal System, Cue section 8.2 Radiation Monitor O-RE-90-122 Flushing After Hi Radiation Signal Isolation of Release.
Comment STEP 2 - - SAT
[1] ENSURE [0-RCV-77-43] Radiation Control Valve is CLOSED.
- - UNSAT Standard: The Examinee refers to the procedure step.
Cue If asked, tell the Examinee to refer to the initial conditions.
Comment
PLANT JPM K Page 5 of 14 I STEP 3 - - SAT
[2] ENSURE [0-77-689AJ Radiation Monitor Inlet Isolation Valve is OPEN.
- - UNSAT Standard: Examinee simulates ensuring [0-77-689A] Radiation Monitor Inlet Isolation Valve is OPEN.
If asked provide the following cue, "valve HW turned in the CW Cue direction slightly and then returned fully CCW valve to original position."
Comment STEP 4 SAT
[3] OPEN [0-77-68981 Discharge to FDCT Isolation Valve.
UNSAT If asked provide the following cue, "valve HW turned in the CCW direction several turns and is now snug."
Comment
PLANT JPM K Page 6 of 14 STEP 5 SAT
[4] CLOSE [0-77-689C] Radiation Monitor Return to Release Header Isolation Valve.
UNSAT Standard: Examinee simulates closing [0-77-689C] Radiation Monitor Return to Release Header Isolation Valve.
Comment STEP 6 - - SAT
[5] VERIFY [0-RE-90-122] radiation monitor pump is running.
- - UNSAT Standard: Examinee simulates ensuring [O-RE-90-122] radiation monitor pump is running.
Cue If asked provide the following cue," Red light above O-HS-90-1228 is ON."
Comment
PLANT JPM K Page 7 of 14 I
STEP 7 - - SAT
[6] ALLOW [0-RE-90-1221 Radiation Monitor to flush to FDCT for 5 minutes.
- - UNSAT Standard: Examinee addresses the procedure step.
Cue Provide the following cue, "Time has been compressed, five minutes has passed."
Comment STEP 8 SAT
[7J OPEN f0-77-689C].
UNSAT If asked provide the following cue, "valve HW turned in the CCW direction several turns and is now snug."
Comment
PLANT JPM K Page 8 of 14 STEP 9 SAT
[8] CLOSE [0-77-689BJ.
UNSAT If asked provide the following cue, "valve HW turned in the CW direction several turns and is now snug."
Comment STEP 10 [9] RECORD O-RE-90-122 reading: - - SAT
- - UNSAT O-RE-90-122 Reading cpm.
Standard: Examinee records O-RE-90-122 reading.
Cue Provide the following cue "O-RE-90-122 is reading 9.00 E+04 cpm" Comment
PLANT JPM K Page 9 of 14 I
STEP 11 - - SAT
[1 OJ IF the reading obtained in step 8.2[9] is below the trip setpoint,
. THEN
- - UNSAT Standard: The Examinee addresses the procedure step as N/A.
Comment STEP 12 [11] IF the reading obtained in step 8.2[9] is still above the trip SAT setpoint, THEN UNSAT PERFORM the following steps to lmver the radiation monitor reading:
[11.1] CLOSE applicable tank isolation valve from release header (NIA tanks not aligned):
Tank Being Released Isolation Valve INITIALS Cask Decon Collector Tank 0-77-679 Monitor Tank 0-77-1306 If asked provide the following cue, "valve HW turned in the CW direction several turns and is now snug."
Comment
PLANT JPM K Page 10 of 14 STEP 13 SAT
[11.2] OPEN [0-VLV-59-735] Demin Flush To Radwaste !SOL UNSAT If asked provide the following cue, "valve HW turned in the CCW direction several turns and is now snug."
Comment STEP 14 SAT
[11.3] OPEN [0-77-68981 Discharge to FDCT Isolation Valve.
UNSAT If asked provide the following cue, "valve HW turned in the CCW direction several turns and is now snug."
Comment
PLANT JPM K Page 11 of 14 STEP 15 SAT
[11.4] CLOSE [0*77 -689CJ Radiation Monitor Return to Release Header Isolation Valve. UNSAT If asked provide the following cue, "valve HW turned in the CW direction several turns and is now snug."
Comment
[11.5] WHEN count rate on fO-RE-90-1221 STEP 16 lowers to its minimum value, THEN SAT
[11.5.1] OPEN f0-77-689CJ Radiation Monitor Return to UNSAT Release Header Isolation Valve.
Cue Provide the following cue, "Count rate on O-RE-90-122 has lowered to 8.0 E+02 cpm and is stable."
If asked provide the following cue, "valve HW turned in the CCW direction several turns and is now snug."
Comment
PLANT JPM K Page 12 of 14 STEP 17 (11.5] WHEN count rate on [O-RE-90-122] SAT lowers to its minimum value, THEN
[11.5.2] CLOSE [0-77-68981 Discharge to FDCT Isolation UNSAT Valve.
If asked provide the following cue, "valve HW turned in the CW direction several turns and is now snug."
Comment STEP 18 SAT
[11.6] CLOSE [O-VLV-59-735) Demin Flush To Radwaste !sol.
UNSAT Cue If asked provide the following cue, "valve HW turned in the CW direction several turns and is now snug."
Comment
PLANT JPM K Page 13 of 14
[11.7] OPEN applicable tank isolation valve previously closed STEP 19 in step 8.2[11.1] (NIA tanks not aligned): SAT Tank Being Released Isolation Valve INITIALS UNSAT Cask Decon Collector Tank 0-77-679 Monitor Tank 0-77-1306 If asked provide the following cue, "valve HW turned in the CCW direction several turns and is now snug."
Comment STEP 20 [11.8] IF hi radiation alarm will NOT clear, THEN
- - SAT NOTIFY the appropriate US/SRO that alarm will NOT clear. - - UNSAT Standard: The Examinee addresses the procedure step as N/A.
Comment Terminating Provide the following cue "Another operator will perform the STOP Cue: remaining steps of this procedure."
Stop Time
JPM BRIEFING SHEET DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. A release from the CDCT has just been initiated using O-S0-77-1 Waste Disposal System and O-Sl-CEM-077-400.1 Liquid Waste Effluent Batch Release.
- 2. The calculated high radiation trip setpoint for O-RM-90-122 is 8.59 E+04 cpm, using O-Sl-CEM-077-400.1, Liquid Waste Effluent Batch Release.
- 3. A high radiation signal on O-RE-90-122 occurred shortly after initiation of the release, causing an isolation of the release.
- 4. O-RCV-77-43 has been verified CLOSED.
- 5. All Prerequisite Actions are complete (Section 4.0)
INITIATING CUES:
- 3. You have been directed to perform Section 8.2 of O-S0-77-1, Waste Disposal System to flush O-RE-90-122 after the High Radiation Isolation.
- 4. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.