ML102371253
| ML102371253 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/25/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-390/08-301 | |
| Download: ML102371253 (157) | |
Text
RevO. PAGE 1 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B PLACE MAIN GENERATOR IN SERVICE AND SYNCHRONIZE TO SYSTEM PER SOI-4702
RevO. PAGE 2 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial Issue. 03/16/08 All D.L.Hughes
RevO. PAGE 3 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B EVALUATION SHEET Task: PLACE MAIN GENERATOR IN SERVICE AND SYNCHRONIZE TO SYSTEM PER SO 1-47. 02 Alternate Path: Once synchronized to the grid the automatic voltage regulator will fail, requiring the performer to take manual control of voltage to prevent generator damage.
Facility JPM #: 3-OT-JPMRO1 14B Rev 0 K/A Rating(s): A4.02 Ability to manually operate and/or monitor in the control room: T/G controls, including breakers [Importance RO/SRO 2.7 / 2.6]
TASK STANDARDS: Turbine Generator synchronized with Grid, generator voltage stable and MEGAVARS slightly outgoing, with voltage being controlled manually.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOI-47.02 Turbo-Generator Startup Operation Revision 0058 Task Number: RO-092-AOI-4-001 APPLICABLE FOR: RO/SRO IOCFR55.45: 3, 4, 6, 12 Validation Time: 25 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
RevO. PAGE 4 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to IC#252
- 2. Acknowledge all alarms.
- 3. Ensure MODs for PCBs 5088 and 5044 are OPEN
- 4. RESET Core Monitor Alarm, enable Core Monitor Alarm.
- 5. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
a) Initialize to IC- 46 b) Perform SOI-47.02 section 5.4 Placing Generator in Service and Synchronizing with the Exciter Regulator On up to step [10.1] PLACE 1-HS-57-19, EXCITER FIELD BREAKER [1-M-1], in CLOSE.)
c) iorzdihs5722 (el) raise d) Acknowledge all alarms e) Place the Simulator in FREEZE.
- 7. After performer indicates understanding of task, place simulator in run.
SIMULATOR OPERATOR INSTRUCTIONS:
When the performer Places SYNC SWITCH to OFF (JPM step 21), ENTER TRIGGER I to fail the automatic voltage regulator.
RevO. PAGE 5 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure to have a clean marked-up copy of SOl-47.02 Turbo-Generator Startup Operation to give to the performer prior to starting the JPM.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
AllI Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- A Unit Startup is in progress and is currently 14% RTP.
- SOl-47.02 Turbo-Generator Startup Operation is in progress and has been completed up thru Section 5.4 step [9].
- Switching Orders have been obtained from Northeast Area Dispatcher (NEAD) and Unit One is to be aligned with PCB 5088 & 5044.
- You are an extra RO.
INITIATING CUES:
Give performer a marked-up copy of S01-47.02 Turbo-Generator Startup Operation.
The Unit Supervisor has directed you to synchronize the Main Generator with PCB 5088 lAW SOl-47.02 Turbo-Generator Startup Operation starting at section 5.4 step [10] and performing all applicable steps up thru step [28].
You are to notify the Unit Supervisor when step [28] is complete.
RevO PAGE 6 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B START TIME:
STEP 1
[10] MONITOR 1-EI-5715, GENERATOR VOLTS while performing the following: CRITICAL STEP
[10.1] PLACE 1-HS-57-19, EXCITER FIELD BREAKER [1-M-1], in CLOSE.
STANDARD: SAT 1-HS-57-19 is placed in the CLOSED position.
COMMENTS:
U N SAT STEP 2: [10.2] Slowly JOG 1-HS-57-23, EXCITER BASE CRITICAL ADJUSTER [1-M-1], until field flashes as STEP indicated by voltage rise..
STANDARD: 1-HS-57-23 is adjusted to flash generator field as indicated SAT on 1-El-57-15, Generator Volts.
COMMENTS:
U N SAT STEP 3: [10.3] ADJUST 1-HS-57-23, EXCITER BASE ADJUSTER {1-M-1], to adjust voltage to 23.5 kV. CRITICAL STANDARD: 1-HS-57-23, EXCITER BASE ADJUSTER [1-M-1], is STEP adjusted to produce a generator voltage to 23.5 kV.
COMMENTS: SAT UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0 PAGE 7 OF 18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B STEP 4: [II] VERIFY 3-phase GENERATOR VOLTS on 1-EI-57-15 using 1-XS-57-15.
SAT 1-XS-57-15 POSITION METER POT A-B METER POT B-C METER POT C-A VOLT REG POT A-B VOLT REG POT B-C VOLT REG POT C-A UNSAT STANDARD: 1-XS-57-15 has been selected to check voltages for meter pots and volt reg pots and voltages are 23.5 kV.
COMMENTS:
STEP 5: [12] PLACE SYNC SWITCH for selected PCB, to indicated CRITICAL position (N/A unused blank): STEP PCB HANDSWITCH POSITION 5088 1-HS-57-27, SYNC SWITCH SYNC CHK INTLK 500KV BUS 2 SAT 5044 2-HS-57-27, SYNC SWITCH SYNC CHK INTLK 500KV BUS 1 5064 SYNC SWITCH on ECB 5 for ON PCB 5064 STANDARD: l-HS-57-27 is placed in SYNC CHECK INTERLOCK position for PCB 5088. UN SAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 8 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B STEP 6: [13] Slowly JOG l-HS-57-23, EXCITER BASE ADJUSTER, CRITICAL to match INCOMING VOLTAGE (1-El-57-2), with STEP RUNNING VOLTAGE (1-El-57-3) [1-M-1].
Generator running voltage is matched to incoming voltage STAN DARD with l-HS-57-23 as observed on 1-El-57-2 & 1-El-57-3.
COMMENTS: SAT UN SAT STEP 7: [14] VERIFY MAIN XFMR COOLER, Preferred Group IN SERVICE, by Red lights above I-HS-57-106 [1-M-1].
SAT STANDARD: l-HS-57-1 06 is checked to verify Transformer Coolers (Preferred Group) in service.
If asked as NAUO to verify which Transformer Coolers Evaluator in service, respond Preferred Group in service.
Cue UNSAT COMMENTS:
STEP 8: [15] PLACE l-HS-57-20, EXCITER REGULATOR [1-M-1], in TEST, and VERIFY Amber light LIT, and Green light OUT.
SAT STANDARD: Voltage regulator l-HS-57-20 is placed in TEST, and amber light is verified LIT and green light OUT.
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 9 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B COMMENTS:
UNSAT
[16] PERFORM the following: CRITICAL STEP 9:
STEP
[16.1] ADJUST l-HS-57-22, EXCITER VOLTAGE ADJUSTER, to obtain 0 on l-EI-57-12, V REG XFER BAL VOLTS.
SAT STANDARD: l-HS-57-22 is adjusted to null the regulator such that the output meter, l-El-57-12, reads 0.
COMMENTS:
U N SAT STEP 10: [16.2] PLACE l-HS-57-20, EXCITER REGULATOR to CRITICAL ON STEP SAT STANDARD: I-HS-5720 is placed in the ON position and red light is verified ON and amber light OFF.
COMMENTS:
V UNSAT STEP 11: [17] NOTIFY Northeast Area Dispatcher (NEAD) that generator is READY to SYNCHRONIZE.
NOTIFY Northeast Area Dispatcher (NEAD) that generator STANDARD SAT READY to SYNCHRONIZE
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0 PAGE 10 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B EXAMINER When notified, acknowledge the report CUE:
COMMENTS: UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated,
RevO PAGE 11 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B STEP 12: [18] CHECK VALVE POSITION LIMIT set 15% OPEN.
SAT STANDARD: Performer checks/adjusts turbine Valve Position Limiter to 15% open. UNSAT COMMENTS:
STEP 13: [19] COORDINATE Turbine operation with Operator on feedwater and reactor controls. SAT STANDARD: Performer notifies ATC that the generator is about to be synchronized and loaded to grid.. Monitor feedwater and UNSAT reactor controls COMMENTS:
STEP 14: [20] PUSH TURBINE MODES OPER AUTO SYNC button.
SAT STANDARD: OPER AUTO SYNC push button on EH panel is depressed & Oper Auto Symc light is checked illuminated COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 12 0F18 Watts Bar Nuclear Plant 3-OT-JPMRII4B STEP 15: [21] ADJUST l-HS-57-21, GENERATOR SPEED OPER AUTO SYNC [1-M-1], to obtain SLOWLY moving SYNC-SCOPE (1-Xl-57-1 or SYNC PNL 1 on ECB 8 if using PCB 5064 to sync) in the FAST direction (one revolution every 10-15 seconds). SAT STANDARD: l-HS-57-21 is adjusted to obtain a SLOW SCOPE in the fast direction. Rotation of scope once every 10-15 seconds.
UNSAT COMMENTS:
STEP 16: [22] ENSURE 1-EI-57-2, INCOMING VOLTAGE, and 1-El-57-3, RUNNING VOLTAGE, are EQUAL SAT STANDARD: Incoming voltage is verified to be equal to running voltage.
COMMENTS:
UNSAT STEP 17: [23] IF Unit is to be synchronized using PCB 5044 (or 5064 spared out for 5044), THEN ENSURE MOD 6127 is OPEN and MOD 6117 is CLOSED.
SAT Performer determines step is not applicable, NAs step and STANDARD. proceeds to next step.
COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0 PAGE 13 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B STEP 18: [24] CLOSE MODs for PCB to be used to sync generator (N/A unused blank).
MOD HANDSWITCH PCB 5087 & 5089 (ECB 6) 5088 SAT 5045 & 5043 (ECB 5) 5044 5065 & 5063 (ECB 5) 5064 STANDARD: Performer checks MOD 5087 and 5089 CLOSED position U N SAT by MOD red lights lit for respective MODs.
COMMENTS:
STEP 19: [25] WHEN 1-Xl-57-1, SYNC-SCOPE or SYNC PNL 1 on ECB 8) reaches 12:00, THEN PLACE HS for CRITICAL selected PCB, in CLOSE (N/A unused blank): STEP HANDSWITCH PCB 1-HS-57-26 5088 2-HS-57-26 5044 PCB 5064 hand-switch on 5064 SAT ECB STANDARD: Generator PCB 5088 is CLOSED when synch roscope reaches 12:00 and all three phases are checked to verify loading.
U N SAT Evaluator If Performer attempts to close PCB 5088 exactly at Note: 12:00, the PCB may not close. The performer is allowed repeated attempts to close PCB 5088 providing closing attempt are within 5 minutes till noon.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0 PAGE 14 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 20: [261 ENSURE generator picks up some load on all 3 phases (DO NOT allow generator to motor):
INDICATOR LOCATION 1-El-57-9, A Phase AMPS 1-M-1 SAT 1-El-57-10, B Phase AMPS 1-M-1 1-El-57-11, C Phase AMPS 1-M-1 STANDARD: All three phases are checked to verify loading.
UNSAT COMMENTS:
STEP 21: [27] PLACE SYNC SWITCH used in Step [12] to OFF.
STANDARD: 1-HS-57-27, 500 kV Bus is placed in the OFF position.
SAT Console Operator Enter Trigger I COMMENTS: U N SAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 15 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B STEP 22: 1 [28] ENSURE 1-El-57-8, MEGAVARS, is slightly outgoing using 1-HS-57-22, EXCITER VOLTAGE ADJUSTER
- CRITICAL STEP
[1-M-1].
STANDARD: The performer should recognize that MEGAVARS, are rising and are not slightly outgoing.
SAT Indication s:
- Exciter Volts (1-El-57-6) rising
- Exciter Amps (1-El-57-7) rising
- Megavars (1-El-57-8) rising UNSAT
- A Phase Amps (1-El-57-9) rising
- B Phase Amps (1-El-57-1O) rising
- C Phase Amps (1 -El-57-1 1) rising
- Annunicator 3C Exciter Field Overcurrent Evaluator *
- The performer may take conservative action at Note: this point, and either:
- 1. TRIP the Turbine and then ensure PCB 5088 OPENS, or
- 2. Just trip the Generator by OPENNING PCB 5088.
Either of these actions constitutes satisfactory performance of this CRITICAL STEP. If the performer performs either, the JPM would be stopped and the remaining JPM steps would be N/A.
If the performer does not perform either of the two above actions, THEN the performer should perform actions IA W ARI 3C which are the following JPM steps.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 16 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B Evaluator The following steps are from ARI-3C Exciter Field Note: Overcurrent STEP 23: [1] IF 1-HS-57-20, Exciter Regulator in ON, THEN: CRITICAL PLACE 1-HS-57-20, Exciter Regulator in OFF. STEP STANDARD: Performer places 1-HS-57-20, Exciter Regulator in OFF.
SAT COMMENTS: UNSAT N/A STEP 24: [2] IF generator trip has not occurred, THEN OPERATE generator in Base Adjust Mode. Notify NEAD within CRITICAL 30 minutes to comply with NERC Standards. STEP STANDARD: Performer control the Base Adjust to obtain MVARS slightly outgoing and notifies NEAD within 30 minutes. SAT Evaluator Acknowledge request to Notify NEAD. If performer ask Que: NEAD concerning where MVARS should be controlled, inform performer slightly outgoing.
UNSAT Evaluator The CRITICAL portion of the step is to control the Base Note: Adjust to obtain MVARS slightly outgoing.
N/A COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 17 0F18 Watts Bar Nuclear Plant 3-OT-JPMRI 14B STEP 25: [3] DISPATCH personnel to Excitation Control Board 1 to check protective relay drawer for alarm(s).
SAT STANDARD: Performer dispatches personnel to Excitation Control Board 1 to check protective relay drawer for alarm Evaluator Acknowledge request to dispatch personnel to Excitation Control Board 1. Inform the performer that UNSAT Que the JPM will stop here; another operator will continue the task.
N/A Comments END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
AlIl Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- A Unit Startup is in progress and is currently 14% RTP.
- SOl-47.02 Turbo-Generator Startup Operation is in progress and has been completed up thru Section 5.4 step [9].
- Switching Orders have been obtained from Northeast Area Dispatcher (NEAD) and Unit One is to be aligned with PCB 5088 & 5044.
- You are an extra RO.
INITIATING CUES:
Here is the in-progress working copy of S0I-47.02 Turbo-Generator Startup Operation.
The Unit Supervisor has directed you to synchronize the Main Generator with PCB 5088 lAW SOI-47.02 Turbo-Generator Startup Operation starting at section 5.4 step [10] and performing all applicable steps up thru step [28].
You are to notify the Unit Supervisor when step [28] is complete.
REV. 5 PAGE 1 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 LOCAL CONTROL MOTOR DRIVEN AFWP LCV FOR #1 S/G LEVEL PER SOI-3.02
REV. 5 PAGE 2 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF DATE PAGES PREPARED!
NUMBER REVISION AFFECTED REVISED BY:
0 Initial Issue. 8/28/92 ALL 1 DELETE KNOWLEDGE 4/7/93 3,5,6,8,9 QUESTIONS, CHANGE VAL TIME, OTHER MINOR CHANGES 2 CHANGE WORDINGAND 12/06/9 7 SETPOINTS IN JPM STEPS 6,7 3 3 REFLECT PROCEDURE REV 20 11/1/95 4,6,7,8 Ed Knoblauch 4 Revised K/A values to Rev 2 of 11/7/99 ALL Albert V. White NUREG 1122, updated procedure references, revised initiating cues, converted format to NRC format.
Added step addressing SG #2 Level Control.
5 Incorporated previously made pen & 9/28/07 ALL D.L. Hughes ink changes to update procedure referenced, add gloves to equipment needed, correct typo in step 8.
Reworded Examiners Cues for steps 5, and 7 to provide more detail.
No change of intent
REV. 5 PAGE 3 0F10 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 4 Task: Local Control Motor Driven AFWP LCV For #1 SIG Level Per SOl-3.02.
Alternate Path: N/A.
Facility JPM #: 3-OT-JPMAO87 Rev 5 K1A Rating(s): 054-AK3.03 [3.8/4.1] 054-AA [4.5/4.4] 2.1.30 [3.9/3.4]
Task Standard: Establish communications with the Control Room Operator and assume local control of #1 S!G level using lA-A Motor-Driven AFWP LCV.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant X Perform Simulate X
References:
SOl-3.02 Auxiliary Feedwater System Rev. 45 -
Task Number:: AUO-003-SOl-3.02-008 APPLICABLE FOR: AUO/RO/SRO IOCFR55.45: 7, 8, 9 Validation Time: 13 mm. Time Critical: No
( Candidate:
NAME SSN/EIN Time Start:
Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
REV. 5 PAGE 4 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J P MA087 Tools/EguipmentlProcedures Needed:
Hard Hat, Safety Glasses, Flashlight, Hearing Protection, Plant Approved Shoes, gloves, and radio.
Latest revision of SOl-3.02.
Ladder Safety since some valves require access from above floor elevation, and ALARA considerations. Auto Start capabilities of the AFW System.
NOTE: Start this JPM in the MCR.
EVALUATOR NOTE: Provide copy of SOI-3.02 Section 8.5 to performer with candidates cue sheet.
READ TO OPERATOR DIRECTION TO TRAINEE: -
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Unit is in Mode 3 with the RCS at 557°F and 2235 psig.
The TD AFW Pump is tagged for maintenance.
The Control Room Operator has been experiencing increasing difficulty in maintaining
- 1 SIG level.
You are the Auxiliary Building AUO and you have already checked out a radio.
INITIATING CUES:
The Unit Supervisor has directed you to establish radio communications with the MCR and then take local control of SG I level via IA-A MD AFWP, per SOI-3.02 Section 8.5.
REV. 5 PAGE 5 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 START TIME:
STEP 1: Obtain a copy of the procedure.
SAT STANDARD: A copy of SOl-3.02 Sect. 8.5.1 has been obtained.
EXAMINERS CUE: Provide copy of SOl-3.02 Section 8.5 to performer.
UNSAT COMMENTS:
NOTE Direct radio communications with UO required to perform this -
section.
STEP 2: Establish communication with the UO.
STANDARD: Radio Communication with the MCR has been established.
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 6 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 STEP 3: [Step 1] ENSURE AFW Pump A-A running.
STANDARD: Performer determines that the lA-A MD AFWP is running by observation or MCR information. SAT
UNSAT
- CUE: If local indications checked, performer can hear/feel normal pump running soundlvibration, discharge pressure 1150 psig COMMENTS:
Note: Performance steps 4 and 5 are part of the same instruction step and must be performed in sequence.
STEP 4: [Step 2] PERFORM the following to fail CLOSED 1-PCV CRITICAL 122, AUX FEEDWATER PMP lA-A DISCHARGE PRESS STEP CONTROL [A3S/713]:
[2.11 CLOSE O-ISV-32-460, ESSENT CNTL AIR ISOL VALVE TO 1-PCV-3-122: SAT STANDARD: O-1SV-32-460 is manually closed. Step is critical to allow isolation of air to fail valve closed.
UNSAT
- CUE: After performer describes how to close valve, state valve handle rotates clockwise until it is snug.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 7 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 STEP 5: [Step 2.2] DEPRESSURIZE air from regulator on 1-PCV CRITICAL 122. STEP STANDARD: Petcock on local pressure regulator on 1-PCV-3-122 located and manually opened to de-pressurize regulator. Step is SAT critical to allow bleed of air to fail valve closed.
- CUE: After drain valve is opened, state that air is heard and felt coming from the drain, which then slows down and UNSAT stops completely.
IF ASKED about I -PCV-3-1 22 response, state that as air was bled off, l-PCV-3-122 stem moved down and is now completely down indicating closed.
COMMENTS:
Note: Performance steps 6 and 7 are part of the same instruction step and_must_be_performed_in_sequence.
STEP 6: [Step 3] IF MANUAL control of SG 1 level is necessary, CRITICAL THEN PERFORM the following to fail OPEN 1-LCV-3-164, STEP MD AFW PUMP lA-A SG 1 LEVEL CONTROL [A3T/737 West Wall]:
[3.1] CLOSE 1-ISV-32-3765, ESSENT CONTROL AIR ISOL SAT VALVE TO 1-LCV-3-164.
STANDARD: 1-ISV-32-3765 is manually closed. Step is critical to allow isolation of air to fail valve open. UNSAT
- CUE: After performer describes how to close valve, state valve handle rotates clockwise until it is snug.
COMMENTS:
- ltalicized Cues Are To Be Used Only if JPM Performance Is Being Simulated.
REV. 5 PAGE 8 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 STEP 7: [Step 3.2] DEPRESSURIZE air from regulator on 1-LCV CRITICAL 164. STEP STANDARD: Petcock on local pressure regulator on 1-LCV-3-164 located and manually opened to de-pressurize regulator. Step is SAT critical to allow bleed of air to fail valve open.
- CUE: After drain valve is opened, air is heard and felt coming from the drain, which then slows down and stops UNSAT completely.
IF ASKED about I -LCV-3-1 64 response, state that as air was bled off, 1-LCV-3-164 stem moved up and is now completely up indicating open.
COMMENTS:
STEP 8: [Step 4] IF MANUAL control of SG 2 level is necessary, THEN PERFORM the following to fail 1-LCV-3-156, MD AFW PUMP lA-A SG 2 LEVEL CONTROL [A3T/737 West Wall]:
[4.1] CLOSE 1-ISV-32-3761, ESSENT CONTROL AIR ISOL VALVE TO l-LCV-3-156. SAT
[4.2] DEPRESSURIZE air from regulator on I -LCV-3-1 56.
STANDARD: Performer determines that this step is N/A and proceeds to the UNSAT next step.
- CUE: If control room contacted, state that manual level control of SG 2 is not required.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 9 OF 10 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 NOTE: Manual Handwheel on top of 1-PCV-3-122 must be turned CLOCKWISE to OPEN.
STEP 9: [Step 5] ADJUST 1-PCV-3-122, AUX FEEDWATER PMP 1A- CRITICAL A DISCHARGE PRESS CONTROL to establish approx 1200 STEP psid between 1-Pl-3-1 17, AUX FEEDWATER PMP lA-A SUCTION PRESS, and 1-PI-3-122B, AUX FEEDWATER PMP lA-A DISCHARGE PRESS [A3S/713]. SAT STANDARD: Manual hand wheel for 1-PCV-3-122 adjusted (clockwise to open) to establish approximately 1200 psid between 1-Pl 117 and 1-PI-3-122B..Step is critical to establish flow path UNSAT to SG 1.
- CUE: After adjustment of 1-PCV-3-122, indicate that 1-PI-3-117 -
reads 20 psig and 1-PI-3-122B reads 1200 psig COMMENTS:
STEP 10: [Step 6] IF SG 1 level to be controlled, THEN UNLOCK and CRITICAL THROTTLE 1-ISV-3-828, MD AFW PUMP IA-A SG 1 LEVEL STEP CONTROL ISOL, per UO instruction [A3T1737 West Wall].
STANDARD: 1-ISV-3-828 is unlocked and manually throttled clockwise to SAT 50%.. Step is critical to control flow path to SO 1.
- CUE: Inform the performer that the lock, if present, is a breakaway type lock. UNSAT
- CUE: Respond as control room and request 1-ISV-3-828 be throttled to 50% open position.
- CUE: After valve is throttled, then respond as control room and state that the Rad Waste AUQ will be contacted if additional adjustments are needed.
COMMENTS:
END OF TASK TIME STOP:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Unit is in Mode 3 with the RCS at 557°F and 2235 psig.
The TD AFW Pump is tagged for maintenance.
The Control Room Operator has been experiencing increasing difficulty in maintaining
- 1 SIG level.
You are the Auxiliary Building AUO and you have already checked out a radio.
INITIATING CUES:
The Unit Supervisor has directed you to establish radio communications with the MCR and then take local control of SG 1 level via IA-A MD AFWP, per SOI-3.02 Section 8.5.
REV. 6 PAGE 1 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 IA-A DIESEL GENERATOR IDLE START FOR WARM UP PER SOI-82.O1
REV. 6 PAGE 2 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 NUCLEAR TRAINING REVISION/USAGE LOG REV DESCRIPTION OF DATE PAGES REVIEWED BY NO. REVISION AFFECTED 0 Initial Issue. Reissue of JPM #SI-8.1.1 9/1/92 ALL 1 Delete knowledge questions and re- 4/7/93 ALL paginate.
2 Reflect Procedure Rev 28 4/29/95 4, 6-9 3 Reflect procedure Rev 28 CN-16, and 10/01/96 ALL A. V. White changed personnel titles.
4 Changed format, incorporate pen & ink 11/01/01 All A. V. White changes which revised a cue to reflect current plant configuration and removed termination cue. Updated procedure reference to Rev 40. Changed idle speed cues.
5 Revised to reflect procedure changes 10/26/04 All A. V. White which added several steps (JPM steps 10, 12, 13 and revised wording on some steps.
6 Incorporated pen & ink changes that 09/07/07 All A. V. White incorporated procedure revisions, corrected typos. Rev 61 of SOI-82.Ol has changed procedure and sections for this JPM. Provided instructions to have extra copy of Appendix B. Changes do no affect task performance or its evaluation.
REV. 6 PAGE 3 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 EVALUATION SHEET Task: lA-A Diesel Generator Idle Start for Warm Up per SOI-82.O1 Alternate Path: N/A Facility JPM #: 3-OT-JPMAO49 Rev 6 K/A Rating(s): 064-A4.Ol [4.0/4.3] 064-A4.06 [3.9/3.9] 064-A3.06 [3.3/3.4]
2.1.30 [3.9/3.4]
Task Standard: lA-A DG is successfully started, brought to idle speed, and shutdown using local controls. The DG is then returned to a standby alignment.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant X Perform Simulate X
References:
SOI-82.O1 Diesel Generator lA-A Rev. 61 Task Number:: AUO-082-SOI-82. 1-001 APPLICABLE FOR: AUO/RO/SRO AUO-082-SOI-82. 1-002 IOCFR55.45: 8 Validation Time: 25 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
REV. 6 PAGE 4 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Hard Hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes.
Ear Muffs (simulate for double hearing protection required when DG in operation)
SO 1-82.01 INSERT EXTRA COPY OF APPENDIX B SOl-82.01 after page 10 of JPM.
Safety considerations: C02 Protected area; Potential for high noise if DG auto starts.
NOTE: Start this JPM in the MCR.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
All DGs are in standby alignment.
IA-A DG has been declared INOPERABLE, maintenance has been completed.
lA-A DG has been rolled one complete revolution four hours ago.
Maint. Crews are on hand to perform required surveillance testing of the lA-A DG.
You are an AUO assigned to work with Maint. on the lA-A DG.
INITIATING CUES:
The Control Room Operator directs you to use SOI-82.01 to locally perform an Idle Start for warm up followed by shutdown on the IA-A DG.
You are to notify the Control Room Operator when you have completed the task and the IA-A DG is returned to standby alignment.
REV. 6 PAGE 5 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 START TIME:
STEP 1: Obtain a copy of the instruction.
STANDARD: A copy of S0l-82.01 section 8.1.1 and 8.1.2 has been SAT obtained.
EXAM IN ERS CUE: After the performer has identified correct instruction, the evaluator can provide a copy of UNSAT the instruction.
EVALUATOR NOTE: Section 8.1.1 contains prerequisite. Initial conditions for this JPM has the information to meet prerequisites. Prerequisite Steps I & 2 are met.
COMMENTS:
Note: The following steps are from Section 8.1.2 Idle Start STEP 2: [1] ENSURE 1-HS.-82-18, DG MODE SELECTOR CRITICAL SWITCH, in (UNIT) PULL FOR LOCAL TRANSFER STEP
[O-M-26j.
STANDARD: Performer contacts the MCR to ensure that 1-HS-82-18 is SAT in PULL FOR LOCAL TRANSFER. This step is critical to enable local control of DG.
UNSAT
- CUE: When contacted, repeat back, then report that I -HS 82-18 has been placed in PULL FOR LOCAL TRANSFER COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 6 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J P MA049 STEP 3: [2] ENSURE VOLTAGE SHUT DOWN, red light LIT
{1-PNL-82-A, Diesel Engine 1A1I1A2 Control Panel].
SAT STANDARD: Performer ensures that voltage shutdown red light is LIT.
- CUE: When checked, state that light is LIT U N SAT COMMENTS:
STEP 4: [3] PRESS l-HS-82-22, TRIP TO LOCAL GEN lA-A, to CRITICAL trip LRX1 A relay to LOCAL. [1 -ARB-82-A!3 Diesel STEP Generator lA-A Relay Board].
STANDARD: The performer presses l-HS-82-22, TRIP TO LOCAL GEN SAT lA-A. This step is critical to enable local control of 0G.
- CUE: If asked, state that an audible snap was heard when UNSAT hand switch was pressed.
COMMENTS:
STEP 5: [4] ENSURE l-RLY-82-LRX1A, DG lA-A LOCAL!
REMOTE CONTROL LOCKOUT, in LOCAL. [l-ARB 82-All Diesel Generator IA-A Relay Board]. SAT STANDARD: The performer ensures that l-RLY-82-LRX1A, DG lA-A LOCAL/REMOTE CONTROL LOCKOUT, in LOCAL U N SAT
- CUE: When LRXIA is checked, STATE that the relay handle is positioned to LOCAL.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 7 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J P MA049 STEP 6: [5] PRESS AND HOLD 1-HS-18-29/1, FUEL OIL CRITICAL PRIMING PUMPS DSL ENG 1A1 & 1A2 PB [1-PNL- STEP 82-A/2], until fuel press gauges indicate greater than 20 psig (l-IPI-18-1000I1, DG ENG 1A1 FUEL OIL PRESS, & 1-lPl--18-1001I1, DG ENG 1A2 FUEL OIL SAT PRESS) [1-PNL-82-AI1, Diesel Engine 1A1I1A2 Control Panel].
STANDARD: 1-HS-18-29/1, FUEL OIL PRIMING PUMPS DSL ENG 1A1 UNSAT
& 1A2 PB, is pressed and held until fuel press gauges are verified >20 psig (1-IPI-18-1000I1 & 1-IPI-18-1001/1).
This step is critical to provide proper prime to fuel injectors.
- CUE: When the pressure gauges are checked, use a pen to simulate that the pressure is 28 psig.
COMMENTS:
NOTE: DG-IA-A should reach speed of 450 +/- 10 rpm and hold.
Speed indication is on 1-PNL-82-A.
STEP 7: [6] PRESS 1-HS-82-25, IDLE START GEN lA-A, CRITICAL
[1-PNL-82-A12, Diesel Engine 1A1I1A2 Control Panel] STEP to start DG.
STANDARD: 1-HS-82-25, IDLE START GEN lA-A, is pressed. This SAT step is critical since it starts the DG.
- CUE: After switch is depressed is pushed, state that the diesel generator starts, and if checked engine is at UNSAT 445 RPM.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 8 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 STEP 8: [7] IF 1-FCV-67-66, DG HX 1A1/1A2 ERCW SUP HDR 1A SQL, is NOT OPEN, THEN OPEN 1-FCV-67-68, DG HX 1A1/1A2 ERCW SUP HDR 2B SQL, using 1-HS-67-68D, DSL GEN ENG 1A1/1A2 HTX ERCW SAT HEADER B SUPPLY. [1-PNL-82-A!1J.
STANDARD: Performer verifies that 1-FCV-67-66 is open.
UN SAT
- CUE: If MCR contacted, state that I -FCV-67-66 is open. If local check is made, use a pen to simulate the local indicator points to open.
COMMENTS:
STEP 9: [8] IF DG startup is for testing, AND a thick black combustion product emits for more than 5 minutes, THEN PERFORM the following:
A. QUICKLY LOAD DG to 4.4MW to burn excess oil. SAT B. IF smoke will NOT clear, THEN NOTIFY SRO to evaluate DG shutdown.
STANDARD: Performer verifies combustion exhaust is normal. UNSAT
- CUE: When performer checks exhaust, state that the combustion exhaust is grayish white in color and not excessive.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 9 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J P MA049 NOTE TO EVALUATOR: The following step refers to intake dampers to the DG room located in the overhead by the north end of the DG.
These when checked (when simulating task performance) are normally closed. When performer checks them, asks what position they are in, then give the CUE below:
STEP 10: [9] MONITOR all 4 groups of the AIR Intake Damper to the outside plenum are full open, AND IF ANY of the 4 groups in the Air Intake Damper fails to fully OPEN, THEN SAT
[9.1] NOTIFY the Duty Engineering Manager to perform an evaluation to determine affect on DG operability.
[9.2] INITIATE WO to repair the failed group. UNSAT WO#_________
STANDARD: Performer verifies that Air Intake Damper 1-FCO-30-443 four groups are fully OPEN.
COMMENTS:
- Ita!icized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 10 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 EVALUATOR NOTE: USE your copy of Appendix B (next page) to assist in indicating to performer the appropriate values.
STEP 11: [10] MONITOR parameters listed on Appendix B during operation.
STANDARD: The performer locates and verifies the parameters as listed SAT in Appendix B.
- CUE: If asked about a parameter AFTER IT IS CHECKED, indicate to performer (pointer, needle, etc.) that the UNSAT parameter within the values listed for the parameter when checked.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 11 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J P MA049 STEP 12: [11] IF any parameter not within specified limits, THEN NOTIFY SM/Unit SRO to evaluate removing DIG from service.
SAT STANDARD: The performer has determined that parameters are within limits (previous step) and continues to the next step.
UNSAT COMMENTS:
STEP 13: [121 IF DG lA-A is to be run at full speed, THEN GOTO Section 8.1.3 after a 10 minute warm-up.
STANDARD: Performer N/As this step and continues (initial conditions SAT stated this is an idle start for warm up).
COMMENTS: UNSAT
- Ita!icized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 12 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49 Evaluator Note: Performance steps 14 through 16 are parts of the same instruction step.
CAUTION: DG may accelerate for approximately 2 sec after actuating the normal stop handswitch due to the time delay inherent in the DG governor circuit which assumes a full speed condition when the normal stop handswitch is actuated. The time delay was added to allow the DG breaker to open before speed dropped to idle speed from full speed.
STEP 14: [13] IF Idle Start is used for warm up followed by CRITICAL shutdown, THEN PERFORM the following: STEP
[13.1] PRESS 1-HS-82-26, LOCAL NORMAL STOP GEN lA-A, to initiate shutdown sequence [l-PNL SAT A/2, Diesel Engine 1A1/1A2 Control Panel].
STANDARD: 1-HS-82-26 is pressed. This step is critical to the shutdown of the DG. UNSAT
- CUE: After switch is depressed is pushed, and if checked engine is at 450 RPM.
EVALUATOR NOTE: Speed indication is on 1-PNL-82-A.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 13 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J P MA049 STEP 15: [13.2] WHEN DG has idled for 10 minutes, THEN CRITICAL VERIFY DG speed dropping to zero. STEP STANDARD: The performer verifies the DG speed dropping to zero using speed indication on 1-PNL-82-A. This step is SAT critical to the proper shutdown of DG to allow return to standby.
COMMENTS:
STEP 16: [13.3] PLACE 1-RLY-82-LRX1A, DG lA-A LOCAL! CRITICAL REMOTE CONTROL LOCKOUT, in REMOTE. [1- STEP ARB-82-A!1 Diesel Generator lA-A Relay Board]
STANDARD: The performer places 1-RLY-82-LRX1A, DG lA-A LOCAL! SAT REMOTE CONTROL LOCKOUT, in REMOTE (Vertical Position) This step is critical to allow return to standby of DG.
U N SAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 6 PAGE 14 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J P MA049 EVALUATOR NOTE Performance steps 17 and 18 may be combined by the performer.
STEP 17: [13.4] PLACE 1-HS-82-18, DG MODE SELECTOR CRITICAL Switch, in UNIT (PUSHED IN position)[O-M-26] STEP STANDARD: Performer contacts the MCR to place 1-HS-82-18, DG MODE SELECTOR Switch, in UNIT. This step is critical SAT to allow return to standby of DG.
- CUE: When contacted, repeat back, then report that I -HS 82-18 has been placed in UNIT. UNSAT COMMENTS:
STEP 18: Notify the Control Room Operator that lA-A DG has been Idle Started for warm up and is presently back in standby. SAT STANDARD: The performer notifies the MCR that lA-A DG has been Idle Started for warm up and is presently back in standby.
UNSAT
- CUE: When notified, acknowledge the report using repeat back.
COMMENTS:
END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being SimuIated
REV. 6 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
All DGs are in standby alignment.
IA-A DG has been declared INOPERABLE, maintenance has been completed.
lA-A DG has been rolled one complete revolution four hours ago.
Maint. Crews are on hand to perform required surveillance testing of the lA-A DG.
You are an AUO assigned to work with Maint. on the lA-A DG.
INITIATING CUES:
The Control Room Operator directs you to use SOI-82.O1 to locally perform an Idle Start for warm up followed by shutdown on the IA-A DG.
You are to notify the Control Room Operator when you have completed the task and the IA-A DG is returned to standby alignment.
REV. 0 PAGE 1 0F9 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO2OB TASK TITLE: PERFORM LOCAL BORATION OF THE RCS PER FR-Si WRITTEN BY:
VALIDATED BY:
APPROVED BY:
(OPERATIONS TRAINING)
CONCURRENCE:
(OPERATIONS REPRESENTATIVE)
REV. 0 PAGE 2 0F9 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO2OB NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF DATE PAGES PREPARED!
NUMBER REVISION AFFECTED REVISED BY:
0 Initial Issue. 03/17/08 All D.L.Hughes
REV. 0 PAGE 3 0F9 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO2OB EVALUATION SHEET Task: Perform local Boration of the RCS per FR-S.1 Alternate Path: When attempting to manually open 1-FCV-62-138, the valve will not move and the performer will be required to manually open 1-ISV-62-929.
Facility JPM #: 3-OT-JPMAO2OB Rev 0 K/A Rating(s): APE 024AA1. Ability to operate and / or monitor the following as they apply to Emergency Boration:
- AA1 .04 Manual boration valve [Importance RO/SRO 3.6 / 3.7]
APE 024AA2. Ability to determine and interpret the following as they apply to the Emergency Boration:
- AA2.02 When use of manual boration valve is needed
[Importance RO/SRO 3.9/4.4]
TASK STANDARDS: Greater than 35 GPM Emergency Borate flow is locally established.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant X Perform Simulate X
References:
FR-S.1 NUCLEAR POWER GENERATION/ATWS (Rev 18)
Task Number: APPLICABLE FOR: RO/SRO 1 OCFR55.45:
VIrIt,ii Time: 12 mm. Time CritrI NO Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
REV. 0 PAGE 4 0F9 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO2OB EVALUATOR INFORMATION SHEET Tools/EguipmentlProcedures Needed:
Hard-hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes Auxiliary Building Entry under RWP.
In-plant safety rules and ALARA Give a current copy of FR-S.1 step 4 to give to the performer.
Note: If already in the RCA, START THIS JPMAT THE RADWASTEAUO DESK IN THE AUX BLDG, otherwise start the JPM at any appropriate location inside the Protected Area.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The unit is experiencing an ATWAS.
The OAC is currently performing step 4.g of FR-S.1 NUCLEAR POWER GENERATION / ATWS.
1-FCV-62-138 can not be opened from the MCR; Emergency Boric Acid Flow has not been established.
You are an extra RO on shift.
INITIATING CUES:
You have been instructed by the Unit Operator to locally establish emergency boric acid flow lAW step 4.g RNO of FR-S.1 NUCLEAR POWER GENERATION I ATWS.
You are to notify the Unit Operator when you task is complete.
REV. 0 PAGE 5 0F9 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO2OB START TIME:
STEP 1: [1 .g] IF BA flow less than or equal to 35 gpm, THEN: Critical Locally OPEN emergency borate valve 1-FCV-62-138 Step
[blender station el 713],
STANDARD: The performer locates 1-FCV-62-138, Emergency Boration Flow Control valve. The manual lever is simulated to be pushed down SAT to the manual position (in direction of arrow) and the performer simulates attempting to turn the hand wheel in the counter clockwise direction.
UNSAT Evaluator After the performer attempts to open FCV-62-138, state that the valve ill not move from the closed position.
After the Evaluator Que, the Performer should go to the step after the OR (see JPM step 2 below):
COMMENTS:
OR STEP 2: Critical ALIGN manual boration: Step
- 1) Locally OPEN alternate boration valve 1-ISV-62-929 [blender station el 713].
STANDARD: 1-ISV-62-929 is OPENED by rotating the valve handwheel SAT counter-clockwise.
Step is critical to proper alignment of flow path.
UNSAT Evaluator After the performer has demonstrated the method of opening the valve,
- 1. state that the valve travels several turns in the counter-clockwise direction and stops.)
- 2. state that flow noise can be heard as the valve is opened.
COMMENTS:
REV. 0 PAGE 6 0F9 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO2OB OR ALIGN manual boration:
STEP 3
- 2) OPEN blender BA supply 1-FCV-62-140.
STANDARD: 1-FCV-62-140 is verified to be OPEN SAT Evaluator IF FCV-62-1 40 is checked locally, state that the valve stem Que: is up. ._UNSAT IF the control room is notified, state that FCV-62-140 indicates open.
COMMENTS:
STEP 4:
OR ALIGN manual boration:
- 3) MONITOR BA flow STANDARD: Performer reads local indicator 1-Fl-62-139, calls the MCR and notifies MCRthatflowon 1-Fl-62139 reads 38 gpm and FR-S.1 SAT step 4.g RNO is complete.
IF performer request control room to monitor flow, state that Evaluator control room indicator 1-FI-62-139, is erratic, flow needs to UNSAT be verified locally.
IF performer checks 1-FI-62-137 using a pointer, point at 0.
IF performer checks 1-FI-62-139 using a pointer, point at 38 and steady..
Acknowledge task completion.
COMMENTS:
END OF TASK TIME STOP:
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The unit is experiencing an ATWAS.
The OAC is currently performing step 4.g of FR-S.1 NUCLEAR POWER GENERATION /ATWS.
1-FCV-62-138 can not be opened from the MCR; Emergency Boric Acid Flow has not been established.
You are an extra RO on shift.
INITIATING CUES:
You have been instructed by the Unit Operator to locally establish emergency boric acid flow lAW step 4.g RNO of FR-S.1 NUCLEAR POWER GENERATION I ATWS You are to notify the Unit Operator when you task is complete.
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REV.O PAGE 2 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB REVISION LOG DATE DESCRIPTION OF CHANGES PAGES REVIEWED REVISION AFFECTED BY LOG INITIALISSUE ALL D.L.Hughes 0 03/10/08
PAGE 3 0F17 REV.O WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB Task: Establish Manual Makeup to Volume Control Tank (VCT) Per SOl-62 Alternate Path: When the Manual Makeup quanity has completed, the dilution valves will not close, requiring actions to secure the Primary Water pumps Facility JPM #: 3-OT-JPMR05OB Rev 0 K/A Rating(s): 004 A4.13 Ability to manually operate and/or monitor in the control room:
VCT level control and pressure control [Importance: RO/SRO 3.3/2.9]
TASK STANDARDS:
Preferred Evaluation Location: Preferred Evaluation Method:
X In-Plant Perform X Simulate Simulator
References:
S0l-62.02 Rev 0047 Boron Concentration Control AOl-03 Rev 0027 MALFUNCTION OF REACTOR MAKEUP CONTROL Task Number: RO-062-SOl-62-017 APPLICABLE FOR: RO/SRO 10CFR55.45: 2, 3, 5, 6, 8 Validation Time: 15 mm. Time Critical: No Time Start:
Candidate:
NAME SSN!EIN Time Finish:
UNSAT Performance Time Performance Rating: SAT I
Examiner: DATE NAME SIGNATURE COMMENTS
REV.O PAGE 4 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to preshot in IC # 258
- 2. Acknowledge all alarms.
- 3. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
Initialize to IC-40 Place 1-HS-62-140A in STOP Place 1-HS-62-118A in divert until VCT level is 18%. -
Insert IMF CVO9 to fail auto makeup to VCT.
Insert lOR ZD1HS62144 CLOSE Insert lOR ZDIHS62143 (el) OPEN Insert lOR ZDIHS62128 (el) OPEN Acknowledge alarms.
- 5. After performer indicates understanding of task, place simulator in run.
SIMULATOR OPERATOR INSTRUCTIONS:
- 1. When the performer is at JPM STEP 8, and Primary Water flow has been adjusted, insert Trigger I to fail I-FCV-62-I28, and I-FCV-62-143 OPEN
REACTW - VERS WB3.2]
VCT MAKEUP INTEGRATOR SETTINGS CALCULATION WATTS BAR UNIT 1 CYCLE 9 INPUT DATA CURRENT RCS BORIC ACID CONCENTRATION 1020 PPM
[I]
CURRENT BAT BORIC ACID CONCENTRATION 6820 PPM
[2]
B-10 DEPLETION VALUE 0 PPM
[3]
CURRENT VCT LEVEL 18 %
[4]
DESIRED VCT LEVEL 30 %
[5]
CALCULATION OUTPUTS B-b CORRECTED BORON CONCENTRATION 1020 PPM
[1]
VCT ADDITION VOLUME 232 GALS
[2]
TOTAL FLOW RATE 82.3 GPM
[3]
CALCULATION CHECK Y THE SAME QUANITIES [1] AND [2] BELOW SHOULD BE APPROXIMATEL VCT ADDITION VOLUME 232 GALS
[I]
[2] ( 35 + 197 )
(BA INTG SETTING +/- PW INTG SETTING)
TOTAL INTEGRATOR SETTING 232 GALS INPUT DATA BA BATCH COUNTER 35 GALS
[1]
(1-FQ-62-139) [1-M-6]
BA TO BLENDER 30.8 %
[2]
(1-FC-62-139) [1-M-6]
BA TO BLENDER FLOW 12.3 GPM
[3]
(1 -FI 139) [1 -M-6]
PW BATCH COUNTER 197 GALS
[4]
(1-FQ-62-142) [l-M-6]
PW TO BLENDER 3 5.0%
[5]
(1-FC-62-142) [I-M-6]
PW TO BLENDER FLOW 70.0 GPM
[6]
(1-FI-62-142) [1-M-6]
PERFORMER DATE IV/SRO DATA
REV.O PAGE 6 0F17 WATTS BAR NUCLEAR PLANT 3-OT-J PMRO5.OB Tools/Equipment/Procedures Needed:
ENSURE clean copies of SOl-62.02 are in all the books on the simulator floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
steps I will explain the initial conditions, and state the task to be performed. All control room e initiating shall be performed for this JPM, including any required communications. I will provid me when you cues and reports on other actions when directed by you. Ensure you indicate to task understand your assigned task. To indicate that you have completed your assigned return the handout sheet I provided you. -
INITIAL CONDITIONS:
- The Unit is at 100% RTP.
- The RCS Cb is at 1020 ppm per Chem Lab report.
- VCT level is stable at 18%, Auto Make-up from the Blender has failed to operate.
- The STA has just completed a REACTW for the desired makeup.
INITIATING CUES:
via 1-FCV-62-128, The Unit Supervisor has directed you to perform a manual makeup to the VCT MAKEUP TO VCT INLET, to increase VCT level to 29-31%.
Notify US when the procedure is complete.
REV.O PAGE 7 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB START TIME:
STEP 1: Obtain a copy of the procedure.
STANDARD: A copy of SOl-62.02 has been obtained COMMENTS:
- __UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
(CUE:If asked, section 4.2, Field Preparations, have been completed)
STEP 2: [1] PERFORM Appendix C, Calculation Of Boric Acid And Primary Water Integrator Setting For Manual Makeup OR USE Appendix B for Blending at greater than 2500 ppm.
SAT EXAMINERS Give the Performer the REACTW CUE:
UNSAT STANDARD:
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 0 PAGE 8 OF 17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 3: [2] PLACE controllers in MANUAL, and CLOSE the following:
[a] 1-FC-62-139, BATO BLENDER SAT
[b] 1-FC-62-142, PW TO BLENDER STANDARD: 1-FC-62-139 and 1-FC-62-142 controllers placed in the MANUAL position and closed. _UNSAT COMMENTS:
STEP 4: [3] ADJUST Batch Counters for the desired quantity of - CRITICAL boric acid and primary water using values from Appendix B STEP or C:
- a. 1-FQ-62-139, BA Batch Counter SAT
- b. 1-FQ-62-142, PW Batch Counter STANDARD: 1-FQ-62-139 and 1-FQ-62-142 have been reset and adjusted (by thumb wheel) to the desired quantity.
- BA Batch Counter @ 35 UNSAT
- PW Batch Counter @ 197 COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 9 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 5: [4] PLACE 1-HS-62-140B, VCT MAKEUP MODE, in MAN.
SAT STANDARD: 1-HS-62-140B has been placed in the MANUAL position.
COMMENTS: UNSAT STEP 6: [5] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to CRITICAL START, and VERIFY Red light is LIT. STEP STANDARD: 1-HS-62-140A, Make up Control Switch, has been placed SAT in the START position and Red Light has been verified LIT.
COMMENTS:
STEP 7: [6] IF Borating OR Blending, THEN PERFORM the CRITICAL following: STEP
[a] OPEN 1-FCV-62-128, MAKEUP TO VCT
- INLET SAT STANDARD:
1-HS-62-128, Makeup to VCT Inlet, has been placed in the OPEN position. UNSAT COMMENTS:
- Ifalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.0 PAGE 10 0F17 WATTS BAR NUCLEAR PLANT 3-OT-J PM RO5OB STEP 8: [6] PERFORM the following: CRITICAL
[bJ MANUALLY ADJUST 1-FC-62-139, BA TO STEP BLENDER, and 1-FC-62-142, PW TO BLENDER, to desired flow(s) using blending flowrates from Appendix C, OR Appendix B for SAT Blending at greater than 2500 ppm.
STANDARD: 1-FC-62-139 has been adjusted to approximately 12 (+/- 0.5) gpm UNSAT 1-FC-62-142 has been adjusted to approximately 70 (+/-5.0) gpm SIMULATOR When Primary Water flow has been adjusted, insert OPERA TOR Trigger I to fail I-FCV-62-128, and I-FCV-62-143 OPEN.
COMMENTS:
STEP 9: [7] IF Diluting, THEN PERFORM the following:
[a] OPEN 1-FCV-62-128, MAKEUP TO VCT SAT INLET.
[b] ADJUST 1-FC-62-142, PW TO BLENDER, to desired flow.
UNSAT STANDARD: The performer has determined that this step does not apply.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 11 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 10: [8] IF Alternate Diluting, THEN PERFORM the following:
[a] OPEN 1-FCV-62-144, MAKEUP TO VCT OUTLET, and 1-FCV-62-128, MAKEUP TO VCT INLET.
[b] ADJUST 1-FC-62-142, PW TO BLENDER, to UNSAT desired flow.
STANDARD: The performer has determined that this step does not apply.
COMMENTS:
STEP 11: [9] IF RCS CB is being changed, THEN PLACE 1-HS 341H, BACKUP HEATER C [1-M-4j, to ON to SAT equalize RCS-Pzr CB.
STAN DARD: The performer has determined that this step does not apply.
UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 0 PAGE 12 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 12: [101 MONITOR parameters listed below:
Instrument Location Parameters SAT 1-Pl-62-122 1-M-6 VCT PRESS 1-Ll-62-129A 1-M-6 VCT LEVEL 1-Fl-62-139 1-M-6 BATO BLENDER FLOW U N SAT 1-FQ-62-139 1-M-6 BA BATCH COUNTER 1-Fl-62-142 1-M-6 PWTO BLENDER FLOW 1-FQ-62-142 l-M-6 PW BATCH COUNTER 1-Ll-62-238 1-M-6 BAT A LEVEL 1 -Ll-62-242 1-M-6 BAT C LEVEL STANDARD: The above listed indicators have been checked periodically during VCT make-up operation.
COMMENTS:
STEP 13: [11] IF 1-Ll-62-129A, VCT LEVEL, increases to 63% THEN ENSURE 1-FCV-62-118A, LETDOWN DIVERT TO SAT HUT, diverts to the HUT.
STANDARD: 1-Ll-62-129A, VCT Level, is monitored periodically during VCT make-up operation and is not allowed to reach 63%. UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 13 0F17 WATTS BAR NUCLEAR PLANT 3-OT-J PM RO5OB STEP 14: [12] WHEN 1-LI-62-129A, VCT LEVEL, is at desired level, THEN PERFORM the following:
[a] PLACE 1-HS-62-140A, VCT MAKEUP SAT CONTROL, to STOP.
[b] CLOSE 1-FCV-62-128, MAKEUP TO VCT INLET.
UNSAT STANDARD: 1-LI-62-129A has been checked at 29-31%.
1-HS-62-140A has been placed in STOP position.
1-FCV-62-128 has been placed in the CLOSE postion.
Performer should realize that dilution flow did not stop and that 1-FCV-62-128 and 1-FCV-62-143 did not close.
COMMENTS:
Evaluator The Critical Task is to take actions to stop Primary Note Water flow in accordance with:
- ARI-112E PW to Blender Flow Deviation and AOl-3 Malfunction of Reactor Makeup Control, OR
- Tl-12.04 Users Guide For AbnormalAnd Emergency Operating Instructions (section2.7 Prudent Operator Actions)
(if Performer takes Prudent Operator action to Stop Primary Water flow, and does not perform ARI-112E, THEN N/A JPM steps 15 19 and complete JPM step 20)
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.0 PAGE 14 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 15: AR! 112E actions:
Corrective Action: SAT
[1] IF dilution controls in AUTO, THEN VERIFY 1-FCV-62-128 and 1-FCV-62-144 CLOSE.
[2] ENSURE VCT makeup control system lined up per SOl 62.02, BORON CONCENTRATION CONTROL. UNSAT
[3] IF manual operation of VCT makeup is required, THEN GO TO SOl-62.02 for system alignment and operation.
[4] IF Cause of alarm is Determined to be: Probable Cause #3.
Dilution/Boration in progress coincident with: THEN Re- N A instate Dilution/Boration activity in progress.
[5] REFER TO AOl-3, MALFUNCTION OF REACTOR MAKEUP CONTROL STANDARD: Performer attempts to perform step 1 above, ensures step 2 (lineup) above is correct, and then goes to AOl-3 COMMENTS:
(
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being SimuIated
REV. 0 PAGE 15 OF 17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 16: A 01-3 actions:
SAT OPERATOR ACTIONS Diagnostics UNSAT IF GO TO Subsection UNEXPLAINED rod insertion.
SRM count rate RISING, or 3.2 N/A T-avg RISING.
UNEXPLAINED rod withdrawal.
SRM count rate DROPPING, or 3.3 T-avg DROPPING.
LOSS of one Demin Water Pump or 3.4 Header while the Primary Water System is in Bypass Mode.
STANDARD: Performer should go to Subsection 3.2 COMMENTS:
A 01-3 actions:
STEP 17:
l.a. CHECK PWST in normal alignment (PWST NOT SAT Bypass Mode).
Evaluator If asked, in form performer that PWST is in normal U N SAT Que alignment STANDARD: Performer goes to step 1 b.
N/A COMMENTS:
- Italicized Cues Are To Be Used Only lf JPM Performance is Being Simulated.
REV.O PAGE 16 0F17 WATTS BAR NUCLEAR PLANT 3-OT-J PMRO5OB A 01-3 actions:
STEP 18:
1.b. ENSURE standby primary water pump HS in MAN. SAT STANDARD: Performer ensures that standby primary water pump HS in MAN. UNSAT COMMENTS:
N/A A 01-3 actions: CRITICAL STEP 19: STEP 1 .c. STOP the running primary water pump.
SAT STANDARD: Performer stops running PW Pump and then verifies that PW flow has stopped. The performer then notifies the SRO. UNSAT EVALUATOR If Performer completes JPM step 20, THEN N/A this JPM NOTE step. N/A COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 17 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB CRITICAL STEP 20: Prudent Operator Action JAW TI-12.04 STEP The Performer performs one or both of the foIowing:
SAT STOPs both primary water pumps and verifies Primary Water flow has stopped on 1-FI-62-142.
STAN DARD:
UNSAT Places 1-FC-62-142 in Manual and CLOSES 1-FCV-62-142 and verifies Primary Water flow has stopped on 1-Fl-62-142.
The performer then notifies the SRO. N/A EVALUATOR If Performer has completed JPM step 19, THEN N/A this NOTE step.
COMMENTS:
Examiner Acknowledge report, notifiy performer that the task is cue: complete. End task TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev. 0 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- The Unit is at 100% RTP.
- The RCS Cb is at 1020 ppm per Chem Lab report. -
- VCT level is at 18%, Auto Make-up from the Blender has failed to operate.
- The problem has been found and a work request initiated by the previous shifts crew.
INITIATING CUES:
The Unit Supervisor has directed you to use the proper procedure to increase VCT level to 29-31%.
Notify US when the procedure is complete.
Rev7 PAGE 1 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 TRANSFER CONTAINMENT SPRAY SUCTION TO RHR CONTAINMENT SUMP PER ES-1.3
Rev7 PAGE 2 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial Issue. Replaces JPM #ES-1.2-2 8/26/92 ALL DELETE KNOWLEDGE QUESTIONS 4/2/93 3, 4 REFLECT PROCEDURE REVISION 2 REFLECTPROCEDUREREVISION 11/20/95 4-10 3 Reflect procedure revision from Rev 6 9/25/97 ALL Albert V.
to Rev 8. Made time without spray White flow time critical. Added admin info, changed titles of ASOS to US, added cautions from procedure, provided step numbers from procedure.
4 Incorporated pen & ink changes which 11/20/99 ALL Albert V.
added information to turnover sheet White that RWST level has just reached 8%.
Made performance step 12 critical since one valve must be open.
Clarified when to begin 120 second time period for critical portion of this JPM. Revised K/A values to Rev 2 of NUREG 1122, updated procedure references, Revised simulator setup instructions.
5 Added procedure step numbers to 10/16/01 ALL Albert V.
Performance Steps, corrected step White number referenced on initial conditions, changed performance step 12 from critical to not critical. Revised procedure step numbers to reflect Rev 10 of ES-1.3.
6 Revised JPM to reflect rev 13 of ES- 08/05/03 ALL A. V. White 1 .3 which deleted one step from JPM and added some step numbers.
7 Revised JPM to reflect rev of ES-1.3 03/13/08 D.L.Hughes and changed Time Critical step to begin when CTMT Spray Pumps are secured. Revised K/A reference.
Revised initial conditions to have RWST at 10%, this adds an additional critical step
Rev7 PAGE 3 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 EVALUATION SHEET Task: TRANSFER CONTAINMENT SPRAY SUCTION TO RHR CONTAINMENT SUMP PER ES-i .3 Alternate Path: N/A Facility JPM #: 3-OT-JPMRO7O Rev 7 K/A Rating(s): 026A4.O1 CSS controls [Importance RO/SRO 4.5/4.3]
TASK STANDARDS: Steps 21 through 24 of ES-i .3 have been correctly performed Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
ES-1.3, Transfer to RHR Containment Sump (REV.17) -
Task Number: RO-113-ES-1.3-OO1 APPLICABLE FOR: RO/SRO IOCFR55.45: 3, 6, 7, 8 Validation Time: 7 mm. Time Critical: YES Candidate: Time Start:
NAME SSN!EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
Rev7 PAGE 4 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 SIMULATOR OPERATOR INSTRUCTIONS:
This JPM has been pre-shot in IC # 254. Should IC # 254 be erased or fail to perform as expected then use the following set-up instructions:
a) Initialize to IC-50.
b) Insert mfp thOib © 100% Severity (Hot Leg Break Loop 2).
c) Acknowledge all alarms and clear motor trip-out white lights d) Stop RCPs.
e) Perform operator actions lAW E-0, and E-1 f) Insert rfi sirl4 (Restore power to FCV-63-1).
g) When required, perform transfer to Containment Sump, steps 1 through 20 of ES-1.3 h) Open 1-FCV-70-153, and 156 (CCS to RHR Hx).
i) Close 0-HS-70-197A (SFP HT EXCH Supply) and 1-HS-70-207 (CDWE Supply from HDR 1B) j) Ensure CCS flows and pressures stabilize.
k) Insert ORP ZAOPDI3O42 © 4 I) Insert ORP ZAOPDI3O43 © 4 m) Insert ORP ZAOPDI3O44 © 4 n) Insert ORP ZAOPDI3O45 © 4
- 0) Insert ORP ZAOPR3O45[1] © 4 p) Insert ORP ZAOPR3O45[2] © 4 q) Acknowledge all alarms r) Freeze simulator when RWST level reaches --10%
- 2. After performer indicates understanding of task, place simulator in run.
Rev7 PAGE 5 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure clean copy ES-i .3, Transfer to RHR Containment Sump is available.
READ TO OPERATOR DIRECTION TO TRAINEE:
e I will explain the initial conditions, which step(s) to simulate or discuss, and provid initiating/operating cues.
ons.
AllI Control Room steps shall be performed for this task, including any required communicati Ensure that you indicate to me when you fully unders tand your task.
INITIAL CONDITIONS: -
- A Large Break LOCA has occurred.
eted.
- E-0 was entered, transition made to E-1 and then to ES-i.3, where Step 20 has been compl
- You are the RO.
INITIATING CUES:
nment The Unit Supervisor directs you to transfer the Containment Spray Pumps to the Contai Sump by performing applicable steps 21 thru 24 of ES-i .3.
Notify Unit Supervisor when Containment Spray has been re-established.
NOTE: PART OF THIS TASK IS TIME CRITICAL.
Rev7 PAGE 6 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 START TIME:
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD: A copy of ES-i .3, Transfer to RHR Containment STANDARD Sump is obtained. __SAT COMMENTS:
UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
CAUTION STEP2
- The containment spray pump MUST stay aligned to the RWST UNTIL the RWST level is less than 8% to ensure sufficient sump inventory for spray pump operation. SAT
- If containment pressure is greater than or equal to 2.0 psig, the containment spray pump suction must be aligned and pump restarted within 120 seconds.
UNSAT Performer reads cautions and abides by requirements.
STANDARD:
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 7 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 Simulator Commence actions to:
Operator
.2 ENSURE ERCW aligned for sump recirc operation:
[21] ALIGN cntmt spray RWST suction:
STEP 3:
[21 .a] CHECK spray pumps RUNNING.
SAT Containment spray pumps verified to be running by red STANDARD: indicating lights or amp meters.
COMMENTS: -
UNSAT STEP 4:
[21 .b] CHECK RWST level less than 8%.
Performer observes that RWST level is not yet less than 8%,
STAN DARD*
goes to E-1.3 step 21.b RNO.
COMMENTS:
U N SAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 8 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070
[2tbRNO] Critical Step STEP 5:
WHEN RWST level less than 8%, THEN PERFORM Substep 21c and ALIGN cntmt spray pumps to cntmt sump.
SAT GO TO Step 27.
Performer monitors RWST level (since it is so close may not go STANDARD to Step 27), and when level is less than 8%, THEN PERFORM Substep 21 c UNSAT Evaluator Note: Critical portion of this JPM step is that the performer waits until RWST level is less than 8% prior to performing Step 21.c COMMENTS:
STEP 6:
[21.c]
STOP both cntmt spray pumps, and PLACE in PULL TO LOCK.
SAT STANDARD: Control Room Hand switches for A and B Cntmt Spray Pumps in PULL-TO-LOCK position. (1-HS-72-1OA & 1-HS-72-27A).
Evaluator Note: When the 2m1 Cntmt Spray Pump is placed in PTL, begin 120 second timer _UNSAT Clock Time: mm/sec COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated
Rev7 PAGE 9 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 7:
[21.d]
ISOLATE cntmt spray suction from RWST:
- CLOSE 1-FCV-72-22. SAT
- CLOSE 1-FCV72-21.
STANDARD: 1-HS-72-21A and 1-HS-72-22A placed in the closed position and valves indicate closed. UNSAT COMMENTS:
STEP 8:
[22] ENSURE ERCW aligned for sump recirc operation:
REFER TO Appendix C (ES.-1 .3), ERCW Operation.
SAT Evaluator Que: STATE to the performer that the BOP operator has completed the ERCW system alignment per Appendix C.)
Performer has verified Appendix C of ES-1.3 completed. UNSAT STANDARD:
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 10 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 9:
[23] ALIGN cntmt spray sump suction:
- a. OPEN 1-FCV-72-44 cntmt spray suction from cntmt sump. SAT STANDARD: 1-HS-72-44A placed in open and valve indicates open.
COMMENTS:
UNSAT STEP 10: .
[23] ALIGN cntmt spray sump suction:
- b. OPEN 1-FCV-72-45 cntmt spray suction from cntmt sump. SAT STANDARD: 1-HS-72-45A placed in open and valve indicates open.
COMMENTS:
UNSAT STEP 11.
[24] MONITOR cntmt press less than 2.0 psig.
Performer uses any of the following indications to determine SAT STANDARD that cntmt press is greater than 2.0 psig, and proceeds to the RNO column of ES-i .3. Step 24
- PDI-30-42
- 1-PDI-30-43
- i-PDI-30-44
- 1-PDI-30-45 _UNSAT
- i-PR-30-45 COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 11 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 12: . Critical Step
[25 RNO] IF cntmt press greater than or equal to 2.0 psig, THEN:
- a. START cntmt spray pumps. SAT STANDARD: Cntmt spray pumps started with 1-HS-72-27A and 1-HS-72-1OA.
Evaluator Note: When the 1st Cntmt Spray Pump is started, stop the 120 second timer UNSAT Clock Time: mm/sec 1t Cntmt Spray Pump s
Critical Step is to have started the prior to 120 seconds.
COMMENTS: -
STEP 13:
[RNO 25.bj OPEN discharge valves 1-FCV-72-2 and 1-FCV-72-39. SAT STANDARD: Discharge valves verified opened by RED lights on 1-HS-72-2A and 1-HS-72-39A.
COMMENTS: UNSAT STEP 14:
[RNO 25.c] ENSURE spray flow on 1-Fl-72-34 and 1-Fl 13.
SAT STANDARD: Performer ensures spray flow indicated on 1-Fl-72-34 and 1-Fl-72-13.
COMMENTS:
UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 12 0F14 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 15: [13) Notify Unit Supervisor that Containment Spray has been transferred to Containment Sump..
EXAMINER When notified, acknowledge the report, notify performer that SAT CUE: the task is complete. End task COMMENTS:
UNSAT END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
AlIl Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- A Large Break LOCA has occurred.
- E-O was entered, transition made to E-l and then to ES-i .3, where Step 2 has been completed.
- You are the RO.
INITIATING CUES:
The Unit Supervisor directs you to transfer the Containment Spray Pumps to the Containment Sump by performing applicable steps 21 thru 24 of ES-i .3.
Notify Unit Supervisor when Containment Spray has been re-established.
NOTE: PART OF THIS TASK IS TIME CRITICAL.
TENNESSEE VALLEY AUTHORITY I WATTS BAR NUCLEAR PLANT I SURVEILLANCE INSTRUCTION I I 1SI--991OB I I 31 DAY FUNCTIONAL TEST OF SSPS TRAIN B I AND REACTOR TRIP BREAKER B -
I Revision 42 I Unit 1 I I QUALITY RELATED I I PREPARED BY: R. S. Henderson I (Type Name> I I SPONSORING ORGANIZATION: MSM APPROVED BY: Edward B. Hall I EFFECTIVE DATE: 03/19/2008 I LEVEL OF USE: CONTINUOUS I
REV. 4 PAGE 1 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A RAISE COLD LEG ACCUMULATOR LEVEL PER SOI-63.O1
REV. 4 PAGE 2 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A NUCLEAR TRAINING REVISION/USAGE LOG Rev # Date Description of changes Pages Affected Reviewed By 0 10/16/01 Initial Issue. ALL A. V. White 11/01/01 Revised format, made changes to reflect rev ALL A. V. White 28 of SOI-63.01. Revised simulator setup instructions and turnover information.
2 11/04/02 Updated procedures referenced, corrected 2,3,5,6, 13, 15 A. V. White typo, revised task assignment sheet, and removed cue from JPM step 3 which was not needed.
3 08/03/07 Incorporated pen & ink change that corrected ALL A. V. White minor wording change due to procedure revision. Added EIN to evaluation sheet.
Updated procedures referenced which changed substep numbers but did not change task performance or its evaluation.
4 03/20/08 Incorporated pen & ink change that corrected ALL D.L.Hughes minor wording issues. Changed substep numbers but did not change task performance or its evaluation.
REV. 4 PAGE 3 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO27A EVALUATION SHEET Task: Raise Cold Leg Accumulator Level Per SOI-63.O1 Alternate Path: N/A Facility JPM #: 3-OT-JPMRO27A Rev 4 K/A Rating(s): O06-A4.O1 [4.1/3.9] 0O6-A1.13 [3.5/3.7] 2.2.21 [3.1/3.2]
Task Standard: Cold Leg Accumulator #1 water level raised to normal level (Annunciator Window 131-A Dark) and system lineup re-established per SOI-63.O1.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
S0I-63.O1 Safety Injection System Rev.42.
Task Number:: RO-063-SOI-63-OO1 APPLICABLE FOR: RO/SRO IOCFR55.45: 3, 4, 6, 7 Validation Time: 14 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
REV. 4 PAGE 4 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to 259
- 2. Acknowledge all alarms. Ensure Source Range Audible Count is audible in horse shoe.
- 3. Place the Simulator in FREEZE.
- 4. Place the Simulator to RUN when the performer indicates an understanding of the task.
- 5. This JPM has been pre-shot in IC #259. Should IC # 259 be erased or fail to perform as expected then use the following set-up instructions:
Initialize to IC-129, go to RUN, cooldown the RCS in accordance with GO-6 to establish conditions where RCS is approximately 1400 psig and temperature 500
°F with C LAs in service.
Ensure Source Range Audible Count audible in horse shoe.
To lower level in CLA-1 to below level alarm setpoint:
- Enter REMOTE FUNCTION rfp sirlO to OPEN drain to RCDT 63-618.
- Manually OPEN 1-63-l3OAon 1M6.
- When either the CLA #1 Low level alarm 131-A Alarms or CLA #1 Low pressure 131-B Alarms then CLOSE 1-63-.130A.
Ensure 1-HS-63-23, 71A, 84, and 64A in the CLOSE position.
Freeze simulator until performer indicates understanding of task.
SIMULATOR OPERATOR INSTRUCTIONS:
NONE
REV. 4 PAGE 5 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A Tools/Equipment/Procedures Needed:
Ensure clean copy of SOl-63.O1 in the simulator copies on the Simulator Floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. -
INITIAL CONDITIONS:
Unit is Mode 3, RCS Heatup is in progress.
Cold Leg Accumulator # 1 Pressure Hi/Lo and Level annunciation are lit.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor directs you to perform the proper instruction to return CLA
- 1 water level to normal, utilizing the IA Safety Injection Pump.
You are to notify the Unit Supervisor when the instruction is complete.
REV. 4 PAGE 6 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A START TIME:
STEP 1: Obtain a copy of the procedure.
SAT STANDARD: A copy of SOl-63.01 Section 8.3.1 has been obtained.
EXAMINERS CUE: After the performer has demonstrated the method of obtaining the correct instruction, the evaluator can UNSAT provide a copy of the instruction.
COMMENTS:
d to be CAUTION: Adding water to more than one CLA at a time while they are require operable places the plant outside design basis. This section is to be used to add water to any selected single CLA. If more than one CLA needs water, separate evolutions must be performed.
STEP 2: [STEP 1] ENSURE Sect 5.1, To Fill & Vent SI Pmps and Piping, COMPLETE. SAT STANDARD: No action required. (Performer proceeds to next step)
UNSAT
- CUE: Inform performer that section 5.1 is complete.
COMMENTS:
STEP 3: [STEP 2] IF RCS pressure is 1000 psig, THEN ENSURE SAT 1-FCV-63-118, CLACCUM 1 OUTLET, CLOSED.
STANDARD: Performer determines that step in Not Applicable and proceeds to the next step.
UNSAT
- CUE: Performer determines that RCS.is filled & vented.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 7 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO27A CAUTION If RCS is 1650 psig or less, ALL SIP injection flow paths must be disabled to prevent inadvertent RCS injection. If l-FCV-63-152 is closed, then SI Pmp A is the only pump that can be used to fill CLA.
STEP 4: [STEP 3] IF RCS 1650 psig or less, AND SIP A is to be used CRITICAL to fill CLA 1, THEN CLOSE 1-FCV-63-152, SI PMP A TOOL STEP 1-2-3-4 [1-M-6].
SAT STANDARD: 1-HS-63-152A is placed to the close position and green valve position indicating light is verified ON, red valve position light OFF on respective valve hand switch. Step is critical to prevent injection to RCS when SI pump is started. UNSAT COMMENTS: -
CAUTION In Mode 4, 5, 6 with the Rx Vessel Head ON, before starting SI Pmp A, 1-FCV-63-1 52 and -156 must be closed, with Hold tags on the handwheels and breakers (Refer to T.S. 3.4.12).
STEP 5: [STEP 4] IF in Mode 4, 5, 6 with SIP lA-A is to be used with Rx Vessel Head ON, THEN
[4.1] ENSURE 1-FCV-63-156, SI PMP A TO HL 1 & 3 [1-M-6], is CLOSED. SAT
[4.2] ENSURE 1-BKR-63-156, SI PUMP IA-A HOT LEG 1 &
3 INJECTION [IA1-A, C/13A], is OFF & TAGGED.
[4.3] ENSURE 1-BKR-63-152, SIP lA-A COLD LEG INJ FLOW CNTL [1A1-A, C/12E}, is OFF & TAGGED. UNSAT
[4.4] ENSURE SAFETY INJECTION PUMP lA-A [6.9kV SD Bd 1A-A/C15j, Breaker racked UP and Closing Spring CHARGED.
STANDARD: No action required. Unit is in Mode 3. The performer N/As the step.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 8 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A CAUTION 1-FCV-63-22, 156, 157 MUST be closed with HOLD Tags on handwheels and bkrs in Modes 4, 5, 6 with vessel head on when running SIP B. (See T.S.
3.4.12)
STEP 6: [STEP 5] IF in Mode 4, 5, 6 with SIP lB-B is to be used with Rx Vessel Head ON, THEN
[5.1] ENSURE 1-FCV-63-22, SI PUMPS CL Injection is CLOSED. SAT
[5.2] VERIFY 1-BKR-63-22, (1B1-B, C/liD) Tagged OPEN with Hold Tag.
[5.3] ENSURE 1-FCV-63-156, SI PUMP 1A HL injection CLOSED. UNSAT
[5.4] VERIFY 1-BKR-63-156, (1A1-A, C/13A) Tagged OPEN with Hold Tag.
[5.5] ENSURE 1-FCV-63-157, SI PUMP lB HL injection CLOSED.
[5.6] VERIFY i-BKR-63-157, (1B1-B, C/13B) Tagged OPEN with Hold Tag.
[5.7] ENSURE 1-FCV-63-152, SI PUMP ATO CL 1-2-3-4 OPEN.
[5.8] ENSURE 1-FCV-63-153, SI PUMP B TO CL 1-2-3-4 OPEN.
[5.9] ENSURE SAFETY INJECTION PUMP lB-B [6.9kV SD Bd 1B-B/C15j, Breaker racked UP and Closing Spring CHARGE.
STANDARD: No action required. Unit is in Mode 3. The performer N/As the step.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 9 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A STEP 7: [STEP 6] PERFORM the following: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID TEST LINE (1-XS-63-100) ISOL 1-M.-6 OPEN 1-FCV-63-187 CKV TEST LINE TO HUT 1-M-6 OPEN 1-FCV-63-71 CLA FILL FROM SI PMPS 1-M-6 OPEN 1-FCV-63-23 STANDARD: Hand switches (1 -HS-63-71 A,1 -HS-63-1 87, &1 -HS-63-23) for SAT each of the above listed valves have been placed in the OPEN position. Step is critical to establish flow path to #1 Accumulator.
U N SAT COMMENTS:
CAUTION If 1-FCV-63-152 was closed in step 8.3.1[3], then SI Pmp IA-A is the only pump that can be used to fill CLA. (JPM Step 4)
STEP 8: [STEP 7] ENSURE the following (N/A pump not selected)
NOMENCLATURE LOCATION POSITION UNID SI PMPS RECIRC HDR TO RWST 1-M-6 OPEN 1-FCV-63-3 SI PMP A RECIRC TO RWST 1-M-6 OPEN 1-FCV-63-4 SI PMP B RECIRC TO RWST 1-M-6 OPEN 1-FCV-63-175 RWST TO SI PMPS SUCTION 1-M-6 OPEN 1-FCV-63-5 SI PMP A SUCTION 1-M-6 OPEN 1-FCV-63-47 SI PMP B SUCTION 1-M-6 OPEN 1-FCV--63-48 SAT STANDARD: The hand switches (1-HS-63-3A, 1-HS-63-4A, l-HS-63-5A, &
1-HS-63-47A red valve position indicating lights are verified on.
COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 10 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO27A STEP 9: [STEP 8] PERFORM the following (N/A pump not selected): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID SI PMP lA-A (ECCS) 1-M-6 START 1-HS-63-1OA SI PMP lB-B (ECCS) l-M-6 START l-HS-63-15A STANDARD: Hand switch 1-HS-63-1OA has been placed to START position SAT and lA-A pump started. Step is critical to provide flow to Accumulator.
EVALUATOR NOTE: Starting of the pump should be announced on P.A. UNSAT COMMENTS:
STEP 10: [Step 9] OPEN 1-FCV-63-1 15, MAKEUP TO CL ACCUM 1, CRITICAL
{1-M-61. STEP STANDARD: 1-HS-63-115A has been placed in the OPEN position. Step is critical to establish flow path to accumulator. SAT COMMENTS:
U N SAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 11 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A NOTE 1-Ll-63-129, CLA 1 LEVEL [1-M-6], is preferred to monitor level due to faster response than 1-LI-63-119.
STEP 1 1: [STEP 10] WHEN CLA is at desired level (Alarm 131 -A, CL CRITICAL ACCUM 1 LEVEL HI/LO, not LIT), THEN PERFORM the STEP following:
NOMENCLATURE I LOCATION POSITION UNID 1-FCV-63-115 MAKEUP TO CLACCUM I I 1-M-6 CLOSED CKV TEST LINE TO HUT f l-M-6 CLOSED 1-FCV-63-71 TEST LINE (1-XS-63-100) ISOL I 1-M-6 CLOSED 1-FCV-63-18 l-FCV-63-23 7
CLA FILL FROM SI PMPS 1-M-6 CLOSED STANDARD: The level has been increased until neither HI/LO alarm on SAT Annunciator 131-A is LIT, THEN 1-HS-63-115A, 1-HS-63-71A, 1-HS-63-187, & 1-HS-63-23 have been placed in the CLOSED position. This step is critical isolate flow path to accumulator UNSAT EVALUATOR NOTE: Annunciator level alarm setpoints are HI 7970 gal, LO 7660 gal and pressure alarms Hi 660 psig, Lo 610 psig COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 12 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A STEP 12: [STEP 11] ENSURE SI pump has operated for greater than CRITICAL 20 minutes, THEN PERFORM the following (N/A pump not STEP selected):
NOMENCLATURE LOCATION POSITION UNID Si PMP lA-A (ECCS) 1-M-6 STOP 1-HS-63-1OA SI PMP lB-B (EGOS) 1-M-6 STOP 1-HS-63-15A STANDARD: Hand switch 1-HS-63-1OA has been placed to STOP position SAT and lA-A SI pump is Stopped. This step is critical to return SI pump to normal after fill.
- CUE: After performer has determined time to take pump off, UNSAT state that the time period has elapsed.
COMMENTS:
NOTE Step 8.3.1[12] or8.3.1[131 may be N/Ad based on SIPs operability requirements.
(JPM steps 13 & 14.)
STEP 13: [STEP 12] ENSURE the following (N/A pump NOT selected): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID SI PMP lA-A (EGGS) l-M-6 A AUTO 1-HS-63-lOA SI PMP lB-B (EGOS) 1-M-6 A AUTO 1-HS-63-15A STANDARD: Hand switch 1-HS-63-1OA has been placed to A AUTO SAT position. This step is critical to assure ES Standby lineup.
COMMENTS:
UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 13 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A STEP 14: [STEP 13] PERFORM the following (N/A pump NOT selected):
NOMENCLATURE LOCATION POSITION UNID SI PMP lA-A (ECCS) 1-M-6 PULL-TO-LOCK 1-HS-63-1OA SI PMP lB-B (ECCS) 1-M-6 PULL-TO-LOCK 1-HS-63-l5A STANDARD: Performer N/As this step. SAT COMMENTS:
UNSAT STEP 15: [STEP 14] IF 1-FCV-63-152, was closed in step 8.3.1[3], CRITICAL THEN OPEN 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 [1-M-6j STEP (N/A in Mode 4, 5, 6.)
SAT STANDARD: 1-HS-63-152A is placed to the open position and red valve position indicating light is verified ON, green valve position indicating light is verified OFF. Step is critical to realign SI flow path to RCS. UNSAT COMMENTS:
STEP 16: [STEP 15] IF 1-FCV-63-118 was closed in step 8.3.1[21, THEN OPEN 1-FCV-63-118, CLACCUM 1 OUTLET if desired.
STANDARD: No action required. Valve was not closed. The performer N/As the step. SAT COMMENTS:
U N SAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV, 4 PAGE 14 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A NOTE CLA 1 press can be read on 1-Pl-63-126 or 128.
STEP 17: [STEP 16] VERIFY CLA pressure in desired range (Alarm 131-B, CLACCUM 1 PRESS HI/LO, not LIT).
STANDARD: The CLA pressure has been checked to be between > 610 psig AND < 660 psig. SAT
- CUE: If pressure >660 psig and performer mentions, acknowledge and state that the CLA will be vented following completion of this procedure. UNSAT EVALUATOR NOTE: Annunciator alarm setpoints are HI 660 psig, LO 610 psig) -
COMMENTS:
STEP 18: Notifies Unit Supervisor that fill of CLA #1 has been completed.
SAT STANDARD: Performer notifies Unit Supervisor that CLA #1 has been filled.
- CUE: As Unit Supervisor acknowledge report using repeat back. UNSAT COMMENTS:
END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 WATTS BAR NUCLEAR PLANT CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit is Mode 3, RCS Heatup is in progress.
Cold Leg Accumulator # 1 Pressure Hi/Lo and Level annunciation are lit.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor directs you to perform the proper instruction to return CLA
- 1 water level to normal, utilizing the IA Safety Injection Pump.
You are to notify the Unit Supervisor when the instruction is complete.
RevO PAGE 1 0F14 Watts Bar Nuclear Plant 3-OT-JPMRI 18a CHANGE FROM TWO TRAINS TO ONE TRAIN OPERATION OF RHR DUE TO CCS LEAK PER SOI-74O1
RevO PAGE 2 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 18a NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial Issue. 03/12/08 All D.L.Hughes
RevO PAGE 3 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 1 8a EVALUATION SHEET Task: CHANGE FROM TWO TRAINS TO ONE TRAIN OPERATION OF RHR DUE TO CCS LEAK PER SOI-74.01 Alternate Path: As 1-HCV-74-37, RHR HEAT EXCHANGER lB MANUAL BYPASS RHR Pump 1 B-B is closed and flow thru RHR Pump 1 B-B flow goes below 750 gpm, 1-FCV-74-24 will not automatically open, requiring manual action.
Facility JPM #: 3-OT-JPMR1 18a RevO K!A Rating(s): 005A4.01 Controls and indication for RHR pumps RO!SRO [3.6! 3.4]
RO/SRO [3*4* 3.1]
005A4.02 Heat exchanger bypass flow control 005A4.03 RHR temperature, PZR heaters and flow, and nitrogen RO/SRO [2.8 ! 2.7]
TASK STANDARDS: A RHR Train in service, RCS temperature and pressure constant at pre- evolution values.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOI-74.01, RESIDUAL HEAT REMOVAL SYSTEM, (Rev 54)
ARI 113C, RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION (Rev 16)
Task Number: RO-074-SOI-74-006 APPLICABLE FOR: RO!SRO IOCFR55.45: 3, 4, 6, 7 Validation Time: 20 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS
RevO PAGE 4 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 1 8a SIMULATOR OPERATOR INSTRUCTIONS:
a) Reset to any RHR cooling IC.
b) Acknowledge all alarms.
c) Place both Trains of RHR in service per SOI-74.O1 section 6.1 and stabilize conditions. Ensure RCS Temperature is between 180°F & 195°F d) Insert mn rh016 to 0 (fails 1-FCV-74-24 to closed) e) When simulator stable, freeze and snap if necessary.
- 2. After performer indicates understanding of task, place simulator in run.
RevO PAGE 5 0F14 Watts Bar Nuclear Plant 3-OT-JPMRI 1 8a EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure clean copy of SOl-74.O1, RESIDUAL HEAT REMOVAL SYSTEM, (Rev 54).
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues AllI Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS: -
- Unit is in Mode 5
- Unit is stable with Both Trains of RHR in service.
- Forced oxide phase is not in progress, RCS activity is not elevated.
- CCS relief valve,1-70-565B, RHR Pump lB-B Seal Water HX Outlet Relief, has developed a leak. The 1 B-B RHR Pump needs to be removed from service to allow repairs.
- Another Operator will control PZR Level and Pressure (Bubble in the Pressurizer) and all secondary and back panel systems.
INITIATING CUES:
Train RHR The Unit Supervisor has directed you as the RO to change from 2 train RHR operation to A operation, maintaining the current RCS temperature and letdown flow/pressure.
You are to notify the Unit Supervisor when that has been completed.
Rev 0 PAGE 6 OF 14 Watts Bar Nuclear Plant 3-OT-JPMR1 1 8a Appendix A (Page 1 of 1)
RHR Pump Operating Flow Limits 4OOO kIe 1, with 23 II above vco,el tiarige 3000 See P & I, T & U.
2500 -
Nt&le 6 with RHR Pump 23 t above vessel flange flow rate SeeP & L T & U.
GPM 2000 Per Pump Minimize Operation in this Range 1 400 750 i
0 FCV-74-1 &-2 Mini flow Reduced FCV-74-1 & 2 Flow path Flow path (One Operation Inventory!
(2 pumps pump only) midloop running)
(One pump only) ----OR----
RevO PAGE 7 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 18a START TIME:
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD: A copy of SOl-74.O1, section 6.3 is obtained.
STANDARD: __SAT COMMENTS:
UNSAT EXAMINERS After the performer has demonstrated the method of obtaining CUE: the correct instruction, the evaluator can provide a copy of the -
instruction.
[1] IF forced oxide phase is in progress with high activity in the STEP 2*
RCS, THEN OBTAIN Chemistry concurrence prior to stopping RHRP B due to possible adverse affects on plant dose rates. SAT STANDARD: Performer determines NO action required and continues with instruction.
UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 8 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 1 8a STEP 3:
[2] OPEN 1-SPV-74-530, RHR HX 1A OUTLET TO CVCS,
[A7W!713 Hx Rm A]. SAT Simulator Operator:
If 1-SPV-74-530 not already open, use RFP rhr03 set to 100 when requested to open 1-SPV-74-530.
Acknowledge the report using repeat back, then state UNSAT 1-SPV-74-530 is OPEN If requested state tt J V. has been con ducted.)
STANDARD: AUO is dispatched to open 1-SPV-74-530 COMMENTS: -
STEP 4: [3] CLOSE 1-SPV-74-531, RHR HX lB OUTLET TO CVCS,
[A7U/713 Hx Rm B].
Simulator SAT Operator: If I -SPV-74-531 not already open, use REP rhr04 set to 0 when requested to close 1-SPV-74-531.
Acknowledge the report using repeat back, then state 1-SPV-74-531 is CLOSED. If requested state LV. has been conducted.) UNSAT STANDARD: AUO is contacted to locaiiy close l-SPV-74-531, RHR HX lB OUTLET TO CVCS.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 9 0F14 Watts Bar Nuclear Plant 3-OT-JPMRI 1 8a STEP 5:
[4] ENSURE 1-HIC-62-81A, LETDOWN PRESSURE CONTROL, maintaining desired letdown flow and pressure.
SAT STANDARD: Performer determines that current letdown flow and pressure is acceptable, and continues in the procedure.
COMMENTS:
U N SAT STEP 6: [5] CLOSE 1-FCV-74-28, RHR HEAT EXCHANGER lB CRITICAL STEP OUTLET FLOW CONTROL -
STANDARD: Performer monitors RHR injection flows using 1-Fl-63-92A&B, 1-Fl-63-91A&B and slowly closes l-FCV-74-28 with 1-HIC-74-28A. SAT While slowly closing FCV-74-28 the performer will increase flow through the A Train Heat Exchanger. Note 1-FCV-74-32 may be adjusted as necessary to maintain total injection flow relatively constant yet maintain flow within Appendix A limits.
Performer should be monitoring RCS temperature to ensure it remains stable. UNSAT COMMENTS:
STEP 7: [6] WHEN header flow is <750 gpm, THEN VERIFY 1-FCV 24, RHR PUMP lB-B MINIMUM FLOW, OPENS.
STANDARD: l-FCV-74-24 is verified to open WHEN header flow is <750 gpm by checking respective valve hand switch in following steps Position camera #3 to view 1-FCV-74-24 hand switch, and Simulator prepare to DELETE malfunction RHRO16 if performer pera or attempts to OPEN 1-FCV-74-24.
UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 10 0F14 Watts Bar Nuclear Plant 3OT-JPMR1 18a STEP 8: [7] THROTTLE 1-FCV-74-16, RHR HEAT EXCHANGER 1A CRITICAL OUTLET FLOW CONTROL to obtain desired RCS STEP temperature control.].
STANDARD: 1-FCV-74-16, is throttled open with 1-HIC-74-16A to maintain SAT RCS temperature cooldown rate as monitored on Cooldown Plot or 1-Tl-74-14.
Note 1-FCV-74-32 may be adjusted as necessary to maintain total injection flow flow relatively constant yet maintain flow within Appendix A limits, and RCS temperature constant.
UNSAT BOP If Alarm 245E RHR HX IA-A Ret Temp Hi annunciates during OPERA TOR this evolution, THROTTLE OPEN I-HS-67-143A to approximately 7000 gpm to lower CCS temperature.
COMMENTS:
STEP 9: [81 CLOSE 1-FCV-74-35, RHR HEAT EXCHANGER lB OUTLET CROSSTIE.
STANDARD: 1-FCV-74-35 is closed using 1-HS-74-35A and verified closed by green light lit and red light off on respective hand switch SAT COMMENTS:
UNSAT
[9] CLOSE 1-FCV-63-94, RHR TO COLD LEG 1 & 4 INJECTION CRITICAL STEP 10:
ISOLATION STEP STANDARD: 1-FCV-63-94 is closed using 1-HS-63-94 and is verified in the closed position by green light lit red light off on respective valve SAT hand switch..
COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 11 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 18a STEP 11: [101 CLOSE 1 -HCV-74-37, RHR HEAT EXCHANGER lB Critical Step MANUAL BYPASS, [A7V!713, Hx Rm B].
Simulator When requested to close 1-HCV-74-37, MFP RHRO7 set to 0.
Operator: Acknowledge the report using repeat back, then state SAT 1-HCV-74-37 is CLOSED. If requested state IN. has been conducted.)
Simulator ENSURE camera #3 is positioned to view 1-FCV-74-24 hand switch, and prepare to DELETE malfunction RHROI6 if __UNSAT Operator performer switches 1-HIS-74-24 to OPEN.
STANDARD: AUO is dispatched to close i-HCV-74-37. As 1-HCV-74-37 is closed, lB-B RHR Pump header flow will lower to <750 gpm and 1-FCV-74-24 will not automatically open as required. Alarm 11 3C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION will annunciate. Performer should perform one of the following to protect 1 B-B RHR Pump from a low flow condition:
- Take MANUAL action to OPEN 1-FCV-74-24, which can be accomplished either by prudent operator action lAW TI-i 204 or by following ARI-1 13C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION (actions described in JPM steps 12, 13, and 14).
- Securing I B-B RHR Pump with 1-HS-74-20A Evaluator The Critical portion of this JPM step is to protect the lB-B Note: RHR Pump from a low flow condition. This can be accomplished by either of the two above standard actions. if the Performer performs either of the two actions at this point, then N/A steps 12, 13, and 14 of this JPM COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 12 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 I 8a STEP 12: 11 3C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION
[Corrective Action 1, 2, & 3]
[1] CHECK the following:
- RCS pressure
- RHRPumpflow SAT
- RHR Pump discharge pressure
[2] IF RCS pressure is greater than 370 psig, THEN REDUCE pressure to less than 370 psig.
[3] IF RCS pressure approaches 450 psig, THEN UNSAT
[a] ENSURE a steam bubble exist in the Pressurizer or STOP Charging Pump.
[b] STOP RHR Pump(s).
[c] CLOSE the following valves:
- 1.FCV-74-8 and -9, RHR SYSTEM ISOLATION BYPASS
[d] GO TO AOI-14, LOSS OF RHR SHUTDOWN COOLING.
Simulator Operator: in asked in this step or subsequent steps:
If asked as NAUO to report lB-B RHR Pump discharge pressure on P1 74-18, use the RHR page on ICS and perort the value on the screen.
If asked as NAUO to report lB-B RHR Pump flow on FE 74-24, report that it is 0 GPM if 1-FCV-74-24 is closed, and 900 gpm if 1-FCV-74-24 is open STANDARD Performer should Observe RCS pressure and determine that it is normal and go to Corrective action step 4.
COMMENTS:
- Itaiicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 13 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 I 8a STEP 13: 11 3C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION Critical Step
[Corrective Action 4]
[4) IF RHR mini flow condition exist, THEN
[a) ENSURE mini flow valve (1-FCV-74-12 or -24 as app) OPEN.
[b] ENSURE system operation in accordance with __SAT SOI-74.O1, RESIDUAL HEAT REMOVAL SYSTEM.
Simulator ENSURE camera #3 is positioned to view 1-FCV-74-24 hand Operator: switch, and DELETE malfunction RHRO16 when performer UNSA T switches 1-HIS-74-24 to OPEN.
N/A STANDARD Performer should OPEN 1-FCV-74-24 using 1-HIS-74-24, and verify open by red indicating light, alarm 11 3C clearing and requesting flow information for 1 B-B RHR Pump (FE 74-24) from NAUO COMMENTS:
STEP 14: 11 3C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION
[Corrective Action 5 & 6]
[5] IF RHR Pump discharge pressure is high, THEN ENSURE system operation in accordance with SAT SOl-74.O1, RESIDUAL HEATREMOVAL SYSTEM.
RHR OUT OF SERVICE:
[6] IF high press exists due to check valve backleakage. THEN CYCLE test vents per SOl-63.O1 UNSAT STANDARD Performer should determine that these steps are N/A and return to S0l-74.O1 COMMENTS:
N/A
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 14 0F14 Watts Bar Nuclear Plant 3-OT-JPMR1 1 8a STEP 15: [12] WHEN Train B is < 200°F, as indicated on 1-TR-74-25, Critical Step THEN STOP RHR PMP B (ECCS) with 1-HS-74-20A..
SAT STANDARD When RHR Train B is <200°F, Train B RHR Pump is stopped using 1-HS-74-20A..
COMMENTS:
U N SAT STEP 16: [13] Notifies Unit Supervisor that B Train RHR is secured.
EXAMINER When notified, acknowledge the report, notify performer that SAT CUE: the task is complete. End task COMMENTS:
UNSAT END OF TASK TIME STOP:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being SimuIated
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues Aill Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- Unit is in Mode 5
- Unit is stable with Both Trains of RHR in service. -
- Forced oxide phase is not in progress, RCS activity is not elevated.
- CCS relief valve1-70-565B, RHR Pump lB-B Seal Water HX Outlet Relief, has developed a leak. The 1 B-B RHR Pump needs to be removed from service to allow repairs.
- Another Operator will control PZR Level and Pressure and all secondary and back panel systems.
INITIATING CUES:
The Unit Supervisor has directed you as the RO to change from 2 train RHR operation to A Train RHR operation, maintaining the current RCS temperature.
You are to notify the Unit Supervisor when that has been completed.
Rev8. PAGE 1 OF11 Watts Bar Nuclear Plant 3-OT-J PM R074 RESPOND TO A SOURCE RANGE INSTRUMENT FAILURE PER AOI-4
PAGE 2 OF11 Rev8.
Watts Bar Nuclear Plant 3-OT-J PM R074 NUCLEAR TRAINING REVISION/USAGE LOG Description of Changes Date Pages Affected Reviewed By Rev. #
0 Initial Issue. 8/26/92 All Replaces JPM #AOl-4-1 1 Delete knowledge questions 4/7/93 3 Major revision due to AOl-4 revision. 5/27/93 All 2
Reflect procedure Rev 14 11/7/95 4,6,7,8 3
09/19/97 All Albert V. White 4 Reflect procedure Rev 14 CN-2 which added a step that initiate SDM calculations, added IC #s, changed titles, added admin info, removed termination CUE 07/31/00 ALL Albert V. White
- 5. Updated procedure reference, revised K/A values to Rev 2 NUREG 1122, revised simulator setup instructions, and task assignment sheet, added step numbers in performance steps, added minor wording to performance step 11 and 12.
10/16/02 ALL Albert V. White 6 Added start/stop time blanks, added note due to procedure change. Changes do not affect task performance nor its evaluation.
08/07/07 All A. V. White 7 Updated to current revision of procedure &
current format. Revised standards slightly due to electronic recorder having replaced 1-NR-45. No change of intent made.
04/03/08 3, 4 D. L. Hughes 8 Updated to current revision of procedure &
current format. No change of intent made.
Rev8. PAGE 3 OF11 Watts Bar Nuclear Plant 3-OT-J PM R074 EVALUATION SHEET Task: Respond to a Source Range Instrument Failure Per AOI-4 Alternate Path: Audible count rate must be selected to Operable Source Range Channel.
Facility JPM #: 3-OT-JPMR0074 Rev 8 K/A Rating(s): 015A3.01 [3.8/3.8] 015A4.02 [3.9/3.9]
015A4.01 [3.6/3.6] 015A3.02 [3.7/3.9]
2.4.4 [4.0/4.3]
TASK STANDARDS:
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
AOl-4 Nuclear Instrumentation Malfunctions, Rev 28 Task Number: RO-092-AOl-4-001 APPLICABLE FOR: RO!SRO IOCFR55.45: 3,4, 6, 12 Validation Time: 10 mm. Time Critical: No Candidate: Time Start:
NAME. SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time
/
Examiner:
NAME SIGNATURE DATE COMMENTS
Rev8. PAGE 4 OF11 Watts Bar Nuclear Plant 3-OT-J PM R074 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to IC # 256 and ENSURE Audio Count Rate Switch is in N-32 position.
- 2. Acknowledge all alarms.
- 3. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
- 4. NOTE: This JPM has been preshot in 1C #256. The following are the setup instructions if needed:
ENSURE Audio Count Rate Switch is in N-32 position.
Initialize to IC-35 (Mode 3, ready for startup). -
BLOCK HI FLUX AT SHUTDOWN alarms at NIS Panel and ensure Annunciator Window 81 B reset.
ENSURE that S2 isselected on 1-NR-145.
Insert imf niOlb © 0% (N-132 failed low).
Insert imf niOla 21 (NI-131 set at a value).
Insert imf niO4a 3e -8 (NI-133 set at a value).
Insert imf niO4b 5e-8 (NI-i 34 set at a value).
Acknowledge all alarms.
Place the Simulator in FREEZE.
After the performer indicates an understanding of the task, place the simulator in RUN.
- 5. After performer indicates understanding of task, place simulator in run.
SIMULATOR OPERATOR INSTRUCTIONS:
Rev8. PAGE 5 OF11 Watts Bar Nuclear Plant 3-OT-J PM R074 EVALUATOR IN FORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure clean copy of AOl-4 Nuclear Instrumentation Malfunctions in the books on the Simulator Floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operat cues.
AWl Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The Unit is in Mode 3 with 6 cps on Source Range Instruments.
A Unit Startup was in progress, when N132 failed low.
All positive reactivity insertion has been stopped.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor has directed you to perform the appropriate procedure concerning the loss of a Source Range Instrument.
You are to notify the Unit Supervisor when ready to begin repairs.
3-OT-J PM R074 PAGE 6 OF11 START TIME:
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD: A copy of AD 1-4 has been obtained. SAT COMMENTS:
UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
NOTE: This step was noted as satisfied in the initial conditions STEP 2: [1] Stop positive reactivity changes or core alterations.
STANDARD: Performer determines NO action required and continues SAT with instruction.
COMMENTS:
UNSAT STEP 3: [2] IF both SRMs required and failed, THEN OPEN Rx trip breakers. SAT STANDARD: As determined by simulator indications and the initial conditions only one source range has failed thus no action is required.
COMMENTS:
UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
3-OT-JPMRO74 PAGE 7 OF11 STEP 4: [3] INITIATE performance of 1-SI-O-1O, Shutdown Margin.
STANDARD: Unit Supervisor or STA is contacted to perform 1-51-0-10, Shutdown Margin. _SAT Examiner Respond as Unit Supervisor or STA and state that 1-SI-CUE: 0-10 will be performed COMMENTS: UNSAT STEP 5: [4] IF SOURCE RANGE HI FLUX AT SHUTDOWN alarm occurs [81-B], THEN:
- a. CHECK alarm valid. SAT
- b. ENSURE Cntmt is evacuated.
- c. CHECK Rx power STABLE.
STANDARD: Performer determines that NO alarm has occurred, thus no action is required. U N SAT COMMENTS:
NOTE: Placing the affected channel in bypass will cause either window 64A or 65A to alarm.
STEP 6: [5] Place failed channel LEVEL TRIP switch to Bypass [1- CRITICAL M-13]. STEP STANDARD: The Level Trip Switch for N-132 has been located and placed in the Bypass position.
Step is critical because if done incorrectly, the operable SAT source range instrument will be bypassed, rendering both channels inoperable.
COMMENTS:
UN SAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
3-OT-JPMRO74 PAGE 8 OF11 STEP 7: [6] Place failed channel HIGH FLUX AT SHUTDOWN switch to Block [i-M-13].
STANDARD: The High Flux at Shutdown switch for N-i 32 is verified in the Block position.
SAT COMMENTS:
U N SAT STEP 8: [7] ENSURE i-NR-145 recording an operable source CRITICAL range channel [i-M-4]. STEP STANDARD: Recorder i-NR-145 is selected to display/record Si.
Step is critical to ensure operable source range SAT instrument will be recorded and displayed, enabling reactivity monitoring of the reactor.
COMMENTS:
UNSAT STEP 9: [8] IF in Mode 3, 4, or 5, THEN:
. CHECK audio count rate audible in control room.
STANDARD: Performer determines NO audible Audio count rate is being SAT received & proceeds to RNO.
COMMENTS:
UNSAT
- italicized Cues Are To Be Used Only if JPM Performance is Being Simulated.
3-OT-J PM R074 PAGE 9 OF11 STEP 10: [8 RNO} PLACE audio count rate channel CHANNEL CRITICAL SELECTOR switch to operable channel [1-M-13j. STEP STANDARD: Audio count rate channel selector switch is located and placed in the N-131 position and started. SAT Step is critical because unless the switch is properly positioned no audible indication of SR counts occurs.
COMMENTS:
U N SAT STEP 11: [8] IF in Mode 3,4, or5, THEN:
- REFER TO Tech Spec 3.3.1, Rx Trip System Instrumentation.
- REFER TO Tech Spec 3.3.3, PAM Instruments. SAT
- REFER TO Tech Spec 3.3.4, Remote Shutdown System.
STANDARD: The Unit Supervisor is notified to check Tech Spec or performer checks Tech Spec. UNSAT EXAMINER When Unit Supervisor notified, acknowledge the report.
CUE: If the performer opens Tech Specs, state that the Unit Supervisor will do the research.)
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
3-OT-J PMRO74 PAGE 10 OF11 STEP 12: [9] If in Mode 6, then:
- CHECK audio count rate audible in control room.
- CHECK audio count rate audible in Cntmt.
- REFER TO Tech Spec 3.9.3, Nuclear Instrumentation. __SAT STANDARD Performer determines NO action is required. Unit is in Mode 3 as stated in the initial conditions.
COMMENTS: UNSAT STEP 13: [10] Notify Operations Duty Manager and Rx Engineering of failed channel.
STANDARD: Performer notifies the Operations Duty Manager and SAT Reactor Engineering of the N132 failed channel.
EXAMINER When each is notified, acknowledge the report CUE:
UNSAT COMMENTS:
STEP 14: [11] INITIATE repairofSRM.
STANDARD: The performer initiates repair by notifying work control or requests that the Unit Supervisor initiate repair.
SAT EXAMINER When notified, acknowledge the report, notify CUE: performer that the task is complete. End task COMMENTS:
UNSAT END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operat cues.
AllI Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The Unit is in Mode 3 with 6 cps on Source Range Instruments.
A Unit Startup was in progress, when N132 failed low.
All positive reactivity insertion has been stopped.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor has directed you to perform the appropriate procedure concerning the loss of a Source Range Instrument.
You are to notify the Unit Supervisor when ready to begin repairs.
REV.O PAGE 1 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Restore Normal Charging and Letdown Per SOl-62.O1
REV.O PAGE 2 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla REVISION LOG REVISION DATE DESCRIPTION OF CHANGES PAGES REVIEWED LOG AFFECTED BY 0 03/9/08 fntiaI issue for NRC Exam ALL D.L.Hughes
REV.O PAGE 3 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Task: Restore Charging and Letdown Per SOl-62.01 Alternate Path: 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, will malfunction and will not maintain temperature less than 127°F, after being placed in Auto, requiring operator action to take the controller to manual and control letdown temperature.
Facility JPM #: 3-OT-JPMR lOla RevO K/A Rating(s): A 4.05 Letdown pressure and temperature control valves(lmportance RO/SRO 3.6/ 3.1 TASK STANDARDS: Charging and Letdown in service with letdown temperature being controlled manually Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
S0I-62.01 Rev 0056 CVCS-Charging and Letdown Task Number: RO-062-SOl-62-006 APPLICABLE FOR: RO!SRO IOCFR55.45: 1,2,5 Validation Time: 20 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS.
REV.0 PAGE 4 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla SIMULATOR OPERATOR INSTRUCTIONS:
Initialize to preshot in IC # 255 or perform the following:
F.
- 1. Reset to any Mode 1 (recommend lC-40, 50, or 60) with PCS temperature >525°
- 2. All POPs running.
- 3. Using SQl 62.01, remove Charging and Letdown per section 8.1 and place Excess Letdown in service per section 8.3.
delay of
- 4. iorzaihic6278A (el 10) 0.01 15 (insert overide for 1-HIC-62-78 to fail to 1% with a 10 seconds and ramped over 15 seconds from event trigger entry)
- 5. Allow PZR Level to stabilize and freeze the simulator.
- 6. Have a working copy of SQl 62.01 for examiner to provide.
After performer indicates understanding of task, place simulator in run.
Trigger I to fail the When performer places 1-HIC-62-78A in Auto, (step 22 of JPM) insert automatic temperature control.
REV.O PAGE 5 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Tools/Equipment/Procedures Needed:
ENSURE clean copies of SOl-62.O1 are in all the books on the simulator floor.
READ TO OPERATOR DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Excess letdown was placed in service 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to an air line fitting vibrating loose on 1-PCV 81. The air leak was just repaired and 1-PCV-62-81 has been tested.
Another Operator is being briefed to remove Excess Letdown from service when you have completed yor task.
INITIATING CUES:
The Control Room Supervisor has directed you to restore normal charging with the 1A CCP running, and 75 gpm Letdown Orifice B by performing Section 8.2 of SQl 62.01 CVCS- Charging and Letdown.
(Consider the plant operating in Cycle 9)
Notify US when the procedure is complete.
REV. 0 PAGE 6 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla START TIME:
STEP 1: Obtain a copy of the procedure.
STANDARD: A copy of SOl-62.01 has been obtained COMMENTS:
SAT U N SAT EXAMINERS After the performer has demonstrated the method of obtaining CUE: the correct instruction, the evaluator can provide a copy of the instruction.
STEP 2: [8.2.1]
[1] ENSURE all letdown orifices CLOSED:
PERF NOMENCLATURE LOCATION LJNID INITIAL LETDOWN ORIFICE A 45 3PM 1-M-6 1-HS-62-72A SAT (CIV-?Al LETDOWN ORIFICE B 75 GPM 1-M-6 1-HS-62-73A (CIV-%A)
LETDOWN ORIFICE C 75 GPM 1-M-G 1-HS-62-74A kCIV-A UNSAT LETDOWN ORIFICE 5 GPM 1-M-6 1HS-62-76 (CIV-2A)
STANDARD:
All letdown orifices CLOSED:
COMMENTS:
STEP 3: [2) CLOSE 1-HIC-62-89A, CHARGING HEADER RCP SEALS FLOW CONTROL.
SAT STANDARD: 1-FCV-62-89 is closed U N SAT COMMENTS:
REV. 0 PAGE 7 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 4: [3] IF NO Charging Pump is IN SERVICE, THEN PERFORM the following:
SAT Step is N/A, since A CCP is operating UN SAT STANDARD:
COMMENTS:
STEP 5: [4] ADJUST 1-HIC-62-93A, CHARGING FLOW PZR LEVEL CONTROL, to between 8 and 13 gpm per RCP.
SAT STANDARD: Seal flow is between 8 - 13 gpm per RCP U N SAT COMMENTS:
STEP 6: [5] ENSURE 1-HS-62-84A, AUX SPRAY TO PZR [1-M-6],
CLOSED.
SAT STANDARD:
1-FCV-62-84 is closed UNSAT COMMENTS:
REV. 0 PAGE 8 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 7: [6] PLACE 1-HS-62-79A, LTDN HI TEMP DIVERT, in VCT.
SAT STANDARD: 1-HS-62-79A, LTDN HI TEMP DIVERT,is in VCT U N SAT SIMULATOR OPERATOR COMMENTS:
STEP 8: 7) ENSURE the following: CRITICAL PERF STEP NOMENCLATURE LOCATION POSITION UNID INITIAL RCS LETDOWN ERM 1.M.6 OPEN 1-HS.62-69A LOOP 3 IN CNTMT 1-HS-62-70A SAT RCS LETDOWN FRM 1-M-G OPEN LOOP 3 IN CNTMT LP LETDOWN ISOL ClV-A 1.M-6 OPEN 1.HS.62-77A STANDARD: UNSAT 1-FCV-92-69, 1-FCV-92-70, 1-FCV-92-77 are OPEN, COMMENTS:
STEP 9: [8J ENSURE 1-HIC-62-78A, LETDOWN HX OUTLET TEMP CRITICAL TCV-70-192 CNTL, in MANUAL and set between 20 and 25% STEP OPEN.
SAT STANDARD: TCV-70-192 CNTL, is in MANUAL nd set between 20 and 25%
OPEN.
UNSAT COMMENTS:
REV.0 PAGE 9 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 10: [9] ENSURE CCS in service to LDHX (1-Fl-70-190)
[0-M-27B]. SAT UNSAT STANDARD: CCS is verified to be in service to LDHX on 1-FI-70-190.
COMMENTS:
STEP 11: [10] ENSURE 1-HIC--62-81A, LETDOWN PRESS CONTROL, in CRITICAL MANUAL and set between 40 and 50% OPEN if using 75 STEP gpm orifice (20-30% OPEN if using 45 gpm orifice).
LETDOWN PRESS CONTROLLER, is in MANUAL and set SAT STANDARD: between 40 and 50% OPEN U N SAT COMMENTS:
REV. 0 PAGE 10 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 12: CRITICAL
[11] ENSURE the following: STEP SAT 1-FCV-62-90 and 1FCV-62-91 are OPEN STANDARD:
UNSAT COMMENTS:
STEP 13: [12] OPEN one chargng valve (N/A valve NOT opened):
LOCATION UNID PERF VERIFIER CRITICAL NOMENCLATURE INITIAL INITIAL STEP NORM CHARGING TO 1-M-6 1-FCV-62-85A LOOP 1 IV ALT CHARGING TO 1-M-6 1-FCV-62-86A LOOP 4 IV SAT STANDARD:
Performer refers to Initial Conditions and determines that 1-FCV 85 is used during odd fuel cycles (cycle 9), therefore 1-FCV-62-85 is opened V UNSAT COMMENTS:
REV.O PAGE 11 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 14: [13] ADJUST 1-HIC-62-89A, CHARGING HEADER RCP SEALS CRITICAL FLOW CONTROL, and 1-HIC-62-93A, CHARGING FLOW STEP PZR LEVEL CONTROL, to establish charging flow greater than 55 gpm (to ensure cooling to Regen Hx), and MAINTAIN between 8 and 13 gpm RCP Seal flow. SAT Performer establishes Charging greater than 55 gpm with Seal STANDARD: injection flow 8 13 gpm per RCP and abides by Caution and Note: UNSAT CAUTIONS
- 1) 1-HIC-62.89A, CHARGING HEADER RCP SEALS FLOW CONTROL, must be opened slowly to avoid thermal shock to Regenerative HX.
- 2) When operating at a minimum charging flow rate, letdown flow must be cooled below 380F. If NOT, charging and letdown flow should be raised by opening an -
additional letdown orifice flow path.
NOTE COMMENTS: Letdown flow should be established promptly after Charging flow is established via 1 -FCV-62.89.
STEP 15: [14] MONITOR 1-TI-62-71, REGEN HX OUT LTDN TEMP, to maintain letdown temperature less than 380°F. SAT STANDARD: Performer monitors Letdown temperature now and in subsecuent UNSAT steps.
COMMENTS:
STEP 16: [15] OPEN 1-HS-62-76A, LETDOWN ORIFICE (5 GPM).
SAT STANDARD: Performer OPENs 1 -HS-62-76A, monitors Letdown flow and temperature.
UNSAT COMMENTS:
REV. 0 PAGE 12 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 17: [16] IF Letdown was isolated for more than 8 hrs AND RCS is 350°F or more, THEN SAT Evaluator Cue: If the performer ask how long it has been since letdown has been isolated, inform them that it has been 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 UNSAT minutes STANDARD: Performer determines that there is no need to hold in this configuration COMMENTS:
[17] WHEN letdown pressure and temperature stabilize, THEN CRITICAL STEP 18:
OPEN 1-HS-62-72A, CVCS LETDOWN ORIFICE A STEP ISOLATION(45 GPM, CIV-ØA), OR IF 75 gpm letdown is desired, THEN SAT PERFORM the following:
[17.1] OPEN one of the following (N/A orifice NOT selectec U N SAT
[17.2] ENSURE 1-HS-62-72A, LETDOWN ORIFICE A ISOLATION (45 GPM), is CLOSED.
STANDARD: Performer allows letdown pressure and temperature to stabilize, and then OPENS Letdown Orfice B, using 1 -HS-62-73A.
Performer also verifies 1-HS-62-72A, Letdown Orfice A Isolation, CLOSED COMMENTS:
REV.0 PAGE 13 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 19: [18] CLOSE 1-HS-62-76A, LETDOWN ORIFICE 5 GPM CIV-OA.
SAT STANDARD: 1-FCV-62-76 IS CLOSED UNSAT COMMENTS:
STEP 20: [19] ADJUST 1-HIC-62-81A, LETDOWN PRESS CONTROL, to CRITICAL maintain between 320 and 350 psig, AND PLACE in AUTO. - STEP 1-HIC-62-81A, LETDOWN PRESS CONTROL, is in AUTO and STANDARD: controlling between 320 and 350 psig. SAT U N SAT COMMENTS:
STEP 21: [20] ADJUST 1-HIC-62-78A, LETDOWN HX OUTLET TEMP CRITICAL TCV-70-192 CNTL, to maintain less than 127°F, AND STEP MAINTAIN 1-TCV-70-192 less than full open.
STANDARD: LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, is less than SAT full open and Letdown Temperature is less than 127L1F COMMENTS:
UN SAT
REV.O PAGE 14 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 22: [21] PLACE 1-HIC-62-78A in AUTO.
SAT Simulator When performer places 1-HIC-62-78A in Auto, insert Trigger Operator CUE I to fail the automatic control _UNSAT STANDARD: Rerformer places 1-HIC-62-78A in Auto, and monitors Letdown Temperature on 1-TI-62-78 [1M-6],
COMMENTS:
STEP 23: [22] PLACE 1-HS-62-79A, LETDOWN HI TEMP DIVERT, to DEMIN, then to P-AUTO. SAT STANDARD: 1-HS-62-79A, is in P-AUTO. UNSAT COMMENTS:
REV.O PAGE 15 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 24: The following steps are associated with alarm response AR! CRITICAL I 1OD LTDN TO DEMINS TEMP H! STEP However if performer realizes the temperature control problem and takes prudent action to take manual control of SAT 1-HIC-62-78A and controls letdown temperature to less than 127°F, that would also be acceptable.
U N SAT STANDARD: Performer should observe letdown temperature on 1-Tl-62-78
[1-M-6J, not being controlled, and take manual control of Letdown temperature to less than 127°F.
COMMENTS: -
STEP 25: ARI hOD Step I CRITICAL STEP IF letdown temperature is greater than 137.5 F on 1-TI-62-78 [1-M-6], THEN ENSURE CVCS demineralizers bypassed (lights above 1-HS-62-79 [1-M-6J).
SAT STANDARD:
1-HS-62-79A, is in Divert, if letdown temperature got greater than V
137.5°F UNSAT COMMENTS:
REV.O PAGE 16 0F18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 26: ARI hOD Step 2 ENSURE letdown flow is 45 gpm to 120 gpm on 1.-Fl-62-82 [1-M-6]. SAT STANDARD:
Letdown Flow is 75 gpm UNSAT COMMENTS:
STEP 27: ARI hOD Step 3 ENSURE charging flow is 57 gpm to 132 gpm on 1-FI-62-93A [1-M-5]. SAT Charging Flow is 57 gpm to 132 gpm STANDARD:
U N SAT COMMENTS:
REV. 0 PAGE 17 OF 18 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 28: ARI hOD Step 4 CRITICAL STEP ADJUST 1-HIC-62-78A to maintain letdown temperature less than 1270 F on 1-TI-62-78. SAT STANDARD: 1-HIC-62-78A is placed in Manual and Letdown temperature controlled to less than 127°F UNSAT COMMENTS:
STEP 29: Performer informs SRO that Charging and Letdown are in service with 1-HIC-62-78A is placed in Manual controlling Letdown _SAT temperature UNSAT Evaluator Cue Acknowledge report, notifly performer that the task is complete. End task In form performer that another operator will take the task from this point.
COMMENTS:
End of Task TIME STOP:
Rev. 0 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Excess letdown was placed in service 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to an air line fitting vibrating loose on 1-PC V 81. The air leak was just repaired and 1-PCV-62-81 has been tested.
Another Operator is being briefed to remove Excess Letdown from service when you have completed yor task.
INITIATING CUES:
The Control Room Supervisor has directed you to restore normal charging with the 1A CCP running, and 75 gpm Letdown Orifice B by performing Section 8.2 of SQl 62.01 CVCS- Charging and Letdown.
(Consider the plant operating in Cycle 9)
Notify US when the procedure is complete.
RevO. PAGE 1 0F16 Watts Bar Nuclear Plant 3-OT-JPMR173 START UP UPPER CONTAINMENT PURGE PER SOI-30.02
RevO. PAGE 2 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial Issue. All D.L.Hughes
RevO. PAGE 3 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 EVALUATION SHEET Task: START UP UPPER CONTAINMENT PURGE PER SOI-30.02 Alternate Path: N/A Facility JPM #: 3-OT-JPMR173 RevO K/A Rating(s):
- 029A2.03 Startup operations and the associated required valve lineups. [Importance:
RO/SRO 2.7/3.1]
- 029A4.01 Containment purge flow rate [Importance: RO/SRO 2.5 / 2.5]
- 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. [Importance: RO!SRO 4.6 /4.1]
TASK STANDARDS: Lower Containment Purge is in service -
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOI-30.02 Containment Purge System Rev 0051.
Task Number: RO-030-SOI-30-007 APPLICABLE FOR: RO/SRO IOCFR55.45: 1,3, & 7 Validation Time: 20 mm. Time Critical: No Time Start:
Candidate:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time
/
Examiner:
NAME SIGNATURE DATE COMMENTS
RevO. PAGE 4 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to any Mode 1 IC that does not have Containment Purge in service.
- 2. Acknowledge all alarms.
- 3. After performer indicates understanding of task, place simulator in run.
- 4. There are no malfunctions, overrides, or booth communications needed for the administration of this JPM
PAGE 5 0F16 RevO.
Watts Bar Nuclear Plant 3-OT-JPMR1 73 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Simulator Ensure clean copy of SOl-30.02 Containment Purge System in the books on the Floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
provide initiating/operat I will explain the initial conditions, which step(s) to simulate or discuss, and cues. -
d Alli Control Room steps shall be performed for this task, including any require communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The Unit is in Mode 1.
You are the BOP.
INITIATING CUES:
nment The Unit Supervisor has directed you to place B train Upper Contai Purge in service, utilizing 1-FCV-30-9 & 53 and 1-FCV-30-1O & 52.
You are to notify the Unit Supervisor when your task is complete.
RevO. PAGE 6 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 START TIME:
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD: A copy of SO 1-30.02 has been obtained. SAT COMMENTS:
UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can -
pro vide a copy of the instruction.
[1] ENSURE Section 4.0, Prerequisite Actions, STEP 2 COMPLETE.
SAT EXAMINERS Inform performer that Section 4.0, Prerequisite Actions CUE: are complete.
STANDARD: Performer determines Section 4.0, Prerequisite Actions, COMPLETE UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
PAGE 7 0F16 RevO.
Watts Bar Nuclear Plant 3-OT-JPMRI 73 STEP 3: [2] PERFORM the following prior to moving irradiated fuel with containment open to ABSCE spaces: (N/A if SAT in Modes 1-4 or if in Modes 5 & 6 with containment isolated)
STANDARD: Performer determines that the step is N/A.
UNSAT COMMENTS:
STEP 4: [3] OBTAIN SRO approval.
STANDARD: Performer determines that Unit Supervisors permission
_SAT was given in the initial conditions.
COMMENTS:
U N SAT STEP 5: [4] OBTAIN Release Permit from Chemistry Countroom.
EXAMINERS Inform performer that Unit Supervisor has obtained SAT CUE: Release Permit from Chemistry Countroom.
STAN DARD: Performer determines that Release Permit from Chemistry Countroom is obtained.
UN SAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
PAGE 8 0F16 RevO.
Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 6: [5] ENSURE appropriate heating/cooling water to Containment Purge Supply per SOi-44.01/SOl-31 .03 (N/A if NOT desired).
SAT EXAMINERS Inform performer that heating/cooling water to CUE: Containment Purge Supply is not desired.
UN SAT STANDARD: Step is N!Aed COMMENTS:
[6] ENSURE Section 5.10 of S0I-90.02, Gaseous STEP 7*
Process Radiation Monitors, has been completed for specific train(s) of containment purge to be placed in service. SAT EXAMINERS If asked, inform performer that Section 5.10 of SOl CUE: 90.02, Gaseous Process Radiation Monitors, has been completed for B train of upper containment purge to be placed in service. UNSAT STANDARD: Perform initials step as complete.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 9 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 8: [7] INDICATE which Train(s) will be used
- Train A Containment Purge Train B Containment Purge SAT
- Both Trains A and B Containment Purge STANDARD: Performer reviews initiating cues, and selects train B.
UNSAT COMMENTS:
STEP 9: [8] IF Wafer Vlv, 1-ISV-78-600, OPEN in Mode 6 WITH SFP & Rx Cavity Full, THEN...
STANDARD: Performer N/As step since plant is in Mode 1 SAT COMMENTS:
UNSAT
[9] IF aligning for 2-Train operation, THEN CHECK A STEP 1O*
Train ABGTS is NOT running.
SAT STANDARD: Performer N/As step since plant is only 1 train operation is desired.
COMMENTS:
UN SAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
PAGE 10 OF 16 Rev 0.
Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 11: [10] CLOSE Containment vent filter flowpath: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID LWR CNTMT PURGE EXH 1-M-9 CLOSED 1-HS-30-37 PRESS RLF LWR CNTMT PURGE EXH 1-M-9 CLOSED 1-HS-30-40 PRESS RLF STANDARD: Performer closes: SAT
- 1-HS-30-37
- 1-HS-30-40 UNSAT COMMENTS:
OPEN Selected Supply Fan(s) Disch damper (N/A if NOT CRITICAL STEP 12: [11]
selected): STEP NOMENCLATURE LOCATION POSITION UNID PURGE SUP FAN 1A DISCH 1-M-9 OPEN 1-HS-30-2 PURGE SUP FAN lB DISCH 1-M-9 OPEN 1-HS-30-5 SAT STANDARD: Performer only OPENS:
1-HS-30-5 UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 11 0F16 Watts Bar Nuclear Plant 3-OT-JPMRI 73 STEP 13: [12.1] IF Train A will be run, THEN CRITICAL STEP PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN 1ATO 1-M-9 OPEN 1-HS-30-213 SHIELD BLDG VNT PURGE EXH FAN 1BTO 1-M-9 CLOSED 1-HS-30-216 SHIELD BLDG VNT SAT
[12.2] IF Train B will be run, THEN PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN 1ATO 1-M-9 CLOSED 1-HS-30-213 UNSAT SHIELD BLDG VNT PURGE EXH FAN 1BTO 1-M-9 OPEN 1-HS-30-216 SHIELD BLDG VNT
[12.3] IF Both Train A and B will be run, THEN PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN 1ATO 1-M-9 OPEN 1-HS-30-213 SHIELD BLDG VNT PURGE EXH FAN 1BTO 1-M-9 OPEN 1-HS-30-216 SHIELD BLDG VNT STANDARD: The Performer (NA steps [12.1] &[12.3]) AND VERIFY CLOSED 1-HS-30-213
. OPENS 1 -HS-30-21 6 COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 12 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 14: [13] OPEN the FCVs in 5.1[13.1] & 5.1[13.2], or 5.1[13.3] & CRITICAL 5.1 [13.4] [1-M-9] (NIA set NOT used>: STEP
[13.1] UPR CNTMT PURGE 1-FCV-30-7 & 51 with 1-HS.-30-7.
[13.2] UPR CNTMT PURGE 1-FCV-30-8 & 50 with 1-HS-30-8.
[13.3] UPR CNTMT PURGE 1-FCV-30-9 & 53 with 1-HS-30-9.
[13.4] UPR CNTMT PURGE 1-FCV-30-10 & 52 with 1 -HS-30-1 0.
STAN DARD Performer reviews JPM initiating que and ONLY OPENS: U N SAT
- FCV-30-9 & 53 with 1-HS-30-9
- 1-FCV-30-1O & 52 with 1-HS-30-1O COMMENTS:
STEP 15: [14] START Selected Purge Sup & Exh Fan(s) (N/A if NOT CRITICAL selected): STEP NOMENCLATURE LOCATION POSITION UNID CNTMT PURGE SUP & EXH 1-M-9 START 1-HS-30-1A FANS 1AAND FCO-30-1A& lB CNTMT PURGE SUP & EXH 1-M-9 START l-HS-30-4A FANS lB AND FCO-30-4A & 4B SAT STANDARD: Performer ONLY starts lB Fans and dampers with 1 -HS-30-4A.
COMMENTS: U N SAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 13 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 16: [15] PERFORM the following (N/A if NOT selected): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN A SUCT 1-M-9 OPEN 1-HS-30-61 PURGE EXH FAN B SUCT 1-M-9 OPEN 1-HS-30-62 STANDARD: The performer ONLY OPENS 1-HS-30-62.
SAT COMMENTS:
UN SAT
[16] ENSURE the following (N/A Train NOT used): CRITICAL STEP 17:
STEP NOMENCLATURE LOCATION POSITION UNID PURGE SUP SUCT ISOL 1-M-9 OPEN FCO-30-294 DAMPER 1-Xl-30-294 PURGE SUP SUCT SQL 1-M-9 OPEN FCO-30-295 DAMPER 1-XI-30-295 Train A DAMPER 1-XI-30-1A 1-M-9 OPEN FCO-30-1A SAT DAMPER 1-XI-30-1B 1-M-9 OPEN FCO-30-1B Train B 1-M-9 OPEN FCO-30-4A DAMPER 1-Xl-30-4A U N SAT 1-M-9 OPEN FCO-30-48 DAMPER 1-Xl-30-4B STANDARD: The performer ENSURES OPEN:
- FCO-30-294
- FCO-30-295
- FCO-30-4A
- FCO-30-4B COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 14 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73
[17] CHECK flow on 1-Fl-90-400, SHIELD BLDG VT STEP 18 FLOW [1-M-9] (N/A if Fl NOT available).
STANDARD: The performer verifies flow on 1-FI-90-400, SHIELD BLDG SAT VT FLOW.
COMMENTS:
UN SAT
[18] IF FI-90-400 is NOT available, THEN ENSURE Flow STEP 19 being estimated per 1-SI-O-2, Shift & Daily Log.
STAN DARD: The performer N/As this step.
SAT COMMENTS:
U N SAT
[19] NOTIFY the Chemistry Countroom of the purge start STEP 2O date and time.
STANDARD: The performer informs Chemistry Countroom of the purge SAT start date and time.
EXAMINER When notified, acknowledge the report.
CUE:
COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 15 0F16 Watts Bar Nuclear Plant 3-OT-JPMRI 73
[20] IF containment pressure approaches or exceeds STEP 21*
Tech Spec value (+0.27 psid in Modes 1-4), THEN PERFORM Section 7.1, SHUT DOWN Upper Containment Purge.
SAT STANDARD: The performer monitors Containment pressure on 1-PDI 133 and verifies it is less than Tech Spec value.
Performer notifies Unit Supervisor that B train Upper __UNSAT Containment Purge in service EXAMINER When notified, acknowledge the report, notify CUE: performer that the task is complete. End task COMMENTS:
END OF TASK TIME STOP:
- ita!icized Cues Are To Be Used Only if JPM Performance is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/opera cues.
AIll Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The Unit is in Mode 1.
You are the BOP.
INITIATING CUES:
The Unit Supervisor has directed you to place B train Upper Containment Purge in service, utilizing 1-FCV-30-9 & 53 and 1-FCV-30-1O & 52.
You are to notify the Unit Supervisor when your task is complete.