ML053210425
| ML053210425 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/19/2005 |
| From: | Roush K Susquehanna |
| To: | Todd Fish Operations Branch I |
| Conte R | |
| References | |
| Download: ML053210425 (170) | |
Text
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 98.G0.001.151 0 09/28/05 26200 1 A4.04 3.613.7 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. KIA Imp.
To Sys. No.
Task
Title:
Synchronize the Main Generator Completed By: Validated Rich Chin 09128/05 Writer Date InstructorNV riter Date Approval :
Nuclear Trng. Supv.
25 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # / S.S. #
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-3 1.8-1, Rev. 0, Page I of 2 2005 NRC Exam Rev. I
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 98.G0.001.101
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES A. OP-198-001, Main Generator System (Rev. 3)
B. GO-100-002, Plant Startup, Heatup And Power Operation (Rev. 49)
III. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. A Plant Startup is in progress, Reactor Power is 19% -
B. Main turbine Startup is complete, the turbine is 8 1800 RPM awaiting Main Generator Startup.
C. Generator Prestart Lineup is complete.
D. GO-100-002, Plant Startup, Heatup And Power Operation has been completed through step 5.61.2 V. INITIATING CUE Synchronize the Main Generator to the Grid IAW section 2.2 of OP-198-001, Main Generator System.
VI. TASK STANDARD Main generator synchronized to grid.
VILTASK SAFETY SIGNIFICANCE Incorrect performance of this task could lead to grid instabilities and/or LOOP (challenging the EDG to perform their function).
Form NTP-QA-3 1.8-I , Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 3 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments EVALUATOR NOTE:
0 Establish task conditions as directed on attached setup instructions.
0 When student is ready to begin JPM, place the simulator in RUN.
0 Due to the nature of this JPM, the candidate may perform an extensive board walkdown to determine current plant status "Prior" to beginning the JPM:
0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
Simulator Setup 0 IC- 13 Reactor Power -19 %, Turbine 8 1800 RPM ready for Generator Sychronization Place Simulator in RUN 0 Insert IMF BR04:lRlOl Prevents Auto Closure Of GEN SYNC BKR 1T HS 10001 (IC-186 for LOC-21 NRC Exam) 1 Obtains controlled copy of procedure Obtains controlled copy of OP-198-001, Main Generator System and refers to section 2.2
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 4 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Standard Eva1 Comments Action 2 Reviews prerequisites and precautions letermines from initial conditions:
0 Main Turbine S/U complete.
0 Generator Prestart Lineup complete.
0 If service water is isolated to the H2 coolers, the Main Generator will overheat. There is NO Control Room indication for the isolation valves EVALUATOR NOTE:
If necessary inform candidate that service water to the H2 coolers was aligned as part of the Generator Prestart Lineup.
CAUTION Allowing Main Turbine To Remain Unloaded At Rated Speed Causes Overheating Of Exhaust Hoods.
3 Ensure the following for EHC: Verifies:
Main Turbine Speed Status AT SET SPEED light AT SET SPEED red light - LIT ILLUMINATED. LOAD LIMIT SET dial pot is at 8.9 LOAD LIMIT SET vernier set at 8.9 (corresponding to MAXIMUM COMBINED FLOW LIMIT dial pot is at 12.5 100%).
MAXIMUM COMBINED FLOW LIMIT vernier set at 12.5 (corresponding to 125%).
- Critical Step #Critical Sequence Form NTP-QA-31.8-2.Rev. 0, Page I of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 5 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments EVALUATOR NOTE:
The next several steps will cause alarms to come in and clear. The candidate is expected to acknowledge the alarms as they are received. Since these are Expected alarms, it will not be necessary to refer to the AR, rather just acknowledge them as Expected alarms.
4 Place Generator Core Monitor and Ha Gas Analyzer in Contacts an NPO to Place Generator Core Monitor and service as follows: H P Gas Analyzer are in service BOOTH CUE:
Insert MRF EC197002 IN-SVC to place Generator Core Monitor and H2Gas Analyzer in service.
EVALUATOR CUE:
Role-play NPO and report Generator Core Monitor and H2Gas Analyzer IN service.
5 Establish generator field: Verifies:
Ensure VOLT REG XFER SELECT HS 10006 switch VOLT REG XFER SELECT HS 10006 switch in in MANUAL. MANUAL.
AND Red light - LIT Amber light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I i PERFORMANCE CHECKLIST Page 6 of 16 Appl. To/JPM No.: S/RO 98.G0.001 .lo1 Student Name:
Action Standard Eva1 Comments Ensure MAN VOLT REG ADJUST HC 10002 at ZERO Verifies:
percent. MAN VOLT REG ADJUST HC 10002 at ZERO Ensure AUTO VOLT REG ADJUST HC 10001 at Verifies:
ZERO percent.
AUTO VOLT REG ADJUST HC 10001 at ZERO Close EXCITER FIELD BKR HS 10005. Places:
Observe: EXCITER FIELD BKR HS 10005 control switch to CLOSE UNIT 1 MAIN GENERATOR AC KILOVOLTS, X I 10006 (Gen Terminal Voltage) Increases to about Verifies:
20KV. Red light - LIT Is0 Phase Bus Duct Cooler Starts if NOT already in Amber light - NOT LIT 0PERAT10N.
UNIT 1 MAIN GENERATOR AC KILOVOLTS, X1 10006 Increases to about 20 KV Is0 Phase Bus Duct Cooler (at 1C628) 0 Red light - LIT 0 Amber light - NOT LIT EVALUATOR CUE:
If necessary, Role-play the NPO and Inform the candidate that the Is0 Phase Bus Duct Coolers are in operation.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0. Page 1 of I 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 7 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments 9 Using MAN VOLT REG ADJUST HC 10002 Turns MAN VOLT REG ADJUST HC 10002 potentiometer, Raise SYNCHRONIZING BKR UNIT 1 potentiometer CLOCKWISE until:
GEN VOLTS to MATCH SYNCHRONIZING BKR SYNCHRONIZING BKR UNIT 1 GEN VOLTS are GRID VOLTS XI 10009. MATCHED with SYNCHRONIZING BKR GRID VOLTS XI 10009.
10 Check proper operation of auto voltage regulation by Turns AUTO VOLT REG ADJUST HC 10001 Adjusting AUTO VOLT REG ADJUST HC 10001 potentiometer CLOCKWISE then potentiometer in INCREASE and DECREASE direction COUNTERCLOCKWISE:
while Observing deviation on VR XFER XI 10012. Verifies:
VR XFER XI 10012 raises and lowers with the adjustments to the AUTO VOLT REG ADJUST HC 10001 potentiometer 11 To balance Auto and Manual Voltage Regulators, Turns AUTO VOLT REG ADJUST HC 10001 Adjust AUTO VOLT REG ADJUST HC 10001 potentiometer as necessary to:
potentiometer until VR XFER XI 10012 Reads ZERO Verify:
volts.
VR XFER XI 10012 is at ZERO 12 WHEN VR XFER XI 10012 Indicates ZERO, (nulled), Places:
Place the VOLT REG XFER SELECT HS 10006 VOLT REG XFER SELECT HS 10006 switch to AUTO.
switch to AUTO.
Verifies:
Red light - NOT LIT Amber light - LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
i PERFORMANCE CHECKLIST Page 8 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments 13 To Ensure Auto Voltage Regulator has Control using Turns AUTO VOLT REG ADJUST HC 10001 AUTO VOLT REG ADJUST HC 10001 potentiometer: potentiometer COUNTERCLOCKWISE then CLOCKWISE:
Lower voltage slightly.
Verifies:
Raise voltage back to original value.
VR XFER XI 10012 lowers and raises with the adjustments to the AUTO VOLT REG ADJUST HC 10001 potentiometer 14 Notify Generation Control Center (GCC) of impending Calls GCC on phone and Notifies them of impending synchronization with the Grid. synchronization with the Grid.
EVALUATOR CUE:
Role-play GCC and acknowledge the report.
EVALUATOR NOTE:
The next step of the procedure would have been reviewed in the pre-job brief. Since this JPM is NOT faulted in this manner, it will NOT be necessary for the candidate to exercise this Main Generator Connected Single Phase procedure. After the candidate reads the step and attempts to review the procedure, provide the candidate with the EVALUATOR CUE.
15 PRIOR to Performing next step, Review ON 198 003, Attempts to review ON 198 003, Unit 1 Main Generator Unit 1 Main Generator Connected Single Phase to , Connected Single Phase to Grid During Startup Grid During Startup.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 9 of 16 Appl. To/JPM No.: S/RO 98.G0.001 .lo1 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
Role-play the Unit Supervisor and inform the candidate that another PCO has been assigned to monitor the Main Generator for potential single phase connection and will implement the Off Normal procedure if necessary.
CAUTION RPV Water Level May Decrease As A Result Of Condenser Parameter Changes During Generator Synchronization.
CAUTION Moisture Separator Drain Tank Levels Will Increase For A Short Duration As A Result Of Steam Flow Changes In The Moisture Separators During Generator Synchronization.
16 Perform either Automatic (preferred) or Manual SYNCHRONIZATION and LOADING section of this procedure EVALUATOR CUE:
Role-play the Unit Supervisor and inform the candidate that AUTOMATIC SYNCHRONIZATION will be performed for this startup.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 10of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments 17 Locates appropriate section of procedure for Refers to section 2.3 of procedure Automatic SYNCHRONIZATION 18 Reviews prerequisites and precautions Determines:
Main Generator S/U complete.
19 Place GEN SYNC SEL 1T HS 10002 switch to MAN. Places:
GEN SYNC SEL 1T HS 10002 keylock switch to MAN Verifies:
SYNCHROSCOPE meter is rotating and the lights are LIT when the meter is NOT at 12 Oclock position 20 Adjust generator output voltage by using AUTO VOLT Turns AUTO VOLT REG ADJUST HC 10001 REG ADJUST HC 10001 potentiometer so potentiometer CLOCKWISE then SYNCHRONIZING BKR UNIT 1 GEN VOLTS are Verifies:
slightly HIGHER THAN SYNCHRONIZING BKR GRID VOLTS XI 10009. SYNCHRONIZING BKR UNIT 1 GEN VOLTS are slightly higher than SYNCHRONIZING BKR GRID VOLTS XI 10009.
21 Ensure SYNCHRONIZING DlFF VOLTS, XI 10007, is Verifies:
slightly to the RIGHT of ZERO. SYNCHRONIZING DlFF VOLTS, XI 10007, is slightly to the RIGHT of ZERO
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0, Page I of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 11 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments 22 Adjust generator frequency using LOAD SELECTOR Depresses:
INCR EASE/DECREASE push buttons unt iI LOAD SELECTOR INCREASE pushbutton until the SYNCHROSCOPE is rotating in the CLOCKWISE SYNCHROSCOPE is rotating in the CLOCKWISE (FAST) direction at approximately 1 revolution per 30 (FAST) direction at approximately 1 revolution per 30 seconds. seconds.
FAULT STATEMENT:
THE GEN SYNC BKR 1T HS 10001 WILL FAIL TO CLOSE IN THE NEXT STEP 23 Perform next three steps Expeditiously to reduce Places:
possibility of a reverse power trip.
GEN SYNC SEL 1T HS 10002 keylock switch to AUTO To Synchronize Main Generator with the grid, Place Verifies:
GEN SYNC SEL 1T HS 10002 switch to AUTO.
GEN SYNC BKR 1T HS 10001 Ensure GEN SYNC BKR 1T Closes by Observing:
Red light - NOT LIT Red indicating light at GEN SYNC BKR 1T HS 10001 ILLUMINATES. Amber light - LIT Megawatts Increase.
Megawatts HAVE NOT INCREASED.
24 Reports Failure to Unit Supervisor Reports Failure to Unit Supervisor
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page I of I 2005 NRC Exam Rev. 1
1 I i PERFORMANCE CHECKLIST Page 12 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Action Standard Comments EVALUATOR CUE:
Role-play the Unit Supervisor acknowledge the report AND Direct the candidate to perform a Manual SYNCHRONIZATION IAW section 2.4.
Locates appropriate section of procedure for Manu2 Refer to section 2.4 of procedure SYNCHRONIZATION Reviews prerequisites and precautions Determines:
Main Generator S/U complete.
Obtain Shift Supervision approval to Manually Determines:
Synchronize main generator. Shift Supervision approval to Manually Synchronize main generator has been received Place GEN SYNC SEL 1T HS 10002 switch to MAN. Places:
GEN SYNC SEL 1T HS 0002 keylock switch to MAN Verifies:
SYNCHROSCOPE meter is rotating and the lights are LIT when the meter is NOT at 12 Oclock position
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 13 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments BOOTH CUE:
Insert DMF BR04:lRlOl to remove the malfunction on GEN SYNC BKR 1T HS 10001 EVALUATOR NOTE:
It may not be necessary to adjust voltage in the next step. This was previously performed back in step 20 of the JPM PRIOR to the Fault. If the candidate determines that no adjustment is necessary at this point, then step 20 becomes the critical step.
f 29 Adjust generator output voltage by using AUTO VOLT Turns AUTO VOLT REG ADJUST HC 10001 REG ADJUST HC 10001 potentiometer so potentiometer COUNTERCLOCKWISEthen SYNCHRONIZING BKR UNIT 1 GEN VOLTS are Verifies:
slightly higher than SYNCHRONIZING BKR GRID VOLTS XI 10009. SYNCHRONIZING BKR UNIT 1 GEN VOLTS are slightly higher than SYNCHRONIZING BKR GRID VOLTS XI 10009.
30 Ensure SYNCHRONIZING DlFF VOLTS, XI 10007, is Verifies:
slightly to the RIGHT of ZERO SYNCHRONIZING DlFF VOLTS, XI 10007, is slightly to the RIGHT of ZERO
- Critical Step #C rit icaI Sequence Form NTP-QA-31.8-2, Rev. 0.Page I of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 14 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments Adjust generator frequency using LOAD SELECTOR Depresses:
INCREASE/DECREASE push buttons until LOAD SELECTOR DECREASE pushbutton until the SYNCHROSCOPE is rotating in the CLOCKWISE SYNCHROSCOPE is rotating in the CLOCKWISE (FAST) direction at approximately 1 revolution per 60 (FAST) direction at approximately 1 revolution per 60 seconds. seconds.
Perform next three steps Expeditiously to reduce When synchroscope is at or slightly before "12 O'clock" possibility of a reverse power trip. position, To Synchronize Main Generator with the grid, when Places:
synchroscope is at or slightly before "12 O'clock" GEN SYNC BKR 1T HS 10001 control switch to CLOSE position Close GEN SYNC BKR 1T HS 10001.
33 Ensure GEN SYNC BKR 1T Closes by Observing: Verifies GEN SYNC BKR 1T HS 10001:
Red indicating light GEN SYNC BKR 1T HS 10001 is Red light - LIT ILLUMINATED. Amber light - NOT LIT Megawatts Increase. Megawatts Increase
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page I of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 15 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Comments 34 Depress Increase push button on LOAD SELECTOR Depresses:
until all BYPASS VALVES are CLOSED.
LOAD SELECTOR INCREASE pushbutton until:
BPVl POSITION indicates ZERO and BPV2 POSITION indicates ZERO and BPV3 POSITION indicates ZERO and BPV4 POSITION indicates ZERO and BPV5 POSITION indicates ZERO 35 Place GEN SYNC SEL 1T HS 10002 Switch to OFF. Places:
GEN SYNC SEL 1T HS 10002 keylock switch to OFF Verifies:
SYNCHROSCOPE meter is NOT rotating and the lights are NOT LIT.
36 Maintain LOAD SET at 100 MWe ABOVE actual load Depresses:
LOAD SET INCREASE pushbutton until:
100 MWe ABOVE actual load
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 N R C Exam Rev. 1
PERFORMANCE CHECKLIST Page 16 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 N R C Exam Rev. 1
TASK CONDITIONS A. A Plant Startup is in progress, Reactor Power is - 19%
B. Main turbine Startup is complete, the turbine is @I - 1800 RPM awaiting Main Generator Startup.
C. Generator Prestart Lineup is complete.
D. GO-100-002, Plant Startup, Heatup And Power Operation has been completed through step 5.61.2 INITIATING CUE Synchronize the Main Generator to the Grid IAW section 2.2 of OP-198-001, Main Generator System.
Page 1 of 2 2005 NRC Exam Rev. 1
TASK CONDITIONS A. A Plant Startup is in progress, Reactor Power is 19%
B. Main turbine Startup is complete, the turbine is @ 1800 RPM awaiting Main Generator Startup.
C. Generator Prestart Lineup is complete.
D. GO-100-002, Plant Startup, Heatup And Power Operation has been completed through step 5.61.2 INITIATING CUE Synchronize the Main Generator to the Grid IAW section 2.2 of OP-198-001, Main Generator System.
Page 2 of 2 2005 NRC Exam Rev. 1
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 79.0P.006.102 0 9128/05 223001 A1.10 3.413.6 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. KIA Imp.
To Sys. No.
Task
Title:
Startup The Containment Radiation Monitor System After Maintenance (CRM A)
Completed By: Validated Rich Chin 9/28/05 Writer Date Inst ructor M Iriter Date Approval:
Nuclear Trng. Supv. Date 15 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # I S.S. #
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 79.0P.006.102
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
- 11. REFERENCES OP-179-003, Containment Radiation Monitoring (Revision 5) 111. REACTIVITY MAN1PULATlONS This JPM satisfies the requirements of Operational Activity(@:
NONE IV. TASK CONDITIONS A. CRM A was shutdown and isolated IAW OP-179-003 section 3.4, to support routine maintenance inspection checks.
B. Maintenance has completed their inspections.
C. CRM A is ready to be returned to service.
D. No Containment Isolation signals are present.
E. All prerequisites have been met.
V. INITIATING CUE Startup CRM A from the control room IAW the appropriate operating procedure. Use Pump 1 to start the monitor.
VI. TASK STANDARD CRM A is sampling the Containment atmosphere.
VII. TASK SAFETY SIGNIFICANCE Provides a diverse means of detecting RCS leakage into the Containment atmosphere.
Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
I i PERFORMANCE CHECKLIST Page 3 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Step Action Standard Eva1 Comments From any at power IC, shutdown and isolate CRM A IAW OP-179-003. Place the simulator in Freeze, and write an IC snap. Check "time" on CRM A screen display to verify it is current, the CRM has a separate processor and could be out of sync with simulatorheal time.
IC-184 for LOC-21 NRC Exam 1 Locates correct procedure. Obtains controlled copy of OP-179-003 2 References correct procedure section. Refers to section 3.1 3 Reviews prerequisites Reviews prerequisites EVALUATOR CUE:
If necessary, Inform candidate that all prerequisites have been met.
4 Reviews Precautions Reviews Precautions f5 Open Supply and Return Primary Containment Places:
Isolation Valves at Containment Monitoring and Recording Panel 1C693 RI 15799A. HS 15711OAl CRM A Drywell Air Sample Inboard Supply & Return Isolation Valves Div I, Place HS 157110A1 CRM A Drywell Air Sample SV 1571OON102A in the OPEN position.
Inboard Supply & Return Isolation Valves Div I, SV 1571OON102A in the OPEN position.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 4 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Step Action Standard Eva1 Comments 6 Observe red open indication for SV 1571OOA. Verifies:
SV 157100A Red Light - LIT Amber Light - NOT LIT 7 Observe red open indication for SV 157102A. Verifies:
SV 157102A Red Light - LIT Amber Light - NOT LIT
$0 Place HS 15711OA2 CRM A Drywell Air Sample Places:
Inboard Supply & Return Isolation Valves Div II, SV 157101A/103A in the OPEN position. HS 157110A2 CRM A Drywell Air Sample Inboard Supply & Return Isolation Valves Div II, SV 157101All 03A in the OPEN position.
9 Observe red open indication for SV 157101A. Verifies:
SV 157101A Red Light - LIT Amber Light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA91.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 5 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
~~~
Action Standard Eva1 Comments 10 Observe red open indication for SV 157103A. Verifies:
SV 157103A Red Light - LIT Amber Light - NOT LIT NOTE:
CRMS may be operated locally or from the Control Room as determined by Shift Supervision.
Based on initiating cue:
Refers to section 3.1.5
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 6 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
~~
Step Action Standard Eva1 Comments
_T 11 To Place Containment Radiation Monitor A in Verifies the following status of CRM A Air service from CONTAINMENT MONITORING Sample Rad Monitor CRT:
AND RECORDING PANEL 1C693 RI 15799A:
Correct approximate time.
Observe CRM A Air Sample Rad Monitor CRT parameters: " I S 0 Control Status Blocks LIT.
Correct approximate time. "LO Temp" Alarm Block NOT LIT.
"OFF" OR "IS0 Control Status Blocks lit. "LO Flow" Alarm Block LIT.
"LO Temp" Alarm Block NOT lit. "LLO Flow" Alarm Block LIT.
"LO Flow" Alarm Block lit. "LO Filter Delta P" Alarm Block LIT.
"LLO Flow" Alarm Block lit.
"LO Filter Delta P" Alarm Block lit.
12 Press ACK to acknowledge local alarms. Presses ACK pushbutton on CRM A keypad 13 Confirm CONTAINMENT MONITORING AND Verifies the following alarm window is LIT:
RECORDING PANEL 1C693, Annunciator A02 "CONTN RAD DET SYSTEM A TROUBLE" lit. CONTAINMENT MONITORING AND RECORDING PANEL 1C693, Annunciator A02 "CONTN RAD DET SYSTEM A TROUBLE".
14 IF CRM A is isolated (Le., IS0 status block lit), Verifies:
the CRM pumps will not start until this status is cleared. "ISO" Status Block is LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 7 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Step Action Standard Eva1 Comments 15 IF CRM "ISO" (isolate) lit, UNISOLATE system Verifies:
as follows:
"ISO" Status Block is LIT 16 Press #O on CRM A on CRM A keypad. Presses 0 on CRM A on CRM A keypad.
17 Observe screen change. Verifies screen changes 18 Press #1 "System Controls." Presses 1 on CRM A on CRM A keypad.
19 Press #6 "lsolate/Off" on CRM A keypad. Presses 6 on CRM A on CRM A keypad 20 Observe "ISO" status block clear. Verifies "ISO" status block clears.
21 Press #O on CRM A keypad. Presses 0 on CRM A on CRM A keypad 22 Ensure CRM A heat trace to reach operating Contacts NPO to verify CRM A heat trace to temperature of approximately 135°F. reach operating temperature of approximately 135°F.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 8 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Step EVALUATOR CUE:
Action Standard Eva1 Comments Role-play NPO and Acknowledge the request, and report that you will ensure that the heat tracing reaches 135°F.
23 Press #O on CRM A keypad. Presses 0 on CRM A on CRM A keypad 24 Press #1 "System Controls" on CRM A keypac. Presses 1 on CRM A on CRM A keypad 25 Observe screen change. Verifies screen changes NOTE:
It may be necessary to repeat steps 3.1.5 f.
and g. several times in order to clear the LLO Flow alarm block. If the pump will not remain running after three attempts, contact I&C (or alternatively Chemistry) for assistance.
jr 26 Start CRM Pump 1P262A1 or 1P262A2 by: Presses 0 on CRM A on CRM A keypad Press #O on CRM A keypad. Verifies small block next to pump 1 is LIT.
27 Observe screen changes. Verifies screen changes.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0.Page 1 of 1 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 9 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Step 28 Press #1 "System Controls."
Action Standard Presses 1 on CRM A on CRM A keypad Comments 29 Press #3 "Pump 1 Control" for 1P262A1 Presses 3 on CRM A on CRM A keypad 30 Observe Control Status Block lit for PUMPl, After a few seconds, after a few seconds.
Verifies Control Status Block for PUMP1 LIT 31 Confirm "LLO Flow" alarm block clears. Verifies:
"LLO Flow" alarm block clears (NOT LIT).
32 Press ACK on CRM A keypad. Presses ACK on CRM A keypad.
33 Confirm "LO Flow" alarm block clears. Verifies:
"LO Flow" alarm block clears (NOT LIT).
34 Confirm CONTAINMENT MONITORING AND Verifies the following alarm window is NOT LIT:
RECORDING PANEL 1C693, Annunciator A02 CONTAINMENT MONITORING AND "CONTN RAD DET SYSTEM A TROUBLE" RECORDING PANEL 1C693, Annunciator A02 clears.
"CONTN RAD DET SYSTEM A TROUBLE".
35 Press #O "Exit" on CRM A keypad. Presses 0 on CRM A on CRM A keypad
'Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
1 PERFORMANCE CHECKLIST Page 10 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Action Standard Comments
~
Observe screen change. Verifies screen changes.
Press #3 "Display Current Data" on CRM A Presses 3 on CRM A on CRM A keypad keypad.
Observe screen change. Verifies screen changes.
Press #3 "System" on CRM A Air Sample Rad Presses 3 on CRM A on CRM A keypad Monitor Keypad.
Observe a flow rate of approximately 1.OO+OO Verifies on CRM A CRT:
SCFM indicating normal system operation.
Flow rate of approximately 1.OO+OO SCFM Press #O "Exit" on CRM A keypad. Presses 0 on CRM A on CRM A keypad Observe screen change. Verifies screen changes.
Press #O "EXIT" on CRM A keypad. Presses 0 on CRM A on CRM A keypad Observe screen change. Verifies screen changes.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 11 of 11 Appl. To/JPM No.: 79.0P.006.102 Student Name:
Step Action Standard Eva1 Comments 45 Press #5 "Countrate Histograms" on CRM A Presses 5 on CRM A on CRM A keypad keypad.
46 Observe CPM Counting on CRM A Air Sample Verifies:
Rad Monitor CRT.
CRM A Air Sample Rad Monitor CRT is counting.
EVALUATOR CUE:
This completes the JPM
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS A. CRM A was shutdown and isolated IAW OP-179-003 section 3.4, to support routine maintenance inspection checks.
B. Maintenance has completed their inspections.
C. CRM A is ready to be returned to service.
D. No Containment Isolation signals are present.
E. All prerequisites have been met.
INITIATING CUE Startup CRM A from the control room IAW the appropriate operating procedure.
Use Pump 1 to start the monitor.
2005 NRC Exam Rev. 1 1 of2
TASK CONDITIONS A. CRM A was shutdown and isolated IAW OP-179-003section 3.4, to support routine maintenance inspection checks.
- 6. Maintenance has completed their inspections.
C. CRM A is ready to be returned to service.
D. No Containment Isolation signals are present.
E. All prerequisites have been met.
INITIATING CUE Startup CRM A from the control room IAW the appropriate operating procedure.
Use Pump 1 to start the monitor.
2005 NRC Exam Rev. 1 2 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 73.0P.001.101 0 1014105 288000 A2.01 3.313.4 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
To Sys. No.
Task
Title:
Vent the D w e l l IAW OP-173-003 Completed By:
Rich Chin 1014105 Writer Date InstructorNV riter Date Approval :
Nuclear Trng. Supv. Date 15 Date of Performance: Allowed Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee ## I S.S. ##
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-3 1.8-1. Rev. 0. Page I of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 73.0P.001.101
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
- 6. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES A. OP-173-003, Primary Containment Nitrogen Makeup And Venting (Rev. 9) 6 . OP-070-001, Standby Gas Treatment System (Rev. 19)
II1. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. Unit 1 is in Mode 1 B. Drywell pressure is 0.4 psig V. INITIATING CUE Your supervisor directs you to reduce Drywell pressure to 0.1 psig IAW OP-173-003, Primary Containment Nitrogen Makeup and Venting section 2.3. All prerequisites have been met. All T M S requirements are satisfied.
VI. TASK STANDARD SGTS in operation, Drywell venting with pressure being reduced.
VII. TASK SAFETY SIGNIFICANCE Avoid an unnecessary high drywell pressure SCRAM.
Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
I i PERFORMANCE CHECKLIST Page 3 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Step Action Standard Eva1 Comments EVALUATOR NOTE:
This JPM must be performed in the simulator.
0 Select any Mode 1 IC Secure Drywell cooling fans until Drywell pressure rises to 0.4 psig. Restart drywell cooling fans.
0 Place simulator in FREEZE.
When student is ready to begin JPM, place the simulator in RUN.
1 Obtain controlled copy of OP-173-003, Primary Controlled copy obtained.
Containment Nitrogen Makeup And Venting.
2 Select the correct section to perform. Selects section 2.3 3 Review the prerequisites and precautions. Ensures all prerequisites and precautions have been met.
EVALUATOR CUE:
If necessary inform the student all prerequisites and precautions have been met.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page I of 1 2005 NRC Exam Rev. 1
f PERFORMANCE CHECKLIST Page 4 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Action Standard Eva1 Comments Manually Start SGTS in accordance with OP-070-001 Controlled copy obtained.
Obtain controlled copy of OP-070-001, Standby Gas Treatment.
EVALUATOR CUE:
Role-play the Unit Supervisor and instruct candidate to start the A train of SGTS.
Select the correct section to perform. Selects section 3.2 Review the prerequisites and precautions. Ensures all prerequisites and precautions have been met.
EVALUATOR CUE:
If necessary inform the student all prerequisites and precautions have been met.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2. Rev. 0, Page I of I 2005 NRC Exam Rev. 1
I (
PERFORMANCE CHECKLIST Page 5 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Step Action Standard Eva1 Comments NOTE:
HD 0755A remains open for approximately 70 seconds and HD 07558 remains open for approximately 120 seconds after their respective pushbuttons are released.
Steps 3.2.3 through 3.2.5 must be performed expeditiously to establish a flow path and allow SGTS to start.
HD 07555A OPEN pushbutton.
8 OBSERVE SGTS Clg OA Dmp HD07555A OPENS to Verifies:
allow suction flow path for start of SGTS Fan A.
SGTS CLG OA DMP HD 07555A Amber light - NOT LIT Red light - LIT
- 9 At Panel OC681, START Standby Gas Treatment Places selector switch for SGTS FAN OV109A to START System A by placing selector switch for SGTS Fan OV109A to START. Verifies:
Amber light - NOT LIT Red light - LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 N R C Exam Rev. I
PERFORMANCE CHECKLIST Page 6 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Step Action Standard Eva1 Comments 10 When Fan starts, OBSERVE flow increases >3000 CFM Verifies:
on SGTS Air Flow FR07553A.
SGTS AIR FLOW FR-07553A increases to greater than 3000 CFM.
EVALUATOR NOTE:
SGTS Fans may not obtain 10,100 CFM due to insufficient suction flow path through SGTS Makeup OA Dmp FD07551A2.
EVALUATOR NOTE:
Flowrate for this JPM should be (-4,800 CFM) 11 Check SGTS Makeup OA Dmp FD07551A2 Approximately 70 seconds after SGTS Fan OV109A MODULATED/OPEN approximately 70 seconds after started.
SGTS Fan OV109A started.
Verifies:
SGTS Makeup OA DMP FD 07551A2 Amber light - LIT Red light - LIT
=
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page7of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Step Action Standard Eva1 Comments 12 CHECK following positioned as indicated: Verifies:
SGTS Fan Inlet Dmp HD07552A FULL OPEN. SGTS FAN INLET DMP HD 07552A Amber light - NOT LIT Red light - LIT 13 SGTS A Inlet Dmp HD07553A FULL OPEN. Verifies:
SGTS A INLET DMP HD 07553A Amber light - NOT LIT Red light - LIT 14 Refers to appropriate venting procedure. Refers to OP-173-003 section 2.3.5 15 Ensure Drywell pressure does not become >0.5 psig Checks drywell pressure and determines N/A for current conditions.
below suppression chamber pressure, to prevent opening vacuum breakers.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 8 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Step Action Standard Eva1 Comments NOTE:
If pressure decreased to low pressure alarm setpoint (approximately 0.1 psig), pressure will have to be increased to approximately 0.5 psig to reset alarm.
EVALUATOR CUE:
Role-play the Unit Supervisor and inform the candidate that it will not be necessary to actually log the vent start time in the next step.
16 Log vent start time in Unit 1 Log. NIA
= -
- Critical Step #Critical Sequence Form NTP-QA-3 1.82, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
I PERFORMANCE CHECKLIST Page 9 of 10 Appl. To/JPM No.: S/RO 73.0P.001 .lo1 Student Name:
Step Action Standard Eva1 Comments
$17 Open following: Places Control switches for the following to the OPEN position:
HD17508A DRWLNVETWELL BURP DMP HD17508A DRWLNVETWELL BURP DMP HD17508B DRWWETWELL BURP DMP HD17508B DRWLNVETWELL BURP DMP HV 15713 DRWL VENT IB IS0 HV 15713 DRWL VENT IB IS0 HV 15711 DRWL VENT BYPS OB IS0 HV 15711 DRWL VENT BYPS OB IS0 AND Verifies:
Amber lights - NOT LIT Red lights - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 10 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name:
Step Action Standard Eva1 Comments 18 Monitor Drywell Pressure using any of the following: Determines Drywell pressure is dropping by checking:
Computer point MAP01 or MAP001Z Computer point MAP01 or MAP001Z AND/OR PlCSY screen CONTN PlCSY screen CONTN PI 15702 CONTN OR SUPP CHMBR PRESS with selector switch HSS 15702 selected to CONTN AN D/O R PI 15702 CONTN OR SUPP CHMBR PRESS with selector switch HSS 15702 selected to CONTN EVALUATOR CUE:
This completes the JPM
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Unit 1 is in Mode 1 B. Drywell pressure is 0.4 psig INITIATING CUE Your supervisor directs you to reduce Drywell pressure to 0.1 psig IAW OP-173-003, Primary Containment Nitrogen Makeup and Venting section 2.3. All prerequisites have been met. All TR/TS requirements are satisfied.
Page 1 of 2 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Unit 1 is in Mode 1 B. Drywell pressure is 0.4 psig INITIATING CUE Your supervisor directs you to reduce Drywell pressure to 0.1 psig IAW OP-173-003, Primary Containment Nitrogen Makeup and Venting section 2.3. All prerequisites have been met. All TWTS requirements are satisfied.
Page 2 of 2 2005 NRC Exam Rev. 1
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 58.0P.008.101 0 09/28/05 212000 K4.03 3.0/3.1 Appl. To JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
Sys. No.
Task
Title:
Transferring Power Supply From RPS M-G Set To Alternate Completed By: Validated:
Rich Chin 09/28/05 Writer Date InstructorNVriter Date Approval:
Nuclear Trng. Supv. Date 15 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee #/S.S. #
Performance ) Satisfactory ( ) Unsatisfactory Evaluation:
Eva1uator Name:
Signature Typed or Printed Comments:
Form NTP-QA-81.8-1, Rev. 0,Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 58.0P.008.101
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsiblefor maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES OP-158-001 RPS System (Revision 29)
II1. R EACTlVlTY MANIPULATlONS This JPM satisfies the requirements of Operational Activity(s):
NONE IV. TASK CONDITIONS A. Unit 1 is in Mode 1 at 68% power B. RPS Shorting Links are installed C. Attachment A of OP-158-001, RPS System, is complete D. RPS Alternate Power supply is available E. All required Tech Spec LCO entries have been made.
V. INITIATING CUE Transfer Power Supply from A RPS M-G Set to Alternate and restore plant systems, IAW the appropriate Attachment.
VI. TASK STANDARD A RPS Bus powered from Alternate with all reset functions RESET.
VII. TASK SAFETY SIGNIFICANCE Provide reliable power source to RPS Form NTP-QA-31.8-1, Rev. 0 , Page 2 of 2 2005 NRC Exam Rev. 1
i I PERFORMANCE CHECKLIST Page 3 of 8 Appl. To/JPM No.: 58.0P.008.101 Student Name:
Step Action Standard Eva1 Cornments EVALUATOR NOTE:
This JPM must be performed in the simulator.
Select Mode 1 IC Complete Attachment A of OP-158-001 (run auto exercise file RPSAXFER-SU) and write an IC Insert pref YPP.CERTJPM-0401 which contains:
pfs 1 MRF RM179024 RESET resets MSL rad monitor RIS-D12-1K603A pfs 2 MRF RM179026 RESET resets MSL rad monitor RIS-D12-1K603C pfs 3 MRF DB106360 CLOSE Closes breaker for RWCU valve HV-144-FOO1 When student is ready to begin JPM, place the simulator in RUN.
{YPP.ILONRCJPMDE for LOG21 NRC exam)
{IC 185 for LOC-21 NRC exam)
Obtain a controlled copy of OP-158-001 RPS System Controlled copy obtained.
Selects the correct section to perform. Selects section 2.4
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
1 PERFORMANCE CHECKLIST Page 4 of 8 Appl. To/JPM No.: 58.0P.008.101 Student Name:
Step Action Standard Eva1 Comments 3 Review the prerequisites. Based on initial conditions, Determines all prerequisites have been met.
4 Review all precautions. Follows all precautions as applicable.
5 Prepare Plant for isolation in accordance with Based on initial conditions, determines Attachment A for A RPS, that this has already been done.
EVALUATOR NOTE:
Alternate Power Supply can supply only one RPS Bus at a time.
6 At Reactor Control Rod Test Instrument Panel 1C610: Verifies:
Check Alternate A Feed To RPS Bus A white Alternate A Fee( To RPS Bus A M, ,ite indicating light ILLUMINATED. indicating light LIT Check M-G Set Transfer switch in NORM position. RPS M-G Set Transfer switch HS-C72B-S1 in NORM position
- Critical Step #Critical Sequence Form NTP-QA91.8-2, Rev. 0.Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 5 of 8 Appl. To/JPM No.: 58.0P.008.101 Student Name:
- Comments Step Action Standard Eva1 EVALUATOR NOTE:
Following step must be Performed Slowly (approximately 2 seconds) to allow sufficient time for all expected actuations and isolations to occur prior to Transfer Switch reaching Alt A position. Multiple alarms will be received when M-G Set Transfer switch HS-C72B-S1 is placed in RPS ALT-A position.
- 7 Slowly Place RPS M-G Set Transfer switch Slowly Places RPS M-G Set Transfer HS-C72B-S1 in the ALT-A position. Switch HS-C72B-S1 in the ALT-A position.
8 Acknowledges the numerous alarms Depresses Silent and Reset pushbuttons for all panels in alarm.
9 Restore systems in accordance with Attachment C Selects Attachment C
- lo Reset A RPS half scram by Momentarily Positioning Places the RX SCRAM RESET switch to REACTOR SCRAM RESET HS-C72A-1SO5 to GRP the GRP 1/4 position then to the GRP 2/3 1/4 position and then to GRP 2/3 position. position and returns to the NORM position.
Verifies:
The following alarm is clear RPS CHANNEL 81/82 AUTO SCRAM, AR-104-A01.
- Critical Step #Critical Sequence Form NTP-QA91.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 6 of 8 Appl. To/JPM No.: 58.0P.008.101 Student Name:
Step Action Standard Eva1 Comments
- 11 Reset NSSSS isolation logic as follows: Depresses:
Depress MN STM LINE DIV 1 IS0 RESET MN STM LINE DIV 1 I S 0 RESET HS-B21-1S32. HS-B21-1S32.
Depress MN STM LINE DIV 2 I S 0 RESET MN STM LINE DIV 2 I S 0 RESET HS-B21-1S33. HS-B21-1S33.
12 Recover from RBCW isolation as follows: Verifies:
Ensure RRP A CLG WTR OB I S 0 VALVES Amber light LIT and red light NOT LIT for HV-18791A1 &A2 CLOSED. RRP A CLG WTR OB IS0 VALVES HV-18791A1 &A2 13 Ensure RRP B CLG WTR IB IS0 VALVES Verifies:
HV-18792A1&A2 CLOSED. Amber light LIT and red light NOT LIT for RRP B CLG WTR IB IS0 VALVES HV-18792A1&A2
- 14 Depress HV-18791A1 &A2 ISOLATION RESET. Depresses:
HV-18791A1&A2 ISOLATION RESET pushbutton
- 15 Depress HV-18792A1&A2 ISOLATION RESET. Depresses:
HV-18792A1&A2 ISOLATION RESET pushbutton
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 7 of 8 Appl. To/JPM No.: 58.0P.008.101 Student Name:
Step Action Standard Eva1 Comments 16 Ensure RRP A CLG WTR OB I S 0 VALVES Verifies:
HV-l879lAl&A2 OPEN. Amber light NOT LIT and red light LIT for RRP A CLG WTR OB I S 0 VALVES HV-18791A1 &A2 17 Ensure RRP B CLG WTR IB IS0 VALVES Verifies:
HV-18792A1&A2 OPEN. Amber light NOT LIT and red light LIT for RRP B CLG WTR IB I S 0 VALVES HV-18792A1&A2 18 Recover from CAC System isolation as follows: Verifies:
Ensure CONTN GAS ANLZR IB I S 0 LOOP A CONTN GAS ANLZR IB IS0 LOOP A HS-15740A CLOSED. HS-15740A Ensure CONTN GAS ANLZR OB IS0 LOOP A CONTN GAS ANLZR OB I S 0 LOOP A HS-15742A CLOSED. HS-15742A Amber lights LIT Red lights NOT LIT EVALUATOR CUE:
Role-play Shift supervision, and inform candidate that It is NOT desired to place A H202Analyzer in service 19 IF RHR Shutdown Cooling isolations were defeated, Determines RHR is NOT in Service Restore as follows
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0 , Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 8 of 8 Appl. To/JPM No.:58.0P.008.101 Student Name:
Step Action Standard Eva1 Comments
- 20 IF RWCU isolations were defeated, Restore as Contacts NPO to Close breaker follows: 16236-053 power supply to RWCU INLET IB IS0 HV-144-F001.
Close breaker 16236-053 power supply to RWCU INLET IB IS0 HV-144-FOOl.
EVALUATOR CUE:
Role-play the NPO and Acknowledge the request BOOTH CUE:
Depress pfs 3 MRF DB106360 CLOSE Contact PCO and inform the PCO that breaker 16236-053 power supply to RWCU INLET IB I S 0 HV-144-FOO1 is CLOSED EVALUATOR CUE:
Role-play Shift supervision, and inform candidate that another operator is available to complete Attachment C
This completes the JPM.
- Critical Step #Critical Sequence Form NTP-QA91.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Unit 1 is in Mode 1 at 68% power B. RPS Shorting Links are installed C. Attachment A of OP-158-001, RPS System, is complete D. RPS Alternate Power supply is available E. All required Tech Spec LCO entries have been made.
INITIATING CUE Transfer Power Supply from A RPS M-G Set to Alternate and restore plant systems, IAW the appropriate Attachment.
2005 NRC Exam Rev. 1 1 of2
TASK CONDITIONS A. Unit 1 is in Mode 1 at 68% power B. RPS Shorting Links are installed C. Attachment A of OP-158-001, RPS System, is complete D. RPS Alternate Power supply is available E. All required Tech Spec LCO entries have been made.
INITIATING CUE Transfer Power Supply from A RPS M-G Set to Alternate and restore plant systems, IAW the appropriate Attachment.
2005 NRC Exam Rev. 1 2 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 55.0N.007.152 0 10/4/05 201003 A2.01 3.413.6 APPl. JPM Number Rev. No. Date NUREG 1123 KIA No. KIA Imp.
To Sys. No.
Task
Title:
Respond To A Stuck Control Rod IAW ON-155-001 Completed By: Validated Rich Chin 1014105 Writer Date InstructorNV riter Date Approval:
Nuclear Trng. Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # / S.S.#
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
c Form NTP-QA-31.8-1,Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 55.0N.007.152 1
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES A. ON-155-001, CONTROL ROD PROBLEMS (Rev. 23)
B. Startup Sequence 82.
111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. Unit 1 is at 68% power B. A Plant Startup is in progress at Unit 1 IAW GO-100-102; step 5.75 has been completed.
V. INITIATING CUE The Unit Supervisor directs you to raise Reactor Power to 75% by SINGLE NOTCH Withdrawing Rods IAW startup sequence 82 beginning at step 554. Notify Reactor Engineering when 75%
power is achieved. Assume the p briefing for this power change has been completed.
VI. TASK STANDARD Rods 18 55, 42-07, and 18-07 withrdrawn to notch 12; Rod 42-55 withdrawn to notch 06 VILTASK SAFETY SIGNIFICANCE
~
Ability to safely add positive Reactivity with control rod motion Form NTP-QA-3 1.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
I I PERFORMANCE CHECKLIST Page 3 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments EVALUATOR NOTE:
0 Establish task conditions as directed on attached setup instructions.
0 Prepare a Startup Sequence 82 signed -off up to step 554.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
When student is ready to begin JPM, place the simulator in RUN.
Simulator Setup 0 MODE 1 68% IC.
0 Place Simulator in RUN 0 Run Display ROD 42-55 select Stuck Rod and Accept 0 Ensure FWFE is on the Venturis 0 Ensure PlCYS screen is on CRDA
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
(
PERFORMANCE CHECKLIST Page 4 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments
- l Selects Rod 18-55for withdraw Depresses 18 - 55 Verifies 18 and 55:
White lights - LIT Full core display reads notch 04
$2 Withdraws Rod 18-55to notch 12 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 06 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 08 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 10 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 12
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
1 I PERFORMANCE CHECKLIST Page 5 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action
-Eva1 Comments
__ ~ ~
- 3 Selects Rod 42-07 for withdraw Depresses 42-07 Verifies 42 and 07:
White lights - LIT Full core display reads notch 04
- 4 Withdraws Rod 42-07 to notch 12 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 06 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 08 Depresses WIDRAW ROD pushbutton Verifies:
Full core display changes to notch 10 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 12
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
i PERFORMANCE CHECKLIST Page 6 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments
- 5 Selects Rod 18-07 for withdraw Depresses 18-07 Verifies 18 and 07:
White lights - LIT Full core display reads notch 04
- 6 Withdraws Rod 18-07 to notch 12 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 06 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 08 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 10 Depresses W/DRAW ROD pushbutton Verifies:
Full core display changes to notch 12
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0,Page 1 of I 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 7 of 20 Appl. To/JPM No.: SIR0 55.0N.007.152 Student Name:
-Step Action Standard Comments
_ _ _ _ _ _ ~
$7 Selects Rod 42-55 for withdraw Depresses 42-55 Verifies 42 and 55:
White lights - LIT Full core display reads notch 04 FAULT STATEMENT:
ROD 42-55 WILL NOT MOVE IN THE NEXT STEP 8 Withdraws Rod 42-55 to notch 12 Depresses W/DRAW ROD pushbutton Verifies:
Full core display DID NOT CHANGE to notch 06 EVALUATOR CUE:
Candidate may request permission to attempt to move rod ONE MORE time before proceeding to the Off-Normal procedure. IF necessary, Role-play Unit Supervisor and grant permission to attempt ONE MORE withdrawal sequence.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2. Rev. 0, Page I of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 8 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
~~
Step Action Standard Eva1 Comments Proceed to applicable section of OFF-Normal Determines step 3.3 is applicable based on initial procedure ON-155-001, Control Rod Problems as conditions.
indicated.
Stuck Control Rod Step 3.3 Rod Drift or Rod Scram Step 3.4 Rod Overtravel Step 3.5 Mispositioned Rod Step 3.6 Multiple Rod Notching Step 3.7 Slow to Settle Rod Step 3.8 NOTE:
Rx Engineering notification is desired, when this section is performed because a control rod has failed to settle properly.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 9 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard
-Eva1 Comments IF rod position indication does not change when valid Uses any 3 of the following to confirm Rod 42-55 is withdraw OR insert signal applied, Perform the STILL AT NOTCH 4 following:
Confirm control rod position using any 3 of the available rod position indication as follows: FULL IN/FULL OUT DISPLAY push button.
0 CRT and SIP 4 ROD DISPLAY. 0 OD7 0 FULL IN/FULL OUT DISPLAY push button. Alarm logging printer, System Event Display Message
- OD7 RSCS Display when below Low Power Alarm 0 Alarm logging printer, System Event Display Point.
Message RWM Main Display when below Low Power 0 RSCS Display when below Low Power Alarm Alarm Point.
Point.
0 RWM Main Display when below Low Power Alarm Point.
CAUTION Scramming a stuck control rod will cause damage to CRD mechanism.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0. Page 1 of I 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 10 of 20 Appl. To/JPM No.: S/RO 55.ON.007.152 Student Name:
I I I Action Standard Eva1 I Comments I
NOTE:
If reactor is shutdown and exercising of rods is being performed in accordance with an approved procedure, double clutching with continuous withdraw may be used (per step (l)(a)2), below) with Shift Supervision approval.
I I I
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 11 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments 11 IF rod failed to withdraw: Simultaneously Momentarily Depresses the:
W/DRAW ROD Attempt to operate drive by:
0 CONTINSERT
>erform either 1) OR 2) below:
pushbuttons 1 . Depress withdraw rod pushbutton.
AND/OR
?. With Shift Supervision approval, Depress withdraw and continuous withdraw rod pushbuttons. Requests permission from Unit Supervisor to Depress withdraw and continuous withdraw rod pushbuttons EVALUATOR CUE:
Simultaneously Momentarily Depresses the:
Role-play Unit Supervisor and grant permission to Depress withdraw and continuous withdraw rod 0 W/DRAW ROD pushbuttons. 0 CONT W/DRAW ROD Simultaneously Momentarily Depress the continuous 0 CONTINSERT insert AND withdraw pushbuttons to Withdraw rod to appropriate position (one notch at power). pushbuttons Uses the following to confirm Rod 42-55 is STILL AT NOTCH 4 0 CRT and SIP 4 ROD DISPLAY.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
I I PERFORMANCE CHECKLIST Page 12 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments 12 IF rod position does not change on 4 rod display, Uses any 3 of the following to confirm Rod 42-55 is Confirm control rod position using available rod STILL AT NOTCH 4 position indications.
0 FULL IN/FULL OUT DISPLAY push button.
0 OD7 0 Alarm logging printer, System Event Display Message RSCS Display when below Low Power Alarm Point.
0 RWM Main Display when below Low Power Alarm Point.
13 -
IF rod failed to move, Attempt to move control rod, as Records the following on Attachment A follows: Date Time Complete rod data on Attachment A.
Rod 42-55 Position 04 Reactor Pressure
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0, Page I of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 13 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action ~ ~
Standard Eva1 Comments
- 14 -
In 50 psid increments, Increase drive water pressure Places DRIVE WTR PRESS THLTG PV-146FOO3 to CLOSE AND UNTIL Perform following at each increment until 5 350 psid reached: DRIVE WATER DlFF PRESSURE PDI-Cl2-1R602 INCREASES FROM -250 TO 300 PSlD CAUTION Elevated drive pressure increases the risk of multiple notch movement.
15 Attempt to operate drive one notch in intended Depresses W/DRAW ROD pushbutton direction, authorized by procedure governing original Verifies:
Control Rod motion, while observing drive water flows Full core display FOR ROD 42-55 DID NOT CHANGE (4 gpm inserV2.5 gprn withdraw). to notch 06 AND EVALUATOR CUE:
Normally, another operator would be assigned to Verifies:
observe drive water flows. If necessary, inform DRIVE WATER FLOW FI-CI2-1R604 RAISE to -2.5 candidate that drive water flow was 2.5 gpm during the gpm withdrawal attempt.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
I i i PERFORMANCE CHECKLIST Page 14 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments 16 IF rod position does not change on 4 rod display, Uses the following to confirm Rod 42-55 is STILL Confirm control rod position using available rod position AT NOTCH 4 indications. 0 CRT and SIP 4 ROD DISPLAY.
0 FULL IN/FULL OUT DISPLAY push button.
0 OD7 Alarm logging printer, System Event Display Message 0 RSCS Display when below Low Power Alarm Point.
0 RWM Main Display when below Low Power Alarm Point.
NOTE:
IF reactor is shutdown AND exercising of rods is being performed in accordance with an approved procedure, double clutching with continuous withdraw may be used (per step (c)l)b), below) with Shift Supervision approval.
- Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NKC Exam Rev. I
f (
PERFORMANCE CHECKLIST Page 15 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments 17 IF rod failed to withdraw: Simultaneously Momentarily Depresses the:
W/DRAW ROD Attempt to operate drive by:
CONTINSERT
'erform either 1) OR 2) below:
pushbuttons
- 1. Depress withdraw rod pushbutton.
AND/OR
- 2. With Shift Supervision approval, Depress withdraw and continuous withdraw rod pushbuttons. Requests permission from Unit Supervisor to Depress withdraw and continuous withdraw rod pushbuttons EVALUATOR CUE:
Simultaneously Momentarily Depresses the:
Role-play Unit Supervisor and grant permission to Depress withdraw and continuous withdraw rod W/DRAW ROD pushbuttons. CONT W/DRAW ROD Simultaneously Momentarily Depress the continuous CONTINSERT insert AND withdraw pushbuttons to Withdraw rod to appropriate position (one notch at power). pushbuttons Uses the following to confirm Rod 42-55 is STILL AT NOTCH 4 0 CRT and SIP 4 ROD DISPLAY.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
! i PERFORMANCE CHECKLIST Page 16 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Eva1 Comments 18 IF rod position does not change on 4 rod display, Uses any 3 of the following to confirm Rod 42-55 is Confirm control rod position using available rod STILL AT NOTCH 4 position indications.
0 FULL IN/FULL OUT DISPLAY push button.
OD7 0 Alarm logging printer, System Event Display Message 0 RSCS Display when below Low Power Alarm Point.
0 RWM Main Display when below Low Power Alarm Point.
19 Repeat as necessary, until 350 psid Determines it will be necessary to raise drive water another 50 psid.
BOOTH CUE:
Remove ROD 42-55 Stuck Rod malfunction
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0,Page 1 of I 2005 NRC Exam Rev. 1
I /
PERFORMANCE CHECKLIST Page 17 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
-Step Action Standard Eva1 Comments
- 20 In - 50 psid increments, Increase drive water pressure Places DRIVE WTR PRESS THLTG PV-146FOO3 to CLOSE AND UNTIL Perform following at each increment until 5 350 psid reached: DRIVE WATER DlFF PRESSURE PDI-C12-1R602 INCREASES FROM -300 TO 350 PSlD CAUTION Elevated drive pressure increases the risk of multiple notch movement.
- 21 Attempt to operate drive one notch in intended Depresses W/DRAW ROD pushbutton direction, authorized by procedure governing original Verifies:
Control Rod motion, while observing drive water flows Full core display FOR ROD 42-55 CHANGES to notch (4 gpm insed2.5 gpm withdraw). 06 AND EVALUATOR CUE:
Normally, another operator would be assigned to Verifies:
observe drive water flows. If necessary, inform DRIVE WATER FLOW FI-C12-1R604 RAISE to -2.5 candidate that drive water flow was 2.5 gpm during the gPm withdrawal attempt.
Reports ROD 42-55 is at NOTCH 06 to Unit Supervisor
- Critical Step #Critical Sequence Form NTP-QA-31.8-2.Rev. 0, Page I of I 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 18 of 20 Appl. To/JPM No.: S/RO 55.ON.007.152 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
Role-play Unit Supervisor and acknowledge the report and direct candidate to complete the ON procedure 22 IF rod moves one notch in intended direction, Go to Proceeds to step 3.3.1 .f.
step 3.3.1 .f.
23 Record drive water pressure required to move control Records the following on Attachment A:
rod on Attachment A.
350 psid drive water pressure required to move control rod 24 Record drive water flow that is indicated while Records the following on Attachment A:
attempting to move stuck control rod on Attachment A.
Indicated drive water flow required to move control rod
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam Rev. I
I I PERFORMANCE CHECKLIST Page 19 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments NOTE (1):
control rod testing is being performed IAW TP-055-001 or TP-055-006, multiple control rod notch movement is allowed at elevated drive water pressure.
Drive water pressure must be returned to 250 psid prior to testing next control rod.
NOTE (2):
Multiple notch movement is permitted for control rods with identified friction (except during startup single notch restraint). If excessive control rod speed is observed, control rod movement must be stopped and drive pressure returned to 250 psid.
3r 25 -
Return drive water pressure to 250 psid, for each Places DRIVE WTR PRESS THLTG PV-146FOO3 to OPEN subsequent rod notch. Document on Attachment A.
UNTIL DRIVE WATER DlFF PRESSURE PDI-C12-1R602 INCREASES FROM -250 PSlD AND Records the following on Attachment A:
250 psid
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 20 of 20 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
This completes the JPM
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Unit 1 is at 68% power B. A Plant Startup is in progress at Unit 1 IAW GO-100-102; step 5.75 has been completed.
INITIATING CUE The Unit Supervisor directs you to raise Reactor Power to 75% by SINGLE NOTCH Withdrawing Rods IAW startup sequence 82 beginning at step 554. Notify Reactor Engineering when 75% power is achieved. Assume the p briefing for this power change has been completed.
Page 1 of 2 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Unit 1 is at 68% power B. A Plant Startup is in progress at Unit 1 IAW GO-100-102; step 5.75 has been completed.
INITIATING CUE The Unit Supervisor directs you to raise Reactor Power to 75% by SINGLE NOTCH Withdrawing Rods IAW startup sequence 82 beginning at step 554. Notify Reactor Engineering when 75% power is achieved. Assume the p briefing for this power change has been completed.
Page 2 of 2 2005 NRC Exam Rev. I
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 52.0P.009.151 0 1014105 206000 A4.14 4.214.1 Apple JPM Number Rev. No. Date NUREG 1123 KIA No. KIA Imp.
To Sys. No.
Task
Title:
Override An Inadvertent Start Of The HPCl System In Accordance With OP-152-001 Completed By: Validated Rich Chin 10/4/05 Writer Date InstructorNVriter Date App rovaI:
Nuclear Trng. Supv. Date 10 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # I S.S. #
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-3 I .8- I , Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 52.0P.009.151
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES A. OP-152-001, High Pressure Coolant Injection (HPCI) System (Rev. 36) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. The plant is in Condition 1 at approximately 68 percent reactor power.
- 8. An inadvertent HPCl initiation has occurred.
V. INITIATING CUE Override HPCl injection IAW the appropriate Hardcard VI. TASK STANDARD HPCl injection stopped with HPCl turbine shutdown.
VII. TASK SAFETY SIGNIFICANCE Ability to control RPV water level.
Form NTP-QA-3 1.8- 1, Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
I (
PERFORMANCE CHECKLIST Page 3 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Student Name:
~ ~
Step Action Standard Eva1 Comments EVALUATOR NOTE:
Establish task conditions as directed on attached setup instructions.
The IC MUST be set up such that an inadvertent HPCl initiation has just occurred AND no action has yet been taken.
A malfunction or override should be used to prevent manual override of HPCl injection, requiring the operator to isolate HPCI.
With the given the Task Conditions/lnitiating Cue Sheet and allowed to observe the panel.
When student is ready to begin JPM, place the simulator in RUN.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
1 Candidate refers to appropriate procedural section. OP-158-001 Attachment C step 2
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0,Page I of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 4 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Student Name:
Step Comments Action Standard Eva1 To stop injection place HPCl pump on minimum flow as Places the control switch for HPCl Aux Oil Pump 1P213 follows: in the START position.
0 Place or CHECK PLACED HPCl AUXILIARY OIL PUMP 1P213 switch to START.
FAULT STATEMENT HPCl INJECTION FLOW WILL NOT DECREASE TO ZERO WHEN PRESSURE IS REDUCED TO LESS THAN REACTOR PRESSURE.
Place HPCl TURBINE FLOW CONTROL FC E41 Places the ManuaVAuto switch on HPCl Turbine Flow 1R600 in MANUAL. Control FC-E41-1R600 to the M position Adjust HPCl TURBINE FLOW CONTROL FC E41 Depresses the Close pushbutton on HPCl Turbine 1R600 to reduce HPCl discharge pressure less than Flow Control FC-E41-1R600 until the HPCl pump Reactor pressure. discharge pressure is less than reactor pressure.
Verifies:
HPCl PP DISCH PRESS PI-E41-1R601 pressure is GREATER THAN any RPV pressure indication
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
j PERFORMANCE CHECKLIST Page 5 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Student Name:
-Step Action Standard Eva1 Comments 5 Ensure HPCl MIN FLOW TO SUPP POOL HV 155 Verifies:
F012 opens when HPCl flow < 500 gpm and discharge pressure > 125 psig. HPCl MIN FLOW TO SUPP POOL HV 155 F012 Red light - NOT LIT Amber light - LIT AND HPCl Flow FI-E41-1R600-1 is STI I INDICATED 6 IF HPCl flow indication does not decrease to zero gpm Determines:
with HPCl pump discharge pressure less than reactor pressure, Shut Down HPCl per following step. HPCl will need Shutdown IAW next step 7 To stop injection/shutdownHPCI: Previously performed Ensure HPCl AUXILIARY PUMP 1P213 switch placed to START.
8 Depress HPCl INT SIG RESET HS E41 1S17 RESET Depresses:
pushbutton.
HPCl INT SIG RESET HS E41 1S17 RESET IF HPCl initiation resets, Shut Down HPCl in pushbutton accordance with "Shutdown" section of OP 152 001.
Verifies:
Green light - LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 N R C Exam Rev. 1
i 1 PERFORMANCE CHECKLIST Page 6 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Student Name:
~~
Step Action Standard Eva1 Comments 9 IF HPCl initiation does not reset, stop injectionhhut Determines HPCl initiation did NOT reset down using following sections (1)preferred, OR (2):
Verifies HPCl INT SIG RESET HS E41 1 S17 RESET Green light - LIT EVALUATOR NOTE:
HPCl Flow controller steps were previously performed and were unsuccessful, candidate should proceed to Isolate HPCl per section 2.2
- io To isolate HPCI: Depresses:
Depress HPCl STM SUPPLY MAN I S 0 HS E41 1S32 HPCl STM SUPPLY MAN I S 0 HS E41 1S32 pushbutton. pushbutton
- 11 Ensure HPCl STM SUPPLY OB IS0 HV 155 F003 Inserts key into keylock switch HPCl STM SUPPLY OB CLOSES. I S 0 HV 155 F003 and places to CLOSE position Verifies:
Red light - NOT LIT Amber light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 7 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Student Name:
Step Action Standard Eva1 Comments 12 Ensure HPCl PUMP SUCT FROM SUPP POOL HV Verifies:
155 F042 CLOSES.
PUMP SUCT FROM SUPP POOL HV 155 F042 Red light - NOT LIT Amber light - LIT 13 Ensure HPCl INJECTION HV 55 F006 CLOSES. Verifies:
HPCl INJECTION HV 155 F006 Red light - NOT LIT Amber light - LIT 14 Ensure HPCl AUX OIL PUMP P213 starts as HPCl Verifies:
turbine coasts down.
HPCl AUX OIL PUMP 1P213 Red light - LIT Amber light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0,Page 1 of I 2005 N R C Exam Rev. 1
PERFORMANCE CHECKLIST Page 8 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Student Name:
Step Action Standard Eva1 Comments
~
$15 Close HPCl STM SUPPLY IB I S 0 HV 155 F002. Places:
HPCl STM SUPPLY IB IS0 HV 155 F002 to CLOSE AND Verifies:
Red light - NOT LIT Amber light - LIT 16 Place HPCl STM SUPPLY OB IS0 HV 155 F003 Previously completed in step 11 of this JPM KEYSWITCH to CLOSE.
EVALUATOR CUE:
This completes the JPM
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. 1
TASK CONDITIONS A. The plant is in Condition 1 at approximately 68 percent reactor power.
B. An inadvertent HPCl initiation has occurred.
INITIATING CUE Override HPCl injection IAW the appropriate Hardcard Page 1 of 2 2005 NRC Exam Rev. 1
TASK CONDITIONS
- A. The plant is in Condition 1 at approximately 68 percent reactor power.
B. An inadvertent HPCl initiation has occurred.
INITIATING CUE Override HPCl injection IAW the appropriate Hardcard Page 2 of 2 2005 NRC Exam Rev. 1
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE
- APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 45.0P.004.151 0 1014105 259001 A3.10 3.413.4 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
To Sys. No.
Task
Title:
Commence Feeding with an additional RFPIShutdown RFP due to High vibrations Completed By: Validated Rich Chin 1014105 Writer Date InstructorNVriter Date Approval:
Nuclear Trng. Supv. Date 15 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee ##IS.S. ##
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 45.0P.004.151
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES OP-145-001, RFP and RFP Lube Oil System (Revision 42) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
NONE IV. TASK CONDITIONS A. Unit 1 is @ 68% power with a plant startup in progress.
B. RFP A and B are feeding the RPV in Automatic level control C. RFP C has been started and warmed, and is ready to feed the RPV.
D. Feedwater venturies selected as input to PlCSY Core Thermal Power Heat Balance.
V. INITIATING CUE Commence feeding the RPV with RFP C IAW with the appropriate procedure.
VI. TASK STANDARD RFP C is shutdown and isolated, with RFP A and B in automatic level control VII. TASK SAFETY SIGNIFICANCE Failure to secure the RFP could lead to unacceptable RPV water level fluctuations, or catastrophic failure of the RFP.
Form NTP-QA-31.8-1, Rev. 0 , Page 2 of 2 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 3 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Comments From any 68% power IC Insert Y PPJLONRCJPMFGH Places F condensate Demin in service IOR QDIHSS116OOF SRVC C RFP TURBINE HI VIBRATION TO 4.2 MILS OVER 15 SECONDS 0 PFS 9 IMF FW145007C 4.2 15 0 0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
0 Verify Feedwater venturies as input to PlCSY Core Thermal Power Heat Balance IC-182 OR 183 for LOC-21 NRC Exam 1 Locates correct procedure. Obtains controlled copy of OP-145-001 2 References correct procedure section. Refers to section 2.5 3 Reviews prerequisites Reviews prerequisites
- Critical Step #Critical Sequence F o n NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 4 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step EVALUATOR CUE:
Action Standard Comments If necessary, Inform candidate that all prerequisites have been met.
4 Reviews Precautions Reviews Precautions 5 ChecWEstablish RFP C discharge pressure 50 - Verifies:
100 psig below Reactor pressure as follows:
RFP C discharge pressure is 50-100 psig below Increase RFP/T C speed using RFP CSPD Reactor pressure CTUDEMAND SIGNAL SIC-C32-1R601C controller, AND Throttle FV 10604C using RX FEED PUMP C RECIRC FLOW FIC-10604C in MANUAL to maintain RFP C FLOW FI-lO604C indication greater RFP C MIN FLOW SET PT FI-10612C indication.
6 Check RFP C discharge temperature Verifies:
approximately equal to in-service reactor feed pump discharge temperature as indicated on RFP DSCH TEMP TR-10608 reactor feed pump RFP DSCH TEMP TR-10608. discharge temperatures are all approximately equal
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 5 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments 7 IF feeding with second feed pump and not Verifies RFP C START UP IS0 HV-10651C already performed per GO-100-002, Ensure Red light - NOT LIT following:
Amber Light - LIT RFP C START UP IS0 HV-10651C CLOSED.
AND RFP C DSCH IS0 HV-10603C OPEN by depressing OPEN push button. RFP C DSCH I S 0 HV-10603C Red light -LIT Amber Light - NOT LIT a Perform following to feed Reactor Vessel with Contacts NPO to Restore a Hydrogen Injection RFP C: string to service IAW HWC OPERATION When Placing Additional Reactor Feed Pump C In IF placing a RFP in service with HWC in service Service section of OP-145-002 in Power Determine Setpoint Mode, Restore a Hydrogen Injection string to service IAW HWC OPERATION When Placing Additional Reactor Feed Pump C In Service section of OP-145-002.
EVALUATOR CUE:
Role-play NPO and acknowledge the request.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 6 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments 9 Adjust RFP C SPD CTUDEMAND SIGNAL SIC- Depresses INC pushbutton on :
C32-1R601C controller to increase turbine speed until incoming pump just begins to feed. RFP C SPD CTUDEMAND SIGNAL SIC-C32-1R601C controller Until FEEDFLOW is observed 10 Monitor Reactor Vessel level to ensure it Monitors Reactor Vessel level to ensure it remains stable. remains stable.
FAULT STATEMENT:
When the candidate begins the next step, the Hi Vibration alarm will annunciate. The candidate should refer to the AR.
BOOTH OPERATOR CUE:
Insert PFS 9 IMF FW145007C 4.2 15 0 C RFP TURBINE HI VIBRATION TO 4.2 MILS OVER 15 SECONDS DO NOT INCREASE to 5 mils, this would require tripping of the pump.
Monitor vibration, increase malfunction magnitude until alarm is received.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 8 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
Role-play Unit supervisor and direct candidate to Shutdown RFP C IAW appropriate procedure.
Field report suggests unusual noises and vibrations at the RFP 14 References correct procedure section. Refers to OP-145-001 section 2.6 15 Reviews prerequisites Reviews prerequisites EVALUATOR CUE:
If necessary, Inform candidate that all prerequisites have been met.
16 IF less than three reactor feed pumps will be in Determines from initial conditions that service, Direct Shift Technical Advisor to Feedwater venturies are already selected as SELECT Feedwater venturies as input to PlCSY input to PlCSY Core Thermal Power Heat Core Thermal Power Heat Balance (OD3) in Balance.
accordance with 01-TA-021, Selection of Feedwater Inputs for Calculation of Core Thermal Power.
- Critical Step #Critical Sequence Form NTP-OA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 9 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments
~
17 IF RFP A or B is to be shut down, Realign to Determines this step to be N/A.
the appropriate RFP OR Shut Down Depleted Zinc Oxide (DZO) Injection System in accordance with OP-144-001.
18 Remove Hydrogen Injection String from service Contacts NPO to Remove a Hydrogen Injection for Reactor Feed Pump being Shutdown IAW string to service IAW HWC OPERATION When HWC System Power Operations section of OP- Placing Additional Reactor Feed Pump C In 145-002. Service section of OP-145-002 EVALUATOR CUE:
Role-play NPO and acknowledge the request.
19 Monitor Reactor Vessel level closely to insure Monitors Reactor Vessel level to ensure it Reactor Feed Pump(s) left in service will remains stable.
maintain reactor vessel level.
NOTE:
A Recirculation Flow Controller FIC-10604 demand signal of 40 will provide pump with adequate minimum flow.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
j PERFORMANCE CHECKLIST Page 10 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Action Standard Eva1 Comments Step 20 Place RFP C SPD CTUDEMAND SIGNAL SIC- Verifies:
C32-1R601C in MANUAL.
RFP C SPD CTUDEMAND SIGNAL SIC-C32-1R601C Amber M light - LIT 21 Slowly Adjust RX FEED PUMP C RECIRC Verifies RX FEED PUMP C RECIRC FLOW FLOW FIC-10604C in MANUAL to - 40% FIC-10604C switch in M position demand.
AND Depresses OPEN Pushbutton on RX FEED PUMP C RECIRC FLOW FIC-10604C until -
40% demand is achieved.
22 Slowly Decrease RFPR C speed using RFP C Depresses DEC Pushbutton on SPD CTL /DEMAND SIGNAL SIC-C32-1R601C controller to obtain RFP C discharge pressure - RX FEED PUMP C RECIRC FLOW FIC-10604C controller 100 psig below reactor pressure; AND Until RFP C discharge pressure is 50 100 psig below Reactor pressure 23 Throttle FV 10604C using RX FEED PUMP C Depresses Open/Close Pushbuttons on RX RECIRC FLOW FIC-10604C in MANUAL to FEED PUMP C RECIRC FLOW FIC-10604C to maintain RFP C FLOW FI-lO604C indication maintain RFP C FLOW FI-lO604C indication greater RFP C MIN FLOW SET PT FI-10612C greater RFP C MIN FLOW SET PT FI-lO612C indication. indication
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 11 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Comments 24 Monitor Rx Vessel level closely and Maintain Monitors Reactor Vessel level to ensure it level with in service pump(s). remains stable.
25 IF Reactor Feed Pump to be placed in Standby Determines step to be N/A on minimum flow during Low Load Operations, Perform following:
26 IF Reactor Feed Pump C to be Verifies:
trippedshutdown:
RFP C discharge pressure is - 100 psig below Ensure Reactor Feed Pump C discharge Reactor pressure pressure - 100 psig below Reactor pressure.
- 27 Close/Check Closed RFP C DSCH I S 0 HV-10603C.
Depresses CLOSED pushbutton on RFP C DSCH IS0 HV-10603C.
Verifies:
Red light - NOT LIT Amber Light - LIT 28 Close :heck Closet RFP START UP IS0 HV- Verifies:
10651C.
RFP START UP IS0 HV-10651C.
Red light - NOT LIT Amber Light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 12 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments f 29 Ensure or Slowly Decrease turbine speed to Depresses DEC Pushbutton on:
EAP LOW SPEED STOP (- 1850 rpm), THEN RFP C SPD CTUDEMAND SIGNAL SIC-C32-1R601C controller Until RFP C turbine speed is at EAP LOW SPEED STOP (- 1850 rpm)
I30 Trip RFPT C at RFPT C TRIP RESET HS- Depresses TRIP pushbutton on:
127452.
RFPT C TRIP RESET HS-12745C.
Verifies:
Red light - NOT LIT Amber Light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0.Page 1 of 1 2005 NRC Exam Rev. 1
/
PERFORMANCE CHECKLIST Page 13 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments 31 At 1C668, Observe following: Verifies:
RFPT C LP I S 0 HV-127096 CLOSES. Red light - NOT LIT RFPT C HP IS0 HV-1271OC CLOSES. Amber Light - LIT RFPT C FIRST STAGE DRN HV- For the following valves:
12717C OPENS.
RFPT C LP IS0 HV-127096 RFP C DSCH CKV HV-10606C RFPT C HP IS0 HV-1271OC CLOSES.
RFP C DSCH CKV HV-10606C AND Red light - LIT Amber Light - NOT LIT RFPT C FIRST STAGE DRN HV-12717C
Depresses FAST pushbutton on:
LOWER RFP C MTR SPD CHANGER, HS-1273061 until:
RFPT C MTR SPD CHANGER at LOW SPEED STOP AMBER (LSS) light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 14 of 14 Appl. To/JPM No.: 45.0P.004.151 Student Name:
Step Action Standard Eva1 Comments 33 Ensure RFPT C MTR SPD CHANGER at LOW Verifies:
SPEED STOP by only Amber (LSS) light ILLUMINATED above RFPT C MTR SPD RFPT C MTR SPD CHANGER at LOW SPEED STOP AMBER (LSS) light - LIT CHANGER push buttons or locally on upper stop.
NOTE:
Decreasing (SIC-C32-1 R601 A,B,C) SPD CTUDEMAND SIGNAL to less than O, may cause RFPT Control Signal Failure to annunciate.
34 Ensure RFP C SPD CTUDEMAND SIGNAL Verifies:
SIC- C32-1R601C in MANUAL with speed RFP C SPD CTUDEMAND SIGNAL SIC-C32-output signal (horizontal meter) set at 0.
1R601C Amber M light - LIT AND Speed output signal (horizontal meter) set at 0
- 35 Close FV 10604C using RX FEED PUMP C RECIRC FLOW FIC-10604C in MANUAL.
Depresses CLOSE pushbutton on RX FEED PUMP C RECIRC FLOW FIC-10604C until it reaches zero demand.
EVALUATOR CUE:
This completes the JPM
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Unit 1 is Q 68% power with a plant startup in progress.
B. RFP A and B are feeding the RPV in Automatic level control C. RFP C has been started and warmed, and is ready to feed the RPV.
D. Feedwater venturies selected as input to PlCSY Core Thermal Power Heat Balance.
INITIATING CUE Commence feeding the RPV with RFP C IAW with the appropriate procedure.
2005 NRC Exam Rev. 1 1 of2
TASK CONDITIONS A. Unit 1 is Q 68% power with a plant startup in progress.
B. RFP A and B are feeding the RPV in Automatic level control C. RFP C has been started and warmed, and is ready to feed the RPV.
D. Feedwater venturies selected as input to PlCSY Core Thermal Power Heat Balance.
INITIATING CUE Commence feeding the RPV with RFP C IAW with the appropriate procedure.
2005 NRC Exam Rev. 1 2 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 00.ON.015.104 0 09/28/05 2950 16 AA1.07 4.014.0 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
To Sys. No.
Task
Title:
Establish and Maintain Reactor Pressure With SRVs from the RSDP IAW ON-100-009 Completed By: Validated Rich Chin 09/28/05 Writer Date InstructorNVriter Date Approval:
Nuclear Trng. Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # / S.S. #
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-3 I .8-1, Rev. 0. Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 00.ON.015.104
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES A. ON-100-009, Control Room Evacuation (Rev. 10)
III. REACTIVITY MAN1PULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. A Hazardous GAS condition exists in the control room requiring abandonment of the Control Room.
B. ON-100-009, Control Room Evacuation has been completed through step 4.2.
C. Reactor vessel water level is being maintained by RCIC.
D. Reactor pressure is being maintained by SRVs cycling.
V. INITIATING CUE Transfer control to the RSDP and commence a RCS cooldown NOT TO EXCEED 1OO"F/Hr with SRVs from the Remote Shutdown Panel beginning at step 4.3 of ON-100-009, Control Room Evacuation.
VI. TASK STANDARD Control transferred to the RSDP and a RCS cooldown 5 1OO°F/Hr is commenced.
VILTASK SAFETY SIGNIFICANCE Ability to cooldown the RPV at less than Tech Spec maximum allowed rate; provide control power to critical plant equipment at the RSDP.
Form NTP-QA-31.8-1,Rev. 0. Page 2 of 2 2005 NRC Exam Rev. 1
1 I PERFORMANCE CHECKLIST Page 3 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Comments EVALUATOR NOTE:
Establish task conditions as directed on attached setup instructions.
IC-20 Place Mode SW to S/D S/D CRD pump to avoid 5 4 level and excessive vessel C/D Place IRMs to range 1 Perform ON-100-009 up to step 4.2 Snap into an IC for the JPM Prepare a signed-off copy of ON-100-009, Control Room Evacuation up through step 4.2 When student is ready to begin JPM, place the simulator in RUN.
EVALUATOR CUE:
Provide candidate with a signed-off copy of ON-100-009, Control Room Evacuation up through step 4.2.
EVALUATOR NOTE:
Student may review previous sections of procedure.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page I of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 4 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Action Standard Eva1 Comments Candidate refers to appropriate procedural section. Candidate refers to ON-100-009, Control Room Evacuation step 4.3.
Upon arrival at Remote Shutdown Panel, Perform following to determine plant status and gain control of critical systems:
NOTE:
Since the laptop is for monitoring purposes only, this should not impact completing the following steps to gain control of the plant.
As time and manpower allows, Connect the PlCSY Requests STA to begin Connecting the PlCSY laptop laptop per Attachment E. per Attachment E.
EVALUATOR CUE:
Inform the candidate that the STA will commence Connecting the PlCSY laptop per Attachment E.
NOTE:
Attachment D contains lists of all functions performed by placing transfer switches to EMERG position.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 5 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
~
Step Action Standard Eva1 Comments
- 4 Transfer control to Remote Shutdown Panel as follows, Places:
Observe Green Light ILLUMINATES for each transfer HSS-14901A INSTR TRANSFER SWITCH A INSTR switch when placed in EMERG position: SET 1,2 in EMERG position Place HSS-14901A INSTR TRANSFER SWITCH A INSTR SET 1,2 in EMERG position (located near the Verifies:
top center of the panel). Green Light - LIT Red Light - NOT LIT
- 5 Place HSS-15110A INSTR TRANSFER SWITCH B Places:
INSTR SET 3, 4 in EMERG position (located near the HSS-15110A INSTR TRANSFER SWITCH 6 INSTR SET 3, 4 in EMERG position top right of the panel).
Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of I 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 6 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments Transfer HSS-14902A CONTROL TRANSFER SWITCH Verifies:
A as follows: 1P-220 BAROMETRIC CDSR COND PUMP Control switch in AUTO.
Ensure 1P-220 BAROMETRIC CDSR COND PUMP THEN aligned to AUTO.
Places:
HSS-14902A CONTROL TRANSFER SWITCH A in Place HSS-14902A CONTROL TRANSFER SWITCH A EMERG position in EMERG position.
Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam Rev. I
I 1 PERFORMANCE CHECKLIST Page 7 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments
- 7 Transfer HSS-149028 CONTROL TRANSFER SWITCH Verifies:
M as follows: HV-149-F059 TURB EXH TO SUPP POOL in OPEN.
1P-219 BAROMETRIC VACUUM PUMP Control switch Ensure HV-149-FO59 TURB EXH TO SUPP POOL in STOP.
aligned to OPEN.
Ensure 1P-219 BAROMETRIC VACUUM PUMP aligned to STOP. THEN Places:
Place HSS-149028 CONTROL TRANSFER SWITCH M HSS-14902B CONTROL TRANSFER SWITCH M in in EMERG position. EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
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PERFORMANCE CHECKLIST Page 9 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments Place HSS-14904A CONTROL TRANSFER SWITCH C Places:
in EMERG position. HSS-14904A CONTROL TRANSFER SWITCH C in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT Place HSS-14905A CONTROL TRANSFER SWITCH D Places:
in EMERG position. HSS-14905A CONTROL TRANSFER SWITCH D in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form N"-QA-3 1.8-2, Rev. 0. Page I of I 2005 NRC Exam Rev. 1
i W
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I PERFORMANCE CHECKLIST Page 11 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
~
Action Standard Eva1 Comments Place HSS-15112B CONTROL TRANSFER SWITCH S Places:
in EMERG position. HSS-151126 CONTROL TRANSFER SWITCH S in EMERG position Verifies:
Green Light - LIT Red Light - NOT IT Place HSS-15113A CONTROL TRANSFER SWITCH G Places:
in EMERG position. HSS-15113A CONTROL TRANSFER SWITCH G in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT Transfer HSS-151138 CONTROL TRANSFER SWITCH Verifies:
T as follows: HV-151-F006B SHUTDOWN CLG SUCT in CLOSE.
Ensure HV-151-F0066 SHUTDOWN CLG SUCT aligned to CLOSE.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 12 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments NOTE:
Indication for HV-151-FO1OB RHR LOOP B CROSSTIE will not illuminate due to supply breaker being open.
Ensure HV-151-FO1OB RHR LOOP B CROSSTIE Verifies:
aligned to CLOSE. HV-151-FO1OB RHR LOOP B CROSSTIE in CLOSE.
Place HSS-15113B CONTROL TRANSFER SWITCH T THEN in EMERG position.
Places:
HSS-15113B CONTROL TRANSFER SWITCH T in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT Verifies:
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 13 of 26 Appl. To/JPM No.: SIR0 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments Transfer HSS-15114A CONTROL TRANSFER SWITCH Verifies:
H as follows: HV-151-FO04B RHR PUMP B SUCT in OPEN.
THEN Ensure HV-151-F004B RHR PUMP B SUCT aligned to OPEN. Places:
Place HSS-15114A CONTROL TRANSFER SWITCH H HSS-15114A CONTROL TRANSFER SWITCH H in in EMERG position. EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT Transfer HSS-151148 CONTROL TRANSFER SWITCH Verifies:
U as follows: SV-12605 INSTR GAS CMP OB SUCT IS0 in OPEN.
THEN Ensure SV-12605 INSTR GAS CMP OB SUCT I S 0 aligned to OPEN. Places:
Place HSS-151148 CONTROL TRANSFER SWITCH U HSS-151148 CONTROL TRANSFER SWITCH U in in EMERG position. EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form NIT-QA-3 1.8-2, Rev. 0,Page I of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 14 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step
~~ -
Action Standard Eva1 Comments
- 20 Place HSS-15115A CONTROL TRANSFER SWITCH J Places:
in EMERG position. HSS-15115A CONTROL TRANSFER SWITCH J in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- 21 Transfer HSS-151158 CONTROL TRANSFER SWITCH Verifies:
V as follows: HV-151-FO476 HX 6 SHELL SIDE INLET in OPEN.
THEN Ensure HV-151-FO478 HX B SHELL SIDE INLET aligned to OPEN. Places:
Place HSS-15115B CONTROL TRANSFER SWITCH V HSS-15115B CONTROL TRANSFER SWITCH V in in EMERG position. EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 15 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments
- 22 Transfer HSS-15116A CONTROL TRANSFER SWITCH Verifies:
K as follows: HV-151-F003B HX B SHELL SIDE OUTLET in OPEN.
THEN Ensure HV-151-F003B HX B SHELL SIDE OUTLET aligned to OPEN. Places:
Place HSS-15116A CONTROL TRANSFER SWITCH K HSS-15116A CONTROL TRANSFER SWITCH K in in EMERG position. EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- 23 Place HSS-15116B CONTROL TRANSFER SWITCH W Places:
in EMERG position. HSS-15116B CONTROL TRANSFER SWITCH W in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 16 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step
~
Action Standard Eva1 Comments
~~
24 Place HSS-15117A CONTROL TRANSFER SWITCH L Places:
in EMERG position. HSS-15117A CONTROL TRANSFER SWITCH L in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT
- 25 Place HSS-15117B CONTROL TRANSFER SWITCH X Places:
in EMERG position. HSS-151178 CONTROL TRANSFER SWITCH X in EMERG position Verifies:
Green Light - LIT Red Light - NOT LIT 26 Ensure Main Steam Lines ISOLATED by EITHER: Verifies:
Observing IB MSIV's indicate CLOSED. Main Steam Line IB IS0 VLVS A, B, C, and D Amber CLOSED Lights - LIT LOCALLY Observing OB MSIV's CLOSED.
Red OPEN Lights - NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
I PERFORMANCE CHECKLIST Page 17 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments 27 Monitor available parameters to determine plant status.
NOTE :
If PlCSY computer available all information that was available in the control room via computer displays will be available at the Remote Shutdown Panel using the PlCSY laptop computer.
NOTE :
If PlCSY computer is not available, the following step is not necessary for control of the plant, but will make the control by the operators smoother.
EVALUATOR CUE:
Inform the candidate that the PlCSY computer is not yet available, the STA is still in the process of connecting and starting-up the laptop computer.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 18 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments 28 IF PlCSY is not available Notify I&C to install: Determines N/A since PlCYS was available.
Temporary Shutdown level indication in accordance with IC-180-004, LT-B21-1NO27 Reactor Range Level Measurement at Rack 1COO5 Temporary reactor coolant temperature indication in accordance with IC-149-005, Installation and Removal of Temporary RTD Readers for Local Monitoring of RHR Heat Exchanger B Inlet (TE-Ell-1N004B) and Outlet (TE-Ell-1N027B)Temperatures.
EVALUATOR CUE:
If candidate elects to have I & C begin installing, Role-play I&C and acknowledge the request.
29 IF PlCSY is not available and the Control Room was Based on initial conditions, determines this to be NIA.
evacuated prior to scramming the reactor, Ensure the reactor scrammed by locally Observing the positions of the scram valves on a few HCUs. (The scram valve indication should be open (up) for both inlet and exhaust valves.)
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0,Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 19 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments NOTE:
Transferring HSS-14454 CONTROL TRANSFER SWITCH Y to EMERG will cause RWCU OB I S 0 HV-144-FO04 to close. Opening Breaker 18 in 1Y219 will de-energize SV-14433 closing HV-144FO33.
EVALUATOR NOTE:
Since there was no indication of RWCU piping leak OR indication of flow being diverted to condenser or Radwaste through RWCU in the initial conditions, the candidate may not contact the NPO to perform the check in the next step.
30 IF there is indication of RWCU piping leak OR May Contact NPO and request checks for:
indication of flow being diverted to condenser or Indication of RWCU piping leak OR indication of flow Radwaste through RWCU, Perform the following: being diverted to condenser or Radwaste through Place HSS-14454 CONTROL TRANSFER SWITCH Y RWCU to EMERG (located near the top of the panel)
AND Observe Green Light ILLUMINATED.
Open Breaker 1Y219-018 (Area 29/719').
EVALUATOR CUE:
If necessary, Role-play NPO and inform candidate that there is NO indication of RWCU piping leak OR indication of flow being diverted to condenser or Radwaste through RWCU
- Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 20 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments
~
31 IF Control Room evacuation was because of fire: Determines N/A Verify that the following Control Structure HVAC Systems are operating:
- a. Computer Room Floor Cooling System
- b. Control Room Floor Cooling System
- c. Control Structure H&V System
- d. Battery Room Exhaust System IF one or more of the above systems are found inoperable, Enter ON 030 001. Loss of Control Structure HVAC within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Perform DC OP 001, Post Fire Recovery Actions within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
CAUTION RHR Pump 1 P202A may spuriously start preventing Unit 2 from running RHR Pump 2P202A when required.
32 IF RHR Pump 1P202A must be tripped, Perform the Determines N/A following at 1A20102:
Place Lateral Control Switch to HANDLE OUT position.
Place Lateral Control Switch to OPEN.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. 1
i I I PERFORMANCE CHECKLIST Page 21 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
- ~
Step Action Standard Eva1 Comments 33 IF Suppression Pool Level drops below 22 feet, Determines N/A WITHIN 10 HOURS:
Ensure no systems are in operation that could cause the decrease.
Ensure no other condition(s) exist that could cause the decrease.
Locally Close manual valve 157025 (Area 27/645').
34 IF the fire has caused hot shorts that have resulted in Determines N/A damage to MOVs required for the operation of RCIC, RHR Suppression Pool Cooling or RHR Shutdown Cooling from the Remote Shutdown Panel, Depressurize the RPV using the available SRVs and Use RHFULPCI in the alternate shutdown cooling mode in accordance with ON-149-001.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 22 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments CAUTION Fires in the Control Room could cause an inadvertent and uncontrolled RPV injection from either Condensate, Core Spray, or the RHR Division not installed on the RSP. The SRV discharge piping has been analyzed for the loading conditions that will result from this condition. To minimize the loads on the SRV discharge piping, assure that an SRV is open as RPV pressure is being reduced and the RPV pressure approaches the shutoff head for each of these systems (Condensate approximately 600 psig; Core Spray and RHR approximately 300 psig). Should Condensate begin to inject, monitor RPV level to assure that the fire has not damaged the RN LO LOAD controller prior to closing the SRV.
NOTE:
Relief mode of SRV's A, 6 , and C will not auto initiate when applicable Control Transfer Switches are in EMERG position, however, safety function is always operable. Also when SRV Transfer Switches are in EMERG spurious auto actuation is prevented due to a Control Room fire.
- Critical Step #Critical Sequence Form NW-QA-31.8-2, Rev. 0, Page I of 1 2005 N R C Exam Rev. 1
i PERFORMANCE CHECKLIST Page 23 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Standard Eva1 Comments Action 35 To control reactor pressure Perform the following: Verifies:
Ensure following valves OPEN: SV-12651 INSTR GAS TO CONTN ISO.
SV-12651 INSTR GAS TO CONTN ISO. SV-12605 INSTR GAS CMP OB SUCT ISO.
SV-12605 INSTR GAS CMP OB SUCT ISO. Amber Lights - NOT LIT Red Lights - LIT CAUTION Level 1 (-129") or high drywell pressure (1.72 psig)
LOCA Isolation Signal is defeated for CIG valves when controlled from the remote shutdown panel.
NOTE:
Placing HSS-151148 Transfer Switch U in EMERG causes lnstr Gas CMP OB suction to cycle possibly tripping CIG compressors on low suction pressure.
36 IF CIG Compressors tripped, Reset as follows at 1C239 Contacts NPO and requests NPO to determine the (Area 25/719'): status of the CIG Compressors Depress Logic Reset push button.
Ensure CIG Compressor STARTS.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 24 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Action Standard Eva1 Comments EVALUATOR CUE:
Role-play NPO and inform candidate that the CIG Compressors are running.
CAUTION If RPV pressure drops below 650 psig, condensate pumps will inject when RPV level < +35 inches.
CAUTION Wide range level indication becomes less accurate as RPV pressure decreases.
EVALUATOR NOTE:
It may be necessary for the candidate to perform several OPEN/CLOSE sequences on the SRVs to obtain the required cooldown rate.
Operate SRV's as follows: Places:
Open SRV's A, B,and C as needed. Safety Relief Valve PSV-141-FO13A, B, or C control switch to OPEN Verifies:
Reactor Vessel Pressure PI-14262 Dropping
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 25 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
Step Action Standard Eva1 Comments NOTE:
Keys to operate SRV's are located in sealed Pink sound powered phone storage box, labeled "JP1207, JP1402, JP2201 inside the Remote Shutdown Panel
,I1 Room.
38 IF pneumatic supply to SRV's A, B, and C not available, Determines N/A Operate SRV's G, J, K, L, M, or N (ADS valves) individually from upper (lower) relay room Panel 1C628 (1C631) using Keylock switches.
EVALUATOR NOTE:
Pay close attention to the actual RPV pressure in the next step. This pressure will be used to determine if the candidate has violated the Tech Spec RCS cooldown rate.
- 39 Refer to Attachment A for RPV Pressure/Temperature Refers to Attachment A and Determines the lowest RPV pressure necessary to achieve the less than 100°F/Hr Correlation. cooldown
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 26 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:
r,,, Action Standard Eva1 Comments
- 40 Plot cooldown in accordance with Attachment A and B. Refers to Attachment A and B Observes Reactor Vessel Pressure PI-14262 Using Attachment A Determines RCS temperature Plots this temperature on Attachment B Verifies cooldown rate is within 1OO"F/Hr limit EVALUATOR CUE:
This completes the JPM
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS
. A. A Hazardous GAS condition exists in the control room requiring abandonment of the Control Room.
B. ON-100-009, Control Room Evacuation has been completed through step 4.2.
C. Reactor vessel water level is being maintained by RCIC.
D. Reactor pressure is being maintained by SRVs cycling.
INITIATING CUE Transfer control to the RSDP and commence a RCS cooldown NOT TO EXCEED 1OO°F/Hr with SRVs from the Remote Shutdown Panel beginning at step 4.3 of ON-100-009, Control Room Evacuation.
Page 1 of 2 2005 NRC Exam Rev. 1
TASK CONDITIONS A. A Hazardous GAS condition exists in the control room requiring abandonment of the Control Room.
B. ON-100-009, Control Room Evacuation has been completed through step 4.2.
C. Reactor vessel water level is being maintained by RCIC.
D. Reactor pressure is being maintained by SRVs cycling.
INITIATING CUE Transfer control to the RSDP and commence a RCS cooldown NOT TO EXCEED 1OO"F/Hr with SRVs from the Remote Shutdown Panel beginning at step 4.3 of ON-100-009, Control Room Evacuation.
Page 2 of 2 2005 NRC Exam Rev. 1
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 24.0P.001.007 0 1015105 264000 A2.09 3.71 4.1 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
To Sys. No.
Task
Title:
Transfer of DG E for DG C Completed By: Validated Rich Chin 10/5/05 Writer Date InstructorNVriter Date Approval:
Nuclear Trng. Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # I S.S. #
Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-31.8-1,Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 24.0P.001.007
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES A. OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C (Revision 25) [Steps 1 and 2 signed as being completed]
111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. Both Units were at 100% Steady State Power B. A Station Blackout occurred C. The A Diesel generator was started LOCALLY D. The control room crew is performing Unit l ( 2 ) Response to Station Blackout EO-1 OO(200)-030, E. To facilitate two diesels in same division operating, the control room is attempting to energize the C bus using the E DIESEL GENERATOR.
F. Another operator is at the E DG and has already performed steps 1 and 2 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C.
V. INITIATING CUE Prepare the C DG for Transfer by performing steps 3 through 1 1 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C.
VI. TASK STANDARD C D/G removed from service, and E D/G ready to supply power to C ESS busses (IAW steps 3 - 1 1 of OP-024-004 attachment C)
VILTASK SAFETY SIGNIFICANCE Provide redundant power supply to safety related equipment.
Form NTP-QA-3 1.8- 1, Rev. 0, Page 2 of 2 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 3 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments Obtain a controlled copy of OP-024-004, TRANSFER Controlled copy obtained from evaluator.
AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C.
EVALUATOR NOTE:
Next step produces Control Room and local alarm EVALUATOR CUE:
If necessary inform candidate that all VERIFY initials are assumed to be completed as required.
- 1. At OC521C Diesel Generator C Engine Control Panel, Places:
PLACE DG C Control Mode Select Switch 43CM to LOCAL.
DG C Control Mode Select Switch 43CM to LOCAL.
- 2. OBSERVE following: Verifies:
Control Switches Not Proper for Remote Auto Oper. ALARM.
Control Switches Not Proper for Remote Auto Oper.
Alarm window E08 - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 4 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments Alarm window E08 is LIT 3 Remote white light EXTINGUISHES. Verifies:
Remote White light NOT LIT EVALUATOR CUE:
Remote White light is NOT LIT 4 Local white light ILLUMINATED. Verifies:
Local White light LIT EVALUATOR CUE:
Local White light is LIT 5 DG C Available for Emergency white light EXTINGUISHES. Verifies:
DG C Available for Emergency White light NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0,Page 1 of I 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page5of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
DG C Available for Emergency White light is NOT LIT
- 6. ENSURE Control Room received DG Panel ALARM. Calls the Control Room to verify DG Panel ALARM has been received.
EVALUATOR CUE:
Role play the control room and inform the candidate that DG Panel ALARM has been received
momentarily placing switch to CLOSE for ESW Supply/Return HV-O1112C/HV-O1122C. ESW Supply/Return HV-O1112C/HV-O1122C switch to CLOSE AND Verifies:
Red light NOT LIT Amber light LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 N R C Exam Rev. 1
1 PERFORMANCE CHECKLIST Page 6 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
-Step Action Standard Eva1 Comments EVALUATOR CUE:
Red light NOT LIT Amber light LIT
momentarily placing switch to CLOSE for ESW Supply/Return HV-0111OC/HV-O1120C. ESW Supply/Return HV-0111OC/HV-O1120C switch to CLOSE AND Verifies:
Red light NOT LIT Amber light LIT EVALUATOR CUE:
Red light NOT LIT Amber light LIT NOTE:
Switching protective equipmen. requirec at switchgear.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
\
PERFORMANCE CHECKLIST Page 7 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments EVALUATOR NOTE:
This JPM will not proceed to the point of racking the breakers. Therefore, Switching protective equipment will not be necessary.
Bldg Ventil Supply Fan OV512C to STOP.
DG C Bldg Ventil Supply Fan OV512C to STOP.
- lo. At OC512C PLACE HS-O0057C, DG C Auto Start Control, Places:
to DISABLE to prevent inadvertent start while transferring HS-O0057C, DG C Auto Start Control, to DISABLE logic.
- 11. At OC512C OBSERVE DG C Aligned white light Verifies:
EXTlNGUISHED.
DG C Aligned white light NOT LIT EVALUATOR CUE:
DG C Aligned white light NOT LIT
- 12. At OC512C SEQUENTIALLY PLACE following switches to SEQUENTIALLY Places the following switches to D/G E position: D/G E position:
- a. HS-00058C Generator Metering & Computer Monitoring
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
/ I (
PERFORMANCE CHECKLIST Page 8 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments
- 3. HS-00059C Generator Field Current Computer Monitoring
- c. HS-00060C Diesel Alarms to Control Room Annunciator Note:
Cycle the following HS several times to clean contacts
- e. HS-00062C ESW Loop A Supply Valve Control
& Indication
- f. HS-00063C ESW Loop A Return Valve Control
& Indication
- g. HS-00064C ESW Loop B Supply Valve Control
& Indication
- h. HS-0006% DG Bypass Indication Unit 1
- i. HS-00066C DG Bypass Indication Unit 2
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 9 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments
- i. HS-00067C Alignment Alarm & Indication Only
- k. HS-00068C ESW Loop B Return Valve Control
& Indication
- I. HS-00069C ESW Bypass Indication and Auto Loop Transfer
- m. HS-00070C Ventilation Supply Fans Control
- n. HS-00071C DG Ctl, Indication, Metering &
Breaker Trip Interlock
- 0. HS-00072C Generator Relaying & Breaker Trip Interlock
- p. HS-00073C Generator Metering & Breaker Trip Interlock
- q. HS-00074C Engine Control & Indication
- r. HS-00075C Engine, Generator & ESW Pump Control
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0,Page I of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 10 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:
Step Action Standard Eva1 Comments
- s. HS-00076C Generator Breaker Control EVALUATOR CUE:
This completes the JPM.
- Critical Step #Critical Sequence Form NTPQA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam Rev. 1
TASK CONDITIONS A. Both Units were at 100% Steady State Power B. A Station Blackout Occurred.
C. The ADiesel generator was started LOCALLY.
D. The control room crew is performing Unit l(2) Response to Station Blackout EO-1OO(200)-030.
E. To facilitate two diesels in same division operating, the control room is attempting to energize the C bus using the E Diesel generator.
F. Another operator is at the E DG and has already performed steps 1 and 2 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C.
INITIATING CUE Prepare the CDG for Transfer by performing steps 3 through 11 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C.
Page 1 of 2 2005 NRC Exam Rev. I
TASK CONDITIONS A. Both Units were at 100% Steady State Power.
- 8. A Station Blackout Occurred.
C. The A Diesel generator was started LOCALLY.
D. The control room crew is performing Unit l(2) Response to Station Blackout EO-1OO(200)-030.
E. To facilitate two diesels in same division operating, the control room is attempting to energize the C bus using the E Diesel generator.
F. Another operator is at the E DG and has already performed steps 1 and 2 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C INITIATING CUE Prepare the C DG for Transfer by performing steps 3 through 11 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C.
Page 2 of 2 2005 NRC Exam Rev. I
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 50.0P.004.152 2 1015105 295016 AA1.06 4.014.1 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
To Sys. No.
Task
Title:
Establish and Maintain Reactor Vessel Level (RCIC Not Injecting) from the RSDP Using the Trip and Throttle Valve Completed By: Validated Rich Chin 1015/05 Writer Date InstructorNVriter Date Approval :
Nuclear Trng. Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # I S.S. #
Performance ( ) Satisfactory ( ) Unsatisfactory Eva1uation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 50.0P.004.152
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES OP-150-001, RClC System (Revision 24) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
39 RClC Manual Start IV. TASK CONDITIONS A. A condition has occurred requiring abandonment of the Control Room.
- 6. All required immediate operator actions of ON-100-009, Control Room Evacuation have been completed prior to abandoning the Control Room.
C. Transfer switch positions have been changed on the RSDP IAW ON-100-009, Control Room Evacuation Section 4.3.
D. Reactor vessel wide range water level is 0 inches and lowering.
E. Reactor pressure is being maintained by SRVs cycling.
F. RClC is not running. There has been no initiation signal.
G . All personnel have been evacuated from RClC pump room and RClC pipe areas 670' Reactor Building V. INITIATING CUE Manually initiate RClC and inject at 625 gpm to restore RPV water level.
VI. TASK STANDARD RClC started and feeding the reactor vessel at 625 gpm.
VII. TASK SAFETY SIGNIFICANCE Provides cooling water to the reactor core.
Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
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PERFORMANCE CHECKLIST Page 4 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Step EVALUATOR NOTE:
Action Standard Eva1 Comments Following interlocks are defeated for RClC when controlled from remote shutdown panel:
Isolations For HV-149-FO07 AND HV-149-FO08 All Turbine Trips Except Overspeed (110% &
124%) AND Manual Exhaust Line Vacuum Breaker Isolations RClC Auto Initiations RClC Turbine Shutdown On High Level 8 (+54")
Min Flow To Supp Pool HV-149-FO19 Operation On Hi/Low Flow Auto Suction Transfer From CST To Supp Pool On Low CST Level Steam Admission Valve HV-150-FO45 With RClC Turbine Exhaust Valve HV-150-FO59 Closed 5 OBSERVE ES-14901 RClC STATIC INVERTER Verifies:
light ILLUMINATED.
RCICST, TIC JVERTER 20\ c o IT AVAILABLE Green Light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
(
PERFORMANCE CHECKLIST Page 5 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Action Standard Eva1 Comments EVALUATOR CUE:
ES-14901 RClC STATIC INVERTER Green Light - LIT ENSURE RClC TURBINE FLOW Verifies:
CONTROLLER FIC-14903 in AUTO set at 625 RClC TURBINE FLOW CONTROLLER gpm. FIC-14903 in AUTO set at 625 gpm.
EVALUATOR CUE:
RClC TURBINE FLOW CONTROLLER FIC-14903 in AUTO set at 625 gpm.
EVALUATOR NOTE:
Once RClC is operating, pump room and pipe areas may be accessed again.
If time permits, EVACUATE personnel from Determines:
RClC pump room and RClC pipe areas 670' From initial conditions that this has already been Reactor Building prior to pump start.
completed.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 6 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Action Standard Eva1 Comments EVALUATOR NOTE:
If malfunction of FIC-14903 is observed, proceed to 2.1 5.7 to place RClC in service using Trip & Throttle Valve HV-15012.
FAULT STATEMENT WHEN RClC CONTROLLER IS PLACED IN MANUAL, IT WILL NOT ADJUST TO ZERO 0.
PLACE RClC TURBINE FLOW CONTROLLER Places:
FIC-14903 in MANUAL set for minimum speed.
RClC TURBINE FLOW CONTROLLER FIC-14903 in MANUAL AND Depresses CLOSE pushbutton AND Verifies:
Output signal decreasing to ZERO EVALUATOR CUE:
RClC TURBINE FLOW CONTROLLER FIC-14903 output signal is STILL at 100%
Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
I PERFORMANCE CHECKLIST Page 7 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Step Action Standard Comments 9 When the controller will not adjust to zero, leave Select Section 2.1 5.7.
Section 2.1 5.6 and go to Section 2.15.7.
EVALUATOR NOTE:
Once RClC is operating, pump room and pipe areas may be accessed again.
10 If time permits, EVACUATE personnel from Determines:
RClC pump room and RClC pipe areas 670' Reactor Building prior to pump start. From initial conditions that this has already been completed.
EVALUATOR NOTE:
RClC turbine can be operated utilizing trip and throttle valve if governor valve is in open position. This could be caused by failure in hydraulic control circuit such as loss of control signal. Loss of control signal will fail governor valve full open and could be caused by inverter failure or loss of power. Time spent in this condition of operation should be limited until full automatic control regained.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2,Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 8 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Step Action Standard Eva1 Comments
- ll For manual startup using trip and throttle valve: Places and HOLDS control switch HV-15012 to CLOSE UNTIL CLOSE TURBINE TRIP AND THROTTLING HV-15012. Amber light - LIT and Red light NOT LIT EVALUATOR CUE:
HV-15012 Amber light - LIT and Red light NOT LIT 12 OPEN STEAM TO RClC TURBINE Places control switch HV-150-FO45 to OPEN HV-150-FO45.
Verifies:
Amber light - NOT LIT and Red light - LIT EVALUATOR CUE:
HV-150-F045 Amber light - NOT LIT and Red light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 9 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
~ ~ _ _ ~
Step STARTRCICBAROCDSRVACUUMPP Action Standard Places control switch RClC BARO CDSR Comments 13 1P219. VACUUM PP 1P219 to START Verifies:
Amber light - NOT LIT and Red light - LIT EVALUATOR CUE:
RClC BARO CDSR VACUUM PP 1P219 Amber light - NOT LIT and Red light - LIT 14 ENSURE MIN FLOW TO SUPP POOL Verifies:
FV-149-FO19 OPEN.
FV-149-FO19 Amber light - NOT LIT and Red light - LIT EVALUATOR CUE:
FV-149-FO19 Amber light - NOT LIT and Red light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0.Page 1 of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 10 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Action Standard Eva1 Comments OPEN RClC INJECTION HV-149-FO13. Places control switch HV-149-F013 to OPEN Verifies:
Amber light - NOT LIT and Red light - LIT EVALUATOR CUE:
HV-149-F013 Amber light - NOT LIT and Red light - LIT INCREASE speed by throttling TURBINE TRIP Intermittentlyplaces control switch HV-15012 to AND THROTTLING HV-15012 until desired flow OPEN obtained.
Verifies:
HV-15012 Amber light - LIT and Red light - LIT AND RClC PUMP INJECTION FLOW (FI-14903) rising to 625 gpm.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
\
PERFORMANCE CHECKLIST Page 11 of 11 Appl. To/JPM No.: 50.0P.004.152 Student Name:
Action Standard Comments EVALUATOR CUE:
HV-15012 Amber light - LIT and Red light - LIT FI-14903 indicates 625 gpm.
When RClC flowrate above 250 gpm, CLOSE Places control switch HV-149-FOI9 to CLOSE MIN FLOW TO SUPP POOL FV-149-FO19. and Verifies:
Amber light -LIT and Red light - NOT LIT EVALUATOR CUE:
FV-149-FO19 Amber light -LIT and Red light - NOT LIT EVALUATOR CUE:
That completes this JPM
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
TASK CONDITIONS A. A condition has occurred requiring abandonment of the Control Room.
B. All required immediate operator actions of ON-100-009, Control Room Evacuation have been completed prior to abandoning the Control Room.
C. Transfer switch positions have been changed on the RSDP IAW ON-100-009, Control Room Evacuation Section 4.3.
D. Reactor vessel wide range water level is 0 inches and lowering.
E. Reactor pressure is being maintained by SRVs cycling.
F. RClC is not running. There has been no initiation signal.
G. All personnel have been evacuated from RClC pump room and RClC pipe areas 670' Reactor Building INITIATING CUE Manually initiate RClC and inject at 625 gpm to restore RPV water level.
2005 NRC Exam Rev. 1 1 of2
TASK CONDITIONS A. A condition has occurred requiring abandonment of the Control Room.
B. All required immediate operator actions of ON-100-009, Control Room Evacuation have been completed prior to abandoning the Control Room.
C. Transfer switch positions have been changed on the RSDP IAW ON-100-009, Control Room Evacuation Section 4.3.
D. Reactor vessel wide range water level is 0 inches and lowering.
E. Reactor pressure is being maintained by SRVs cycling.
F. RClC is not running. There has been no initiation signal.
G. All personnel have been evacuated from RClC pump room and RClC pipe areas 670' Reactor Building INITIATING CUE Manually initiate RClC and inject at 625 gpm to restore RPV water level.
2005 NRC Exam Rev. 1 2 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 55.0P.007.001 1 1015105 201001 A2.07 3.213.1 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp.
To Sys. No.
Task
Title:
Shift The CRD Flow Stations From A To B In Accordance With OP-255-001 Completed By: Validated Rich Chin 1015105 Writer Date I nstructorNV riter Date Approval:
Nuclear Trrtg. Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I. Employee # I S.S. #
Performance ) Satisfactory ( ) Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam Rev. 1
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 55.0P.007.001
- 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
- 6. All applicable safety precautions shall be taken in accordance with established PP&L safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
II. REFERENCES OP-255-001, Control Rod Drive Hydraulic System (Rev. 34) 111. REACTIVITY MANIPULATIONS This JPM satisfies the following Operational Activity(s):
None IV. TASK CONDITIONS A. Unit 2 is at 80 percent reactor power.
- 6. While adjusting Control Rods per Reactor Engineering Instructions, it is noted that the A CRD Flow Control station is not responding properly.
C. The B CRD Flow Control Station needs to be placed in service so that I&C can investigate.
V. INITIATING CUE Swap CRD flow control stations from CRD DRIVE WATER HEADER FLOW VALVE FV-2F002A to CRD DRIVE WATER HEADER FLOW VALVE FV-2F002B.
VI. TASK STANDARD CRD DRIVE WATER HEADER FLOW VALVE FV-2F002B in service and CRD DRIVE WATER HEADER FLOW VALVE FV-2F002A removed from service VILTASK SAFETY SIGNIFICANCE Provide reliable drive water flow to the control rod drive mechanisms Form NTP-QA-3 1.8-1. Rev. 0, Page 2 of 2 2005 NRC Exam Rev. 1
r PERFORMANCE CHECKLIST Page 3 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments EVALUATOR NOTE:
With the A flow control station in service the following conditions exist:
M/A-2D009A is in auto.
0 Closed and Open position indicator lights for FCV are illuminated.
0 M/A-2D009B is in MAN.
0 FCV 6 closed light is ILLUMINATED and the open light is EXTINGUISHED.
1 Obtain a controlled copy of OP-255-001. Obtains controlled copy.
2 Select the correct section to perform. Selects Section 2.4.
3 Review the prerequisites. Ensures prerequisites are met.
EVALUATOR CUE:
Inform the student that all prerequisites have been met.
if
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
1 PERFORMANCE CHECKLIST Page 4 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Action Standard Comments NOTE Following steps change from Flow Control Valve FV-2F002A to FV-2F002B. To change from valve B to A, use valves in parentheses.
Ensure FC-C12-2R600, CRD Flow Controller, Calls the Control Room and confirms that in AUTO CRD FLOW CONTROLLER FIC-Cl2-2R600 is in AUTO.
EVALUATOR CUE:
FIC-Cl2-2R600 is located on Panel 2C601 in the Control Room.
Role-play the control room and inform the candidate that the controller is in automatic.
Ensure M/A-2D009B Man/Auto Station Control Verifies:
Valve B controller in MAN with Red pen indicating 0. Red pen displays MANUAL M/A-2D009B Man/Auto Station in MAN demand on the local controller. AND Red pen is at 0.
- Critical Step #Critical Sequence Form NIT-QA-31.8-2,Rev. 0. Page I of 1 2005 NRC Exam Rev. 1
i PERFORMANCE CHECKLIST Page 5 ot 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
WA-2D009B Man/Auto Station in MAN AND Red pen is at 0.
6 Ensure FV-2F002B CLOSED, as indicated by Verifies:
Position Indicator Flow Control Valve B Amber light ILLUMINATED 4ND Red light Position Indicator Flow Control Valve B EXTINGUISHED. Amber light LIT Red light NOT LIT EVALUATOR CUE:
Amber light LIT Red light NOT LIT 7 Ensure 246F0468, Flow Control Valve B Iso, Rotates:
OPEN.
Flow Control Valve B Is0 246F046B handwheel CLOCKWISE until valve stem moves in close direction then rotates handwheel COUNTER CLOCKWISE until valve stem is returned to full open.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 6 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
Inform the candidate that the valve is FULL COUNTER CLOCKWISE NOTE To prevent large (20 to 25 gpm) flow changes, following step should be performed very slowly.
EVALUATOR CUE:
In the next step, as the candidate begins opening the valve, provide a cue that an audible sound can be heard coming from the flow through the pipe.
AFTER candidate stops moving valve, provide cue that the Audible sound change has STOPPED.
- 8 Slowly Crack Open Flow Control Valve B Is0 Very slowly rotates:
246F047B.
Flow Control Valve B Is0 246F047B handwheel COUNTER CLOCKWISE until flow is established.
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 7 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments 9 Observe following, indicating flow stabilized: Verifies:
Audible sound change has STOPPED Audible sound change has STOPPED.
M/A-2D009A Man/Auto Station Control Valve WA-2D009A Man/Auto Station Control Valve A Black pen STABLE. The black pen displays A Black pen STABLE.
control room demand.
Flow Control Station Total Water Flow FI-Flow Control Station Total Water Flow FI- 2R019 - 63 gpm.
2R019 - 63 gpm.
EVALUATOR CUE:
Audible sound change has STOPPED.
M/A-2D009A Man/Auto Station Control Valve A Black pen STABLE.
Flow Control Station Total Water Flow FI-2R019 - 63 gpm.
10 WHEN stable flow indicated, THEN Fully Rotates:
Open 246F0478, Flow Control Valve B Iso.
Flow Control Valve B Is0 246F047B handwheel COUNTER CLOCKWISE until full open is reached.
EVALUATOR CUE:
Flow Control Valve B Is0 246F047B is full COUNTER CLOCKWISE
- Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page I of 1 2005 NRC Exam Rev. 1
t PERFORMANCE CHECKLIST Page 8 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Comments EVALUATOR NOTE In the next step Flow Control Valve A will go in the closed direction as Flow Control Valve B is opened.
Both indicating lights for both valves will be LIT during this transition.
- 11 Slowly Rotate the manual adjust knob on WA- Slowly Rotates:
2D009B Man/Auto Station Control Valve Manual adjust knob on WA-2D009B Man/Auto UNTIL Black and red pens CLOSELY Station Control Valve UNTIL Black and red MATCHED as possible pens CLOSELY MATCHED as possible.
EVALUATOR CUE:
WA-2D009B Man/Auto Station Control Valve Black and red pens are MATCHED c
- Critical Step #Critical Sequence Form NTP-QA-31.8-2.Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
PERFORMANCE CHECKLIST Page 9 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments
~
12 Observe following indicating flow stabilized: Observes the following indicating flow stabiIized:
Audible sound change STOPPED.
Audible sound change STOPPED.
M/A-2D009A Man/Auto Station Control Valve A Black pen DECREASES AND STABILIZES 0 M/A-2D009A Man/Auto Station Control Flow Control Station Total Water Flow FI-Valve A Black pen DECREASES AND STAB1LIZES.
2R019 2R019 - 63 gpm Flow Control Station Total Water Flow FI-2R019 2R019 - 63 gpm.
EVALUATOR CUE:
Audible sound change HAS STOPPED.
M/A-2D009A Man/Auto Station Control Valve A Black pen DECREASED AND IS NOW STABILE.
Flow Control Station Total Water Flow FI-2R019 2R019 - 63 gpm.
EVALUATOR NOTE:
Nothing will occur when this step is performed.
The candidate should match these needles as closely as possible. The closer the match the smaller the change when the controller is placed in manual later.
- Critical Step #Critical Sequence Form NTF'-QA-31.8-2, Rev. 0, Page 1 of 1 2005 N R C Exam Rev. 1
PERFORMANCE CHECKLIST Page 10 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Comments 13 Slowly Rotate manual adjust knob on M/A- Slowly Rotates:
2D009A Man/Auto Station Control Valve until Manual adjust knob on M/A-2D009A Man/Auto Black and Red pens CLOSELY MATCHED.
Station Control Valve CLOCKWISE until Black and Red pens CLOSELY MATCHED.
EVALUATOR CUE:
M/A-2D009A Man/Au.J Station Pens are matched.
14 Ensure Flow Control Station Total Water Flow Verifies:
FI-2R019 - 63 gpm and stable Flow Control Stabn Tota Water Flow FI-2R019 - 63 gpm and stable.
EVALUATOR CUE:
Total Water Flow FI-2R019 is 63 gpm and STABLE 15 Place M/A-2D009A Man/Auto Station Control Rotates:
Valve A control switch to MAN.
M/A-2D009A Man/Auto Station Control Valve A control switch CLOCKWISE to MAN.
- Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. I
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PERFORMANCE CHECKLIST Page 12 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments EVALUATOR CUE:
M/A-2D009A Man/Auto Station Red pen is at 0 AND Position Indicator Flow Control Valve A Red light is NOT LIT.
18 Ensure Flow Control Station Total Water Flow Ensure Flow Control Station Total Water Flow FI-2R019 - 63 gpm and stable. FI-2R019 - 63 gpm and stable.
EVALUATOR CUE:
Total Water Flow FI-2R019 is 63 gpm and STABLE NOTE To prevent large (20 to 25 gpm) flow changes, following step should be performed very slowly.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
PERFORMANCE CHECKLIST Page 13 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments
~
19 Slowly Close Flow Control Valve A Is0 Slowly Rotates:
246F047A.
Flow Control Valve A Is0 246F047A valve handwheel CLOCKWISE until full closed is reached EVALUATOR CUE:
Flow Control Valve A Is0 246F047, valJe is FULL CLOCKWISE 20 IF the in-service CRD Flow Control Valve, Verifies the following indicating lights for FV-FV-2F002B is at a mid-position and dual 2F002A :
indication is not indicated, THEN Perform the Position Indicator Flow Control Valve A following at panel 2C601 Red light-NOT LIT.
Red light and Amber light - LIT AND Determines no additional actions needed EVALUATOR CUE:
Position Indicator Flow Control Valve A Red light-NOT LIT.
Red light and Amber light - LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam Rev. 1
1 i PERFORMANCE CHECKLIST Page 140f 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Student Name:
Step Action Standard Eva1 Comments 21 Check following for normal CRD System Check following for normal CRD System parameters: parameters:
0 Flow Control Station Total Water Flow FI-2R019 - 63 gpm.
0 Downstream P-C/Rea Differential Pressure PDI-2R005 < 50 psid.
0 Upstream P-C/Rea Differential Pressure PDI-2R009 - 250 psig.
EVALUATOR CUE:
Flow Control Station Total Water Flow FI-2R019 is 63 gpm.
Downstream P-C/Rea Differential Pressure PDI-2R005 is 40 psid.
Upstream P-C/Rea Differential Pressure PDI-2R009 is 250 psig.
EVALUATOR CUE:
This completes the JPM.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of I 2005 NRC Exam Rev. 1
TASK CONDITIONS:
L A. Unit 2 is at 80 percent reactor power.
- 8. While adjusting Control Rods per Reactor Engineering Instructions, it is noted that the A CRD Flow Control station is not responding properly.
C. The B CRD Flow Control Station needs to be placed in service so that I&C can investigate.
INITIATING CUE:
Swap CRD flow control stations from CRD DRIVE WATER HEADER FLOW VALVE FV-2F002A to CRD DRIVE WATER HEADER FLOW VALVE FV-2FOO2B.
Page 1 of 2 2005 NRC Exam Rev. 1
TASK CONDITIONS:
- A. Unit 2 is at 80 percent reactor power B. While adjusting Control Rods per Reactor Engineering Instructions, it is noted that the A CRD Flow Control station is not responding properly.
C. The B CRD Flow Control Station needs to be placed in service so that I&C can investigate.
INITIATING CUE:
Swap CRD flow control stations from CRD DRIVE WATER HEADER FLOW VALVE FV-2F002A to CRD DRIVE WATER HEADER FLOW VALVE FV-2FOO2B.
Page 2 of 2 2005 NRC Exam Rev. 1