ML022130332
| ML022130332 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/08/2002 |
| From: | Bielby M NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| ER-02-301 | |
| Download: ML022130332 (87) | |
Text
PROPOSED NRC-AUTHORIZED WALKTHROUGH JPMS FOR THE LASALLE INITIAL EXAMINATION - APRIL 2002
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Secure RHR Service Water System Examination Level: RO /SRO /SRO(I)
Date: April 8, 2002 Developed by: Raymond Keith Walton Date: March 14, 2002 Reviewed by:
Approved by:
Date:
Date:
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.1.a Task
Title:
Secure RHR Service Water System K/A
Reference:
400000A4.01 Examinee:
NRC Examiner:
Time Started:
Estimated Time to Completion:
15 min K/A Importance:
3.1/3.0 Date:
Time Finish-ed:
Time Critic-Task: NO Method of testing:
Performance:
Simulated X
Actual Location:
X Simulator Plant Task Standard:
Required Materials:
LOP-RH-05, Operation of the RHR Service Water System General
References:
LOP-RH-05, Operation of the RHR Service Water System, Rev 22,1/17/2001 READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss. and provide initiating cues. Tell me when you have successfully completed the task.
Initial Conditions:
Plant Conditions are as shown. 'B' RHRSW has been running for a pump vibration and flow data test. B RHR SW Process Radiation Monitor is INOP. Chemistry has completed the required sample within the last hour. 1 E12-F448 and 1E12-F4541 have been cycled as part of the test. The test is complete.
There are no Tech Spec time clocks in effect. An operator is standing by to assist you.
Initiating Cue:
The Unit Supervisor has dircctcd you to secure 'B' RHRSW IAWA LCD-RH-05. Inform the Unit Supervisor when the task is comp!cte.
Page 2 of 8
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
This JPM can be run from any IC.
It is OK to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2.
Verify Div 1 and Div 2 Thermal O/L Bypass switches are in NORMAL.
- 3.
Start 'B' RHR Service Water system Start 'C RHR Service Water pump (1 El 2-C300C)
Open 'B' RHR Service Water Heat Exchanger Outlet Valve, 1E12-F068B Start 'D' RHR service Water pump (1 E12-C300D)
- 4.
This completes the setup for this JPM.
Page 3 of 8
JOB PERFORMANCE MEASURE Initial Conditions:
Plant Conditions are as shown.
0
'B' RHRSW has been running for a pump vibration and flow data test.
B RHR SW Process Radiation Monitor is INOP.
Chemistry has completed the required sample within the last hour.
0 1 El 2-F448 and 1 El 2-F4541 have been cycled as part of the test.
The test is complete.
There are no Tech Spec time clocks in effect. An operator is standing by to assist you.
Initiating Cue:
The Unit Supervisor has directed you to secure 'B' RHRSW lAW LOP-RH-05. Inform the Unit Supervisor when the task is complete.
Page 4 of 8
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
NOTE: All steps of this JPM are to be completed at CR Panel 1H13-P601 Element Expected Response C
E Cn E
z o
D0 0
- 1.
If RHR Service Water Process radiation Monitor is inoperable, VERIFY that Chemistry has collected the proper samples.
- 2.
Locally Backwash the operating strainer per LOP-RH-14.
CUE:
Candidate determines conditions met from 'Initial Conditions.'
Local operator directed to backwash B RHRSW strainer.
As local operator, acknowledge direction. Wait a minute, then report that the B RHRSW strainer has been backflushed lAW LOP-RH-1i4.
- 3.
PLACE the O/L Bypass for 1E12-FO03B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94 Thermal Overload bypass switch to test.
- 4.
Log positioning of O/L Bypass switch in Unit Log.
O/L Bypass for 1 El 2-FO03B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94 Thermal Overload bypass switch placed in TEST.
Position of O/L Bypass switch o
Logged in unit log o
Requested to be logged by Unit NSO.
CUE:
If requested, as Unit NSO, acknowledge request, report that the O/L Bypass for 1E12-FO03B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94 Thermal Overload bypass switch to TEST has been logged.
- 5.
If required, START 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock Candidate determines that an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> timeclock must be started.
If requested, as Unit SupervisOr, acknowledge Tech Spec Time clock infnrmrtinn, state that the Unit NSO will perform the necessary actions for the Tc.;,ii S~icc Time clock.
Page 5 of 8 CUE:
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E co E
z o
C/)
D (O
Expected Response
- 6.
If only on RHRSW pump is in operation... (Step E.5.4).
- 7.
Place control switch for 1 El 2 F068B, 'B' RHR Hx water outlet vlv to CLOSE.
- 8.
When flow indicated on 1 El 2 R602B decreased below 4000 gpm, STOP one RHRSW pump 1E12 300C/D.
- 9.
When 1 E-F068B, 'B' RHR water outlet valve is closed, STOP the running RHRSW pump 1E12 300D/C.
Candidate determines step is not applicable and continues with step E.5.5.
Control switch for 1 El 2-F068B, 'B' RHR Hx water outlet vlv placed in close position.
C or D RHRSW pump control switch taken to STOP when flow decreases to <4000 gpm.
D or C RHRSW pump control switch taken to STOP when 1 E F068B, 'B' RHR water outlet valve is closed.
- 10.
VERIFY flow decreases to 0 gpm on Flow decrease to 0 gpm on flow flow indicator 1 E12-R602B indicator 1 E12-R602B.
- 11.
Place the O/L Bypass for 1 El 2 F003B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94 Thermal Overload bypass switch to NORMAL.
- 12.
Log position O/L Bypass switch in unit lu.
O/L Bypass for 1 E12-F003B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94 Thermal Overload bypass switch to NORMAL.
Position of O/L Bypass switch o
Logged in unit log Requested to be logy.
Unit NSO.
Page 6 of 8 Element
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
Expected Response E
iCO)
E z
o Wl n
O CUE:
If requested, as Unit NSO, acknowledge request, report that the O/L Bypass for 1E12-FO03B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94 Thermal Overload bypass switch to NORMAL has been logged.
- 13.
If required, STOP 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock Candidate determines that an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> timeclock must be stopped.
CUE:
If requested, as Unit Supervisor, acknowledge Tech Spec Time clock information, state that the Unit NSO will perform the necessary actions for the Tech Spec Time clock.
- 14.
Shutdown the RHR SW process Candidate determines that step to by radiation monitor per LOP-PR-not applicable.
06.
- 15.
Locally in the DG bulding penthouse, VERIFY the Div 2 Unit 1 1VY06C RHRSW Ventilation fan stops.
Step determined to be Not applicable.
CUE:
As local operator, acknowledge direction and then report that Div 2 Unit 1 1VY06C RHRSW Ventilation fan has stopped.
- 16.
Verify the appropriate ESF Status Panel Annunciator RHR B Cont Heat Rem Inop (#36) is CLEARED.
- 17.
Inform US that LOP-RH-05 is complete.
CUE: THIS JPM IS COMPLETE.
Enter JPM Stop Time:
ESF Status Panel Annunciator window #36 is cleared.
Unit Supervisor informed that LOP R H -0 5 is c o m p le t e...........
Page 7 of 8 Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
Page 8 of 8
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Transfer a Turbine Driven Reactor Feed Pump from Manual Backup Station to 3-Element Control Examination Level: RO /SRO /SRO(I)
Date: March 5, 2002 Developed by: Raymond Keith Walton Reviewed by:
Date:
D ate:
Approved by: _
Date:
I 4
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.1.b Task
Title:
Transfer a TDRFP from Manual Backup Station to 3-Element Control JoA e2 K/A
Reference:
259002A4.02 K/A Importance:
3.9/3.7 Examinee:
NRC Examiner:
Date:
Time Started:
Time Finished:
Time Critical Task: NO Method of testing:
Perfo'-mance:
Simulated X
Actual Location:
X Simulator Plant Task Standard:
Required Materials:
LOP-FW-04, Startup o' a Turbine Driven Reactor Feed Pump, Rev 33, May 15, 2001 LOP-RL-01, Operation of the Reactor Level Control System, Reve 14, 8/24/1999 General
References:
LOP-FW-17,TDRFP Manual Backup Station Operation LOP-RL-01, Operation of the Reactor Level Control System READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.
Initial Conditions:
Unit 1 experienced slight oscillations in the AUTO control signal for the 'B' TDRFP.
The pump was transferred to the demand substitution mode on the manual backup station IAW LOP-FW-17, Step E.1.
Initiating Cue:
The Unit Supervisor has directed voiu to restore control of the B TDRFP to the M/A station lAW LOP-FW Step E.2 and then place F1I into automatic (ti:.
ýc c-ont control) on its M/A s-:,
\\V LOP-RL-01.
Page 2 of 7
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Reset the simulator to IC 22 (rst22).
It is OK to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2.
Conditions as follows:
Place the simulator in RUN Place the B TDRFP in Manual on its M/A station Shift it to the manual backup station in demand substitution mode Lower the M/A station signal to minimum
- 3.
Freeze the simulator until cued by examiner.
- 4.
When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the noted steps on the Job Performance Measure Validation Checklist located on page 2.
- 5.
This completes the setup for this JPM.
Page 3 of I/
JOB PERFORMANCE MEASURE INITIAL CONDITIONS (To be read by examinee)
Initial Conditions:
Unit 1 experienced slight oscillations in the AUTO control signal for the 'B TDRFP.
The pump was transferred to the demand substitution mode on the manual backup station lAW LOP-FW-17, Step E.1.
Initiating Cue:
The Unit Supervisor has directed you to restore control of the B TDRFP to the M A station lAW LOP-FW-17, Step E.2 and then place the 'B' TDRFP into automatic (three eleme-It control) on its M/A station lAW LOP-RL-01.
Page 4 o1 7
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
All steps of the JPM are to be completed at control room panel H1 3-P603 unless otherwise noted.
Element Expected Response E
HU)
E z
0 I)
D
)
- 1.
VERIFY Manual Backup Station MODE SELECTOR switch in AUTO.
- 2.
RAISE/LOWER demand at the M/A Xfer Station to extinguish AUTO HI or AUTO LO LEDs and illuminate RESET Permissive LED.
- 3.
RESTORE control of the 'B' TDRFP to the M/A station by Depressing RESET TO AUTO pushbutton.
- 4.
Observing the CHECK DEMAND SUBSTITUTION and DIRECT VALVE POSITIONING LEDs extinguish.
- 5.
Match the output of the 'B' TDRFP to the 'A' TDRFP Manual Backup Station MODE SELECTOR switch in AUTO.
Candidate RAISES/LOWERS demand at the M/A Xfer Station to extinguish AUTO HI or AUTO LO LEDs and illuminate RESET Permissive LED.
Candidate depresses RESET TO AUTO pushbutton.
The candidate verifies the CHECK DEMAND SUBSTITUTION and DIRECT VALVE POSITIONING LEDs are extinguished.
Candidate RAISES/LOWERS demand at the M/A Xfer Station for the 'B' TDRFP as needed until it matches the output of the 'A' TDRFP M/A station.
CUE: If feed pump flows are not balanced when M/A station outputs are equal, the candidate may request guidance from the Unit Supervisor. If so, inform the candidate to get M/A station outputs approximately equal and balance feed pump flows.
Page 5 ol V
.IOR PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E S (Q E
Z 0
Co)
D 0
Expected Response
- 6.
VERIFY Reactor Water Level is stable and deviation meter on Single Element Controller is within Green Band.
- 7.
Check M/A station manual and automatic signals equal.
- 8.
Place the 'B' TDRFP in AUTO and VERIFY level control stable.
- 9.
Inform Unit Supervisor that B TDRFP is now in 3-element control.
Candidate verifies Reactor Water Level is stable and deviation meter on Single Element Controller is within Green Band.
Candidate request IMD to check signal output voltages are approximately equal.
CUE: as IMD, report that signal output voltages have been checked for TDRFP 1 B and the signals are approximately equal.
Candidate depresses the AUTO pushbutton on the 'B' TDRFP M/A station and observes RWL stable.
Candidate states that TDRFP is now in 3-element control.
(CUE) THIS COMPLETES THIS JPM Record Stop Time:
I1agc 6 ol 7 Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
Page I ol' 7
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Main Turbine Weekly Surveilla-ce Test Examination Level: RO /SRO /SRO(l)
Date: March 5, 2002 Developed by: Raymond Keith Walton Reviewed by:
Approved by:
Date: 3/14/2002 Date:
L
b II IT I
JOB PERFORMANCE MEASURE Facility:
LaSalle N-clear Station Task No:
B.1.c Task
Title:
Main -jrbine Weekly Surveillance Test K/A
Reference:
241000A4.06 Examinee:
NRC Examiner:
Time Started:
K/A Importance:
3.9/3.9 Date:
Time Finished:
Estimated Time to 1/2:mpletion: 20 min.
Method of testing:
Pe-" rmance:
Simulated X
Actual Time Critical Task: NO Location:
X Simulator Plant Task Standard:
Required Materials:
LOS-TG-W1, Turb -e Weekly Surveillances, Rev 34,11/2/2001 General
References:
LOS-TG-W1, Turb -e Weekly Surveillances READ TO THE EXAMINEE:
I will explain the in:: al conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.
Initial Conditions:
Unit 1 is at <50% o full power.
Initiating Cue:
Unit supervisor has directed you to perform Turbine Weekly Surveillance testing per LOS-TG-W1, A, Section A.2 (BPV). All Prerequisites and Precautions have been met. The Load
['Lspatcher has given permission to perform this surveillance.
Page 2 of 8
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Setup for <50% power operations and main turbine generator on line.
Page 3 of 8
JOB PERFORMANCE MEASURE Initial Conditions:
Unit 1 is at <50% of full power.
Initiating Cue:
Unit supervisor has directed you to perform Turbine Weekly Surveillance testing.er LOS-TG-W1, Attachment 1A, Section A.2 (BPV). All Prerequisites and Precauticos have been met. The Load Dispatcher has given permission to perform this surveillance.
Inform your supervisor when this task has been completed.
Page 4 of 8
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E CO E
z o
C)
D 0
Expected Response "1.
TEST OPEN Turbine Bypass Valve 1B21-MSBPV-1:
- a. CHECK BPV Ready to Select light is energized.
- b. Place the BYPASS VALVE TEST selector SW in Postion 1
- c. DEPRESS the TEST BYPASS VALVE button.
- d. Release the TEST BYPASS VALVE button.
- 2.
TEST OPEN Turbine Bypass Valve 1B21-MSBPV-2:
- a. CHECK BPV Ready to Select light is energized.
- b. Place the BYPASS VALVE TEST selector SW in Position
- 2.
- c. DEPRESS the TEST BYPASS VALVE button.
- d. Release the TEST BYPASS VALVE button.
- 3.
Candidate REFOR I S failure of MSBP\\V-2 tQ,,
,1,i final 10% of travel.
BPV Ready to Select light is energized Bypass Valve Test selector switch in Postion 1.
Depresses the TEST BYPASS VALVE button 1 B21 -MS-BPV-1 goes to Full open exhibiting fast open characteristics the final 10% of travel.
Test Bypass Valve button released 1 B21 MS-BPV-1 goes to Full closed.
BPV Ready to Select light is energized Bypass Valve Test selector switch in Position 2.
Depresses the TEST BYPASS VALVE button.
1B21-MSBPV-2 goes to Full open exhibiting fast open characteristics final 10% of travel.
Test Bypass Valve button released 1 B21 MSBPV-2 goes to Full closed.
CUE: Unit Supervisor acknowlý. -
failure. US will activate TADS.
Page 5 of 8 Element
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
Expected Response E
oU)
E
Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
8 of 8
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Stuck Control Rod Drive Examination Level: RO /SRO /SRO(I)
Date: April 8, 2002 Developed by: Raymond Keith Walton Date:
Reviewed by:
Date:
- roved L, II II
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.1.d Task
Title:
Stuck Control Rod Drive K/A
Reference:
201001A4.04 K/A Importance:
3.1/3.0 Examinee:
NRC Examiner:
Date:
Time Started:
Time Finished:
Estimated Time to Completion:
Time Critical Task: NO Method of testing:
Performance:
Simulated Location:
X Simulator X
Actual Plant Task Standard:
Required Materials:
Copy of LAP 100-13, Attachment C, for rod moves.
General
References:
LOA-RD-1 01, Control Rod Drive Abnormal, Rev 4, 3/27/2001 LAP 100-13, Control Rod Sequence Package Preparation, Review and Implementation.
READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.
Initial Conditions:
Unit 1 at full power operation.
Initiating Cue:
Unit Supervisor has instructed you to adjust control rods lAW LAP 100-13, Attachment C and qualified nuco'ar engineer instructions.
Page 2 of 7
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Setup for full power operations
- 2.
Have "in-step" CRD stick at present position. CRD will not respond to manual rod motion controls.
Page 3 of 7
JOB PERFORMANCE MEASURE INITIAL CONDITIONS Initial Conditions:
Unit 1 at full power operation.
Initiating Cue:
Unit Supervisor has instructed you to ac-just control rods lAW LAP 100-13, Attachment C and qualified nuclear engineer instructions.
Page 4 of -
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
Expected Response 44:
E H-U)
E z
o UW D
0
- 1.
Operator reviews LAP 100-13, Attachment C for CRD moves.
- 2.
ATTEMPTS to INSERT CRD
(?) by DEPRESSING notch in Pushbutton.
"3.
NOTIFIES Unit Supervisor that CRD will not move.
Candidate reviews LAP 100-13, Attachment C. Notes that rods are to be moved in 4 steps.
CRD (?) selected. Candidate depresses CRD INSERT pushbutton.
NOTE: Candidate should refer to LOA RD-1 01, CRD Abnormal Procedure, Section B.5.
CUE: Unit Supervisor acknowledges problems with CRD moving. Need to move rods!
- 4.
VERIFIES CRD Hydraulic System NORMAL.
- 5.
CHECK Control Rod Position Indication is NORMAL.
- 6.
Attempts to INSERT CRD (?).
OBSERVE Directional Control Valve Sequencing.
- 7.
CHECK Directional Control Valve Sequencinq NORMAL.
- 8.
CHECK GRD ('2 F:i',nd to move with drive war
<450 psid.
CRD Hydraulic System is Normal.
Control Rod Position indication system normal.
Attempts to insert control rod but control rod does not move.
Directional Control Valve Sequencing normal.
CRD (?) Failed to move with drive water prw
<-450 psid.
Page 5 of 7 Element
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
NOTE TO EXAMINER:
INITIATE ALTERNATE PATH PORTION OF JPM.
Goal is to insert CRD by increasing CRD pressure by throttling on CRD PCV.
Expected Response E
Cl)
E z
0 I)
D 0
- 9.
RAISE Drive Water pressure to 500 psid.
- 10.
Attempt to INSERT CRD (?).
Depresses CRM INSERT pushbutton
"*11. RAISE Drive Water Pressure to 550 psid.
"*12.
Depresses CRM INSERT pushbutton
"*13 RETURN Drive Water pressure to NORMAL
"*14.
Attempts to more CRD (?) In 1 notch.
(CUE) THIS COMPLETES THIS JPM Record Stop Time:
Candidate adjusts drive water pressure to 500 psid by throttling PCV 1C11-F003.
Depresses CRM INSERT pushbutton. Control Rod has not moved.
Candidate adjusts drive water pressure to 550 psid by throttling PCV 1C11-F003.
Control Rod moves. Candidate moves CRD (?) In 1 notch Candidate adjusts drive water pressure to <450 psid by throttling PCV 1C11-F003 Candidate depresses CRM pushbuttop. CRD (?) Moves in one notch.
P (ý,.4, of 7 Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's sicnature and date:
Fa-c " of 7
LaSalle Station UNIT I,-2 AND COMMON OPERATING DEPARTMENT SURVEILLANCE TECHNICAL SPECIFICATIONS WEEKLY SURVEILLANCES LOS-AA-W 1 Revision 47 March 13, 2002 7
/
T,-
STP TH Acj R EVIEW Procedure Resi)onsibility/Review/Approval Requiremients Responsible Department Head:
SOS Minimum Review Tvpe:
TR Required Cross-Discipline Review(s):
QNE & ISTC Annro, al Position Reiu i red: I SOS SpCcifiIC Requirements:
- 1.
Rc,1:,-/Approval requirements apj)y to non-editorial proccdw;
, sions.
lov', of Use "c
ce I of 72 Approval Position Required: I
TECHNICAL SPECIFICATIONS WEEKLY SURVEILLANCES TABLE OF CONTENTS A.
P U R P O S E.......................................................................................................................
3 B.
PRER EQ U ISITES...................................................................................................
8 C.
P R E C A U T IO N S..............................................................................................................
9 D.
L IM IT A T IO N S...............................................................................................................
9 E.
P,RO C E D U RE...............................................................................................................
I I F.
REV IEW A N D SIG NO FF.......................................................................................
28 G.
R E F E R E N C E S..............................................................................................................
28 ATTACHMENTS I A Unit One Technical Specification Weekly Surveillance Sign-Off Sheet.........
.29 113 Unit One Rod Operability Check Sign-Off Sheet For Fully Withdraw\\ n Rocs....... 38 I B-hnt Unit One Rod Operability Check Sign-Off Sheet For Intermediate Rods............. 44 I C Unit One CRD Accum ulator Pressures..........................................................
45 II)
Unit One Technical Specification Weekly Offsite Power Lineup Verification....... 46 1 E Unit One Control Room / AEER AC Power Lineup Verification................... 49 2A Unit Two Technical Specification Weekly Surveillance Sign-Off Sheet............... 5 I 2B Unit Two Rod Operability Check Sign-Off Sheet For Fully Withdrawn Rods...... 60 2B-lnt Unit Two Rod Operability Check Sign-Off Sheet For Intermediate Rods......
66 2C Unit Two CRD Accumulator Pressures........................................................... 67 2D Unit Two Technical Specification Weekly Offsite Power Lineup Verification...... 68 2E Unit Two Control Room / AEER AC Power Lineup Verification...................
7 I Lo,'2. of Use LCS-A-\\\\ I "2 of 72 RcNi ioi' -4
..- mc nce
-llc
TECHNICAL SPECIFICATION WEEKLY SURVEILLANCES A.
PURPOSE A. I Objective To satisfy the following Technical Specification week,, surveillance requirements:
Tech Spec SR 3.1.3.2, SR 3.1.3.3, SR 3.1.3.5 and SR 3.9.5.1, Demonstrate withdrawn control rods are operable.
Tech Spec SR 3.1.5. I and SR 3.9.5.2, Determine each control rod scram accumulator operable.
Automatic Depressurization System Tech Spec SR 3.5.1.3 Verify ADS accumulator supply header pressure is > 150 psig. (Tech Spec requirement i', every 31 days)
Tech Spec SR 3.5.1.4 Verify ADS accumula,,or backup compressed gas system bottle pressure is > 511 psig.
(Tech Spec requirement is every 31 days)
Containment:
Tech Spec SR 3.6.1.6.1, Verify suppression Thamber-dry,.ell vacuum breakers operable.
TRM 3.6.b, Verify suppression chamber-dr\\ 'a ell vacuum breaker closed, if vacuum breaker indication is inoperable.
Tech Spec SR 3.6.3.2. 1, Determine drywell and suppression chamber oxygen concentration within specification.
CO, System:
'1l*-nich l Requirements raNnu81 TISR 3.7.1.1 mid.TSR 3.7.1.2, I,,;, Ir, pressuIre C()2 5\\v.t.fl
- ,,,,rnble.
Level of Use
-L.OS-
\\A-\\v efcerence 3 of 72 Rcilsion 47 Iq
CR / AEER Air Conditioning (AC) Breaker Alignment Tech Spec SR 3.7.5.2, Determine correct breaker alignent[I and indicated power available to control room area / AEER. ventilation AC subsystems.
Electrical Distribution:
Tech Spec SR 3.8. 1. 1, Determine required A.C. Sources Operating between the offsite transmission network and onsite Class 1 E distribution system operable.
Tech Spec SR 3.8.2. 1, Determine required A.C. Sources Shutdown between the offsite transmission network and onsite Class I E distribution system operable.
Tech Spec SR 3.8.7.1. Determine required A.C. Distribution Operating system electrical divisions operable.
Tech Spec SR 3.8.8.1, Determine required A.C. Distribution Shutdown system electrical divisions operable.
Spent Fuel Storage Pool Tech Spec SR 3.7.8. 1, Determine spent Fuel Storage Pool water level above low level limit.
A.2 Discussion Control Rods:
Operability of the control rods is verified by actual insertion of the control rods. On a weekly frequency, all control rods that are fully withdrawn when the surveillance is performed, are exercised. On a monthly frequency. all control rods that are at an intermediate position when the surveillance is performed, are exercised. An additional subsection provides methods for clearing high temperature conditions for any control rod that has a loss of cooling due to tile operability check.
Operability of control rod accunmlaIorIs is verified by checking the I ICU iaccLu ila itor pressures. lftheC II JCCI1u mLulator prcssurC is Outf (1C snuci! ied limits, corrective actions ar,,e provided.
Vc-ification of no overtravel is accom)plished during tie weekly conimlU rod Level of Use 4 o f Reference4of72 l\\iion 47 Refeencel\\V.
2O(0 JX
- I I i
E.3.2 E.1.3 E.3.3. 1 E.3. 1.2 E.3.3.3 E.3.3.4 Level of Use Reference 13 of" 72 LOS-AA-W I Revision 47 NuI'I 13, 2002 Ifreactor power is NOT above the Low Power Setpoint ofTech Spec 3.3.2. 1, ENTER a note on Attachment I A(2A) sign off sheet under "Comments" that Attachment I B(2B)/ 13-I
-nt(213-hIt) is NOT appllicable because power is at or below the Low Power Setpoint. Also, Tech Spec 3.9.5 is applicable for each CRD that is continuously Withdrawn for 7 days in Mode 5.
Itf reactor power is above the Low Power Setpoi nt:
If core thermal power is at or above 25%, DETERMINE current MFLPD and FDLRX (if applicable) Value as follows:
0 DEMAND OD-20 Option 1.
o If reactor power level has NOT changed since last CMSS Core Performance Log, CHECK that print out.
If core thermal power is at or above 2"5%, CHECK MFLI'D and FDLRX (if applicable) are less than or equal to 0.950.
o If either is greater than 0.950, a Control Rod Maneuver Request (CRMR) is required and must be obtained from a QNE.
o If both are less than or equal to 0.950, no powver reduction is necessary and a CRMR is not required.
VERIFY the APRM Gains are within 2% of RTP. Ifany ofthe GOins are out, NOTIFY IMD to perform LIS-NR-109 (209).
OBTAIN and ATTACH an OD-7 Option 2 computer edit of the Control Rod Positions. If the Process Computer is unavailable, use of the Four-Rod Display is allowed.
E.3.3.5 Level of Use.
Reference 14 of I-i)S-AA-\\W I Revision 47 ih II. 2002 For each control rod NOT at position 00, on Attachment 113(2B):
For Intermediate rods, RECORD the rod position in the column marked "Rod Position".
If Intermediate rods will NOT be exercised per Attachment I B-Int(2B-Int), ENTER N/A for each Intermediate control rod in the column marked "Initials".
If Intermediate rods will be exercised per Attachment I B-Int(2B-Int), ENTER each Intermediate control rod number and position on that Attachment and INITIAL the cohlumn marked "Initials" for each Intermediate control rod.
For rods full out (position 48), INDICATE rod position by lea% ing the "Rod Position" colunm blank.
Prior to exercising Control Rods, SELECT the "Rod Exercise" mode \\ia the RWM Touch Screen.
E.3.3.6 NOTE If required, Rod Drift Test should be performed concurrently with exercising one control rod.
While exercising Control Rods. if rods are out in Mode I or 2, at I (2)H 13-P603, TEST Rod Drift Alarm as follows:
DEPRESS the Rod Drift Test push-button.
NOTCH a control rod as followvs:
o If above the LPSP, per rod exercising steps (an edge rod is preferred) o If below the LPSP, per QNE direction.
E.3.3.7.3 VERIFY I(2)H13-P603 A504 CRD Drift alarm and red light on full core display is illuminated.
E.3.3.7.4 DEPRESS Rod Drift Reset push-button and NOTE CRD Drift alarm and I-ed light on full core display clears.
E.3.3.7.5 RECORD testing of Rod Drift Alarm on Attachment IB(2B).
CAUTION Elevated drive water pressures may result in multiple rod notch moves during rod Cxercising.
I NSERT acah 1-:;:,
ontiol Rod one (1) notV:
'al whi Ic monitoring the Rod poylition and OBSERVE thait the Pod has moved.
I 15 of!72 LOS-AA-W1 Re\\ ision 47 1Iamrch 13, 200?
E.3.3.7 E.3.3.7. 1 E.3.3.7.2 NOTES If any control rod multiple notches % hile exercising, the Shift Manager or his designee should be notified to determine if CRD Flushing should be performed. Control Rod Drive Problem Identification sheet of Attachment 1(2)B and a Condition Report shall be completed for any control rod that multiple notches.
CRD Flushing should NOT be perfonred on a drive if there is an associated work request written identifying the control rod as a multiple notching rod.
Level of Uqe Referpncr.
I
FE.'..
-)
E.3.
.0 r3/4,veI r U se Reter" nce~
- ) of 72 L()S-\\A\\ \\V Rc\\vision 47 NIrCIh 1)0 700, RETURN the Rod to its or i gi nal position and PERFORNI a coupling check. verifying the rod does not go to tlhe o\\'ertravel lposition.
(Tech Spec SR 3.1.3.5)
RECORD satisfactory Control Rod operation on Attachment 11(211) by initialing the "Initials" column for each rod.
For those rods full-out (position 48) idCntified as multiple notching rods which do NOT have an associated work request, if conditions permit PERFORM the following to flush the Control Rod Drive.
Elevate drive p)ressLIue to between 350-400 psid.
Apply a continLIous \\withdrawal signal and hold for 60-90 seconds.
Repeat application of continuous wilthdravwal signal at lCa.t 10 times.
For those rods which were flushed, REPEAT Rod Exercising Steps.
If the control rod multiple notches a second time, NOTE all pertinent information on Control Rod Drive Problem Identification sheet of Attachment 1(2)B and ROUTE to System Engineer to evaluate for further corrective action.
E.), -2
E.3.3.13 If Intermediate control rods are to be exercised, INSERT each Control Rod NOT at position 48 or 00, one (!I notch individually while monitoring the Rod position.
0 OBSERVE that the Rod has moved.
E.3.3.13. I RETURN the Rod to its original position.
E.3.3. 13.2 RECORD satisfactory Control Rod operation on Attachment I B Int(2B-lnt) by initialing the "Performed" column for each rod.
E.3.3.13.3 Independently VERIFY satisfactory Control Rod operation on Attachment I B-Int(2B-Int) by initialing the "Verified" column for each rod.
E.3.3.14 VERIFY all control rods required to be exercised have been checked.
INDICATE any Control Rods that were NOT tested using the following notations on Attachment IB(2B ):
o Full In - 00 o
Isolated - Isol o
Electrically Disarmed - ED E.3.3.15 OBTAIN and ATTACH an OD-7 Option 2 computer edit of the Control Rod Positions.
E.3.3.16 COMPARE the initial OD-7 obtained with the final OD-7 obtained to VERIFY there are no mispositioned rods.
i,.3..17 RETAIN Aticlhment IB(2B)/1B-Int(2B-Inii K ',tihmittal with Attachm-vic:
Level of Use LOS-AA-\\\\ i Reference 17 of 72 Revision 47 R:efecr 1, c NOTE For each control rod NOT at position 48 or 00, a second licensed operator or qualified member of the System Engineering Department shall verify the CRD movement and both the NSO performing the CRD movement and the Second Verifier shall initial on the appropriate check line.
E.3.3.18 When control rod exercising is complete:
EXIT the Rod Exercise mode.
o RETURN to Power Reduction mode.
o INCREASE core thermal power.
o RESTORE reactor power per QNE.
o INITIATE a Condition Report regarding any control rod(s) that double notched.
E.4 If CRDs become hot after exercising, ESTABLISH cooling water as follows:
E.4.1 OPEN CRD FCV to increase CRD cooling water flo'k to approximately 70 gpm for intermediate position hot CRDs.
E.4. 1.1 If 70 (pm cannot be obtained with the CRD FCV I 00<- open, CRD drive water differential pressure should be temporarily lowered.
NOTE The increased flow should be maintained for up to fifteen minutes, in an attempt to clear as many of the hot CRDs as possible.
E.4.1.2 After flushing, CHECK that:
CRD system parameters return to the normal ranges.
Any CRD filter dP alarms caused by this evolution are clear.
I-ev, :i of Use LSA-V n o f 72 Rc\\ision 47 K
r.re,-ce
",trch 13, 200?
ATTACHMENT l B UNIT ONE ROD OPERABILITY CHECK SIGN-OFF SHEET FOR FULLY WVITHtDRA\\WN ROI)S OBTAIN and ATTACH an OD-7 Option 2.
Rod Drift Alarm Tested Sat (Mode I or _)
RECORD satisfactory Control Rod operation.
/
/
ROD ROD:`
INITIALS ROD ROD:ý:
INITIALS ROD ROD::
INITIALS NO.
POSITION No.
POSITION No.
POSITION
[4-07 14-11 14-15 14-19 14-23 14-27 14-31 14-35 14-39 14-43 14-47 14-51 02-19 0 2-2 3 02-27 02-31 02-35 02-39 02-43 06-15 06-19 0{6-23 06-27 06-3 I 06-35 06-39
- NOTATIONS for Rod Position Column Intermediate Position -Rod Position Full Iii - K00 ElIctrically Disarmed - ED Fuli ()'I[
icaI\\e llank t evel of Use Reference 38 of 72 L OS
\\.A....
Rei1,ion -.,
Mlarch !3.2(!'
E.3.3.3 E.3.3.6.5 E.3.3.9 06-43 06-47 10- I 10_ I I10-_
1 10-23 10- 2 10-31 10-35 10-39 1)-43 10 47 10-51 14-55
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Failure of SBGT System to Automatically Initiate Examination Level: RO /SRO /SRO(I)
Date: April 8, 2002 Developed by: Raymond Keith Walton Reviewed by:
Apprcx,.c Date: 3/14/2002 Date:
1!
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.1.e Task
Title:
Fuel Assembly Damagqe Results in Manual Actuation of ESF System K/A
Reference:
261 000A2.12 Examinee:
NRC Examiner:
Time Started:
K/A Importance:
3.2/3.4 Date:
Time Finished:
Estimated Time to Completion:
Method of testing:
Performance:
Simulated X
Actual Time Critical Task: NO Location:
X Simulator Plant Task Standard:
Required Materials:
LOA-FH-001, Irradiated Fuel Assembly Damage, Rev 0, 7/31/1996 LOP-VG-01, Preparation for Standby Operation of the SBGT System, Rev. 9, 11/6/2000 General
References:
LOA-FH-001, Irradiated Fuel Assembly Damage, Rev 0, 7/31/1996 LOP-VG-01, Preparation for Standby Operation of the SBGT System, Rev. 9, 11/6/2000 READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.
Initial Conditions:
Unit 1 is in Mode 5 with fuel shuffles in progress. Unit 2 is operating in Mode 1. Fuel handling supervisor calls you in control room to inform you that they have just dropped a fuel bundle in the spent fuel pool. The dropped fuel is emitting gas bubbles. The radiation monitor on the fuel handling bridge is alarming. RP personnel have ordered an evacuation of thc refuel floor.
Initiating Cue:
Thr, Unit Supervisor h:ý-
t ', you to implement LOP. -' I or),
'1 rrm your supervisor,.L"*'r `- lack i as been completed.
Page 2 of 1
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Reset Simulator to IC 26 (rst 26).
NOTE: It is OK to use a similar IC to the IC listec above, provided the IC actually used to verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2.
Set Simulator up for Mode 5 operations.
- 3.
Enter fault: SBGT system does not start with the control switch.
- 4.
About 10 seconds after starting this JPM, insert annunciator H13-P601-E306, Fuel Pool Vent Rad Hi, in alarm condition.
Page 3 of 7
JOB PERFORMANCE MEASURE INITIAL CONDITIONS Unit 1 is in Mode 5 with fuel shuffles in progress.
° Unit 2 is operating in Mode 1.
° Fuel handling supervisor calls you in the control room to inform you that they have just dropped a fuel bundle in the spent fuel pool.
The dropped fuel is emitting gas bubbles. The radiation monitor on the fuel handling bridge is alarming.
RP personnel have ordered an evacuation of the refuel floor.
Initiating Cue:
The Unit Supervisor has directed you to implement LOA-FH-001. Inform your supervisor when this task has been completed.
Pagc 4 e
I
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
NOTE: All steps of the JPM are to be completed at Control Room E
<)
E H-co~ E z
o W3 D
0 Expected Response
- 1.
REFERS to LOA-FH-101, Irradiated Fuel Assembly Damage.
- 2.
CHECK Reactor Bldg Exhaust Duct Radiation <10 mr/hr.
- 3.
VERIFY that Reactor Bldg Ventilation System isolates Locates and opens LOA-FH-1 01.
RB exhaust radiation >10 mr/hr Annunciators H13-P601-E204, E205 &
Annunciators H13-P601 -F204, F205 illuminated.
Verifies RB Ventilation fans off and RB Ventilation inlet/outlet valves closed.
- 4.
IDENTIFY SBGT system failed SBGT fans NOT operating, SBGT to start.
valves did NOT open.
- 5.
Informs Unit Supervisor that SBGT failed to start.
- 6.
START SBGT by DEPRESSING SBGT Test Push button on Panel PM07J.
- 7.
Informs Unit Supervisor that SBGT failed to start using Manual System Test Pushh, Mtton.
If the candidate asks CUE: Start SBGT using the Manual System Test Pushbutton on Panel PM07J.
Depresses SBGT PB on PM07J.
SBGT fans NOT operating, SBGT valves did NOT open.
CUE: Need to have SBGT operating.
PaEte 5 -l1 7 Element
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
NOTE TO EXAMINER: INITIATE ALTERNATE PATH PORTION OF JPM.
Goal is to manually initiate SBGT system.
Expected Response I--
o E
CO E
z o
C)
D 0
- 8.
REFERs to LGA-VG-1 01, Secondary Containment Pressure Control.
- 9.
Manually lines up and initiates least one SBGT system lAW LGA-VG-101, Secondary Containment Pressure Control.
S SUSPEND all refueling operations.
ti*.
EVACUATE unnecessary personnel from Refuel Floor.
Locates and Opens LGA-VG-101 at OPEN:
1/2VG002, SBGT Inlet Isol Valve.
1/2VG003, SBGT Disch Isol Valve.
ON:
1/2VG01 C, SBGT Primary fan 1/2VG01A, SBGT Electric Htr Coil OFF:
1/2VG02C, SBGT Cooling Fan Verify flow 3600 - 4400 CFM on 1/2FR-VG009 & 1/2FI-VG003.
Picks up CR phone, calls refuel floor RP desk and informs supervisor to suspend all refueling operations and evacuate personnel from refuel floor.
CUE: THIS COMPLETES THIS JPM Record Stop Time: _
!';,lw; 6 of 7 Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Exm mincr', signature and date:
Page 7 of 7
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Transfer Electrical Loads from SAT 142 to UAT 141 Examination Level: RO /SRO /SRO(I)
Date: March 5, 2002 Developed by: Raymond Keith Walton Date:
Reviewed by:
Date:
Approvcd by K
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.1.f Task
Title:
Transfer Loads from SAT 142 to UAT 141 K/A
Reference:
262001 K5.01 K/A Importance:
Examinee:
NRC Examiner:
Time Started:
Estimated Time to Completion:
Method of testing:
Performance:
Simulated X
Actual Date:
Time Finished:
Time Critical Task: NO Location:
X Simulator
__ Plant Task Standard:
Required Materials:
LOP-AP-08, System Auxiliary Transformer SAT 142 Operation in Shutdown, Rev 25, 4/2/2002.
General
References:
LOP-AP-08, System Auxiliary Transformer SAT 142 Operation in Shutdown LOP-AP-01, Unit Auxiliary Transformer Backfeeding Operations LOR PM01J-A317, SAT 142 Trouble Alarm LOA-TRAN-1 01, Unit 1 Transformer Trouble, B1 3, Combustible Gas Monitor READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Inform me when you successfully completed the task..
Initial Conditions:
Unit 1 is shutdown (Mode 4). All electrical loads are powered from SAT 142. Ul Main Generator Disconnect Links open and UAT 141 Transformer Disconnect Links to Switchyard are closed.
BRAkfeeding operations had previously been completed lAW LOP-AP-01, Unit Auxiliary Transformer Backfeeding Operations. UAT 141 is available for backfeeding.
S,i:g Cue:
Minitor Panel PMO1J for alanms. Inhform your supervisor when this task has been completed.
Page 2 of 9 3.1/3.4
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Reset Simulator
- 2.
Set up Simulator for Mode 4 with Unit 2 at full power.
- 3.
All Unit 1 loads powered from SAT 142. ACBs 1415 & 1425 are closed.
- 4.
Backfeed operations for UAT141 have been completed, Generator Output disconnect open, UAT141 Transformer Output disconnect closed.
- 5.
When cued by examiner, input annunciator SAT 142 Trouble alarm (PM01J-A317).
- 6.
After a short period of time, call and inform candidate that SAT 142 has a high gas concentration. Fifth LED OFF (Confirms very high gas reading). Other LED status as follows: first LED: blinking yellow, second LED ON (green), third LED ON (green), fourth LED ON (green). If asked, sixth LED is OFF (high gas reading). Gas level is
-(?)
JOB PERFORMANCE MEASURE INITIAL CONDITIONS (To be read by examinee)
Initial Conditiors:
Unit 1 is shutdcwn (Mode 4). All electrical loads are powered from SAT 142. Ul Main Generator Disconnect Links open and UAT 141 Transformer Disconnect Links to Switchyard are closed. Backfeeding operations had previously been completed lAW LOP-AP-01,Unit Auxiliary Trans-ormer Backfeeding Operations. UAT 141 is available for backfeeding.
Initiating Cue:
Monitor Panel PM01J for alarms.
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
Element
- 1.
Annunciator PM01J-A317 alarms.
- 2.
Refers to annunciator response procedure. Requires that an operator be DISPATCHED to SAT 142.
Expected Response Candidate reviews annunciator response procedure for alarm.
I--
o E
SZo E
Z o
Cl)
D 0
Candidate calls simulator operator and dispatches auxiliary operator to SAT 142.
CUE: Receives a call from operator stating that the Combustible Gas Monitor is Alarming.
- 3.
REFERS to LOA-TRAN-1 01:
CHECK SAT 142 energized C
- 4.
REMOVE Outer Monitor Cover and locate 6 small LEDs
- 5.
CHECK fifth LED OFF
- 6.
VERIFY the Combustible Gas Monitor is operating properly:
CHECK status of LEDs:1I t LED blinking yellow: 2nd, 3rd & 4t" LEDs are ON (green)
- 7.
CONTACT System Engineering with Gas Level.
- 8.
IMMEDIATELY REMOVE SAT 142 from service On Panel PM01J: SAT 142 indicates energized Directs NLO to perform actions.
(NLO reports that 51 LED is ON) 1st LED blinking yellow: 2nd, 3rd & 4h LEDs are ON (green) (Normal conditions).
CUE: Shift Supv to contact System Engineering Candidate RECOMMENDS removing loads from SAT 142 CUE: Inform candidate to transfer electrical loads from SAT 142 to UfA-14i by establishing a backfeed lAW LOP-AP-08, 'SAT 142 Operation in Shutd.-wan," step E.1.
Page 5 of 9
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E co)
E z
o c)
D 0
Expected Response
- 9.
VERIFY UAT 141 ready to supply power for backfeeding per LOP-AP-01.
Candidate may verify 345 KV bkrs CLOSED:
OCB 1-9, OCB 9-10, OCB 10-11, OCB 11 13, OCB 1-13.
lPagc 0 of 9 Element
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
NOTE: Allow candidate to locate and review copy of LOP-AP-08.
Element
- 8.
Transfer Bus 152 from SAT to UAT:
VERIFY CLOSED ACB
- 1522, SYNCHRONIZE & CLOSE ACB 1521, OPEN ACB 1522.
- 9.
Transfer Bus 151 from SAT to UAT:
VERIFY CLOSED ACB
- 1512, SYNCHRONIZE & CLOSE ACB 1511, OPEN ACB 1512.
- 10.
- '-: : ý IRM LOS-AP-01 Expected Response SYNCHRONIZE ACB:
Engage Synchroscope for oncoming ACB.
Verify synchroscope at 12:00 position, incoming &
running voltages equal and sync lights NOT illuminated.
° Verify 6.9 KV Paralleled Bus Alarm annunciates.
Open off going circuit bkr.
Verify electrical bus parameters are normal Disengage the synchroscope.
Reset Parallelled Bus Annunciator ACB 1521 indicate closed, ACB 1522 indicates open.
SAT UNSAT SYNCHRONIZE ACB:
Engage Synchroscope for oncoming ACB.
Verify synchroscope at 12:00 position, incoming &
running voltages equal and sync lights NOT illuminated.
Verify 6.9 KV Paralleled Bus Alarm annunciates.
Open off going circuit bkr.
Verify electrical bus parameters are normal Disengage the synchroscope.
Reset Parallelled Bus Annunciator ACB 1511 indicate closed, ACB 1512 indicates open.
SAT UNSAT O:J7 Step E.1.4, LOS-AP-R-
.- :ate Power Source Breaker Operability Surveillance is NOT required.
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
Element Expected Response "11.
Transfer Bus 141Y & 141X from SAT to UAT:
VERIFY CLOSED ACB 1415, SYNCHRONIZE & CLOSE ACB 1411, OPEN ACB 1412
"*12.
Transfer Bus 142Y & 142X from SAT to UAT:
VERIFY CLOSED ACB 1425, SYNCHRONIZE & CLOSE ACB 1421, OPEN ACB 1422.
SYNCHRONIZE ACB:
Engage Synchroscope for oncoming ACB.
Verify synchroscope at 12:00 position, incoming
& running voltages equal and sync lights NOT illuminated.
Verify 6.9 KV Paralleled Bus Alarm annunciates.
Open off going circuit bkr.
Verify electrical bus parameters are normal Disengage the synchroscope.
Reset Parallelled Bus Annunciator ACBs 1415 & 1411 indicate closed, ACB 1412 indicates open.
SAT UNSAT SYNCHRONIZE ACB:
Engage Synchroscope for oncoming ACB.
Verify synchroscope at 12:00 position, incoming
& running voltages equal and sync lights NOT illuminated.
Verify 6.9 KV Paralleled Bus Alarm annunciates.
Open off going circuit bkr.
Verify electrical bus parameters are normal Disengage the synchroscope.
Reset Parallelled Bus Annunciator ACBs 1425 & 1421 indicate closed, ACB 1422 indicates open.
SAT.....
U 1"4 SAT CUE. This completes this JPM Corn.!etiorr.
Time:
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Reestablish Shutdown Cooling After Clearing Level 3 PCIS Signal Examination Level: RO /SRO /SRO(I)
Date: April 8, 2002 Developed by: Raymond Keith Wal.ton Reviewed by:
Approvc Date:
Date:
D-'te.:
r S
-r
----
i
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.1.g Task
Title:
Reestablish Shutdown Cooling After PCIS Level 3 Signal Cleared K/A
Reference:
20500A2.06 Examinee:
NRC Examiner:
K/A Importance: 3.4/3.5 Date:
Time Started:
Time Finished:________
Estimated Time to Completion:
Method of testing:
Performance:
Simulated X
Actual Time Critical Task: NO Location:
X Simulator Plant Task Standard:
Required Materials:
LOA-RH-101, RHR Abnormal, Rv. 4, 12/5/2000 LOP-RH-07, Shutdown Cooling System Startup, Operation and Transfer, Rv. 46,10/27/2000 General
References:
LOA-RH-101, RHR Abnormal, Rv. 4, 12/5/2000 LOP-RH-07, Shutdown Cooling System Startup, Operation and Transfer, Rv. 46,10/27/2000 READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.
Initial Conditions:
Plant is in Mode 4. A spurious PCIS Level signal 3 had occurred which resulted in 'A' RHR pump tripping and a loss of shutdown cooling. The PCIS level 3 signal has been reset. The 'B' RHRSW is out of service for maintenance. Both trains of CS are operable. The 'A' RHRSW system is in operation Initiating Cue:
The Shift Manager h,-,*.
',,ou reestablish chi
ý
,-,c!ing on 'A' train of fHR lAW.
C.'R, H 07, Shutdown Cooling c-ysLtoi Startup, Operation and i iin;ier. Inform your supervisor vviienl this task has been completed.
Page 2 of 11
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Setup Simulator for Mode 4 operations: Reactor temperature 120 degrees F, RPV pressure 100 psig, RPV water level at 50" and both recirculation pumps operating at 15 hz.
- 2.
SDC valves associated with 'A train RHR have been closed by PCIS level 3 and remain closed.
- 3.
Plant conditions as shown:
'B' RHRSW in operation
'A' RHRSW system OOS (OOS tag hung on 'B' RHRSW pump control sw)
- 3.
Input a failure for 'A' RHR pump to start.
Page 3 of 11
JOB PERFORMANCE MEASURE INITIAL CONDITIONS Initial Conditions:
Plant is in Mode 4. A spurious PCIS Level 3 signal had occurred whic-esulted in 'A' RHR pump tripping and a loss of shutdown cooling. The PCIS level 3 signa ias been reset. The 'B' RHRSW is out of service for maintenance. Both trains of CS are operaEnle. The 'A' RHRSW system is in operation.
Initiating Cue:
The Shift Manager has requested you reestablish shutdown cooling or A' train of RHR lAW LOP-RH-07, Shutdown Cooling System Startup, Operation and Transfe,. Inform your supervisor when this task has been completed.
" 0 Page 4 of I I
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E I-co E
z o
W D
0 Element Expected Response
- 1.
Refer to LOP-RH-07, Shutdown Locate and Open LOP-RH-07. Start Cooling System Startup, Operation at step E.1.
and Transfer.
CUE: RHR & SDC systems have been filled & vented.
Cycled Condensate is in operation and RBEDT is available.
- 2.
DECLARE LPCI Mode of 'A' RHR inoperable.
- 3.
CLOSE valves:
1E12-F004A, A RHR Pmp Suction 1E12-F064A, A RHR In Flow
- 4.
OPEN valve 1E12-F006A, A RHR shutdown cooling suction valve.
- 5.
LOCALLY CLOSE 1 El 2-F085A, A RHR/LPCS Water Leg Pump Discharge Valve.
- 6.
VERIFY OPEN 1 E12-F048A, A RHR Hx Bypass VIv.
- 7.
VERIFY CLOSED:
1 El 2-F047A, A RHR Hx Inlet VIv 1 F-12-FO03A, A RHR Hx Outlet VIv CUE: Shift Manager notified.
1E12-F004A and 1E12-F064A valves -
indicate closed.
1 E12-FO06A valve indicates open CUE: Operator reports 1E12-F085A -
valve closed.
1 E12-F048A valve indicates open.
1 El 2-F047A and 1 El 2-FO03A valves indicate closed.
Page 5 of 11
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
Element
- 9.
VERIFY OPEN valves:
1E12-FO08, RHR Shutdown Cooling Suction Inboard and 1E12-FO09, RHR Shutdown Cooling Suction Outboard Isolation
- 10.
Start RHRSW pump.
- 11.
If reactor water temperature exceeds 'A' RHR Hx outlet temperature by 100 degrees F, perform warmup procedure.
- 12.
CHECK both recirculation pumps in operation. Both recirc suction and discharge valves OPEN.
"*13. OPEN 1E12-FO47A, 'A' RHR Hx Inlet Vlv.
- 14.
VERIFY OPEN 1E12-F048A, A' RHR Hx Bypass VIv.
Expected Response E
U)
E z
o U)
D 0
CUE: 1E12-F008 chain operator unlocked and removed.
Bkr for 1E12-F008 valve previously closed.
Valves 1 E12-F008 and 1E12-F009 indicate closed. Operator opens F008 and F009 valves.
Should verify RHRSW 'A' pump operating.
Cue: If necessary, warmup procedure waived by Shift Manager.
Verifies both recirulation pumps in operation with suction and discharge valve open.
Opens 1 E12-F047A.
1 El 2-F048A indicates ope' P-ge 6 of 1.1
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E o
E z
c Co DO© Expected Response
- 15.
VERIFY CLOSED Vlvs:
1 El 2-F053A, 'A' Shutdown Cooling Return Isolation Vlv.
1E12-F003B, 'A' RHR Hx Outlet Vlv.
- 16.
VERIFY Reactor Level >40"
"*17. Attempts to Start 'A' RHR pump. Identifies that pump does NOT start
"*18. DETERMINES pump inoperable and trips 'A' RHR pump.
1 El 2-F053A & 1 El 2-F003A indicate closed.
Verifies Reactor Level >40" Candidate attempts to start pump.
Verifies by looking at Pump amps, flow rate and pump breaker indication light that pump does NOT start.
Pump switch in OFF position NOTE TO EXAMINER: Initiate Alternate Path portion of JPM. Goal is to establish an alternative method of removing decay heat from core.
"*19. REFERS to LOA-RH-101, "U1 RHR Abnormal," Section B.1, step 4.5.1.
Recommends another heat removal method.
NOTE: Methods of alternative decay heat removal are prioritized. Applicant should recommend 'A' SDC (drain path) and LPCS (charging path). If candidate recommends another method of SDC, as Shift Supervisor, have candidate perform LOP-RH-17, "PJtcrnte Shutdown Cooling"' using 'A' train shutdown-,
rooing suction and L.-.
return. Hand chndid.4' A1.-chment A of LOP-RH 17 (Signatures on items 3 for steps E.16_and E.17).
- 20.
Rcviews Attachment A of LOP-RH-17.
Reviews Attachment A -f LOP RH-1 7.
Page 7 of 11 Standard
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk) 41:1 F-
-C E
I-CO E
z o
co DO0 Element Expected Response
"*21 OPEN E12-F047A,'A' RHR Hx E12-F047A indicates OPEN Inlet Valve.
- 22.
VERIFY CLOSED:
E12-FO03A, 'A' RHR Hx Outlet valve E12-FO04A, 'A' RHR pump Suction Valve E12-F065A, 'A' RHR Hx level Controller
- 23.
VERIFY:
E12-FO51A, 'A' RHR Hx Press.
Controller E12-R605, RHR Hx Drain to RCIC Suct. Press Controller.
- 24.
PLACE applicable air supply isolation switch (no EPN) in OPEN: E12-F065A/51A.
- 25 VERIFY the following valves are CLOSED:
E12-F074A, 'A' RHR Hx vent Upstream valve E12-F073A, 'A' RHR Hx vent Downstream valve E12-F052A, 'A' RHR Hx Steam inlet valve
E12-FO03A, indicates closed El12-F004A, indicates closed.
E12-R604A in Manual and full closed.
Switch El 2-R606A in Manual and full closed.
Switch E12-R605 in Manual and full closed E12-F065A/51A air supply switch in OPEN E12-F074A indicates closed.
E12-F073A indicates :closed.
E12-F052A indicates closed.
EL1 2-FO48A indicatc El 2-F026A indicates closed.
Page 8 of 11
JOB PERFORMANCE MEASURE (Denote c-tical steps with an asterisk)
E E
F-U)
E z
o cU)
DO Expected Response
- 27. OPEN E12-F008 & E12-F009, RHP SDC Suct.Outboard and Inbcard Isol Valves.
- 28. READS NOTE in LOP-RH-17.
Mus: keep drain flow >450 gpm and must read Computer digital poin:s to determine drain flow rate.
Orders NLO to Open E12-F020.
E12-F008 and E12-F009 Valves indicate open.
Accesses computer points A800.
Valve El 2-FO06A indicate open
- 30.
START 'A' RHR Service Water. Verifies 'A' RHRSW operating.
- 31.
NOTIFY RP of changing dose rates.
- 32. OPERATE LPCS pump per LOP-LP-05:
Verify open DG035, LPCS Pump Cooler Isol. Valve.
START LPCS pump E21-COO1.
Throttle open E21-F012, LPCS Tes: to SP valve Establish flow rate between 6000 gpm to 6500 gpm.
CUE: SS will notify RP of changing dose rates.
CUE: Time does not permit performing steps E.A and E.2.
DG035 indicates open.
LPCS pump indicates ON E21-F012 indiopns opcn Flow rate established between 6000 gpm and 6500 gpm.
Page 9 of 1I Eler-ent
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E W E I--
Ci)
E z
o W9 D
0 Expected Response
- 32. OPERATE LPCS Pump per LOP-LP-05, (Cont'd)
VERIFY E21-F011, LPCS Pump Min Flow valve closes.
VERIFY PM01J, 0 EDG Cooling Water Pump RUNNING.
VERIFY Local CSCS Equipment Cooling panel operating.
RAISE reactor water level:
Throttle Open E21 -FOO5, LPCS Injection Valve.
CLOSE E12-F048A, 'A' RHR Hx Bypass Valve.
OPEN E12-F003A, 'A' RHR Hx Outlet Valve.
- 35. OBTAIN desired cooldown rate of less than 100 °F/hr by adjusting drain flow.
CUE: THIS COMPLETE3 THIS JPM.
Record Stop Time:
E21 -F01 1 indicates Closed.
0 EDG Cooling Water Pump running.
Local Operator calls from local panel and states all equipment is running.
E21 F005 throttled open.
E12F048A indicates closed.
E12-FO03A indicates open.
E12F024A indicates open. Candidate monitors flow rate on computer point A800.
Establishes cooldown rate of
<100°F/hr Page 1001 1I Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
Page Ilof II
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Startup RPS MG Set and Transfer Power from Alternate Source to Normal Source Examination Level: RO /SRO /SRO(I)
Date: April 8, 2002 Developed by: Raymond Keith Walton Reviewed by:
Approved by: _____
Date: 3/14/2002 Date:
Dato:
-i
n=a-a
-a
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.2.a Task
Title:
Startup RPS MG Set and Transfer Power from Alternate Source to Normal Source K/A
Reference:
212000A2.02 Examinee:
NRC Examiner:
Time Started:
Estimated Time to Completion:
Method of testing:
Performance:
X Simulated Actual K/A Importance:
3.7/3.9 Date:
Time Finished:________
Time Critical Task: NO Location:
Simulator X Plant Task Standard:
Required Materials:
LOP-RX-01, RPS MGS Set Startup and Operation LOP-RX-03, RPS Bus A Transfer General
References:
LOP-RX-01, RPS MGS Set Startup and Operation LOP-RX-03, RPS Bus A Transfer READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues, Inform me when you have successfully completed the task.
Initial Conditions:
Unit 1 is operating in Mode 1. Bus 'A' RPS power is on Alternate supply. There are no surveillances being performed which produce half RPS or half PCIS actuations.
Initiating Cue:
You have been instructed by the Shift Manager to Startup the 'A' RPS MG set and transfer RPS power from Alternatc to -Normal. Previously, an operator Ihad completed prerequisite steps for the LOP-OP-03 RPS MG !
!-'-:'*,i-*
p Procedure. The samr ý
_rr
,r also completed prereq~i.
a*.-
.s and steps E.1 through E., ior HPS Bus 'A' Transfer Operaoi ig vrocedure. Inform your supe visor whien tis task has been comr1/2tted.
Page 2 of 8
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
NONE: In-plant Page 3 of 8
JOB PERFORMANCE MEASURE INITIAL CONDITIONS (To be read by examinee)
Initial Conditions:
Unit 1 is operating in Mode 1. Bus 'A' RPS power is c-i Alternate supply. There are no surveillances being performed which produce half RFS or half PCIS acuations.
Initiating Cue:
You have been instructed by the Shift Manager to:
Startup the 'A' RPS MG set lAW LOP-RP-01, ýRPS MG Set Startup and Operation" and Transfer RPS power from Alternate to Normal 1AW LOP-RP-03, "RPS Bus A Transfer."
Previously, an operator had:
completed prerequisite steps for LOP-RP-01, flPS MG Set Startup Procedure" and
° completed prerequisite steps E.1 through E.7 'or LOP-RP-03, "RPS Bus 'A' Transfer" Operating Procedure.
Inform your supervisor when this task has been comp eted.
])hge 4 of 8
JOB PERFORMANCE MEASURE (Denote crilcal steps with an asterisk)
All plant operations are to be simulated.
CUE: Give candidate partially completed copies of LOP-RP-01 and LOP-RP-03 Expected Response E
Z 0
U)
Z 0
- 5. PRESS and HOLD the 'A' RPS MG set Motor On pushbutton (1 PB) at local 'A' RPS MG set control panel. Observe:
"* Motor ON light illuminates
"* Local volt meter indicates 120 VAC.
RELEASE Motor ON pushbutton.
- 7. *,wuk Electrical Protection Ascrmbly (EPA) breaker 1C71 -SO03A Red Motor Gen liaht ON.
Locate and Open LOP-RP-01 Procedures. Candidate to perform steps E.1 and E.2 of LOP-RP-01.
Candidate closes Feeder Breaker 135X-2, A-5.
Candidate starts the 'A' RPS MG set.
'A' RPS MG set output breaker checked open.
Candidate presses and holds 1 PB to
CUE: Motor ON light illuminates Local Voltmeter indicates 120 VAC.
Candidate closes 'A' BPS MG set output breaker CUE: EPA bkr 1C71-,Suu3A tied Motor Gen light ON.
Page 5 of 8 Element
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E I-0 E
.<1 Z
o Cl)
D 0
Expected Response
- 8. CLOSE EPA breaker 1 C71 -SO03A.
- 9. Check Electrical Protection Assembly (EPA) breaker 1C71-S003A Red RPS bus light ON.
- 10.
Check Electrical Protection Assembly (EPA) breaker 1C71 -SO03C Red Motor Gen light ON.
"*11.
CLOSE EPA breaker 1 C71 -S003C.
- 12.
Check Electrical Protection Assembly (EPA) breaker 1 C71 -SO03C Red RPS bus light ON.
- 13.
Main Control Room panel 1H13-P610 white Generator A' feed light illuminated.
CUE: EPA bkr 1C71-S003A breaker indicates closed CUE: EPA bkr 1C71-SO03A Red RPS Bus light ON.
CUE: EPA bkr 1C71-S003C Red Motor Gen light ON.
CUE: EPA bkr 1C71-S003C breaker indicates closed CUE: EPA bkr 1C71-SO03C Red RPS Bus light ON.
CUE: 1H13-P610 white Generator
'A' feed light illuminated in MCR.
"*'cTE:
Operator s-.
- -1tn.
from LOP-RP
+- ' nD-RP-03. Start "t c '
LOP-RP-03.
,iIJ,u,Ldate should N/AsIep L.o.
Page 6 of 8 Standard
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
C)
E I-03 E
z o
- 03) 0 Expected Response
- 14.
At 1H13-P610, VERIFY the GEN A Feed lamp is energized.
- 15.
VERIFY plant conditions will allow a half scram and half isolation.
"*16.
SLOWLY position the RPS BUS Power Supply Transfer Switch to NORM.
Feed Lamp Energized.
CUE: Plant conditions allow half RPS and half PCIS.
CUE: RPS BUS Power Supply Transfer Switch to NORM. Not necessary to RESET half scram or half PCIS, this will be done by another operator.
(CUE) THIS COMPLETES THIS JPM Record Stop Time:
Page 7 of 8 Element
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
Page 8 of f.
LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Startup and Operation of RCIC from the Remote Shutdown Panel Examination Level: RO /SRO /SRO(!)
Date: April 8, 2002 Developed by: Raymond Keith Walton Reviewed by:
Date: 3/14/2002 '
Date:
I.,
I ___________________________
__d by:
Date:
JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:
B.2.b Task
Title:
Startup and Operate RCIC from Remote Shutdown Panel K/A
Reference:
295016 AA2.02 Examinee:
NRC Examiner:
Time Started:
K/A Importance:
4.2/4.3 Date:
Time Finished:________
Estimated Time to Completion:
Method of testing:
Performance:
X Simulated Actual Time Critical Task: NO Location:
X Simulator Plant Task Standard:
Required Materials:
Copy of LOP-RX-04, Startup and Operation of RCIC from the Remote Shutdown Panel, Rev 12, 10/17/2000 General
References:
Licensee JPM S-RX-05, Rev 6, 8/31/1999 LOP-RX-04, Startup and Operation of RCIC from the Remote Shutdown Panel, Rev 12, 10/17/2000 READ TO THE EXAMINEE:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Inform me when you have successfully complete the task.
Initial Conditions:
The Control Room has been evacuated. Control has been transferred to the Remote Shutdown Panel.
Suppression Pool Cooling has been established from the Remote Shutdown Panel. Ul CYtank level has been locally verified to be above 15 feet. Plant operators are available.
Initiating Cue:
The Unit SUPý!Vrc.,.,K Ihas directed you to start RFIC from the Remote Shutdown Pancl and inject and stabiw! 7.'W
';m the Unit EuIcr,'
.'h.-n RCIC is injecting and le"'-! hIc-ctobilized. Inform your supe, v,,ui v, it,,, a11 task has been ooi,,itec.
Page ? of 8
JOB PERFORMANCE MEASURE Simulator Setup Instructions:
- 1.
Reset Simulator
- a.
Insert malfunction to prevent RCIC automatic initiation, (imf mnb080-150)
- b.
Place MDRFP control switch in PTL
- c.
- d.
Place the mode switch to Shutdown
- e.
Trip both TDRFPs and close the FW01OA and FW01OB valves
- f.
Place all Remote Shutdown Panel transfer switches to Emergency lAW LOA-RX-101.
- g.
Start Suppression Pool Coolin lAW LOP-RX-06
- h.
Stabilize reactor water level between -30 inches to -10 inches.
- i.
Verify the RCIC turbine trip light is NOT lit on RSP.
- 2.
Freeze simulator until examinee has acknowledged the initiating cue(to prevent reactor water level from going too high or too low for this JPM to be performed)
- 3.
Have a copy of LOP-RX-04 available to replace one used by examinee.
Page 3 of 8
JOB PERFORMANCE MEASURE Initial Condions:
The Control Room has been evacuated.
a Cor:rol has been transferred to the Remote Shutdown Panel.
Suporession Pool Cooling has been established from the Remote Shutdown Panel.
Ul CY tank level has been locally verified to be above 15 feet.
Plar: operators are available.
Initiating Cue:
The Unit Supervisor has directed you to start RCIC from the Remote Shutdown Panel and inject and stabilize RPV level.
Inform the Unit Supervisor when RCIC is injecting and level has stabilized. Inform your supervisor when this task has been completed.
Page 4 of 8
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
NOTE: All steps of the JPM are to be completed at the Unit 1 Remote Shutdown Panel.
Simulator Operator: Place simulator in RUN.
Element I-E SZ)
E
<c:*
Z o
C/)
D 0
Expected Response
- 1.
VERIFY RCIC flow controller is SET at 100%.
- 2.
VERIFY OPEN 1E51-F068, RCIC Turbine Exhaust Valve.
- 4. CONCURRENTLY
"* OPEN 1E51-F045, RCIC Turbine Steam Supply Stop Valve.
"* OPEN 1E51-F059, RCIC Full Flow Test to CST Stop Valve.
- 5.
START RCIC Barometric Condenser Vacuum Tank Vacuum Pump
- 6.
CHECK that RCIC Pump flow is increasing as indicated on RCIC flow controller.
Examinee adjusts RCIC flow controller to 600 gpm.
Examinee verifies valve is open.
Examinee places and holds 1 E51 F022 control switch in OPEN until valve is fully open.
Examinee simultaneously turns both control switches to OPEN.
Examinee turns control switch to START.
Examinee checks flow increasing on flow controller.
Examinee turns control switch to OPEN.
Exminee turns control switch to OPEN.
Examinee places and holds 1 E51 F022 control switch in Cl OSE until valve is f.ully closed.
Page 5 of 8
JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)
E C3)
E z
o Standard Expected Response WO D
0
- 10.
ADJUST RCIC flow controller setpoint tape to increase or decrease flow to maintain desired level.
- 11.
VERIFY that RCIC System flow indicates above 120 gpm.
- 12.
CLOSE 1E51-F059, RCIC Full Flow Test to CST Stop Valve.
- 13.
ADJUST flow to the Reactor Vessel as necessary to maintain vessel level after closing 1 E51 F022, RCIC Full Flow Test Upstream Stop Valve.
- 14.
OPERATE the Condensate Vacuum Tank Condensate Pump 1 E51 -C004 as necessary to keep the vacuum tank high level and low level lights cleared.
- 15.
NOTIFY Unit Supervisor RCIC is injecting and level is stable.
"*16 Have candidate locate remote shutdown panel in plant CUF: THIS COMPLETES THPZ JP0M.
,-u.i d Stop Time:
Examinee leaves tape setpoint at 600 gpm (level is below designated band)
Examinee verifies flow above 120 gpm.
Examinee turns control switch to CLOSE.
Examinee leaves tape setpoint at 600 gpm (Level is below designated band).
Examinee STARTS/STOPs pump as necessary to keep the lights cleared.
Examinee notifies Unit Supervisor.
Candidate locates remote shutdown panel in plant.
Page 6 of 8
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date performed:
Number of attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date:
Page, of
PREPARATION OF THE REMOTE SHUTDOWN SYSTEM FOR STANDBY OPERATION A.
PURPOSE Outline the steps necessary to prepare the Remote Shutdown Panel for standby operation.
B.
REFERENCES
- 1.
P & ID's:
- a.
M-96 (M-142), Residual Heat Removal (RHR).
- b.
M-101 (M-147), Reactor Core Isolation Cooling (RCIC).
- c.
M-68 Service Water (WS).
- d.
M-93 (M-139), Nuclear Boiler and Reactor Recirculation.
- e.
M-87 (M-134), CSCS Equipment Cooling Water System.
- f.
M-90 (M-137), Reactor Building Closed Cooling Water (RBCCW).
- g.
M-55 (M-1 16), Main Steam.
- 2.
Electrical Schematics.
- a.
IE-1(2)-4214, Remote Shutdown RS (C61).
- b.
1E-1 (2)-4226, Reactor Core Isolation Cooling RI (E5 1).
- c.
IE-1 (2)-4220, Residual Heat Removal RH (E 12).
- d.
IE-1(2)-4201, Auto Depressurization System.
- e.
IE-1(2)-4205, Reactor Recirc Pump Suction Valve.
- f.
1E-0-4449, Service Water Jockey Pump.
- g.
1E-1 (2)-4097, Service Water 1WS 113 Valve.
- h.
I E- (2)-4096, Reactor Buildinc Closed Cooling Water.
- i.
!E ] (2)-4033, Fire Detecti]6,.
- 3.
TRPIf A j......... ix F Level of Use LOP-RX-0I Reference I of 2 Revision 4 j
Seplc*fi~cr
?C)1
C.
PREREQUISITES
- 1.
None.
D.
PRECAUTIONS
- 1.
Taking a Remote Shutdown Transfer switch to the "Emergency Position",
provides system control at the Remote Shutdown Panel while disabling normal Control Room control.
- 2.
In the "Emergency Position", Automatic system initiations, Primary Containment Isolation functions, and Automatic protection of the associated components is lost.
- 3.
Taking a Remote Shutdown Transfer switch to the "Emergency Position" will cause a visual and audible alarm in the Control Room.
E.
LIMITATIONS
- 1.
The Remote Shutdown Monitoring Instrumentation shall be operable as specified in Tech Spec 3.3.3.2, TRM Appendix F.
F.
PROCEDURE
- 1.
VERIFY that the Remote Shutdown Panel is lined up in accordance with LOP-RX-01E(02E).
- 2.
VERIFY that the RCIC Flow Controller at the Remote Shutdown Panel is set at:
- a.
600 gpm.
- b.
AUTO.
- 3.
VERIFY that valve and pump control switches located on the Remote Shutdown Panel are in accordance with LOP-RX-0 IT.
G.
CHECKLISTS
- 1.
None.
H.
TECHNICAL ?,.PECIFICATION REFETFN(C7S
- 1.
'1 ech Spec 33.3.2, Remote Shutdow,,ii Mt onitoring: System Level of Use Reference 2 of12 i,OP-RX-01 Revision 4 S.!,,il, 14, 2001
TRANSFER OF REACTOR SUPERVISORY INDICATION TO THE REMOTE SHUTDOWN PANEL A.
PURPOSE A.I Objective Outline the steps necessary to transfer reactor supervisory indication to the Remote Shutdown Panel.
B.
PREREQUISITES B. 1 The Remote Shutdown System is prepared for standby operation in accordance with LOP-RX-01, Pýeparation of the Remote Shutdown System for Standby Operation.
C.
PRECAUTIONS C. I Transfer of reactor pressure, leve'. and RCIC alarms are from the same transfer switch.
D.
LIMITATIONS D. I Supervisory Indications referred :o by this procedure are:
0 Wide Range Pressure, 0 - 1500 psig.
E.
PROCEDURE E. I PLACE Remote Shutdown Transfer Switch S-18; Nuclear Boiler Instruments, to Emergency.
F.
REVIEW AND SIGNOFF F.I None G.
REFERENCES M-93 (M-139); Nuclear Boiler ad Reactor Recirculation.
Electrical Schematic; 1E-1 (24*-
2; Remote Shutdown System.
TRM Appendix F Technical Spec Referenccs
).3.3.2,: Remote Stutdc,,vne 4 o nring System Level of Use Reference lof I LOP-RX-02 Revision 3 S....,....14, 2001 G.1 G.2 G.3 G.4 G.4.1