ML022380387
| ML022380387 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/29/2002 |
| From: | Pisano L Constellation Nuclear |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| References | |
| 05000410/02-301 05000410/02-301 | |
| Download: ML022380387 (62) | |
Text
Facility:
Nine Mile Point #2 Facility:
Nine Mile Point # 2 Exam Level (circle one): RO & SRO B. I Control Room Systems Date of Examination:
7/29/2002 Operating Test No.: RO 1,2/SRO-I All System / JPM Title JPM 1 Recirc Flow Control/ Transfer Operating RCS HPU Subloops KA 202002 A4.02 2.8/2.8; Task 202-907-01-0 1; N2-OP-29 F.2.0 JPM 2 Feedwater Level Control/ Resetting Feedwater Level Setdown KA 259002 A4.10 3.1/2.9; Task 259-903-01-0 1; N2-OP-3 H.2.0 JPM 3 High Pressure Core Spray/ Add Water To Suppression Pool With CSH Pump (Alternate Path) CSH Pump Trip Continue Filling By Gravity Drain KA 209002 A4.09 3.4/3.5;Tasks 206-907-01-01,206-906-01-01; N2-OP-33 JPM 4 Reactor Water Cleanup & PCIS/ Return Reactor Water Cleanup To Normal Following Reduction Of Feedwater Stratification Operation (Alternate Path, WCS Leak Requires Manual Isolation)
KA 223002 A2.03 3.0/3.3; Task 204-911-01-01; N2-OP-37 F.7.0, N2 SOP-83 JPM 5 Reactor Protection System/ Perform RPS Weekly Manual Scram Surveillance Test For "C" And "B" Channels KA 212000 A4.02 3.6/3.7; Task 212-002-01-01; N2-OSP-RPS-W002 JPM 6 RCIC/ RCIC Injection With Oscillations Alternate Path, Requires Manual Speed/Flow Control (02-OPS-SJE-217-2-05)
KA 217000 A4.01 3.7/3.7; Task 217-915-01-01: N2-OP-q35 Type Code*
Safety Function S/N S/N/L 1
2
-I I. ____________
S/N/A S/N/L/A S/N S/D/A 3
2 I
7 4
JPM 7 AC Distribution/ Energize NNS-SWG-015 from ENS*SWG 103 During Station Blackout Recovery (PRA)
S/N 6
KA 262001 A2.07 3.0/3.2; Task 262-935-05-01; N2-SOP-3 Section D.10.0 B.2 Facility Walk-Through JPM 8 AC Distribution RPS/ Reset EPA Breaker 2VBS*ACB2AWith N/A 6
Overvoltage Condition Present (Alternate Path)
KA 262001 A2.06 2.7/2.9; Task 212-901-01-04; N2-SOP-97 Section 4.2.3 Condition One JPM 9 Control Rod Drive/Vent Scram Air Header in the Reactor D/R Building (02-OPS-PJE-200-2-04)
KA 201001 A2.09 3.2/3.1; Task 200-960-05-04; N2-EOP-6 Att 14 Step 3.2.2 JPM 10 Spent Fuel Pool Cooling/Lineup Service Water To Spent Fuel N/R 9
Pool Cooling Heat Exchanger With Control Room Evacuated KA 233000 A2.08 2.9/3.1; Task 233-923-04-01; N2-SOP-38 Section 4.5 I
'ype Codes: kli)rect from oank, kVI)oaified Irom bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA I
I I
Facility:
Nine Mile Point # 2 Date of Examination:
7/29/2002 Exam Level (circle one): SRO Operating Test No.:
SRO Upgrade 1, 2 & 3 B. 1 Control Room Systems System / JPM Title Type Code*
Safety Function JPM 1 Recirc Flow Control! Transfer Operating RCS HPU Subloops S/N 1
KA 202002 A4.02 2.8/2.8; Task 202-907-01-01; N2-OP-29 F.2.0 JPM 2 Feedwater Level Control/ Resetting Feedwater Level Setdown S/N/L 2
KA 259002 A4.10 3.1/2.9; Task 259-903-01-01; N2-OP-3 H.2.0 JPM 3 High Pressure Core Spray/ Add Water To Suppression Pool With CSH Pump (Alternate Path) CSH Pump Trip Continue Filling By Gravity Drain S/N/A 3
KA 209002 A4.09 3.4/3.5; Tasks 206-907-01-01, 206-906-01-01; N2-OP 33 B.2 Facility Walk-Through JPM 8 AC Distribution RPS/ Reset EPA Breaker 2VBS*ACB2AWith M/A 6
Overvoltage Condition Present (Alternate Path)
KA 262001 A2.06 2.7/2.9; Task 212-901-01-04; N2-SOP-97 Section 4.2.3 Condition One JPM 10 Spent Fuel Pool Cooling/ Lineup Service Water To Spent Fuel N/R 9
Pool Cooling Heat Exchanger With Control Room Evacuated KA 233000 A2.08 2.9/3.1; Task 233-923-04-01; N2-SOP-38 Section 4.5 SType Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE Fitle:
Task Number:
Approvals:
Recirculation Flow Control, Transfer Operating RCS HPU Subloops Revision: 0 202-907-01-01-2 Startup the Hydraulic Power Unit from the Control Room and Transfer to Alternate Sub-Loop GnrlSuperv'isor Date Operations Training (Designee)
Configuration Control Dae Operations (Designee)
Date
/ 1/S/
Performer:
.(RO/SRO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
Plant X
Simulator Expected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task:
No Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
Date:
NRC EXAM JPM # 1 I
APRIL 2002
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC 13 Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2.
During Evaluated JPM:
Self verification shall be demonstrated.
- 3.
During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OP-29, Rev 08, Sect. F 2.0
- 2. NUREG K/A 202002 A4.02 Tools and Equipment:
- 1. None Task Standard:
Hydraulic Power Unit "A" has been transferred such that Subloop 1 is in "LEAD" operation.
NRC EXAM JPM # 1 2
APRIL 2002
Initial Conditions:
- 1. The Plant is operating at 25% power.
- 2.
Routine equipment rotations are taking place at this time.
Initiating Cues:
"(Operator's name), transfer HPU "A" operational Subloop from Subloop 2 to Subloop 1 per N2-OP-29, Section F.2.0. Because this is being done for routine equipment rotation GETARS trending is NOT required for this evolution."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O l/Operations Manual)
RECORD START TIME
- 2.
Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Verify operational status of Subloop 2 HPU.
- 4. Verify Subloop 1 HPU readiness for operation.
- 5. Start Subloop I HPU's Pump/Fan Motor.
CUE:
If asked, function as the AO and report local gauge pressure reading of approximately 1900 psig for Subloop 1.
If asked, function as the AO and report local gauge pressure for the standby subloop is reading is reading "0psig N2-OP-29 obtained.
Precautions & limitations reviewed & section F.2.0 referenced.
At P634, verify Subloop 2 HPU operational AND controlling Flow Control Valve.
Verify or if necessary, momentarily depress Subloop 1 ""READY" pushbutton to obtain;
"* Subloop 1 "READY" light illuminated.
"* Subloop 1 "MAINTENANCE" light extinguished.
Momentarily depress Subloop I "PUMP/FAN MOTOR" pushbutton AND verify the following Subloop I indications are illuminated;
"* Subloop 1 "PUMP/FAN MOTOR" light.
"* Subloop I "PRESSURIZED" light OR local pressure gauge indicates 1850-1950 psi.
NRC EXAM JPM # I Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail i
3 APRIL 2002
PromneSesStandard l
- 6.
Place Subloop 1 HPU into "LEAD" operation.
CUE: If asked, function as the AO and report local gauge pressure is still reading of approximately 1900 psig.
- 7. Respond to Annunciator 602105 "RECIRC FCV "A" MOTION INHIBIT".
CUE: Inform Candidate that another Operator has responded to the ARP and the alarm cleared immediately following its receipt.
Depress Subloop 1 "LEAD" pushbutton and verify the following indications illuminated;
"* Subloop 1, "LEAD" light.
"* Subloop I, "OPERATIONAL" light.
"* Subloop 1, "PRESSURIZED" light OR local pressure gauge indicates 1850-1950 psi.
"* Subloop 2, "PUMP/FAN MOTOR STOP" light.
"* Subloop 2, "READY" light.
References the next step in the procedure and calls the system engineer so that the event can be trended.
CUE: As the system engineer acknowledge the report of annunciator 602105 receipt during the Subloop transfer.
- 98. Ensure Subloop 2 is in the "Standby" mode.
CUE:
If asked, function as the AO and report local gauge pressure for Subloop 2 is reading approximately 0
.9. Notify the SSS of the condition of Hydraulic Power Unit "A".
CUE:
As the SSS, acknowledge the Candidates report concerning the status of HPU "A".
Terminating Cue:
If the "MAINTANANCE" light came on for Sat/Unsat/
the idle Subloop AFTER the Subloop NA transfer, perform the following;
"* Depress the "READY" pushbutton to place Subloop 2 in "STANDBY".
"* Initiate a PID to correct the potential nitrogen bladder leakage.
Notifies the SSS of the following:
HPU "A" Subloop I is in OPERATION.
HPU "A" Subloop 2 is in STANDBY.
Sat/Unsat Sat/Unsat Hydraulic Power Unit "A" Subloop 1 is in "operation" and Subloop 2 is in "standby".
RECORD STOP TIME NRC EXAM JPM # I Pass/Fail Sat/Unsat Performance Steps
- tanctnrd 4
APRIL 2002
Perfrmane Stps Sandad Grade~
NRC EXAM JPM # I Performance Steps Standard
- rnclo 5
APRIL 2002
Initial Conditions:
- 1. The Plant is operating at 25% power.
- 2. Routine equipment rotations are taking place at this time.
Initiating Cues:
"(Operator's name), transfer HPU "A" operational Subloop from Subloop 2 to Subloop 1 per N2-OP-29, Section F.2.0. Because this is being done for routine equipment rotation GETARS trending is NOT required for this evolution."
NRC EXAM JPM # 1 6
APRIL 2002
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE
Title:
Resetting Feedwater Level Setdown.
Task Number:
259-903-01-01 Reset a Level Setpoint Setdown.
Approvals:
General Supervisor Date "
8reneral Supervisor Operations Training (Designee)
Operations (Designee)
Configuration Control Revision: 0 Date D~e Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
Plant X
Simulator Expected Completion Time:
12 min.
Time Critical Task:
No Alternate Path Task:
No Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
Date:
NRC EXAM JPM # 2 02-OPS-SJE-259-2-04 APRIL 2002 I
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC 13 Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2. During Evaluated JPM:
Self verification shall be demonstrated.
- 3. During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OP-3, Sect. H.2.0
- 2. NUREG K/A 259002 A4.10 Tools and Equipment:
- 1. None Task Standard:
Reset Feedwater Level Setdown at 25% power following an inadvertent actuation of the circuit by I&C.
NRC EXAM JPM # 2 2
APRIL 2002 02-OPS-SJE-259-2-04
Initial Conditions:
- 1. A Plant shutdown is in progress and Reactor Power is currently 25%.
- 3. All surveillance testing and Plant power changes have been halted at this time.
Initiating Cues:
"(Operator's name), reset the Feedwater Level Setdown Setpoint in accordance with N2-OP-3, Section H.2.0."
Performance Stens Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O l/Operations Manual)
RECORD START TIME
- 2.
Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3.
Confirm level setpoint Setdown and Reactor Pressure Vessel (RPV) water level.
- 4. Place Feedwater Level Control System in Master Manual.
- 5. Restore AND Maintain Reactor Pressure Vessel water level between 178.3" and 187.3".
3 NRC EXAM JPM # 2 02-OPS-SJE-259-2-04 N2-OP-3 obtained.
Precautions & limitations reviewed & section H.2.0 referenced.
Level setpoint setdown AMBER light is LIT.
Places the FWLC System in MASTER MANUAL by performing the following;
"* Depress MANUAL (M) pushbutton on 2FWS-HIC1600 FEEDWATER MASTER CONTROLLER, and
"* Observing the Auto (A) Green light extinguishes and the Manual (M) Amber light is illuminated.
Using the open/close detent pushbuttons on 2FWS-HIC1600; Slowly RESTORE RPV water level to between 178.3" and 187.3" Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Pass/Fail Pass/Fail APRIL 2002
a pGrade Evaluator Note: Candidate is expected to restore and maintain water level between 178.3" and 187.3".
- 6. Reset the Feedwater Level Control System Setdown Setpoint.
- 7. Null the appropriate Controller.
- 8. Return Feedwater Level Control System to Automatic operation.
- 9. Monitor Reactor Pressure Vessel Water Level.
CUE: As the SSS, acknowledge the Candidates report concerning the FWLC System.
Terminating Cue:
Control RPV water level between 178.3" and 187.3" without causing a High Water Level Trip at 202.8" AND without causing a Low Water Level Scram at 159.3 "
Resets the Feedwater Level Control System Setdown Setpoint by;
"* Depressing the Setdown Setpoint Reset pushbutton, and
"* Confirms the Amber light is extinguished.
Using the thumbwheel on 2FWS-HIC1600 null the Controller by; Moving the RED indicating needle into the green band indicated on the dial.
Places the FWLC System in MASTER AUTOMATIC by performing the following;
"* Depress AUTOMATIC (A) pushbutton on 2FWS-HIC1600 FEEDWATER MASTER CONTROLLER, and
"* Observing the Auto (A) Green light illuminates and the Manual (M) Amber light is extinguished.
Observes and monitors Reactor Pressure Vessel (RPV) WATER LEVEL.
Notifies the SSS of the following:
Feedwater Level Control System Setdown Setpoint has been RESET.
FWLC has been placed in MASTER AUTOMATIC at 2FWS-HIC1600.
Reactor Vessel Water level IS remaining constant at this time.
Feedwater Level Control System Setpoint has been reset in accordance with N2-OP-3, Section H.2.0.
RECORD STOP TIME NRC EXAM JPM # 2 02-OPS-SJE-259-2-04 4
Pass/Fail Pass/Fail Sat/Unsat Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat APRIL 2002 Performance Steps Standard Grade
Perfrmane Seps tandrd rade NRC EXAM JPM # 2 02-OPS-SJE-259-2-04 5
APRIL 2002 Performance Steps Standard Grade
Initial Conditions:
- 1. A Plant shutdown is in progress and Reactor Power is currently 25%.
- 3. All surveillance testing and Plant power changes have been halted at this time.
Initiating Cues:
"(Operator's name), reset the Feedwater Level Setdown Setpoint in accordance with N2-OP-3, Section H.2.0."
NRC EXAM JPM # 2 02-OPS-SJE-259-2-04 6
APRIL 2002
Fitle:
Task Number:
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE Add Water to the Suppression Pool Using the HPCS System Revision: 0 206-907-01-01-2 Add Water to the Suppression Pool using the HPCS Pump. AND 206-906-01-01-2 Add Water to the Suppression Pool via the HPCS System (Gravity Drain)
Approvals:
General Supervisor Date Operations Training (Designee)
Configuration Control Date' Performer:
G&
al Sti-ervisor Operations (Designee)
(RO/SRO)
Date Trainer/Evaluator:
Evaluation Method:
X Perform Evaluation Location:
Plant Simulate X
Simulator Expected Completion Time:
Start Time:
15 mim.
Time Critical Task:
Stop Time:______
No Alternate Path Task:
Yes Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given ifany critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Sigrnature:___________________
Date:
NRC EXAM JPM # 3 APRIL 2002 a*&
vO*-
I
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC 13 Malfunction CS05 - to trip CSH Pump five (5) seconds after the pump start - ET063.
Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2. During Evaluated JPM:
Self verification shall be demonstrated.
- 3. During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OP-33, Section H.3 and Section H.2
- 2. NUREG K/A 209002 A4.15 Tools and Equipment:
- 1. None Task Standard:
Using the High Pressure Core Spray System raise Suppression Pool water level to 199.9 feet.
NRC EXAM JPM #i 3 2
APRIL 2002
Initial Conditions:
- 1. Reactor Power is 25%.
- 2. Suppression Pool water level is currently 199.7 feet.
"-- Initiating Cues:
"(Operator's name), in accordance with N2-OP-33, Section H.3, raise the water level in the Suppression Pool to 199.9 feet using the High Pressure Core Spray System."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
CUE: Tell candidate that Subsection F.1.0 has been completed.
- 3. Verify operational status of the CSH System with the SSS.
CUE: Responding as the SSS, state that the CSH System HAS been declared inoperable.
- 4. Start CSH*Pl.
N2-OP-33 obtained.
Precautions & limitations reviewed & section H.3.0 referenced.
Request Operational status of the CSH System.
Verify pump suction aligned to the CST.
Places control switch for CSH*P1 in the "START" position.
"* Checks for "RED" light (Breaker closed).
"* Checks CSH pump motor amps.
- 5.
Verify open CSH*MOV105, Minimum Flow Bypass Valve.
Checks valve "RED" light on.
NRC EXAM JPM # 3 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat m
3 APRIL 2002
PromneSesStandardGrd
- 6.
Monitor CST AND Suppression Pool levels.
- 7.
Respond to CSH*P1 trip.
CUE: As the SSS, acknowledge the candidates' report that CSH*P1 has tripped.
CUE: As the SSS, direct the candidate to continue filling the Suppression Pool using the CSH System and raise pool level to 199.9 feet.
- 9.
Review/utilize the correct section of the procedure.
- 10. Verify suction flow path.
- 11. Monitor and maintain CSH discharge pressure to ensure system operability.
.12. Monitor CST AND Suppression Pool levels.
Monitors Suppression Pool water level on either SPDS or 2CMS-LI11B or A.
Monitors Panel 851, CNS-LI-08A & B for CST water level.
Notify SSS that CSH*P1 has tripped on an electrical fault.
Place control switch for CSH*P1 in the "PULL-TO-LOCK" position.
Verify system flow and pressure Dispatch an AO to investigate the cause of the electrical fault on CSH*P1.
References section H.2.0 Verify open CSH*MOV101, PUMP SUCTION FROM CST's.
Throttle OPEN CSH*MOV1 11, TEST RETURN TO SUPPRESION POOL.
"* Monitor 2CSH*PI1 17
"* Throttle OPEN CSH*MOVl1
"* Maintain System pressure > 65 psig.
Monitors Suppression Pool water level on either SPDS or 2CMS-LI11B or A.
Monitors Panel 851, CNS-LI-08A & B for CST water level.
NRC EXAM JPM # 3 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat SatlUnsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Performance Steos Standard
- rnda 4
APRIL 2002
Perfrmace SepsStandard CUE: At the Examiners discretion, cue the operator that Suppression Pool Level is at 199.9 feet.
- 12. Secure filling the Suppression Pool.
CUE: As the SSS, acknowledge the candidates report concerning the closure of CSH*MOV111 and the operability concerns.
Terminating Cue:
Check either SPDS or 2CMS-LI11B to ensure Suppression Pool water level is 199.9 feet and holding.
Closes CSH*MOV1 11, TEST RETURN TO SUPPRESION POOL.
Notifies the SSS that CSH*MOVl1l is closed, Suppression Pool level is 199.9 feet AND the operability concern per DER 2-98 0557 no longer exists, but the pump trip has left the CSH System inoperable.
Sat/Unsat Pass/Fail Sat/Unsat Suppression Pool water level at 199.9 feet as read on SPDS or 2CMS-LI11B and the fill lineup secured.
RECORD STOP TIME NRC EXAM JPM # 3 Performance Stems Standard 5
APRIL 2002
Initial Conditions:
- 1. Reactor Power is 25%.
`2. Suppression Pool water level is currently 199.7 feet.
Initiating Cues:
"(Operator's name), in accordance with N2-OP-33, Section H.3, raise the water level in the Suppression Pool to 199.9 feet using the High Pressure Core Spray System."
NRC EXAM JPM # 3 APRIL 2002
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE "Title:
Return Reactor Water Cleanup to Normal following reduction of Feedwater Stratification Operation.
Task Number:
204-911-01-01-2 Transfer the WCS Return to the Feedwater System Approvals:
Revision: 0 General Supervisor Operations Training (Designee)
Configuration Control Performer:
Date
- een*ral'S up~ervisor*
Operations (Designee)
Date (RO/SRO)
Trainer/Evaluator:
Evaluation Method: X Perform
'valuation Location:
Plant
-Simulate X
Simulator Expected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task:
Yes Start Time:
JPM Overall Rating:
Stop Time:
Pass Completion Time:
Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:___________________
Date:
Unit 2 NRC JPM #4 Date
-I-April 2002
Recommended Start Location: (Completion time based on the start location)
Simulator
'mulator Set-up (if required):
IC 13 Place fourth Filter Demin in service Close WCS*MOV404A Appendix "R" Breakers "SHUT" - Remote CU05 SHUT Open WCS*MOV 107 to the Main Condenser and establish 20 gpm blowdown flow Throttle WCS*MOV200 to obtain F/D flows of 175 gpm Insert Malfunction CU08, WCS fails to isolate - QUEUED Activate Malfunction CU07 at 80% when closing WCS*MOV107 to secure blowdown flow Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a".".
- 2.
During Evaluated JPM:
Self verification shall be demonstrated.
- 3.
During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OP-37, Rev 08, Sect. F.7.0, N2-SOP-83, ARP 602320 and 602313
- 2.
NUREG K/A 223002 A2.03 Tools and Equipment:
- 1. None Task Standard:
WCS Pumps are tripped and the WCS Primary Containment Isolation Valves are closed.
Unit 2 NRC JPM #4 April 2002
Initial Conditions:
- 1. Reactor Startup in progress with power at 25%.
- 2. Reactor Water Cleanup System (WCS) is operating with two (2) pumps and four (4) filter/demins to reduce "I-` Feedwater Stratification.
- 3.
Reject flow to the Main Condenser is 20 gpm.
Initiating Cues:
"(Operator's name), return the Reactor Water Cleanup System to NORMAL operations and secure reject flow to the Main Condenser in accordance with N2-OP-37, Section F.7.0."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3.
Establish "NORMAL" WCS flow to the Feedwater headers.
N2-OP-37 obtained.
Precautions & limitations reviewed & section F.7.0 referenced.
Monitor WCS differential flow indications on Panels P632 and P642.
0 2WCS-FI1620A&B SLOWLY open 2WCS*MOV404A.
Notify CSO to log TIME and DATE for the valve opening.
Unit 2 NRC JPM #4 Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Grade April 2002
Perfrmace SeusStandard
- 4. Secure "REJECT" flow to the Main Condenser from the WCS System.
NOTE:
When the Candidate starts closing 2WCS*MOV107, activate malfunction CU07, WCS leak outside Primary Containment, at 80% using F3.
CU08, Failure of WCS to Isolate, malfunction is already active as it was queued at the beginning of this JPM.
- 5. Respond to Annunciator 602320, RWCU DIFF FLOW TIMER BYPASS.
CUE:
When candidates checks flow timer at P642, inform candidate that the timer is functioning the same way as the P632 timer.
(E3 1 -R62 1 B Timer at P642 is not functional in the simulator).
NOTE: This annunciator indicates that WCS differential flow has exceeded its setpoint of 150.5 gpm and that E31-R621A and/or B have started timing out. At the end of 45 seconds, if differential flow has not dropped below 150.5 gpm, a full WCS isolation SHOULD occur.
e6.
When Annunciator 602313, RWCU DIFFERENTIAL FLOW HIGH actuates, determines WCS Isolation should have occurred and did not.
CUE: As SSS, concur with recommendation to isolate WCS.
NOTE:
Candidate will either close Isolation Valves based on entry into N2-SOP-83 or Annunciator response for 602313. IF N2 SOP-83 is used as the basis for Unit 2 NRC JPM #4 Slowly lower reject flow as indicated on G33 R606 to zero (0) using the manual control of Reject Flow, 2WCS-FIC135 on P602.
Close 2WCS*MOV 107, REJECT TO MAIN CONDENSER.
Suspend any operational evolutions that may be causing a perturbation in cleanup system flow UNTIL this annunciator clears.
Prepare to respond to a cleanup isolation per the appropriate sections of N2-OP-37.
Observes 2WCS*MOV102 AND 2WCS*MOV 112 DID NOT close by observing RED lights "ON" and GREEN lights "OFF".
Informs SSS that WCS has failed to isolate.
April 2002 Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Performance Steos Standard Performance Steps Standard closing the valves, the candidate is expected to followup in the Annunciator Response Procedure.
e7. Manually closes 2WCS*MOV102 AND/OR 2WCS*MOV 112 per N2-SOP-83 (or Annunciator 602313, RWCU DIFFERENTIAL FLOW HIGH response).
NOTE: Candidate is to be graded as "Pass" for the critical step if either valve is closed to isolate the leak. The expectation is that both valves will be manually closed.
.8 Followup actions for Annunciator 602313, RWCU DIFFERENTIAL FLOW HIGH, if valves were closed using N2-SOP-83.
Manually closes 2WCS*MOV 102 AND/OR 2WCS*MOV1 12
"* Obtain KEYS and inserts into keylock switches
"* Rotates keylock switches to CLOSE position.
"* Observes GREEN Lights "ON" and RED light "OFF" when valve is full closed.
Confirms Isolation valves 2WCS*MOV 102 AND 2WCS*MOV1 12 closed.
Verifies 2WCS-P1A AND 2WCS-P1B have tripped.
"* Pump GREEN light "ON", AND
"* Actuation of Annunciator 602314, RWCU PUMP 1A/1B AUTO TRIP.
CUE:
If asked what is supplying WCS pump seals, reply that the Control Rod Drive System is supplying WCS Pump seals.
e9. Provide vent path for WCS Pump seals, to protect the WCS Pump suction piping from over-pressurization.
Throttle open 2WCS-MOVI 10, FILTER DEMIN BYPASS VALVE.
Reports the following to the SSS the WCS System has been manually isolated.
Unit 2 NRC JPM #4 Grade Pass/Fail Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat April 2002
Performance Steps Standard Grade Terminating Cue:
WCS System is isolated, the WCS Pumps are tripped and 2WCS*MOV10 is throttled open.
RECORD STOP TIME Unit 2 NRC JPM #4 April 2002
Initial Conditions:
- 1. Reactor Startup in progress with power at 25%.
- 2. Reactor Water Cleanup System (WCS) is operating with two (2) pumps and four (4) filter/demins to reduce Feedwater Stratification.
- 3. Reject flow to the Main Condenser is 20 gpm.
Initiating Cues:
"(Operator's name), return the Reactor Water Cleanup System to NORMAL operations and secure reject flow to the Main Condenser in accordance with N2-OP-37, Section F.7.0."
Unit 2 NRC JPM #4 April 2002
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE ritle:
Reactor Protection System Weekly Manual Scram Test Task Number:
212-002-01 Place a RPS Channel in the Tripped Condition Approvals:
General Supervisor Date 0e),!r~lSupervisor Operations Training (Designee)
Operations (Designee)
Revision: 0 Date Configuration Control Date Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
Plant X
Simulator expected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task:
No Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:__________________
Date:
NRC EXAM JPM # 5 APRIL 2002 I
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC 13 Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a"*".
- 2. During Evaluated JPM:
Self verification shall be demonstrated.
- 3. During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OSP-RPS-W002, Sects. 8.3 and 8.4
- 2. NUREG K/A 2129000 A2.03, A4.02 Tools and Equipment:
- 1. None Task Standard:
Complete the RPS Weekly Manual Scram surveillance test for the "C" and "B" RPS channels.
NRC EXAM JPM # 5 2
APRIL 2002
Initial Conditions:
- 1. Reactor Power is 25%.
nitiating Cues:
"(Operator's name), Surveillance Test N2-OSP-RPS-W002 is in progress and has been completed through step 8.2.12. The person performing the test is ill and you need to continue its performance until the replacement arrives. Here is the surveillance, continue at step 8.3 and complete through step 8.4, the "C" and "B" RPS channels. By the time you are finished with these two channels the replacement will have arrived."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Request assistance for backpanel readings during this surveillance.
CUE: Respond to the Candidates request and say that you will be providing the requested information from 2CEC*PNL609 and 2CEC*PNL611.
- 4. Verify Plant conditions for performing the manual scram Channel "C" test.
N2-OSP-RPS-W002 obtained.
General Test Methods, Precautions &
limitations reviewed & sections 8.3 and 8.4 referenced.
Requests the SSS supply an individual to check backpanel reading on 2CEC*PNL609 and 2CEC*PNL611.
Verify that there is NO half scram on RPS "B" side.
"* RPS B AUTO TRIP, annunciator 603410, NOT in alarm.
"* RPS B MANUAL TRIP, annunciator 603411, NOT in alarm.
"* PILOT SCRAM VALVE SOLENOIDS B, D, F & H are illuminated.
NRC EXAM JPM # 5 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat 3
APRIL 2002
Performance Stens Standard Grade
- 5. Notify CSO of RPS Weekly Manual Scram Surveillance Test for RPS "C".
- 6. Initiate a half scram.
- 7. Verify Status of Indicating Lights.
CUE: When asked the status of the REACTOR SCRAM TRIP LOGIC A2 indicating light on 2CEC*PNL609, reply that; "REACTOR SCRAM TRIP LOGIC A2 indicating light on 2CEC*PNL609 is extinguished."
- 8. Reset the half scram.
- 9. Verify computer printouts for the TRIPPED condition.
Notify CSO prior to the start of the surveillance.
Ensures the CSO is aware that the surveillance WILL generate a HALF SCRAM on the "A" side of RPS.
Arm the REACTOR SCRAM A2 pushbutton by rotating the sleeve clockwise.
Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, has alarmed.
Depress AND hold the REACTOR SCRAM A2 pushbutton.
"* Verify annunciator 603110, RPS A AUTO TRIP, has alarmed.
"* Verify annunciator 603111, RPS A MANUAL TRIP, has alarmed.
Check and verify that the indicating lights for the PILOT SCRAM VALVE SOLENOIDS A, C, E & G are extinguished.
Place the REACTOR SCRAM RESET LOCIC "C" switch on P603 to the RESET position and then let it return to NORMAL.
Verify that the "SEQUENCE OF EVENTS" printer, printed the following for the "TRIPPED" condition:
0 RPSUC01, RPS A MANUAL TRIP, printed out as "TRIPPED".
RPSUC03, RPS A AUTO TRIP, printed out as "TRIPPED".
NRC EXAM JPM # 5 Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Performnance Steos Standard Grade 4
APRIL 2002
Standard Grade
- 10. Verify annunciators and computer printouts for the RESET condition.
- 11. Verify Status of Indicating Lights.
CUE: When asked the status of the REACTOR SCRAM TRIP LOGIC A2 indicating light on 2CEC*PNL609, reply that; "REACTOR SCRAM TRIP LOGIC A2 indicating light on 2CEC*PNL609 is illuminated."
- 12. Disarm the RPS Channel A2 manual scram pushbutton.
Verify that the "PLANT COMPUTER" printer, printed the following for the "TRIPPED" condition:
"* RPSUCO1, RPS A MANUAL TRIP, printed out as "TRIPPED".
"* RPSUC03, RPS A AUTO TRIP, printed out as "TRIPPED".
Verify annunciator 603110, RPS A AUTO TRIP, has extinguished.
Verify annunciator 603111, RPS A MANUAL TRIP, has extinguished.
Verify that the "SEQUENCE OF EVENTS" printer, printed the following for the "RESET" condition:
RPSUC01, RPS A MANUAL TRIP, printed out as "ALMCLR".
RPSUC03, RPS A AUTO TRIP, printed out as "ALMCLR".
Verify that the "PLANT COMPUTER" printer, printed the following for the "RESET" condition:
"* RPSUC01, RPS A MANUAL TRIP, printed out as "ALMCLR".
"* RPSUC03, RPS A AUTO TRIP, printed out as "ALMCLR".
Check and verify that the indicating lights for the PILOT SCRAM VALVE SOLENOIDS A, C, E & G are illuminated.
Disarm the REACTOR SCRAM A2 pushbutton by rotating the sleeve counter clockwise.
Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, has extinguished.
NRC EXAM JPM # 5 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Performance Stetos Standard Grade 5
APRIL 2002
Pe~rformance Sten Stsad rd
- 13. Verify Plant conditions for performing the manual scram Channel "B" test.
- 14. Notify CSO of RPS Weekly Manual Scram Surveillance Test for RPS "B".
- 15. Initiate a half scram.
- 16. Verify Status of Indicating Lights.
Verify that there is NO half scram on RPS "A" side.
"* RPS A AUTO TRIP, annunciator 603110, NOT in alarm.
"* RPS A MANUAL TRIP, annunciator 603111 NOT in alarm.
"* PILOT SCRAM VALVE SOLENOIDS A, C, E & G are illuminated.
Notify CSO prior to the start of the surveillance.
Ensures the CSO is aware that the surveillance WILL generate a HALF SCRAM on the "B" side of RPS.
Arm the REACTOR SCRAM BI pushbutton by rotating the sleeve clockwise.
Verify annunciator 603413, RPS B MANUAL SCRAM SWITCH ARMED, has alarmed.
Depress AND hold the REACTOR SCRAM B1 pushbutton.
"* Verify annunciator 603410, RPS B AUTO TRIP, has alarmed.
"* Verify annunciator 603411, RPS B MANUAL TRIP, has alarmed.
Check and verify that the indicating lights for the PILOT SCRAM VALVE SOLENOIDS B, D, F & H are extinguished.
CUE: When asked the status of the REACTOR SCRAM TRIP LOGIC B1 indicating light on 2CEC*PNL611, reply that; "REACTOR SCRAM TRIP LOGIC Bi indicating light on 2CEC*PNL611 is extinguished."
NRC EXAM JPM # 5 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Pass/Fail Sat/Unsat SatfUnsat Sat/Unsat Standard Grade Perfnrmance Stens APRIL 2002 6
Performance Steos Standard Grade
- 17. Reset the half scram.
- 18. Verify computer printouts for the TRIPPED condition.
- 19. Verify annunciators and computer printouts for the RESET condition.
Place the REACTOR SCRAM RESET LOCIC "B" switch on P603 to the RESET position and then let it return to NORMAL.
Verify that the "SEQUENCE OF EVENTS" printer, printed the following for the "TRIPPED" condition:
"* RPSUC02, RPS B MANUAL TRIP, printed out as "TRIPPED".
"* RPSUC04, RPS B AUTO TRIP, printed out as "TRIPPED".
Verify that the "PLANT COMPUTER" printer, printed the following for the "TRIPPED" condition:
"* RPSUC02, RPS B MANUAL TRIP, printed out as "TRIPPED".
"* RPSUC04, RPS B AUTO TRIP, printed out as "TRIPPED".
Verify annunciator 603410, RPS B AUTO TRIP, has extinguished.
Verify annunciator 603411, RPS B MANUAL TRIP, has extinguished.
Verify that the "SEQUENCE OF EVENTS" printer, printed the following for the "RESET" condition:
RPSUC02, RPS B MANUAL TRIP, printed out as "ALMCLR".
RPSUC04, RPS B AUTO TRIP, printed out as "ALMCLR".
Verify that the "PLANT COMPUTER" printer, printed the following for the "RESET" condition:
RPSUC02, RPS B MANUAL TRIP, printed out as "ALMCLR".
RPSUC04, RPS B AUTO TRIP, printed out as "ALMCLR".
NRC EXAM JPM # 5 Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Performance Steos Standard Grade 7
APRIL 2002
Performance Stens Sadr rd
- 20. Verify Status of Indicating Lights.
CUE: When asked the status of the REACTOR SCRAM TRIP LOGIC B1 indicating light on 2CEC*PNL611, reply that; "REACTOR SCRAM TRIP LOGIC BI indicating light on 2CEC*PNL611 is illuminated."
- 21. Disarm the RPS Channel BI manual scram pushbutton.
- 22. Notify the SSS of surveillance status.
Check and verify that the indicating lights for the PILOT SCRAM VALVE SOLENOIDS B, D, F & H are illuminated.
Disarm the REACTOR SCRAM B1 pushbutton by rotating the sleeve counter clockwise.
Verify annunciator 603413, RPS B MANUAL SCRAM SWITCH ARMED, has extinguished.
Notifies the SSS that N2-OSP-RPS-W002, Sections 8.3 and 8.4 for the "B" and "C" RPS Channels have been completed.
CUE: As the SSS, acknowledge the Candidates report and tell him/her that the replacement for the performance of this test has arrived.
Terminating Cue:
The RPS Weekly Manual Scram surveillance test for the "C" and "B" RPS channels has been completed and all half scram signals are reset.
RECORD STOP TIME NRC EXAM JPM # 5 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat 8
Standard Grade Performance Stens APRIL 2002
Initial Conditions:
- 1. Reactor Power is 25%.
Initiating Cues:
"(Operator's name), Surveillance Test N2-OSP-RPS-W002 is in progress and has been completed through step 8.2.12. The person performing the test is ill and you need to continue its performance until the replacement arrives. Here is the surveillance, continue at step 8.3 and complete through step 8.4, the "C" and "B" RPS channels. By the time you are finished with these two channels the replacement will have arrived."
NRC EXAM JPM # 5 APRIL 2002 9
N[NE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE "Fitle:
RCIC Injection With Oscillations (]
Task Number:
2179150101 - Perform a manual sta Approvals:
General Supervisor Date Operations Training (Designee)
Configuration Control Date Faulted) rtup of RCIC from the Control Room Revision:
2 eea S ervisor Date Operations (Designee)
Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
Plant X
Simulator iExpected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task:
Yes Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator's Signature:
NRC EXAM JPM # 6 02-OPS-SJE-217-2-05 Date:
May 2002
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
- 1. RPV pressure >300 psig
- 2. Malfunction RC04, Queued off Event Trigger 049 [Relatives]
Event Trigger 050
- 3. RPV water level < 125 inches and lowering.
Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has detennined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a "."
- 2. During Evaluated JPM:
0 Self-verification shall be demonstrated.
- 3. During Training JPM:
Self-verification shall be demonstrated.
Additional verification shall be demonstrated.
References:
- 1. N2-OP-35, Section F.2.0
- 2. NUREG K/A 217000 A4.01 3.7/3.7 Tools and Equipment:
None Task Standard:
RCIC Flow Controller in Manual and injecting to RPV at approximately 600 gpm.
NRC EXAM JPM # 6 2
May 2002 02-OPS-SJE-217-2-05
Initial Conditions:
- 1. Reactor pressure is (report digital pressure reading on P603)
- 2. RPV level is lowering.
Initiating Cues:
"(Operator's name), initiate RCIC per N2-OP-35, Section F.2.0, inject into the RPV and establish rated flow."
Performance Steps Standahrd Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary.
Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Initiate RCIC.
- 4. Verify RCIC System response.
NRC EXAM JPM # 6 02-OPS-SJE-217-2-05 N2-OP-35 obtained. Precautions &
limitations reviewed and Section F.2.0 referenced.
At P601, rotate RCIC manual initiation pushbutton collar to armed position.
Depress RCIC manual initiation pushbutton.
Verifies RCIC has started properly by verifying the following:
Gland Seal System Air Compressor STARTS.
0 21CS*MOV 116, Lube Oil Cooling Water Supply, OPENS.
21CS*MOV120, Turbine Steam Supply Valve, OPENS.
0 2 ICS*MOV126, RCIC Pump discharge to the Reactor, OPENS.
21CS*MOV143, RCIC Pump minimum flow to the Suppression Pool. OPENS and then CLOSES once discharge flow is greater than 220 gpm.
2 ICS*AOV 156 and 157, RCIC Injection Outboard and Inboard Isolation Valves, OPEN once System Pressure is greater than Reactor Pressure.
May 2002 Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat
.qtandard 3
PromneSesStandard t--
- 5. Observe and respond to failure of the RCIC System flow controller in "AUTO".
- 6. Report system response.
CUE: As the SSS, respond to the Candidates report on the RCIC System.
CUE: If asked, tell the Candidate that RCIC flow is still required, and to monitor the RCIC System for any further signs of malfunctions.
Terminating Cue:
Recognizes as RCIC Flow is increasing that the flow to the Reactor Vessel is OSCILLATING.
Places 21CS*FC 101, RCIC Flow Controller in "MANUAL" and ESTABLISHES approximately 600 gpm flow rate.
Pass/Fail Pass/Fail Reports to the SSS; RCIC is injecting to the Reactor Vessel at 600 gpm in the MANUAL mode.
The Flow Controller, 21CS*FC 101, IS NOT in the AUTOMATIC mode due to flow oscillations during startup of the RCIC System.
Current Reactor Vessel Level.
Sat/Unsat Sat/Unsat The RCIC System is injecting in the manual mode at rated flow conditions.
RECORD STOP TIME NRC EXAM JPM # 6 02-OPS-SJE-217-2-05 May 2002 Performance Steps Standard 4
Initial Conditions:
- 1. Reactor pressure is (report digital pressure reading on P603)
- 2. RPV level is lowering.
Initiating Cues:
"(Operator's name), initiate RCIC per N2-OP-35, Section F.2.0, inject into the RPV and establish rated flow."
NRC EXAM JPM # 6 02-OPS-SJE-217-2-05 May 2002 5
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE
Title:
Energizing 2NNS-SWG015 from 2ENS*SWGIO3 Revision: 0 Task Number:
262-935-05-01-2 Energize 2NNS-SWGO15 from an EDG during Station Blackout conditions. (PRA)
Approvals:
General Supervisor Date General Supervisor Date-r Operations Training (Designee)
Operations (Designee)
ýj A- (.N,4A, EEC Configuration Control Date Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator Expected Completion Time:
12 min.
Time Critical Task:
No Alternate Path Task:
No Start Time: _
Stop Time: _
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if ay critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
Date:
NRC EXAM JPM # 7 1
APRIL 2002
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC 13 Insert Malfunctions ED02A and ED02B by queuing them.
Manually SCRAM the Reactor using the Mode Switch.
Let conditions stabilize and then save the setup to a clean IC Perform SOP-03, D.2.4 Fault Identification.
Perform SOP-03, D.9.5 to energize ENS*SWG103 from Division III Emergency Diesel Generator Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2. During Evaluated JPM:
Self verification shall be demonstrated.
- 3. During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-SOP-3, Section D.10.3
- 2. NUREG K/A 2629001 A2.07
- 3. PRA Task 262-935-05-01 Tools and Equipment:
- 1. None Task Standard: Energize 2NNS-SWG015 from 2ENS*SWGlO3.
NRC EXAM JPM # 7 2
APRIL 2002
Initial Conditions:
- 1. The Reactor has just been manually scrammed.
- 2.
A Station Black Out (SBO) is in progress.
- 3.
2NNS-SWGO 15 is required for this SBO recovery.
- 4. N2-SOP-3, Section D.2.4, Fault Identification is complete.
- 5.
ENS*SWG 103 is energized from the Division III Emergency Diesel Generator, per N2-SOP-3, D.9.5 Initiating Cues:
"(Operator's name), energize 2NNS-SWGOI5 from 2ENS*SWGI03 in accordance with N2-SOP-03, Section D. 10.3."
Performance Steps S~tandard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction ifnecessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Secure Normal electrical feed to 2NNS SWGO15.
- 4.
Bypass the Division II LOCA signal.
N2-SOP-3 obtained.
Section D. 10.3 is referenced.
Disconnect 2NNS-SWGO 15 from 2NPS SWG003.
Verifies Breaker 15-3 in the "Pull-to Lock" position.
Obtain a PA2235 KEY from the CSO's desk.
At P852, place the Division II LOCA Signal Bypass Switch to the "ON" position.
- Verifies annunciator 852236 EDG 3 LOCA Bypass switch "ON".
NRC EXAM JPM # 7 APRIL 2002 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Rtanclnrct 3
Performance Steps Standard Grade
- 6. Verify status of Breaker 103-8 on 2ENS*SWG103.
Dispatch an AO to 2ENS*SWG103, in the Control Building 261' elevation.
Verify reset on 86-2ENSY12.
CUE: When dispatched as the AO wait one minute and report that "86-ENSY12 is reset."
- 7. Close emergency feed breaker from 2ENS*SWG103.
- 8. Close emergency supply breaker to 2NNS SWG015.
- 9. Reports electrical status of 2NNS-SWG015 to the SSS.
CUE: As the SSS, acknowledge the Candidates report and tell him/her that is all for now.
Terminating Cue:
Close Breaker 103-8, 2ENS*SWG103 Feeder Breaker to 2NNS-SWG015.
0 Observe RED light "ON".
Close Breaker 15-8, 2NNS-SWG015 Supply Breaker from 2ENS*SWG103.
"* Observe RED light "ON".
"* Observe 4KV normal Bus NNS-015 at about 4200 VAC.
Reports the following to the SSS;
"* 2NNS-SWG015 is being supplied from 2ENS*SWG103
"* Current voltage reading on 2NNS SWG015 is about 4200 VAC.
Pass/Fail Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat 2NNS-SWG015 is re-energized from 2ENS*SWG103.
RECORD STOP TIME NRC EXAM JPM # 7 APRIL 2002 Sat/Unsat 4
Initial Conditions:
- 1. The Reactor has just been manually scrammed.
- 2. A Station Black Out (SBO) and recovery is in progress.
- 4. N2-SOP-3, Section D.2.4, Fault Identification is complete.
- 5. ENS*SWG103 is energized from the Division III Emergency Diesel Generator, per N2-SOP-3, D.9.5 Initiating Cues:
"(Operator's name), energize 2NNS-SWG015 from 2ENS*SWGl03 in accordance with N2-SOP-03, Section D. 10.3."
NRC EXAM JPM # 7 APRIL 2002 5
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE "fitle:
Reset EPA Breaker 2VBS*ACB2A with an Overvoltage condition present.
Revision: 0 Task Number:
212-901-01-04-2 Reset a Reactor Protection System Electrical Protection Assembly (EPA)
Approvals:
General Supervisor Date Date Operations Training (Designee)
Operations (Designee)
Configuration Control Date Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method:
Perform X
Simulate Evaluation Location:
X Plant Simulator
"-xpected Completion Time:
10 min.
Time Critical Task:
No Alternate Path Task:
Yes Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
Date:
NRC EXAM JPM # 8 1
APRIL 2002
Recommended Start Location: (Completion time based on the start location)
EPA Breaker 2VBS*ACB2A Simulator Set-up (if required):
-.. 'irections to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2.
During Evaluated JPM:
Self verification shall be demonstrated.
- 3. During Training JPM:
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-SOP-97, Section 4.2.3, Condition 1
- 2. NUREG K/A 262001 A2.06 Tools and Equipment:
- 1. None Task Standard:
Reset and close EPA Breaker 2VBS*ACB2A.
NRC EXAM JPM # 8 2
APRIL 2002
Initial Conditions:
- 1. The Plant is operating at 100% power.
- 2. EPA Breaker 2VBS*ACB1A is closed.
- 3. EPA Breaker 2VBS*ACB2A is tripped.
Initiating Cues:
"(Operator's name), reset EPA Breaker 2VBS*ACB2A in accordance with N2-SOP-97, Section 4.2.3."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O I/Operations Manual)
RECORD START TIME
- 2.
Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
..__3. Observe and record the status of EPA Breaker 2VBS*ACB2A.
CUE: When asked by the Candidate which of the protective relays has tripped, reply that:
"The Undervoltage target and Underfreq uency target lights are OUT.
The Overvoltage target light is LIT."
- 4. Reset EPA Breaker 2VBS*ACB2A.
NRC EXAM JPM # 8 N2-SOP-97 obtained.
Section 4.2.3 is referenced.
Observe AND record, which targets of the protective relays, has TRIPPED.
Simulate a RESET of EPA Breaker 2VBS*ACB2A.
Simulate placing the OUTPUT breaker (handle) in the RESET position.
AND THEN simulate placing the OUTPUT breaker (handle) in the ON position.
3 Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail APRIL 2002
Performance Steps Standard Grade CUE: Inform the Candidate that the EPA Breaker 2VBS*ACB2A has re tripped, again on an overvoltage condition.
Alternate Path
- 5. Reset EPA Breaker 2VBS*ACB2A, bypassing the protective relay.
CUE: Cue the Candidate, as each step occurs:
"* Tamper Proof is removed
"* Red Knife Switch is open
"* TS 3.3.8.2 has been referenced and it is acceptable to proceed.
"* EPA Breaker remains closed
- 6. Report EPA Breaker 2VBS*ACB2A status to the Control Room.
Simulate REMOVING the tamper proof cover for the OVERVOLTAGE TEST SW, located to the right of the Overvoltage Relay.
Simulate BYPASSING the protective function by simulating OPENING the "RED" KNIFE SWITCH 900.
Notifies SSS to refer to Tech Spec 3.3.8.2 Simulate a RESET of EPA Breaker 2VBS*ACB2A.
"* Simulate placing the OUTPUT breaker (handle) in the RESET position.
"* AND THEN simulate placing the OUTPUT breaker (handle) in the ON position.
Notify the Control Room; Sat/Unsat The EPA Breaker 2VBS*ACB2A is RESET and ON.
The RED KNIFE SWITCH for OVERVOLTAGE is "OPEN".
CUE: Acting as the SSS, acknowledge the Candidates report and say that ITS is being investigated at this time.
Terminating Cue:
EPA Breaker 2VBS*ACB2A has been "RESET" and is "ON" with the Overvoltage relay function bypassed using the "red" Knife Switch.
RECORD STOP TIME NRC EXAM JPM # 8 4
APRIL 2002 Pass/Fail Pass/Fail Pass/Fail Pass/Fail
Initial Conditions:
- 1. The Plant is operating at 100% power.
_2. EPA Breaker 2VBS*ACB1A is closed.
- 3. EPA Breaker 2VBS*ACB2A is tripped.
Initiating Cues:
"(Operator's name), reset EPA Breaker 2VBS*ACB2A in accordance with N2-SOP-97, Section 4.2.3."
NRC EXAM JPM # 8 5
APRIL 2002
NIAGARA MOHAWK POWER CORPORATION OPERATOR JOB PERFORMANCE MEASURE
Title:
Vent the Scram Air Header Revision:
6 Task Number: 200-960-05-01-2 Manually Vent the Scram Air Header per EOP-6, attachment 14.
Approvals:
General Supervisor Date "en-eral"-upervisor Date Operations Training (Designee)
Operations (Designee)
Configuration Control Date Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method:
Perform X
Simulate Evaluation Location:
X Plant Simulator Expected Completion Time:
10 minutes Time Critical Task:
No Alternate Path Task:
No Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE:
A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator's Signature:
NRC EXAM JPM # 9 02-OPS-PJE-200-2-04 Date: April 2002
Recommended Start Location: (Completion time based on the start location)
Reactor Building El. 261' by access Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2.
During Evaluated JPM:
0 Self-verification shall be demonstrated.
- 3. During Training JPM:
"* Self-verification shall be demonstrated.
"* Additional verification shall be demonstrated.
References:
- 1. N2-EOP-6, Attachment 14, "Alternate Rod Insertions", Section 3.2.2
- 2. NUREG K/A: 201001 A2.09 Tools and Equipment:
L660 key for EOP box. (If procedure obtained locally)
NRC EXAM JPM # 9 April 2002 02-OPS-PJE-200-2-04
Task Standard:
CRD Scram Air Header depressurized by locally isolating instrument air makeup and venting the air header.
Initial Conditions:
- 1. A failure to SCRAM has occurred.
- 2.
All scram solenoid power lights are OFF.
- 3. Numerous scram valves have failed to open.
- 4. Annunciator 603306 "CRD scram valve pilot air header pressure "high/low" is extinguished.
- 5.
Instructor to ask operator for any questions.
Initiating Cues:
"(Operator's name), using EOP-6, Attachment 14 Section 3.2.2, vent the Scram Air Header manually from the Reactor Building."
Performance Steps Standard e
1--iau1 I. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary.
Proper communications used for repeat back.(GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2.
Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Isolate instrument air makeup.
CUE: Once the Candidate has located the appropriate valve, simulate V595 unlocked and shut.
- 4. Vent air header.
CUE: Once the Candidate has located the appropriate valve, simulate V43 open and air header depressurizing.
N2-EOP-6, Attachment 14 obtained.
Section 3.2.2 referenced.
Locate 2RDS-V595 in the RB 261' elevation, by RDS flow control valves.
(On ARI solenoid valve rack)
S 0
BREAK lock wire and ROTATE handwheel for 2RDS-V595 clockwise to the shut position.
Locate 2RDS-V43 in the RB 261' elevation, east end of 2NHS-MCCO12.
- ROTATE the handwheel for 2RDS-V43 counter-clockwise to the open position.
NRC EXAM JPM # 9 02-OPS-PJE-200-2-04 Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail April 2002 Standard
Performance Steps Standard Grade
- 5. Verify Annunciator 603306 in alarm.
CUE: Acting as the Control Room contact person tell the Candidate that, "Annunciator 603306, CRD SCRAM VALVE PILOT AIR HDR PRESSURE HIGH/LOW is energized."
- 6. Check Control Rod Positions.
Cue:
Acting as the Control Room contact person tell the Candidate that, "all Control Rods are fully inserted."
Terminating Cue:
Contact the Control Room.
Verify annunciator 603306, CRD SCRAM VALVE PILOT AIR HEADER PRESSURE HIGH/LOW is energized.
Contact the Control Room.
Verify the status of CONTROL ROD POSITIONS.
SatlUnsat Sat/Unsat Sat/Unsat SatlUnsat All Control Rods fully inserted with the Control Rod Drive Scram Air Header isolated and vented.
RECORD STOP TIME NRC EXAM JPM # 9 02-OPS-PJE-200-2-04 April 2002
Initial Conditions:
- 1. A failure to SCRAM has occurred.
- 2. All scram solenoid power lights are OFF.
- 3. Numerous scram valves have failed to open.
- 4. Annunciator 603306 "CRD scram valve pilot air header pressure "high/low" is extinguished.
- 5. Instructor to ask operator for any questions.
Initiating Cues:
"(Operator's name), using EOP-6, Attachment 14 Section 3.2.2, vent the Scram Air Header manually from the Reactor Building."
NRC EXAM JPM # 9 02-OPS-PJE-200-2-04 April 2002
Fitle:
Task Number:
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE Align Service Water to Spent Fuel Pool Cooling Heat Exchanger "A" Revision: 0 233-923-04-01-2 Restoration of Spent Fuel Pool Cooling System during Control Room evacuation per N2-SOP-38.
Approvals:
,A
_ / c/ /
"General Supervisor Date Operations Training (Designee)
Configuration Control Date
- en rfal Supervisor Date Operations (Designee)
Performer:
(RO/SRO)
Trainer/Evaluator:
Evaluation Method:
Perform X
Simulate Evaluation Location:
X Plant Simulator Expected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task:
No Start Time: _
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
NRC EXAM JPM # 10 Date:
APRIL 2002 I
Recommended Start Location: (Completion time based on the start location)
Plant - North Auxiliary Bay 240' elevation.
Simulator Set-up (if required):
_._irections to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SSS / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
"8 For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a
- 2. During Evaluated JPM:
Self verification shall be demonstrated.
- 3.
During Training JPM:
"* Self verification shall be demonstrated.
"* No other verification shall be demonstrated.
References:
- 1. N2-SOP-38, Section 4.5.1
- 2.
NUREG K/A 233000 A2.08 Tools and Equipment:
- 1. None Task Standard:
Align and supply Service Water to Spent Fuel Pool Heat Exchanger "A".
NRC EXAM JPM # 10 2
APRIL 2002
Initial Conditions:
- 1. The Main Control Room has been evacuated.
- 2.
Spent Fuel Pool Cooling Pump 2SFC*P1A is running.
- 3. Reactor Building Closed Loop Cooling Water System (CCP) has been lost.
- 4.
The SSS has authorized performance of this evolution
- 5. A second operator is standing by in the Division I Switchgear Room to assist.
Initiating Cues:
"(Operator's name), Line-up Service Water to supply Spent Fuel Pool Cooling Heat Exchanger "A", in accordance with N2-SOP-38, Section 4.5."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O I/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
CUE: As the SSS, tell the Candidate that you have direct that sampling is to be performed later.
CUE:
When asked to perform the preceding steps wait one minute and then reply that "the breakers for 2EHS*MCC103-4A and 2EHS*MCC 103-4B are OFF."
N2-SOP-38 obtained.
Section 4.5.1 is referenced.
Direct second operator in the DMSION I SWITCHGEAR ROOM to "OPEN" the following breakers;
"* 2EHS*MCC103-4A, CL LOOP CLG WTR TO SFP CLG HE A SPLY V 2CCP*MOV14A.
"* 2EHS*MCC103-4B, CL LOOP CLG WTR TO SFP CLG HE A RTN V 2CCP*MOV I 8A.
NRC EXAM JPM # 10 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat APRIL 2002
Performance Steps Standard Grade
- 4. De-energize the SWP SUPPLY and RETURN isolation valves for the "A" SFP Heat Exchanger.
CUE: As candidate repositions the two breakers, cue that the breakers switches are OFF.
CUE:
As candidate rotates handwheel in clockwise (closed) direction, cue that the valve stem and collar are moving in the closed direction.
- 6.
Open the SWP SUPPLY and RETURN isolation valves for the "A" SFP Heat Exchanger.
CUE:
As candidate rotates handwheel in counter-clockwise (open) direction, cue that the valve stem and collar are moving in the open direction.
NRC EXAM JPM # 10 Locate MCC 102 in the North Auxiliary Bay 240' elevation.
Simulates OPENING by rotating breaker cubicle switches clockwise to OFF position;
"* 2EHS*MCC102-2A, SWP TO SPENT FUEL POOL HE -2SWP*MOV17A.
"* 2EHS*MCC1I02-2B, SWP FROM SPENT FUEL POOL HE 2SWP*MOVl 8A.
Locate the CCP SUPPLY and RETURN isolation valves for the "A" SFP Heat Exchanger in the Reactor Building 215' elevation.
Simulates CLOSING the following valves by pulling down on lever/handle for manual handwheel engaging, then rotating MOV handwheel clockwise and observes stem and collar movement in closed direction:
"* 2CCP*MOV14A, SFP HEAT EXCHANGER RBCLC INLET.
"* 2CCP*MOV18A, SFP HEAT EXCHANGER RBCLC OUTLET.
Locate the SWP SUPPLY and RETURN isolation valves for the "A" SFP Heat Exchanger in the Reactor Building 196' elevation by the north stairwell.
Simulates OPENING the valves by pulling down on lever/handle for manual handwheel engaging, then rotating MOV handwheel counter-clockwise and observes stem and collar movement in open direction:
"* 2SWP*MOV17A, SFP HEAT EXCHANGER SERVICE WTR INLET.
2SWP*MOV 18A, SFP HEAT EXCHANGER SEVICE WTR OUTLET.
4 Sat/Unsat Pass/Fail Pass/Fail SatiUnsat Pass/Fail Pass/Fail Sat/Unsat Pass/Fail Pass/Fail APRIL 2002
Performance Steps Standard Grade
- 7.
Report task completion to SSS Notifies SSS that Service Water System is Sat/Unsat supplying cooling water SFC "A" Heat Exchanger The Service Water System is aligned and supplying water to the "A" Spent Fuel Pool Cooling Heat Exchanger.
RECORD STOP TIME NRC EXAM JPM # 10 APRIL 2002 Terminating Cue:
5
Initial Conditions:
- 1. The Main Control Room has been evacuated.
- 2. Spent Fuel Pool Cooling Pump 2SFC*PlA is running.
- 3. Reactor Building Closed Loop Cooling Water System (CCP) has been lost.
- 4. The SSS has authorized performance of this evolution
- 5. A second operator is standing by in the Division I Switchgear Room to assist.
Initiating Cues:
"(Operator's name), Line-up Service Water to supply Spent Fuel Pool Cooling Heat Exchanger "A", in accordance with N2-SOP-38, Section 4.5."
NRC EXAM JPM # 10 6
APRIL 2002