ML100910288
| ML100910288 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/14/2009 |
| From: | Garchow S Operations Branch IV |
| To: | Energy Northwest |
| References | |
| Download: ML100910288 (149) | |
Text
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE PREVENT A RCIC HIGH EXHAUST PRESSURE TRIP (PLANT)
LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LR001505 Rev. No. 4 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/01/01 REVISED BY Ron Hayden DATE 06/15/09 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
N/A JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: None Safety Items: None Task Number: RO-0545, EO-1447 Validation Time: 4 Minutes Prerequisite Training: N/A Time Critical: No PPM
Reference:
PPM 5.6.1 Step 6.15 Rev. 17 Location: Plant NUREG 1123 Ref: 295003 AA1.03 (4.4/4.4) Performance Method: Simulate LR001505 Rev. 4 Page 1 of 1
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Due to a series of events Columbia Generating Station has entered into a station CONDITIONS: blackout. PPM 5.6.1 is being performed.
INITIATING CUE: The CRS has directed you to prevent a RCIC high exhaust pressure trip by performing PPM 5.6.1 Step 6.15. Inform the control Room when the trip has been prevented. The performance of this JPM will be simulated. Control manipulations will not be performed.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
CUE: Cue response of simulated actions based on procedure and student actions Step 6.15.1 Close RCIC-V-756A Simulates turning handwheel in S/U*
(RCIC-PS-9A Instrument the clockwise direction to close Isolation Valve) RCIC-V-756A Step 6.15.2 Remove the pipe cap Indicates wrench to be used and S/U*
between RCIC-PS-9A and that the pipe cap between RCIC-RCIC-V-756A PS-9A and RCIC-V-756A would be turned counter-clockwise to remove it Step 6.15.3 Close RCIC-V-756B, Simulates turning handwheel in S/U*
(RCIC-PS-9B Instrument the clockwise direction to close Isolation Valve) RCIC-V-756B Step 6.15.4 Remove the pipe cap Indicates wrench to be used and S/U*
between RCIC-PS-9B and that the pipe cap between RCIC-RCIC-V-756B PS-9B and RCIC-V-756B would be turned counter-clockwise to remove it Termination Criteria: Student informs CRS that the RCIC high exhaust pressure trip has been prevented RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
LR001505 Rev. 4 Page 2 of 2
RESULTS OF JPM:
PREVENT A RCIC HIGH EXHAUST PRESSURE TRIP Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: A RCIC high exhaust pressure trip has been prevented per PPM 5.6.1.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 4 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LR001505 Rev. 4 Page 3 of 3
STUDENT JPM INFORMATION CARD Initial Conditions:
Due to a series of events Columbia Generating Station has entered into a station blackout.
PPM 5.6.1 is being performed.
Cue:
The CRS has directed you to prevent a RCIC high exhaust pressure trip by performing PPM 5.6.1 Step 6.15.
Inform the control Room when the trip has been prevented.
THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
LR001505 Rev. 4 Page 4 of 4
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE RESPOND TO CONTROL ROOM HVAC HIGH RADIATION LESSON TITLE (PLANT) (FAULTED)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001595 Rev. No. 1 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 2006 REVISED BY Ron Hayden DATE 6/16/09 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
N/A JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: None Safety Items: None Task Number: RO-0114 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM
Reference:
ABN-RAD-CR Rev. 5 Location: PLANT NUREG 1123 Ref: 288000A2.02 (3.7/3.8) Performance Method: SIMULATE LO001595 Rev. 1 Page 1 of 5
JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is different from that VALIDATION listed on the JPM, verify that the critical task steps are the same. Evaluator copy may be used for marking step completion, and comments.
INITIAL A Reactor Building High Radiation signal is present. All automatic actions have been CONDITIONS: verified. The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating. A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM).
No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal).
INITIATING The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CUE: CR. Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Step 7.1.1 Verify WOA-V-51B is Checks the stem position indicator is S/U open (SE #2) Remote pointed to OPEN intake outboard isolation Cue: If candidate checks WOA-V-51B is open and independent verification of the step has been performed.
Step 7.1.2 Verify WOA-V-52B is Checks the stem position indicator is S/U open (SE #2) Remote pointed to OPEN intake inboard isolation Cue: If candidate checks WOA-V-52B is open and independent verification of the step has been performed.
Step 7.1.3 Unlock and close WOA-V- Observes that the valve is open and 51A, NW (#1) Remote attempts to close it.
Intake Outboard Isolation. S/U*
If remote air intake #1 is See Cue below.
isolated using only valve WOA-V-52A, then N/A This step should be N / Aed this step and step 7.1.4 Cue: When student attempts to close WOA-V-51A, inform the student that the operator is broken and the valve is danger tagged in the open position.
LO001595 Rev. 1 Page 2 of 5
- Items are Critical Steps Comments Element Standard Sat/Unsat Step 7.1.4 Verify WOA-V-51D Per Step 7.1.3, this step is N / Aed N/A Opens, NW (#1) Remote Intake Purge, (WOA-V-51A Closed)
Step 7.1.5 Unlock and close WOA-V- Simulates using key to unlock the 52A, NW (#1) Remote lock.
Intake Inboard Isolation S/U*
Uses handwheel and closes WOA-V-52A.
Step 7.1.6 If remote air intake #1 is Simulates pulling fuse F4. Fuse is in isolated using only valve the panel and is located in the upper E-CP-COHV/1 is WOA-V-52A, then remove left side of the panel S/U*
labeled COHV-1. fuse F4 in Control, Cable Cover for F4 is Spreading and Critical labeled with a 4 and door aid indicates Switchgear Rooms Control TB-F4 Panel E-CP-COHV/1 (RW 525) to open WOA-V-51D, NW (#1) Remote Intake Purge. Otherwise N/A Cue: If candidate checks, WOA-V-51D opens.
Termination Criteria: Student informs CRS that the NW Remote Air Intake is isolated, only WOA-V-52A is closed, and Fuse F4 has been pulled.
RECORD TERMINATION TIME: _________
Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
LO001595 Rev. 1 Page 3 of 5
RESULTS OF JPM:
RESPOND TO CONTROL ROOM HVAC HIGH RADIATION (ONE INTAKE)
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The Northwest Remote Air Intake to the Control Room Ventilation System is isolated per ABN-RAD-CR.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LO001595 Rev. 1 Page 4 of 5
STUDENT JPM INFORMATION CARD Initial Conditions:
- A Reactor Building High Radiation signal is present
- All automatic actions have been verified
- The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating
- A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM)
- No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal)
Cue:
The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CR Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition CONTROL MANIPULATIONS WILL NOT BE PERFORMED ALL ACTIONS AND STEPS WILL BE SIMULATED LO001595 Rev. 1 Page 5 of 5
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESTART OF RPS-MG-1 AND REPOWER RPS BUS (FAULTED) (PLT)
LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001641 Rev. No. 1 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Donald Hughes DATE 06/10/08 REVISED BY Ron Hayden DATE 10/21/08 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
None Special Setup Instructions:
None JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
Tools/Equipment: None. Safety Items: None Task Number: RO-0248 Validation Time: 12 Minutes Prerequisite Training: N/A Time Critical: No PPM
Reference:
SOP-RPS-START Section 5.1 and 5.3 Rev. 0 Location: Plant NUREG 1123 Ref: 212000A2.01 (3.7/3.9) Performance Method: Simulate LO001641 Rev. 1 Page 1 of 7
JPM CHECKLIST PROCEDURE Verify the revision number of procedure copies for evaluator and student. If the procedure VALIDATION revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.
INITIAL RPS Division A has been de-energized due to a fault. The fault has been identified CONDITIONS: and corrected. The RPS-MG-1 supply breaker (RPS-DISC-7A1B) on MC-7A is closed.
INITIATING The CRS has directed you to restart RPS-MG-1 and repower the Division 1 RPS bus CUE: in accordance with SOP-RPS-START section 5.1 and 5.3. Inform the CRS when the RPS bus has been re-powered. The performance of this JPM is simulated. Control manipulations will not be performed.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
CUE: Cue response of simulated actions based on procedure and operator actions for steps without a separate cue Step 5.1.1 Verify RPS-D1SC-7A1B is Given in initial conditions N/A CLOSED (RPS Bus Mtr Gen MG-1 Supply Bkr) (E-MC-7A)
Step 5.1.2a Perform the following at E-CP-C72/S001A (RPS- MG-1 Observes the green MOTOR Control Panel):
OFF indicating light is S/U Verify the MOTOR OFF indicating illuminated light illuminated (green)
CUE: Green light is illuminated, red light is extinguished Step 5.1.2b Verify RPS-CB-MG1 OPEN Observes RPS-CB-MG1 is S/U (Generator Output Breaker) open with lever in OFF position CUE: The lever for RPS-CB-MG1 is in the OFF position Step 5.1.2c DEPRESS and HOLD Simulates depressing and S/U*
RPS-RMS-MG1/ START, holding RPS-RMS- MG1/
pushbutton (MOTOR ON) START, MOTOR ON pushbutton depressed Step 5.1.2d Verify the following: Observes the green MOTOR S/U OFF indicating light
- MOTOR OFF indicating light extinguishes and the red extinguished (green) MOTOR ON indicating light
- MOTOR ON light illuminates (red) is illuminated CUE: Red light is illuminated, Green light is extinguished LO001641 Rev. 1 Page 2 of 7
- Items are Critical Steps Comments Element Standard Sat/Unsat CUE: If asked, the RPS MG set is up to speed (should take LT 5 seconds)
Step 5.1.2e When RPS-MG-1 has come up to Simulates releasing the S/U*
speed, then release RPS-RMS- MOTOR ON pushbutton when MG1/START pushbutton cued that RPS-MG-1 is up to speed Step 5.1.2f If voltage is not indicated at rated Verbalizes that voltage S/U*
speed, then momentarily depress indication would be expected RPS-RMS-MG1/START, MOTOR ON pushbutton to reset the trip Cue: When the operator checks voltage, cue that no voltage is indicated.
Step 5.1.2f If voltage is not indicated at rated Simulates momentarily S/U*
speed, then momentarily depress depressing the RPS-RMS-RPS-RMS-MG1/START, MOTOR MG1/START, MOTOR ON ON pushbutton to reset the pushbutton overvoltage trip Cue: When the operator checks voltage, cue that voltage is now indicated on RPS-VM-MG1A.
Step 5.1.2g Verify RPS-VM-MG1A voltage Observes voltage stabilizes at S/U stabilizes at about 120 VAC 120 VAC Cue: When the operator checks voltage, cue that voltage is stable at 120 VAC on RPS-VM-MG1A.
Step 5.1.2h Close RPS-CB-MG1 Simulates closing S/U*
RPS-CB-MG1 by pushing up on lever to ON Step 5.1.3 PROCEED to Section 5.3 Performs section 5.3 as S/U follows:
Step 5.3.1 VERIFY Section 5.1 completed Section 5.1 just completed S/U Step 5.3.2 Obtain required EPA breaker keys Obtains breaker key# 166 and from the control room key locker #168 from CR key locker S/U*
NOTE: The student does not have to go to the control room to obtain keys. Ask where the keys are kept - student should verbalize the keys are in the key locker outside the Shift Manages office.
Step 5.3.3a CLOSE RPS-EPA-3A as follows (EPA Breaker) (RPS-MG2 Room):
VERIFY breaker keylock switch Observes switch S1 on RPS- S/U S1 in NORMAL EPA-3A is in NORMAL Step 5.3.3b VERIFY breaker keylock switch Observes switch S2 on RPS-S/U S2 in OPER EPA-3A is in OPER Step 5.3.3c VERIFY the POWER IN indicator Observes POWER IN light S/U illuminated illuminated LO001641 Rev. 1 Page 3 of 7
- Items are Critical Steps Comments Element Standard Sat/Unsat CUE: When step below (5.3.3d) is done, the under voltage and under frequency lights are illuminated.
Step 5.3.3d IF any of the following indicators Rotates the breaker key lock S2 are not extinguished, THEN switch to RESET S/U*
ROTATE keylock switch S2 to the RESET AND RETURN to OPER: Rotates S2 back to OPER
- OVER VOLTAGE
- UNDER VOLTAGE
- UNDER FREQUENCY
- POWER OUT CUE: When step below (5.3.3e) is done and if properly reset, the undervoltage and under frequency lights are not illuminated.
Step 5.3.3e VERIFY the following indicators Observes all lights extinguished: extinguished S/U
- OVERVOLTAGE
- UNDERVOLTAGE
- UNDERFREQUENCY
- POWER OUT Step 5.3.3f OPEN RPS-EPA-3A to reset it Resets RPS-EPA-3A by pushes S/U*
lever fully downward Step 5.3.3g Close RPS-EPA-3A Closes RPS-EPA-3A by lifting S/U*
up on lever Step 5.3.3h VERIFY POWER OUT indicator Observes POWER OUT light S/U illuminated illuminated CUE: When checked, the POWER OUT indicator is illuminated.
Step 5.3.4 IF the UNDERVOLTAGE light is Observes UNDERVOLTAGE S/U illuminated and the breaker is light out closed, THEN INITIATE a work request Step 5.3.5a CLOSE RPS-EPA-3C as follows Observes switch S1 on RPS-S/U (EPA Breaker) (RPS-MG2 Room): EPA-3C is in NORMAL VERIFY breaker keylock switch S1 in NORMAL Step 5.3.5b VERIFY breaker keylock switch Observes switch S2 on RPS-S/U S2 in OPER EPA-3C is in OPER CUE: When checked, the POWER IN indicator is illuminated.
Step 5.3.5c VERIFY the POWER IN indicator Observes POWER IN light S/U illuminated illuminated CUE: When checked, the undervoltage and under frequency lights are illuminated.
LO001641 Rev. 1 Page 4 of 7
- Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.3.5d IF any of the following indicators Rotates the breaker key lock S2 are not extinguished, THEN switch to RESET S/U*
ROTATE keylock switch S2 to the RESET AND RETURN to OPER: Rotates S2 back to OPER
- OVERVOLTAGE
- UNDERVOLTAGE
- UNDERFREQUENCY
- POWER OUT CUE: If reset properly, the undervoltage and under frequency lights are not illuminated.
Step 5.3.5e VERIFY the following indicators Observes all lights extinguished: extinguished S/U
- OVERVOLTAGE
- UNDERVOLTAGE
- UNDERFREQUENCY
- POWER OUT Step 5.3.5f OPEN RPS-EPA-3C to reset it Resets RPS-EPA-3C by pushes S/U*
lever fully downward Step 5.3.5g Close RPS-EPA-3C Closes RPS-EPA-3C by lifting S/U*
up on lever CUE: When checked, the POWER OUT indicator is illuminated.
Step 5.3.5h VERIFY the POWER OUT Observes POWER OUT light S/U indicator illuminated illuminated Step 5.3.5i IF the UNDERVOLTAGE light is Observes UNDER VOLTAGE S/U illuminated and RPS-EPA-3C is light out CLOSED, THEN INITIATE a work request to evaluate Step 5.3.6 Verify Generator A Feed white Contacts the Control Room and S/U power available indicating light asks if the light is illuminated illuminated (H13-P610)
CUE: When checked, the power available light is illuminated.
Termination Criteria: Student informs the CRS that Division 1(A) RPS bus is powered.
RECORD TERMINATION TIME: _________
Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
LO001641 Rev. 1 Page 5 of 7
RESULTS OF JPM RESTART RPS MG-1 AND REPOWER THE RPS BUS Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: RPS-MG-1 is running and RPS Bus has been re-energized per SOP-RPS-START.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial box) Time Time 12 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LO001641 Rev. 1 Page 6 of 7
STUDENT JPM INFORMATION CARD Initial Conditions:
RPS Division A has been de-energized due to a fault The fault has been identified and corrected The RPS-MG-1 supply breaker (RPS-DISC-7A1B) on MC-7A is closed.
Cue:
The CRS has directed you to restart RPS-MG-1 and repower the RPS bus in accordance with SOP-RPS-START section 5.1 and 5.3.
Inform the CRS when the RPS bus has been re-powered.
THE PERFORMANCE OF THIS JPM IS SIMULATED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
LO001641 Rev. 1 Page 7 of 7
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE PERFORM CRO1 REVIEW OF RPV HEATUP SURVEILLANCE (ADMIN)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001688 Rev. No. 0 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/17/09 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Special Setup Instructions:
Fill out cover page. Fill in the data on Attachments 9.3 and 9.5 as follows:
Perform Instrument Channel check requirements and fill in data as follows: RRC-TR-650 (Pt 1 & 2) and RWCU-Ti-607 PT5) = 100°F; MS-PI-9, RFW-PI-605 and RCIC-PI-602 at zero psig. Place an double asterisk on RCIC-PI-2 and on from of surveillance indicate the asterisk indicates RCIC is isolated as RPV/P is LT 75 psig 100 °F readings = Temp is 101°F and pressures are 0 psig with double asterisk for RCIC 200°F readings = Temp 204 and 205 and pressures 2 and 3 psig. Zero for RCIC and double asterisk 300°F readings = Temp is 311, 313 and 314 and pressures are 67 and 68 (same for RCIC as above)
Heatup Log should start at time 0600 and a reading every 15 minutes. Last reading is done at 0915 Coolant Temp is from RRC-TR-650 (1) and enter starting at top as follows:101, 115, 127, 149, 167, 190, 205, 207, 226, 247, 259, 279, 290, 313 RPV Pressure is read on MS-PI-9 and data is: 0, 3, 1, 0, 3, 2, 3, 4, 4, 12, 22, 37, 41, 67 Saturation Temp is N/A for all times 15 Min dT data is: N/A, 14, 12, 22, 18, 23, 15, 8, 19, 21, 12, 20, 11 ,23 Projected Hourly data is: N/A, 56, 48, 88, 72, 92, 60, 32, 76, 84, 48, 80, 44, 92 Actual Hourly dT (from/To/°F) from top is: N/A / N/A / N/a (N/A the first 4 lines) and at 0700 data is:
0600-0700-66, 0615-0715-75, 0630-0730-78, 0645-0745-58, 0700-0800-59, 0715-0815-57, 0730-0839-54, 0745-0845-72, 0800-0900-64, 0815-0915-66 RPV Metal Temp is read on RWCU-TI-607 Pt. 5 and data from top is: 100, 116, 129, 152, 160, 193, 204, 207, 229, 241, 253, 271, 281, 303 Initial Data taker and CRO1 and use CRO1 initials for block records within limits Initial appropriate steps in procedure as complete JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: None Safety Items: N/A Task Number: RO-0186 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: No PPM
Reference:
OSP-RCS-C101 Rev. 7 Location: Admin JPM NUREG 1123 Ref: 2.1.25 (3.9 / 4.2) Performance Method: Perform Page 1 of 5 LO001688 Rev.0
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Columbia is starting up with a heatup in progress. Both RRC Pumps are running.
CONDITIONS: RWCU-P-1A is running at 50 gpm CRO1 has requested that you perform a peer check of the results of the heatup surveillance that have been recorded so far.
INITIATING CUE: Perform the requested peer check of the RPV Heatup Surveillance, OSP-RCS-C101.
Indicate the result of your review on the JPM Answer Sheet. When you are done, hand the filled in JPM Answer Sheet and surveillance attachments to the examiner.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
CUE: Cue response of simulated actions based on procedure and student actions The student is given a Performs the review and determines copy of surveillance OSP- that all data is within the acceptable S/U*
RCS-C101 which is filled heatup limits in with data and cued to perform the CRO1 review RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 2 of 5 LO001688 Rev.0
RESULTS OF JPM:
PERFORM CRO1 REVIEW OF RPV HEATUP SURVEILLANCE Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The JPM Answer Sheet is initialed indicating that all data is within limits Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
Page 3 of 5 LO001688 Rev.0
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is starting up with a heatup in progress.
Both RRC Pumps are running RWCU-P-1A is running at 50 gpm CRO1 has requested that you perform a peer check of the results of the heatup surveillance that have been recorded so far Cue:
Perform the requested peer check of the RPV Heatup Surveillance, OSP-RCS-C101 Indicate the result on the JPM Answer Sheet When you are done, hand the filled in JPM Answer Sheet and surveillance attachments to the examiner Page 4 of 5 LO001688 Rev.0
JPM ANSWER SHEET If all data is within limits:
- 1. Initial the line indicating all data is within limits.
If all data is NOT within limits:
- 1. Red circle the out-of-tolerance readings on the surveillance attachment
- 2. Initial the line indicating all data is not within limits All data entered on OSP-RCS-C101 is within limits Initials All data entered on OSP-RCS-C101 is not within limits Initials Page 5 of 5 LO001688 Rev.0
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE MAIN TURBINE CHANGE OF LOAD RATE DETERMINATION (ADMIN)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001573 Rev. No. 1 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/19/06 REVISED BY Ron Hayden DATE 06/17/09 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
N/A JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: SOP-MT-START Safety Items: None Task Number: RO-0325 Validation Time: 7 Minutes Prerequisite Training: N/A Time Critical: No PPM
Reference:
SOP-MT-START Rev. 10 Location: Any NUREG 1123 Ref: 245000 K5.07 (2.6 / 2.9) Performance Method: Perform Page 1 of 4 LO001573 Rev.0
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Columbia is in the process of starting up. The Main Turbine is on the line and is CONDITIONS: currently 5% loaded per SOP-MT-START Attachment 6.1.
INITIATING CUE: You have been directed to determine the time required to change load from Columbias current load to a load of 95%. Assume a fatigue index of 15,000 cycles.
Inform the CRS (Examiner) of your determination when complete by writing it and circling it on Attachment 6.1.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Refers to SOP-MT-START Attachment 6.1 S/U Correlates 5% load to a First Stage Steam Temperature of 50°F S/U Correlates 95% load to a First Stage Steam Temperature of 285°F (accept 280° to 290°) S/U Calculates difference (285°-50°) to be 235°F S/U*
(accept 230° to 240°)
Plots First Stage Steam Temperature Change to Time to Change Load-Hours using the S/U*
15,000 cycles curve and determines time to change load is 3.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> (Accept a range of 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)
Termination Criteria: Student hands examiner Attachment 6.1 and has indicated that the time to change load from 5% to 95% based on a 15,000 cycle index is 3.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 2 of 4 LO001573 Rev.0
RESULTS OF JPM:
MAIN TURBINE CHANGE OF LOAD RATE DETERMINATION Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The Time to change Load has been calculated, written and circled on .1 of SOP-MT-START and is within the range allowed.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 7 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
Page 3 of 4 LO001573 Rev.0
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is in the process of starting up.
The Main Turbine is on the line and is currently 5% loaded.
Cue:
You have been directed to determine the time required to change load from Columbias current load to a load of 95% per SOP-MT-START Attachment 6.1.
Assume a fatigue index of 15,000 cycles.
Inform the CRS (Examiner) of your determination when complete by writing it and circling it on Attachment 6.1.
Page 4 of 4
INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A (ADMIN)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001644 Rev. No. 0 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/6/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
Have the following drawings ready for candidate to reference:
M-526 Sheet 1 E-503 Sheet 7 and Sheet 12 EWD-38E-001 EWD-38E-021 JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: N/A Safety Items: N/A Task Number: RO-1181 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: No PPM
Reference:
PPM 1.3.64; SWP-OPS-3; M-526-1; E-503-7 Location: Simulator / Classroom E-503-12; EWD-38E-001; EWD-38E-021 NUREG 1123 Ref: 2.2.13 4.1 / 4.3 Performance Method: Perform LO001644 Rev. 0 Page 1 of 6
DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Columbia is operating at full power. It is a Division 1 work week. Maintenance wants CONDITIONS: to replace the pipe coupling (3 inch to 6 inch) located at the discharge of FPC-P-1A.
INITIATING You have been directed to determine the clearance order boundary component, required CUE: component position, and component tagging requirement necessary to perform work on the coupling downstream of FPC-P-1A.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Identifies boundary and References M-526-1 and determines valve position required to the following valves should be isolate coupling closed to isolate FPC-P-1A:
downstream of FPC-P-1A S/U
- FPC-V-114
- FPC-V-115A
- FPC-V-116A
- FPC-V-181A Determines tagging Determines the following valves requirements should be danger tagged:
S/U*
- FPC-V-114
- FPC-V-115A
- FPC-V-116A
- FPC-V-181A Identifies FPC-P-1A Vent Refers to M-526-1 Detail 3 and and Drain valves determines vent and drain valves for FPC-P-1A: S/U
- FPC-V-187A (Vent)
- FPC-V-150A (Drain)
LO001644 Rev. 0 Page 2 of 6
DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A
- Items are Critical Steps Comments Element Standard Sat/Unsat Determines tagging Determines that either FPC-V-187A requirements AND/OR FPC-V-150A should be S/U*
danger tagged opened Identifies breaker and References E-503 sheet 12 and position required to isolate determines breaker 9B on MC-7B-B S/U FPC-P-1A electrically should be open/off Determines tagging Determines that breaker 9B on MC- S/U*
requirements 7B-B should be danger tagged Identifies breaker and References E-503 sheet 7 and position required for FPC- determines breaker 1C on MC-7B-A S/U*
V-181A should be open/off Determines tagging Determines that breaker 1C on MC- S/U*
requirements 7B-A should be danger tagged Identifies Control Switch References EWD-38E-001 for FPC-requirements for FPC-P- P-1A and determines switch should S/U*
1A be danger or blue tagged in AUTO or AUTO after STOP or IR-71 position Identifies Control Switch References EWD-38E-021 for FPC-requirements for FPC-V- V-181A and determines switch S/U*
181A should be danger or blue tagged in the NORM or NORM after CLOSE position Termination Criteria: Student completes the attached answer sheet and hands it to the examiner.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
LO001644 Rev. 0 Page 3 of 6
DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A ANSWER KEY:
COMPONENT REQUIRED TYPE OF TAG (Blue/
POSITION Danger/Caution)
FPC-V-114 Closed Danger FPC-V-115A Closed Danger FPC-V-116A Closed Danger Breaker 9B for FPC-P-1A on Open/Off Danger MC-7B-B Breaker 1C for FPC-V-181A Open/Off Danger on MC-7B-A FPC-V-150A and / or Open Danger FPC-V-187A Control Switch for Auto or Auto Danger or Blue FPC-P-1A after Stop or IR-71 Control Switch for Norm or Norm Danger or Blue FPC-V-181A after Close LO001644 Rev. 0 Page 4 of 6
DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A RESULTS OF JPM:
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Student correctly identifies the components, component position, and tagging requirements to mechanically and electrically isolate FPC-P-1A.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 15 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LO001644 Rev. 0 Page 5 of 6
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is operating at full power.
It is a Division 1 work week.
Maintenance wants to replace the pipe coupling (3 inch to 6 inch) located at the discharge of FPC-P-1A.
Cue:
You have been directed to determine the clearance order boundary component, required component position, and component tagging requirement necessary to perform work on the coupling downstream of FPC-P-1A.
Page 5 of 6
JPM ANSWER SHEET The following is required to perform work on coupling downstream of FPC-P-1A:
REQUIRED TYPE OF TAG COMPONENT POSITION (BLUE/DANGER/CAUTION
)
When completed, hand this sheet to the examiner.
Page 6 of 6
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETERMINATION OF STAY TIME IN A HIGH RADIATION AREA (ADMIN)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LR001794 Rev. No. 2 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/24/06 REVISED BY Ron Hayden DATE 6/17/09 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
Candidate needs access to a set of procedures that includes GEN-RPP-06.
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0557; SRO-0026 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: NO PPM
Reference:
GEN-RPP-06 Rev. 5; Location: Admin JPM GEN-RPP-11 Rev. 5 NUREG 1123 Ref: 2.3.4 (3.2 / 3.7) Performance Method: Perform LR0001794 Rev. 2 Page 1 of 5
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL You have been selected to work with maintenance on a valve in a High Radiation Area.
CONDITIONS: The job is expected to take five hours. You have an accumulated dose of 1600 mrem for the calendar year. The work area dose rate is at the minimum value for the High Radiation Area.
INITIATING Determine your personal maximum stay time for this job. Write your answer on the CUE: bottom of this page and hand it to the examiner.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Determines radiation Admin limit Determines a 2 rem TEDE Admin limit is applicable S/U*
Determines the minimum High Determines the minimum Radiation Area dose rate High Radiation Area dose S/U*
rate is 100 mrem/hr Calculates dose remaining to reach Calculates 400 mrem (2000 admin limit of 2 rem (2000 mrem) - 1600 = 400) remains to reach limit Calculates 200 mrem (1800 S/U*
May also use a dose limit of 1800 mrem
- 1600 = 200) remains to reach limit Calculates maximum stay time Calculates stay time: 400 mrem divided by 100 mrem/hr equals 4 hrs S/U*
Calculates stay time: 200 mrem divided by 100 mrem/hr equals 2.0 hrs Documents maximum stay time On Student Information Card documents maximum stay time of 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> if 2 S/U*
rem used or a stay time of 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is 1800 mrem was used LR0001794 Rev. 2 Page 2 of 5
- Items are Critical Steps Comments Element Standard Sat/Unsat Termination Criteria: Candidate fills out bottom of cue sheet indicating his maximum stay time and hands it to examiner.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
LR0001794 Rev. 2 Page 3 of 5
RESULTS OF JPM:
DETERMINATION OF MAXIMUM STAY TIME Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate determines that 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is his personal maximum stay time if 2 rem used and 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> if 1800 mrem used and that is indicated on the bottom of the cue sheet handed back to the examiner.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LR0001794 Rev. 2 Page 4 of 5
STUDENT JPM INFORMATION CARD Initial Conditions:
You have been selected to work with maintenance on a valve in a High Radiation Area.
The job is expected to take five hours.
You have an accumulated dose of 1600 mrem for the calendar year.
The work area dose rate is at the minimum value for the High Radiation Area.
Cue:
Determine your personal maximum stay time for this job.
Write your answer on the bottom of this page and hand it to the examiner.
My MAXIMUM stay time for this job is:
Page 5 of 5
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE IF VOLUNTARY ENTRY INTO AIA IS ALLOWABLE MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001687 Rev. No. 0 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/16/09 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
Student should have access to SOPs and Volume 3 procedures JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: None Safety Items: None Task Number: SRO-0122 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: N/A PPM
Reference:
PPM 3.2.1 Rev. 60 Location: Admin JPM NUREG 1123 Ref: 2.1.25 (3.9 / 4.2) Performance Method: Perform Page 1 of 5 LO001687 Rev.0
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Columbia Generating Station is shutting down per PPM 3.2.1. Reactor Power is 60%.
CONDITIONS: Per the Reactivity Control Plan and CRS direction, Rod Line is 90%. RFW-TI-5 on H13-P840 is reading 340°F. Core Flow is 55 Mlbm/Hr. A planned entry into the Area Of Increased Awareness is scheduled for your shift INITIATING On the page provided indicate if you would or would not direct the planned AIA entry.
CUE: Fill in all required information based on your answer.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
CUE: Cue response of simulated actions based on procedure and student actions Refers to PPM 3.2.1 for Normal Plant Shutdown and notes Step S/U 5.1.29 that states: Prior to a planned entry into the AIA (i.e. S/U Single Loop Operation), then verify Reactor Feedwater temperature, as indicated on RFW-TI-5 (H13-P840), is within the Normal Operating Region Attachment 7.3 Refers to Attachment 7.3, plots Initials block for would not the parameters given, and direct planned entry into AIA S/U*
recognizes that the pant is And fills in a reason similar to currently in the Operation operation outside the Normal Prohibited region.
Operating Region of PPM 3.2.1 Attachment 7.3 Termination Criteria: Student hands filled in form (Page 5 of 5) to the examiner.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 2 of 5 LO001687 Rev.0
RESULTS OF JPM:
PLANNED ENTRY INTO AIA Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Student handout is initialed for would not direct entry into AIA and a reason similar to operation is currently in the Operation Prohibited region of PPM 3.2.1 Attachment 7.3 Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
Page 3 of 5 LO001687 Rev.0
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia Generating Station is shutting down per PPM 3.2.1 Reactor Power is 60%
Per the Reactivity Control Plan and CRS direction, Rod Line is 90%
RFW-TI-5 on H13-P840 is reading 340°F Core Flow is 55 Mlbm/Hr A planned entry into the Area Of Increased Awareness is scheduled for your shift Cue:
On the page provided indicate if you would or would not direct the planned AIA entry Fill in all required information based on your answer Page 4 of 5 LO001687 Rev.0
JPM ANSWER SHEET YES - I would direct the planned entry into the Area of Increased Awareness.
Initials NO - I would not direct the planned entry into the Area Of Increased Awareness for the following reason(s):
Initials Page 5 of 5 LO001687 Rev.0
INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE COMPENSATORY MEASURES FOR INOPERABLE PREACTION SYSTEM AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT (ADMIN)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001686 Rev. No. 0 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/22/09 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
DETERMINE COMPENSATORY MEASURES FOR INOPERABLE PREACTION SYSTEM AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
Ensure candidate has access to a set of Volume One procedures and specifically to PPM 1.3.10B.
Ensure candidate has access to a LCS book.
Have a copy of the Fire Protection System Impairment Notification form ready to give to candidate after impairment is identified.
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0158 Validation Time: 20 minutes Prerequisite Training: N/A Time Critical: NO PPM
Reference:
PPM 1.3.10B Rev. 14; Location: Simulator/Plant/Table Top LCS 1.10.2 and 1.10.6 and Bases NUREG 1123 Ref: 2.1.25 (2.8 / 3.1) Performance Method: Perform LO001686 Rev. 0 Page 1 of 5
DETERMINE COMPENSATORY MEASURES FOR INOPERABLE PREACTION SYSTEM AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL As the Production SRO, you have been informed that during investigation into the CONDITIONS: cause of the inoperable fire detection system affecting the Reactor/Radwaste Corridor, elevation 441, a worker accidentally stepped onto the preaction sprinkler pipe for the Reactor/Radwaste Corridor, causing the pipe to break in half.
INITIATING Based on the report provided, determine if compensatory actions are required. Initial CUE: the attachment indicating either actions are required or actions are not required. If actions are required fill in those actions on the JPM Answer Sheet. When you are done with your assessment and have filled in the required information, hand the JPM Answer Sheet to your examiner.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Refers to LCS 1.10.6 table 1.10.6-1 and determines that the inoperable fire detection system is associated with detection zone S/U 66D.
The note indicates that any one of the four zones being disabled, disables all four sub-zones.
Refers to LCS 1.10.2 and determines the broke preaction pipe is also associated with System P66.
Per LCS 1.10.2A, a Fire Protection System Impairment is required S/U*
immediately AND establish a Continuous Fire Tour with backup fire suppression equipment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. S/U*
NOTE: The other possible compensatory measure is to manually flood the preaction sprinkler system piping and establish an hourly fire tour. This can not be accomplished as the cue indicates the preaction sprinkler pipe has been broke in half.
The candidate should fill in the JPM Answer Sheet indicating:
- 1. A Fire Protection System Impairment is required immediately
- 2. A Continuous Fire Tour with backup fire suppression equipment needs to be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
CUE: Once the candidate informs the examiner that a FPSI Permit is required to be completed, provide the candidate with a blank form to fill out (Attachment 9.1 of PPM 1.3.10B) and inform the candidate that the Fire Marshall is not on site.
LO001686 Rev. 0 Page 2 of 5
DETERMINE COMPENSATORY MEASURES FOR INOPERABLE PREACTION SYSTEM AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT
- Items are Critical Steps Comments Element Standard Sat/Unsat The FPSI Permit is filled out with the following information:
- System Impaired: Preaction is checked S/U*
- Reason for Impairment: Inoperable Preaction Sprinkler System (Broken Pipe) S/U*
- Building/Elevation: Reactor/Radwaste Corridor, 441 S/U*
elevation
- Compensatory Action Taken: Establish a Continuous Fire S/U*
Tour with backup fire suppression equipment Termination Criteria: Student hands the examiner a completed FPSI permit.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
LO001686 Rev. 0 Page 3 of 5
DETERMINE COMPENSATORY MEASURES FOR INOPERABLE PREACTION SYSTEM AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT RESULTS OF JPM:
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate identifies that a Continuous Fire Tour needs to be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and an FPSI permit is required to be initiated and completes the form with the required information.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 20 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LO001686 Rev. 0 Page 4 of 5
STUDENT JPM INFORMATION CARD Initial Conditions:
As the Production SRO, you have been informed that during investigation into the cause of the inoperable fire detection system affecting the Reactor/Radwaste Corridor, elevation 441, a worker accidentally stepped onto the preaction sprinkler pipe for the Reactor/Radwaste Corridor, causing the pipe to break in half.
Cue:
Based on the report provided, determine if compensatory actions are required.
Initial the attachment indicating either actions are required or actions are not required.
If actions are required fill in those actions on the JPM Answer Sheet.
When you are done with your assessment and have filled in the required information, hand the JPM Answer Sheet to your examiner.
LO001686 Rev. 0 Page 5 of 6
JPM ANSWER SHEET INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:
IF ACTIONS ARE REQUIRED, THEY ARE:
LO001686 Rev. 0 Page 6 of 6
INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE VERIFY TAGOUT FOR RHR-P-3 (Admin)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001689 Rev. No. 0 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/17/09 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
Ensure candidate has the following drawings: M 521-2; M521-3; E-503-8; EWD-9E-010 JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: None Safety Items: None Task Number: SRO-0434 Validation Time: 13 Minutes Prerequisite Training: N / A Time Critical: N / A PPM
Reference:
PPM 1.3.64 Rev. 14 Location: Admin JPM NUREG 1123 Ref: 2.2.15 (3.9 / 4.3) Performance Method: Perform Page 1 of 5 LO001689 Rev.0
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Columbia is in a refueling outage. A tagout for RHR-P-3 is in process of being CONDITIONS: approved. As the Production SRO, the Shift Manager has directed you to perform the final approval before the tagout is hung.
INITIATING CUE: Perform a review of the tagout for RHR-P-3. Indicate on the JPM answer sheet if you would approve this tagout as written, or not approve it because discrepancies were noted. Fill in the applicable information on the JPM Answer Sheet based upon your review. When completed hand the JPM Answer Sheet to your examiner.
- Items are Critical Steps Comments Standard Sat/Unsat RECORD START TIME: __________
Reviews M521-2 and M521-3 to determine tagging boundary. S/U*
Observes that RHR-V-85C has been left off of the tagout Reviews E-503-8 and EWD 9E-010 and determines that RHR-P-3 is electrically isolated with a Disconnect and not a Circuit Breaker S/U*
and the disconnect position is OFF not Racked Out Reviews tagout and determines that RHR-V-737(V) required S/U*
position is Closed but should be OPEN Reviews tagout and determines that RHR-V-737(V) and RHR-V- S/U*
738(D) have caution tags but at least one of them should have danger tag Termination Criteria: Candidate hands the completed JPM answer sheet to the examiner RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
RHR-P-3 the Disconnect should be OFF not Racked Out RHR-V-85C not included on tagout but should be danger tagged closed RHR-V-737(V) is tagged closed but should be tagged open RHR-V-737(V) is caution tagged but should be danger tagged and/or RHR-V-738(D) is caution tagged but should be danger tagged Page 2 of 5 LO001689 Rev.0
RESULTS OF JPM:
REVIEW/APPROVE RHR-P-3 TAGOUT Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The JPM Answer Sheet has been reviewed and the deficiencies have been identified.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 13 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
Page 3 of 5 LO001689 Rev.0
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is in a refueling outage A tagout for RHR-P-3 is in process of being approved As the Production SRO, the Shift Manager has directed you to perform the final approval before the tagout is hung Cue:
Perform a review of the tagout for RHR-P-3 Indicate on the JPM answer sheet if you would:
approve this tagout as written, or not approve it because discrepancies were noted Fill in the applicable information on the JPM Answer Sheet based upon your review When completed hand the JPM Answer Sheet to your examiner Page 4 of 5 LO001689 Rev.0
JPM ANSWER SHEET EQUIPMENT TAG EQUIPMENT PLACEMENT ID TYPE DESCRIPTION CONFIGURATION RHR-RMS-P/3 Equipment RHR WATER LEG PUMP - RHR-P-3 STOP Configuration RHR-42-8B7A Danger RHR-P-3 DISCONNECT RACKED OUT RHR-V-85B Danger WATER LEG ISOLATION CLOSED RHR-V-210 Danger WATER LEG MINIMUM FLOW CLOSED RHR-V-82 Danger WATER LEG SUCTION CLOSED RHR-V-737(V) Caution SYSTEM VENT CLOSED RHR-V-738(D) Caution SYSTEM DRAIN OPEN I WOULD APPROVE TAGOUT AS WRITTEN:
Initials I WOULD NOT APPROVE THIS TAGOUT. ALL DISCREPANCIES NOTED BELOW:
Initials Page 5 of 5 LO001689 Rev.0
INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS (ADMIN)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001590 Rev. No. 1 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 2006 REVISED BY Ron Hayden DATE 6/21/09 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS Page 2 of 9
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
Candidate needs a calculator and access to ABN-OG JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0658 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM
Reference:
ABN-OG Rev. 1 Location: Simulator/Table Top NUREG 1123 Ref: 271000A2.04 (4.1) Performance Method: Perform LO001590 Rev. 1 Page 1 of 5
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION: that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL Columbia is operating at full power. Various alarms are locked in due to suspected CONDITIONS: fuel pin damage. Offgas system parameters are as follows:
OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7821 mr/hr INITIATING Based on the above, per ABN-OG, determine what action, if any, should be taken.
CUE:
Fill in the result of your determination on the JPM Answer Sheet provided.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Refers to ABN-OG and, using bases for step 4.1.2 calculates the following: Main Condenser Gross gamma activity = OG-RR-604 X OG-FR-620 divided by 1000 S/U Main Condenser Gross gamma activity = 7821 mr/hr times 43 SCFM divided by 1000 OR Main Condenser Gross gamma activity S/U
= 336.303 mCi/sec Based on a Main Condenser Gross gamma activity reading of 336 mCi/sec, candidate determines that a power reduction per PPM S/U*
3.2.4 to maintain Main Condenser Gross gamma activity LT 332 mCi/sec is required.
Termination Criteria: Student hands the JPM Answer Sheet to the examiner RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
LO001590 Rev. 1 Page 2 of 5
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS RESULTS OF JPM:
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate fills out the attachment and has determined that a power reduction per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity LT 332 mCi/sec.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:
Evaluator's Signature: Date:
LO001590 Rev. 1 Page 3 of 5
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is operating at full power.
Various alarms are locked in due to suspected fuel pin damage.
Offgas system parameters are as follows:
OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7821 mr/hr Cue:
Based on the above, per ABN-OG, determine what action, if any, should be taken.
Fill in the result of your determination on the JPM Answer Sheet provided.
LO001590 Rev. 1 Page 4 of 5
JPM ANSWER SHEET INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:
ACTIONS IF REQUIRED:
LO001590 Rev. 1 Page 5 of 5
INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE CLASSIFY THE EVENT AFTER DYNAMIC EXAM SCENARIO (TC) (SIM)
MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code Rev. No.
JPM PQD Code LO001604 Rev. No. 1 Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/17/06 REVISED BY Ron Hayden DATE 6/18/09 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A - Scenario completed per Scenario Guide.
Setup Instructions:
This JPM is designed to be performed after completion of a Dynamic Exam Scenario.
JPM Instructions:
This JPM is a Generic JPM that may be used anytime a JPM is run after a simulator dynamic exam. The values that are filled in by the student are applicable to the scenario performed. Indicate the scenario PQD code this JPM was run against in the comment section of the results page.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0529, SRO-0629 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: Yes 30 minutes PPM
Reference:
PPM 13.1.1 Location: Simulator NUREG 1123 Ref: 2.4.41 (2.9 / 4.6) Performance Method: Perform LO001604 Rev. 1 Page 2 of 6
JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL You have just been relieved as the SRO following the scenario. It is not raining outside.
CONDITIONS:
INITIATING The Shift Manager has directed you to classify the event and initiate a CNF for the just CUE: completed scenario. This will be the initial classification. The CNF should be initiated for the highest classification related to this scenario. Present a completed Classification Notification Form to the examiner. This is a time critical JPM and your time starts now.
- Items are Critical Steps Comments Standard Sat/Unsat RECORD START TIME: __________
Fills in the following information:
- 1. Checks block 1a or 1b (Emergency or Drill) 1. S / U *
- 2. Enters 1 2. S / U
- 3. Enters name and phone number 3. S / U *
- 4. Checks block 4.a and enters date and time 4. S / U *
- 5. Checks Block 5C for Site Area Emergency 5. S / U *
- 6. Leaves Blank 6. S / U
- 7. Enters Wind Speed of 8.2; Wind Direction of 269; Checks No 7. S / U
- for precipitation; Enters C for Stability Class
- 8. S / U
- 8. Checks No Release
- 9. N/A
- 9. Checks N/A
- 10. N/A
- 10. Checks N/A
- 11. S / U
- 11. Checks No
- 12. S / U *
- 12. Enters EAL# 3.1.S.1; Enters description similar to: Drywell Pressure Response not consistent with LOCA conditions
- 13. S / U
- 13. Checks either block a, b, or d Termination Criteria: Student hands the examiner the completed Classification Notification Form.
RECORD TERMINATION TIME: _________
LO001604 Rev. 1 Page 3 of 6
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
LO001604 Rev. 1 Page 4 of 6
RESULTS OF JPM:
CLASSIFY THE EVENT AFTER DYNAMIC EXAM SCENARIO Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate accurately completes a Classification Notification Form with the required information for the completed scenario.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 15 Minutes / 30 minutes COMMENTS:
Evaluator's Signature: Date:
LO001604 Rev. 1 Page 5 of 6
STUDENT JPM INFORMATION CARD Initial Conditions:
You have just been relieved as the SRO following the scenario.
It is not raining outside.
Cue:
The Shift Manager has directed you to classify the event and initiate a Classification Notification Form for the just completed scenario This will be the initial classification The CNF should be initiated for the highest classification related to this scenario Present the completed CNF to the examiner THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW LO001604 Rev. 1 Page 6 of 6
INSTRUCTIONAL COVER SHEET PROGRAM OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Swap CRD pumps; RPS-B Trip with a Scrammed Rod That Fails To Insert and FDR-V-4 that Fails to Close; RFP-B Control Oil Pressure Drop; Steam LESSON TITLE Leak Causes RCIC Isolation; RCIC-V-8 & 63 Fail to Auto Close; Feed Line Rupture; HPCS-P-1 Shaft Break; LOCA; ED On RPV Low Level LENGTH OF LESSON 1.5 Hours S INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code LO001677 Rev. No. 0 JPM PQD Code Rev. No.
Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/28/09 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE APPROVED DATE Operations Training Manager LO001604 Rev. 1 Page 7 of 6
Verify materials current IAW SWP-TQS-01 prior to use.
LO001604 Rev. 1 Page 8 of 6
Appendix D NRC Scenario No. 1 FORM ES-D-1 Columbia Generating Station ILC NRC Exam October, 2009 Facility: Columbia NRC Scenario No: 1 Examiners: _______________ Operators: _______________
Initial conditions: Columbia is operating in MODE 1 at full Power.
Turnover: Swap running CRD pumps to CRD-P-1A running and CRD-P-1B in stby Event Timeline Event Event Description No. Type*
- 2. T = 10 C (All) Loss of RPS-B; FDR-V-4 Fails to Close; Also - a scrammed rod. Rod TS (CRS) 18-11 fails to fully insert
- 3. T = 10 R (ATC) Reduce Reactor Power with RRC Flow to LE 80 Mlbm/hr TS (CRS) Drive control rod 18-11 that failed to fully insert
- 6. T = 50 Leak in the CBP discharge piping leading to a reactor scram and loss of the Condensate and Feedwater systems
- 7. T = 55 M (All) LOCA - Containment Sprays
- 8. T = 55 C (BOP) HPCS-P-1 Shaft Break
- 11. T = 75 Re-Initiation of Containment Sprays
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 9 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SCENARIO DESCRIPTION The scenario begins with Columbia operating at full power. Turnover information will direct CRD Pumps be swapped.
EVENT 1 - Swap CRD pumps to CRD-P-1B running and CRD-P-1A in standby EVENT 2 - After the CRD pump swap, there will be a loss of RPS B due to a failed MG set motor. FDR-V-4 fails to close on the loss of RPS and will not close when manually attempted.
EVENT 3 - On the loss of RPS B, control rod 18-11 will scram due to blown fuses on the A RPS side. The rod will not fully insert and is at position 10. The crew will reduce core flow to LE 80 Mlbm/hr and drive rod 18-11 full in.
The CRS will refer to Tech Specs for the scrammed control rod 18-11.
The CRS will refer to Tech Specs for FDR-V-4.
RPS B will be repowered from alternate power supply.
EVENT 4 - A slow loss of control oil pressure on the B Reactor Feedwater Pump. The Auxiliary Oil Pump will fail to auto start but can be started manually.
EVENT 5 - A steam line rupture in the RCIC supply line that causes a RCIC isolation. On the isolation, RCIC-V-8 and RCIC-V-63 fail to auto close. When manually attempted both RCIC-V-8 and RCIC-V-63 will close. The CRS will enter ABN-RAD-HIGH and EOP PPM 5.3.1, Secondary Containment Control and will refer to Tech Specs for RCIC System being OOS.
EVENT 6 - A rupture of the condensate line downstream of the Condensate Booster Pumps that will require a manual Reactor scram. The RFW pumps will trip and all Condensate and Condensate Booster Pumps will have to be secured in order to stop the leak.
EVENT 7 - A LOCA will develop shortly after the Reactor scram. Containment sprays will be initiated as appropriate.
EVENT 8 - When RPV Level drops to -50 inches, HPCS will initiate and the MSIVs will close. When HPCS initiates, HPCS-P-1 shaft breaks.
EVENT 9 - RPV level will drop to Top Of Active Fuel.
EVENT 10 - When RPV level reaches -163 inches, the CRS will direct an Emergency Depressurization be performed.
EVENT 11 - When RPV Level is GT TAF, Containment Sprays will be initiated as appropriate.
The scenario will be terminated when RPV level is being returned with injection from low pressure ECCS pumps, Sprays have been re-initiated as appropriate, or as directed by the scenario coordinator.
Page 10 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 1
==
Description:==
Swap CRD Pumps to CRD-P-1B running and CRD-P-1A in standby The event is initiated by turnover information and will be performed after shift turnover Time Position Applicants Actions or Behavior T=0 CRS Directs to swap CRD pumps to CRD-P-1B running and CRD-P-1A in standby ATC Refers to SOP-CRD-Pumps Section 5.1:
- Step 5.1.2 - Contacts OPS2 and verifies oil level in CRD-P-1B gear unit bulls eye GE 1/2 full
- Flags P603.A7 3.6 and 5.8 as expected alarms
- Step 5.1.3Places CRD-FC-600 in MANUAL
- Ensures announcement is made for CRD pump swap
- Step 5.1.4 - Starts CRD-P-1B
- Step 5.1.5 - Stops CRD-P-1A
- Step 5.1.6 - Nulls CRD-FC-600
- Shift CRD-FC-600 to Automatic
- 5.1.8 - Slowly adjusts CRD-V-3 to establish approximately 260 psid on CRD-DPI-602 ROLEPLAY: As OPS2 report CRD-P-1B running normally COMMENTS:
Page 11 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 2
==
Description:==
Loss of RPS-B; FDR-V-4 Fails to Close; Control Rod 18-11 scrams but fails to fully insert (see event 3)
This event is initiated when the RCC pump swap is completed by ACTIVATING TRIGGER 1 Time Position Applicants Actions or Behavior T = 10 ATC Acknowledges alarms Reports half scram system B Reports control rod scram (& accumulator light) illuminated 18-11 and it is NOT full in (at position 10)
Reports power/pressure/level Refers CRS to ABN-ROD due to the scrammed control rod (Refer to Event 3 for the remainder of actions associated with control rod)
BOP Informs CRS of RPS Trouble annunciator.
Refers to 4.800.C5 DROP 9-5 RPS BUS B TROUBLE:
- Announces to immediately stop all maintenance and surveillance testing in progress that has a potential for generating a trip on unaffected RPS channel (RPS A system)
- Refers CRS to ABN-RPS Contacts OPS 2 and directs investigation of RPS B loss ROLEPLAY: As OPS 2 wait three minutes and report that the B RPS MG Set is not running, the motor is hot to the touch, and there is an electrical smell in the room with no indication of fire Page 12 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 2 BOP Per ABN-RPS:
Throttles open RWCU-V-104 Ensures all automatic actions have occurred When checked, notes that FDR-V-4 did not close Attempts to close FDR-V-4 and notes and reports that it did not close when C/S taken to close position SRO Refers to Tech Spec 3.6.1.3 and notes condition A applies Directs RPS-B be energized from alternate power BOP Repowers RPS B as follows:
- Verifies alternate power available by observing Alternate Feed white light illuminated
- Places the RPS Power Source Select Switch in position ALT B BOOTH OPERATOR: When the SCRAM (NOT B RPS) is reset, remove the scrammed rod malfunction in the Director window (right click on the line and select remove)
Page 13 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 2 BOP Restores RPS B per step 4.6.2:
- Reset half scram at H13-P603
- Resets MS Line Monitors MS-RIS-610B and 610D at P633
- Depresses Isolation logic A & B reset P/B
- Depresses Isolation logic C & D reset P/B
- Resets RC-1 by depressing WMA-RMS-FAZ/3AXY on RC-1
- Resets RC-2 by depressing WMA-RMS-FAZ/3BXY on RC-2
- Opens RRC-V-19 and RRC-V-20
- Opens EDR-V-19 and EDR-V-20 (LEAK DET DRYWELL EQUIP DRAIN FLOW HIGH is an anticipated annunciator)
- Opens TIP-V-15
- Returns RWCU to service per SOP-RWCU-START COMMENTS: Event 4 may be commenced any time after RC-1 and RC-2 are reset.
Page 14 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 3
==
Description:==
Control Rod 18-11 Scrams but fails to go full in (stuck at position 10)
The event is initiated when the loss of RPS B is activated Time Position Applicants Actions or Behavior T = 10 ATC Reports control rod scram light illuminated for 18-11 Reports entry into ABN-ROD Reports control rod 18-11 does not indicate full in Selects control rod 18-11 and reports it is at position 10 SRO Enters ABN-ROD and directs subsequent actions per section 4.2:
- Directs core flow be lowered to LE 80 Mlbm/hr ATC Observes both RRC pump individual controllers are in Auto (RRC-M/A-R676A and 676B) and depresses the LOWER Pushbutton on the Master Controller (RRC-M/A-R675) to lower flow as directed Reports RRC flow is LE 80 Mlbm/hr (should be about 42 Hz) (RPV High level alarm is expected)
SRO Per ABN-ROD directs section 4.2.3 be performed ATC Per ABN-ROD step 4.2.3:
- Selects rod 18-11
- Depresses the Continuous Insert P/B
- Drives rod 18-11 full in
- Releases Continuous Insert P/B and verifies it remains full in
- Resets rod accumulator trouble and control rod drift annunciators
- Directs CRS to Tech Spec - Reactivity Reports power/level/pressure after rod insertion Page 15 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 3 ATC Acknowledges SDV Not Drained Alarm and refers to ARP (This alarm may or may not annunciate depending on speed of RPS B reset. It takes about 8.5 minutes to get this alarm)
Verifies SDV vent and drains open when Scram is reset SRO May direct BOP to check SDV level indications SRO Refers to Tech Spec 3.1.3 Condition C Requests information on slow and inoperable control rods Directs STA to initiate a MON run Notes that a CR should be generated to document the rod problems ROLEPLAY: IF asked inform the CRS that a MON run has been performed and no thermal or preconditioning limits have been exceeded ROLEPLAY: If asked there are NO inop or slow control rods COMMENTS:
Page 16 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 4
==
Description:==
Slow drop of RFW-P-1B Control Oil Pressure with failure of RFW-P-AOP/1B to start.
The event is initiated any time after the BOP operator resets RC-1 and RC-2 by ACTIVATING TRIGGER 2 (It takes about 2 minutes to get alarm)
Time Position Applicants Actions or Behavior T = 25 ATC Acknowledges TURB B CNTR OIL PRESS LOW annunciator and refers to ARP Reports current control oil pressure (at approx 70 psig) on RFT-PI-2/1B ATC Notes that RFW-P-AOP/1B should have started per ARP but is not running and informs the CRS SRO Directs RFW-P-AOP/1B be started (RO may start the pump without direction - auto action that should have occurred but did not)
BOP Dispatches OPS 3 to investigate ATC Starts RFW-P-AOP/1B and reports the pump start to CRS Reports control oil pressure returned to normal and clearing of control oil pressure low annunciator SRO Contacts Production SRO/System Engineer to investigate problem with RFW-P-AOP/1B ROLEPLAY: If OPS 3 is contacted report no obvious signs of a control oil leak and you will continue your investigation COMMENTS:
Page 17 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 5
==
Description:==
RCIC Steam Line Break resulting in RCIC isolation signal with RCIC-V-8 and RCIC-V-63 failing to auto close (may be closed manually)
The event is initiated when the B RFW Aux Oil Pump is started by ACTIVATING TRIGGER 3 (It takes 90 seconds to get alarm and 4 minutes to get the RCIC isolation signal)
Time Position Applicants Actions or Behavior Critical Task is to Close RCIC-V-8 and RCIC-V-63 to stop steam leak T = 30 BOP Acknowledges REACTOR BUILD RAD HIGH alarm (602-A5 3-1) and reports TIP Drive Area, ARM-RIS- 7, reading GT 25 mr/hr and rising Informs CRS of ABN-RAD-HIGH and Secondary Containment EOP entry condition SRO Announces entry into ABN-RAD-HIGH and PPM 5.3.1 Secondary Containment Control Per ABN-RAD-HIGH, directs evacuation of personnel in the Reactor Building ROLEPLAY: As OPS2 report that there is steam coming from the room above the TIP room and you are leaving the Reactor Building BOP/ATC Evacuates Reactor Building as directed BOP Acknowledges LEAK DET RWCU/RCIC PIPE AREA TEMP HIGH alarm and investigates Leak Detection Monitors to determine temperature Reports temperatures as they rise above alarm points BOP/ATC Acknowledges alarms and informs CRS of EOP Entry conditions on RWCU Room Temperature Hi-Hi and RCIC Pipe Routing Area Temperature Hi Hi Alarms H13-P601 A2 1-1 & 2-2 and H13-P601 A3 1-8 & 2-5 Page 18 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 5 SRO Re-enters PPM 5.3.1 as necessary BOP Reports Leak Detection Monitor point A1-5, LD-TE-24K, RWCU/RCIC Room 313, is GT Max Safe value of 212°F when it occurs Reports Leak Detection Monitor points A2-4, LD-TE-24F, is GT Alarm but LT Max Safe value of 340°F BOP/ATC Reports RCIC Trip annunciator and RCIC Steam Line valves RCIC-V-8 and RCIC-V-63 failed to close SRO Directs RCIC-V-8 and RCIC-V-63 be manually closed BOP Obtains keys and closes RCIC-V-8 and RCIC-V-63 and reports closure to CRS SRO Refers to Tech Specs 3.5.3 and performs actions for Condition A:
- Restore RCIC to operable status in 14 days BOP Reports clearing of high temperature alarms and dropping area temperatures indicating the leak is isolated COMMENTS:
Page 19 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 6
==
Description:==
Leak in the CBP discharge piping leading to a loss of the condenstate/feedwater systems as a feed source and a reactor scram The event is initiated after actions associated with RCIC steam leak are completed by ACTIVATING TRIGGER 4 Time Position Applicants Actions or Behavior T = 50 ROLEPLAY: As OPS3 report there is a water line rupture in the Turbine Building 441 elevation. It looks like water is coming from the Condensate Booster Pumps discharge line and you are getting out of the area ATC Checks pressures associated with the Condensate and Feedwater systems and observes lowering RFW pump suction pressures and informs the CRS SRO Enters ABN-FLOODING May direct evacuation all personnel from the Turbine Building BOP Announces a evacuation of personnel in the Turbine Building if directed ATC Acknowledges RFW PUMP SUCT PRESS LOW alarms (If reactor has not been manually scrammed)
SRO Directs CRO1 to insert a manual reactor scram ATC Performs immediate scram actions:
- Announces to listen up for the scram report
- Places Mode Switch to Shutdown
- Reports APRMs downscale
- Reports Reactor Pressure and trend
- Reports RPV level and trend
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 6 SRO Repeats back scram report and enters PPM 5.1.1, RPV Control, on Low RPV Level ATC Reports trip of both RFW pumps on low suction pressure SRO Directs all Condensate and Condensate Booster Pumps be stopped BOP/ATC Secures Condensate and Condensate Booster Pumps as directed ROLEPLAY: If Condensate pumps are not secured, as OPS3 report water is still flowing from line rupture.
ROLEPLAY: If asked, as OPS3 report the water has stopped coming from piping rupture.
COMMENTS:
Page 21 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 7
==
Description:==
This event is auto initiated when the MSIVs close Time Position Applicants Actions or Behavior T = 55 BOP Recognizes MSIV closure and updates Crew that the MSIVs are closed and he has pressure control on SRVs at 800 to 1000 psig pressure band BOP Recognizes rising DW Pressure and reports EOP entry at 1.68 psig Also reports additional primary containment EOP entries as they occur SRO Enters EOP 5.2.1, Primary Containment Control and re-enters 5.1.1 RPV Control, due to high DW pressure Directs actuations for +13, -50 and 1.68 psig be verified as appropriate BOP Reports Wetwell pressure when it reaches 2 psig SRO Directs Wetwell sprays/Suppression Pool Cooling with RHR A Directs securing sprays if pressure drops below 1.68 psig BOP Using quick card, initiates wetwell sprays and supplements with suppression cooling Page 22 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 7 RO/BOP Reports Wetwell pressure when it reaches 12 psig SRO Directs Drywell Cooling Fans be secured BOP Secures Drywell Cooling Fans as directed SRO Directs DSIL verification Directs Drywell Sprays be initiated with RHR B Directs securing sprays if drywell pressure drops below 1.68 psig BOP Verifies within DSIL and using quick card, initiates Drywell Sprays as directed Reports Sprays effective as Drywell pressure drops COMMENTS: Drywell Spray initiation may be delayed until after Emergency Depressurization Page 23 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 8
==
Description:==
HPCS-P-1 Shaft Breaks This event is activated at the beginning of the scenario but only realized when HPCS initiates Time Position Applicants Actions or Behavior T = 55 BOP When HPCS initiates on High Drywell Pressure or RPV/L at -50, verifies HPCS status Recognizes that HPCS-P-1 is running with no flow and only 100 psig discharge pressure and informs CRS SRO Directs HPCS-P-1 be checked ROLEPLAY: If asked, as OPS2 report that there are parts to the shaft coupling for HPCS-P-1 all over the HPCS Pump room SRO May directs HPCS-P-1 be secured BOP Secures HPCS-P-1 if directed COMMENTS:
Page 24 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 9
==
Description:==
This event starts when scram is initiated Time Position Applicants Actions or Behavior T = 55 ATC Reports RPV level drop Gives RPV level reports as level continues to lower May direct ABN-CRD-MAXFLOW be performed NOTE - From scram time it takes about 1.5 minutes to get to -50 It takes another 7 minutes to get to -129 It takes another 80 seconds to get to TAF at -161 It takes another 30 seconds to get to -183 SRO Directs ADS be inhibited when ADS timers initiate (at
-129)
As level drops, expands RPV band given ATC/BOP When RPV/L drops to -129 and the ADS timers intimate, takes both ADS inhibit switches to inhibit ATC/BOP Reports RPV level as it transitions from Wide Range to Fuel Zone indicators Reports RPV level at -161 (TAF)
Page 25 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 COMMENTS:
Page 26 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 10
==
Description:==
Emergency Depressurization and Return RPV Level to +13 to +54 This event is initiated when RPV Level reaches -161 (Top Of Active Fuel)
Time Position Applicants Actions or Behavior Critical Task is to Emergency Depressurize the RPV when RPV Level reaches TAF at -161 T = 70 SRO Determines that Emergency Depressurization is required at -161 Exits the pressure leg of PPM 5.1.1 and enters PPM 5.1.3, Emergency RPV Depressurization Determines wetwell level is GT 17 and directs 7 ADS SRVs be opened ATC/BOP Opens 7 ADS SRVs as directed SRO Directs containment sprays and Suppression Pool cooling be secured to facilitate RPV injection Directs RPV Level be returned to +13 to +54 level band RO/BOP Secures sprays and Suppression Pool cooling as directed Allows ECCS injection valves to open at 470 psig and RPV injection as it occurs Reports RPV level rising and when GT -161 inches COMMENTS:
Page 27 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 11
==
Description:==
Re-initiation of Wetwell and Drywell Sprays This event is initiated by the SRO when RPV level is greater than TAF Time Position Applicants Actions or Behavior T = 75 SRO Directs initiation of Wetwell sprays if WW Pressure is GT 2 psig Directs initiation of Drywell sprays if Wetwell Pressure is GT 12 psig Directs Suppression Pool Cooling as required ATC/BOP Secures injection systems as necessary to return RPV level to +13 to
+54 band Initiates Wetwell and Drywell sprays as appropriate Initiates suppression pool cooling if directed Termination Criteria: The scenario will be terminated when RPV level is being returned with injection from low pressure ECCS pumps, Sprays have been re-initiated as appropriate, or as directed by the scenario coordinator Page 28 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 TURNOVER INFORMATION Initial conditions: Columbia is operating in MODE 1 at full Power.
Turnover: A PM is scheduled to swap CRD Pumps.
After shift turnover swap CRD pumps to CRD-P-1B running and CRD-P-1A in standby.
OPS 2 is standing by for the CRD Pump swap evolution.
Page 29 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SIMULATOR SETUP INSTRUCTIONS Reset to IC-213.
Page 30 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SCHEDULE
<SCHEDULE>
<ITEM row = 1>
<ACTION>Insert malfunction AOV-SCN013F after 1 to FAIL_AS_IS</ACTION>
<DESCRIPTION>FDR-V-4 DW FLOOR DRN OUTBD ISOL</DESCRIPTION>
</ITEM>
<ITEM row = 2>
<ACTION>Insert malfunction PMP-CSS001B after 1</ACTION>
<DESCRIPTION>HPCS-P-1 HPCS PUMP SHAFT BREAK</DESCRIPTION>
</ITEM>
<ITEM row = 3>
<ACTION>Insert malfunction MAL-RMC005-1811 after 1</ACTION>
<DESCRIPTION>ROD 1811 STUCK at position 10</DESCRIPTION>
</ITEM>
<ITEM row = 4>
<ACTION>Insert malfunction MOV-RCI016F to FAIL_AUTO_CLOSE</ACTION>
<DESCRIPTION>RCIC-V-8 Fails to Auto Close</DESCRIPTION>
</ITEM>
<ITEM row = 5>
<ACTION>Insert malfunction MOV-RCI012F to FAIL_AUTO_CLOSE</ACTION>
<DESCRIPTION>RCIC-V-63 Fails to Auto Close</DESCRIPTION>
</ITEM>
<ITEM row = 6>
<ACTION>Insert malfunction ANN-820B2F06 to OFF</ACTION>
<DESCRIPTION>GLAND SEAL STM PRESS HIGH</DESCRIPTION>
</ITEM>
<ITEM row = 8>
<EVENT>1</EVENT>
<ACTION>Insert remote LOA-EPS277 to TRIP on event 1</ACTION>
<DESCRIPTION>RPS-CB-MG2 MG-B OUTPT BKR O/C</DESCRIPTION>
</ITEM>
<ITEM row = 9>
<EVENT>1</EVENT>
<ACTION>Insert malfunction MAL-RMC007-1811 on event 1</ACTION>
<DESCRIPTION>ROD 1811 SINGLE ROD SCRAM</DESCRIPTION>
</ITEM>
<ITEM row = 11>
Page 31 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009
<EVENT>29</EVENT>
<ACTION>Insert malfunction MAL-RMC005-1811 after 1 on event 29 delete in 3</ACTION>
<DESCRIPTION>Deletes stuck rod malfunction</DESCRIPTION>
</ITEM>
<ITEM row = 12>
<ACTION>Event Events/LO001677.evt</ACTION>
<DESCRIPTION>Brings in Events</DESCRIPTION>
</ITEM>
<ITEM row = 14>
<EVENT>2</EVENT>
<ACTION>Insert override IND-FPT022 to 68 in 120 on event 2</ACTION>
<DESCRIPTION>RFT-PI2-1B TURBINE OIL CONTROL PRESS METER SIGNAL M</DESCRIPTION>
</ITEM>
<ITEM row = 15>
<EVENT>2</EVENT>
<ACTION>Insert override IND-FPT023 to 18 in 120 on event 2</ACTION>
<DESCRIPTION>RFT-PI3-1B TURBINE OIL BEARING PRESS METER SIGNAL M</DESCRIPTION>
</ITEM>
<ITEM row = 16>
<EVENT>2</EVENT>
<ACTION>Insert malfunction ANN-840A1E05 after 110 to ON on event 2</ACTION>
<DESCRIPTION>CONTROL OIL TURB B PRESS LOW</DESCRIPTION>
</ITEM>
<ITEM row = 18>
<EVENT>28</EVENT>
<ACTION>Insert malfunction ANN-840A1E05 to ON after 1 on event 28 delete in 1</ACTION>
<DESCRIPTION>Removes Control Oil TURB B press low on Aux Pump red light illuminated</DESCRIPTION>
</ITEM>
<ITEM row = 20>
<EVENT>28</EVENT>
<ACTION>Insert override IND-FPT023 to 18 after 1 on event 28 delete in 1</ACTION>
<DESCRIPTION>Returns RFT-PI3-1B to normal on LO Pump red light illuminated</DESCRIPTION>
</ITEM>
<ITEM row = 21>
<EVENT>28</EVENT>
<ACTION>Insert override IND-FPT022 to 68 after 1 on event 28 delete in 1</ACTION>
<DESCRIPTION>Returns RFT-PI2-1B to normal on LO Pump red light illuminated</DESCRIPTION>
</ITEM>
Page 32 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009
<ITEM row = 22>
<EVENT>3</EVENT>
<ACTION>Insert malfunction MAL-RCI006 to 2000000 in 3600 on event 3</ACTION>
<DESCRIPTION>RCIC BREAK BETWEEN RCIC-V-8 & PCN</DESCRIPTION>
</ITEM>
<ITEM row = 24>
<EVENT>4</EVENT>
<ACTION>Insert malfunction MAL-CFW006 to 20000 in 600 on event 4</ACTION>
<DESCRIPTION>LEAK IN COMMON CBP DISCHARGE</DESCRIPTION>
</ITEM>
<ITEM row = 26>
<EVENT>26</EVENT>
<ACTION>Insert malfunction MAL-RRS004B to 2 in 1200 on event 26</ACTION>
<DESCRIPTION>RECIRC LINE RUPT- RRC-P-1B SUCT</DESCRIPTION>
</ITEM>
<ITEM row = 28>
<EVENT>27</EVENT>
<ACTION>Insert override OVR-FPT002B to ON on event 27</ACTION>
<DESCRIPTION>RFW TURBINE 1A EMERG TRIP</DESCRIPTION>
</ITEM>
<ITEM row = 29>
<EVENT>27</EVENT>
<ACTION>Insert override OVR-FPT007B to ON on event 27</ACTION>
<DESCRIPTION>RFW TURBINE 1B EMERG TRIP</DESCRIPTION>
</ITEM>
<ITEM row = 30>
<EVENT>27</EVENT>
<ACTION>Insert malfunction ANN-840A1H03 to ON on event 27</ACTION>
<DESCRIPTION>RFW PMP A SUCT PRESS LOW</DESCRIPTION>
</ITEM>
<ITEM row = 31>
<EVENT>27</EVENT>
<ACTION>Insert malfunction ANN-840A1H07 to ON on event 27</ACTION>
<DESCRIPTION>RFW PMP B SUCT PRESS LOW</DESCRIPTION>
</ITEM>
</SCHEDULE>
Page 33 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 EVENTS
<EVENT>
<TRIGGER id="26" description="Inserts LOCA when MSIVs close">X01O194G>0</TRIGGER>
<TRIGGER id="27" description="Trips both RFW Pumps when B/U scram light on">X03O004F>0</TRIGGER>
<TRIGGER id="28" description="Deletes RFW-B lube oil malfunctions">X8AO160R>0</TRIGGER>
<TRIGGER id="29" description="Deletes Stuck rod when Insert P/B light illuminates">XRLO033I >0</TRIGGER>
</EVENT>
Page 34 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Start ASD Channel 1A1; Raise Power with Flow; Swap RCC Pumps; B Flow Unit Failure; FPC-P-1B Failure; Main Turbine Trip on High MSR LESSON TITLE Level; Hydraulic ATWS; Reduced SLC Capacity; Lower RPV Level; S/R/S Inserts Rods LENGTH OF LESSON 1.5 Hours S INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code LO001678 Rev. No. 0 JPM PQD Code Rev. No.
Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/30/09 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE APPROVED DATE Page 35 of 26
Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
Page 36 of 26
Appendix D NRC Scenario No. 2 FORM ES-D-1 Columbia Generating Station ILC NRC Exam October, 2009 Facility: Columbia NRC Scenario No: 2 Examiners: _______________ Operators: _______________
Initial conditions: Columbia is operating at reduced power. Yesterday ASD Channel 1A 1 tripped.
The problem has been corrected and Channel 1A1 is ready to be re-started.
Turnover: Start ASD Channel 1A1 per SOP-RRC-ASD. Step 5.6.1 is complete. After the channel is started, raise Reactor Power with flow to exit the OPRM Enabled Region. The SNE is working on a reactivity plan to continue the power increase from that point. Also RCC Pumps need to be swapped for run time equalization.
Start RCC-P-1A and place RCC-P-1C in standby.
Event Timeline Event Event Description No. Type*
- 5. T = 30 C (ATC) Flow Unit B Failure; TS (SRO) Tech Spec (LCS 1.3.2.1 and TS 3.3.1.1)
- 6. T = 35 (C) BOP FPC-P-1B Failure; FPC-P-1A Fails to Auto Start
- 10. T = 55 N (BOP) Perform PPM 5.5.10 and 5.5.11 to insert Control Rods
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 37 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SCENARIO DESCRIPTION The scenario begins with Columbia at approximately 56% power with RRC Pumps running at 32 Hz. ASD Channel 1A1 tripped yesterday and is now ready to be returned to service. When the Crew takes the shift they will re-start ASD Channel 1A1 and swap RCC Pumps.
EVENT 1 - Start RRC ASD Channel 1A1 EVENT 2 - Swap running RCC pumps to RCC-P-1A running and RCC-P-1C in standby EVENT 3 - When Channel 1A1 is restarted, place RRC-A ASD into Auto and raise power with flow to exit the OPRM Enabled Region.
EVENT 4 - Failure of RCIC Coupling Bolts. The Control Room will be contacted and informed that the coupling for the RCIC Turbine to Pump has only 2 of 5 bolts engaged. The crew should insert a RCIC trip to prevent it from starting and refer to TS 3.5.3 Condition A.
EVENT 5 - Failure of the B Flow Unit. The ATC operator will investigate alarms and determine the B Flow Unit has an active INOP trip. The CRS will refer to Tech Specs (LCS1.3.2.1 and TS 3.3.1.1)and direct the Flow Unit be bypassed.
EVENT 6 - Failure of FPC-P-1B. FPC-P-1A will not auto start on low pressure but the BOP operator will start FPC-P-1A manually and secure FPC-P-1B.
EVENT 7 - High Level MSR Drain Tank. A failure of the valves for MSR Drain Tank will occur. The BOP operator will attempt to take manual control and reduce drain tank level but will not be successful Eventually a MSR High Level alarm annunciates. The crew should take action and insert a manual scram and trip the Main Turbine which will trip on High MSR Level in 30 seconds from receipt of the alarm.
EVENT 8 - Hydraulic ATWS and Lower RPV Level. When a scram is inserted the crew will determine a hydraulic ATWS occurs. Reactor Power will be about 25%. The RRC Pumps trip when the MT Trips. The CRS will direct all injection be secured and lower RPV level to LT -65. When RPV level is about -100, Reactor Power will be LT 5%
EVENT 9 - Reduce SLC capacity. When the CRS directs SLC initiation, both SLC pumps start but only 20 gpm SLC flow will develop.
EVENT 10 - Insert Control Rods. Rod Insertion. PPM 5.5.10 and 5.5.11 will be performed to insert Control Rods.
EVENT 11 - The rods will insert on the first S/R/S. When all rods are in, RPV Level will be returned to
+13 - +54 band.
The scenario will be terminated when RPV level is being returned to normal band or as directed by the scenario coordinator.
Page 38 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 1
==
Description:==
Start RRC-P-1A ASD Drive 1A1 This event is initiated by shift turnover Time Position Applicants Actions or Behavior T=0 SRO Directs that ASD Channel 1A1 be started per SOP-RRC-ASD Section 5.6.
ATC Commences Section 5.6 at step 5.6.2:
- a. Verifies frequency of drive 1A2 at LE 35 Hz
- b. Depresses the ASD START button
- c. Verifies the red lamp illuminates (observes red light illuminates, green light goes out and channel failure limit alarm clears)
- d. Verifies heater breaker is OFF by contacting OPS4 Informs CRS that ASD Channel 1A1 has been started ROLEPLAY: If asked the Heater Breaker is in the OFF position COMMENTS:
Page 39 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 2
==
Description:==
Swap RCC Pumps to RCC-P-1A running and RCC-P-1C secured.
The event is initiated by turnover information and will be performed immediately after shift turnover Time Position Applicants Actions or Behavior T=0 CRS Direct RCC-P-1A be started and RCC-P-1C be secured BOP Refers to SOP-RCC-OPS Section 5.1.1a and starts RCC-P-1A:
- Contacts OPS 2 and verifies RCC-V-1A is OPEN
- Contacts OPS 2 and verifies RCC-V-2A is OPEN
- Place RCC-RMS-P-1A in AUTO after START Refers to section 5.1.2c:
- Places RCC-RMS-P-1C in AUTO after STOP
- Contacts OPS 2 and verifies RCC-V-23C CLOSED ROLEPLAY: RCC-V-1A and RCC-V-2A are open and RCC-V-23C did close when asked COMMENTS:
Page 40 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 3
==
Description:==
Place ASD in Auto and Raise Power With Flow to Exit OPRM Enabled Region The event is initiated by the SRO when ASD Channel 1A1 has been started Time Position Applicants Actions or Behavior T = 10 SRO Directs ATC to place A RRC Pump ASD control in Automatic ATC Verifies Master and Individual controller setpoints matched and places RRC-A ASD in Auto SRO Directs ATC to raise Reactor Power with flow to exit the OPRM Enabled Region at a rate not to exceed 10 MWE/minute ATC Raises reactor power with flow as directed COMMENTS:
Page 41 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 4
==
Description:==
RCIC Turbine Shaft Coupling Bolts Missing - Inops RCIC The event is initiated by OPS 2 contacting the Control Room when power has been raised and the OPRM Region has been exited Time Position Applicants Actions or Behavior T = 20 ROLEPLAY: As OPS 1 call the control room on extension 2393 and inform the reactor operator that you are down in the RCIC Room and found a nut on the turbine by the pump coupling. What I found is that only two of the five bolts for the coupling that connects the turbine to the pump are still engaged.
BOP Answers the phone and informs the CRS that the RCIC turbine/pump coupling only has 2 of the 5 bolts still connected.
SRO Calls Production/Work Control and informs them of the RCIC turbine situation ROLEPLAY: If called as Production/Work Control acknowledge the info and tell them a team will be put together to investigate.
SRO Directs BOP operator to insert a manual trip of the RCIC turbine to prevent it from starting BOP Trips the RCIC turbine by either depressing the Turbine Trip P/B or manually closing RCIC-V-1 SRO Refers to Tech Specs 3.5.3 Condition A:
- Restore RCIC to operable status within 14 days SRO/BOP Refers to OI-49 and determines that HPCS and ADS-SYS 1A/B be protected BOP Places protected signs of HPCS and both ADS divisions Page 42 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 4 Contacts OPS2 to hang protected signs on HPCS system COMMENTS:
Page 43 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 5
==
Description:==
Flow Unit B Failure The event is initiated when the OPRM Region has been exited and is initiated by ACTIVATING TRIGGER 1 Time Position Applicants Actions or Behavior T = 30 ATC Acknowledges Rod Out Block and Flow Reference Off Normal annunciators, informs CRS and refers to ARP for Flow Reference Off Normal (P603 A8 3-6)
ATC Per ARP determines the white light is illuminated indicating Flow Unit B is INOP Refers CRS to LCS 1.3.2.1 and TS 3.3.1.1 and TS Bases page 3.3.1.1-9 SRO Refers to LCS 1.3.2.1 and TS 3.3.1.1 and TS Bases page 3.3.1.1-9 and determines requirement is to place in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SRO Directs ATC Operator to bypass Flow Unit B ATC Places Flow Unit B in the Bypass position Notes the INOP light goes out and the BYPASS light illuminates COMMENTS:
Page 44 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 6 Description Lowering FPC System pressure with a failure of the standby pump to Auto Start The event is initiated when Tech Specs have been referenced for RCIC and systems protected by ACTIVATING TRIGGER 2 Time Position Applicants Actions or Behavior T = 35 BOP Acknowledges CIRCULATION PUMP B DISCHARGE PRESS LOW on P627.FPC2 3-1 and refers to ARP Informs CRS of the alarm and that the automatic actions should be an Auto start of FPC-P-1A but that FPC-P-1A did not auto start (The BOP may start pump and then inform CRS of actions based on auto action that should have occurred but did not)
SRO Directs the start of FPC-P-1A if not already running SRO Directs that FPC-P-1B be secured BOP Secures FPC-P-1B as directed (If FPC-P-1B is stopped before FPC-P-1A restores pressure, it may restart unless the control switch is put in the (Pull to Lock) IR-69 position)
SRO Contacts production/Work Control/OPS2 to investigate FPC-P-1B COMMENTS:
Page 45 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 7
==
Description:==
Failure of MSR Drain tank 1A level control valves HD-LIC-9A and 9A2 closed The event is initiated by ACTIVATING TRIGGER 3 after actions for Flow Unit and FPC failures have been completed (Drain Tank alarm annunciates in 10 seconds and it takes about 6 minutes to get MSR A High Level Alarm after trigger activation)
Time Position Applicants Actions or Behavior T = 40 BOP Acknowledges alarm and reports MSR Drain Tank 1A Level High alarm.
Refers to ARP.
Investigates controllers at H13-P835 to ensure they are in Auto and recognizes the controllers are opening drain valves but level continues to rise. May attempts manual operation but valve is already full open.
Reports controllers functioning in Auto (or Manual) and level indication is off scale high.
SRO Conduct a brief on actions if level continues to rise and MSR Level High alarm is received.
ATC/BOP Acknowledges and reports MSR A Level High alarm and refers to ARP (Turbine Trip has a 30 second time delay)
SRO Directs a manual reactor scram prior to automatic scram actuation (SRO may direct a scram prior to MSR A high Level alarm)
ATC Scrams the reactor and performs immediate operator actions of PPM 3.3.1:
- mode switch to shutdown
- monitors/reports Power/Pressure/Level Recognizes failure to scram (ATWS) - (REFER TO EVENT 8)
COMMENTS:
Page 46 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 8
==
Description:==
Hydraulic ATWS This event is setup at the beginning of the scenario and occurs automatically when a manual scram is inserted Critical Task is to lower RPV level and establish an LL (Lowered Level).
Time Position Applicants Actions or Behavior T = 45 ATC Continues with immediate scram actions after recognizing all control rods did not insert:
- Depress the manual scram pushbuttons
- Initiate ARI and verifies valves opened
- Insert SRMs and IRMs Announce EOP entry into PPM 5.1.1 on low Reactor Water level and/or Power GT 5% and a scram required Reports reactor power SRO Enters PPM 5.1.1 and directs/verifies that the Mode Switch has been placed in SHUTDOWN and exits PPM 5.1.1 via the Power leg to PPM 5.1.2, RPV Control ATWS Directs BOP to:
- Verify all appropriate isolations and initiations have occurred
- Verify pressure is being maintained by the bypass valves BOP Takes both ADS control switches to the INHIBIT position and Page 47 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 8 acknowledges associated BISIs Arms and Depresses the HPCS system initiation P/B while holding the control switch for HPCS-P-1 to STOP Closes HPCS-V-4 when it get fully opened Reports completion to SRO SRO Directs bypassing the MSIV isolation interlocks per PPM 5.5.6 Directs performance of PPM 5.5.1 BOP Performs PPM 5.5.6 and updates Crew:
At H13-P609 places MS-RMS-S84 to BYPASS At H13-P611 places MS-RMS-S85 to BYPASS Performs PPM 5.5.1 and updates Crew:
At H13-P625 places HPCS-RMS-S25 in OVERRIDE At H13-P629 places LPCS-RMS-S21 in OVERRIDE At H13-P629 places RHR-RMS-S105 in OVERRIDE At H13-P618 places RHR-RMS-S106 in OVERRIDE At H13-P618 places RHR-RMS-S107 in OVERRIDE SRO Direct the ATC to:
Stop and prevent all injection into the RPV except by Boron injection systems, RCIC, and CRD Lower level to a band less than -65 inches but greater than -183 inches (preferred band is -80 to -140)
Records the upper limit as LL Maintain level as directed from LL to -183 inches with systems Page 48 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 8 listed in Table 5 (Band should be -80 to -140)
SRO Directs SLC initiation when RRC pumps are off (SLC may be started prior to this as RRC-Pumps are off when MT Trips) (REFER TO EVENT 9).
ATC Uses Quick Cards to stops and prevent condensate and feedwater and lines up on the startup flow control valves as directed Reports EOP entry on low RPV level Reports Reactor Power as it drops due to lowering level When Reactor Power is LT 5%, marks RPV level to establish an LL Maintains RPV level between LL and -183 inches as directed (-80 inches to -140 inches)
SRO Directs PPM 5.5.10 and 5.5.11 (Tabs B, F) performance for a hydraulic ATWS. (REFER TO EVENT 10)
COMMENTS:
Page 49 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 9
==
Description:==
Failure of SLC pumps to deliver normal SLC flow to RPV This event is activated at the beginning of the scenario and realized by the crew when SLC control switches are taken to OPER to initiate SLC Time Position Applicants Actions or Behavior T = 50 SRO Recognizes RRC Pumps have tripped off and directs SLC initiation before SP temp reaches 110°F ATC Initiates SLC per the quick card:
Swaps keys and places two switches to OPER Verifies squib valves fire Verifies RWCU-V-4 closure Verifies flow and SLC tank level Reports reduced SLC flow (about 18 gpm) and initial tank level COMMENTS:
Page 50 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 10
==
Description:==
Insert control rods using PPM 5.5.10 and 5.5.11 Tab B.
This event is initiated by the SRO direction.
Time Position Applicants Actions or Behavior T = 55 SRO Directs PPM 5.5.10 and PPM 5.5.11 be performed to insert control rods BOP Performs:
PPM 5.5.10 - Override ARI Logic - pulls 2 fuses PPM 5.5.11 Tab B - Starts the second CRD Pump, places the SDV HIGH LEVEL Trip control switch to BYPASS on P603, and determines that scram cannot be reset per PPM 5.5.11 PPM 5.5.11 Tab F - The second CRD Pump should already be running, the SDV HIGH LEVEL Trip control switch should already be in BYPASS on P603, and determines that CRD drive header pressure can be established per PPM 5.5.11 Directs Instructor to perform back panel operations associated with Tab B and Tab F FLOOR OPERATOR: Take direction from BOP to perform back panel steps of Tab B (Step Q-3 to perform attachment 6.1) and Tab F (Step Q-6 to perform attachment 6.2).
Activate Trigger 28 to install RPS jumpers and Trigger 30 to install RSCS jumpers When completed with steps, initial by the blocks and inform the BOP operator that they are completed by standing next to Board S and giving the crew an update:
UPDATE READY - Attachment 6.1 per Tab B and Attachment 6.2 per Tab F of PPM 5.5.11 has been completed, END OF UPDATE.
Page 51 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 10 BOP Performs remainder of PPM 5.5.11 Tab B actions to scram/reset/scram:
- resets Scram and notes time
- After 2 minutes, checks rod density and inserts a manual reactor scram and informs CRS of results If rods do not insert continues scram/reset/scram Tab B BOP Performs remainder actions of PPM 5.5.11 Tab F:
- Places RWM Bypass Control Switch to BYPASS
- Informs CRS of readiness to drive rods SRO Directs rod insertion starting at rod 10-43 and inserting every other rod every other row until all rods are inserted skipping the peripheral rods BOP Drives Control Rods as directed COMMENTS: It may take two S/R/S actions before all rods go in.
Page 52 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 11
==
Description:==
Control Rods Insert and RPV Level returned to +13 to +54 band This event is activated when RPV level has been lowered and S/R/S is being performed Time Position Applicants Actions or Behavior Critical Task is to insert Control Rods by performing PPM 5.5.11 Scram/Reset/Scram BOOTH OPERATOR: When RPV Level has been lowered and is being controlled in the desired band, and scram/reset/scram is being performed to insert control rods:
Remove malfunctions associated with ATWS (CRD007A1, 7A2, 7B1 and 7B2)
T = 65 BOP Checks control rod density Initiates a manual scram Notes Control Rod motion Recognizes and reports All Rods In to the SRO SRO Directs SLC be stopped RO Takes control switches out of OPER and observes both SLC pumps stop SRO Exits PPM 5.1.2 and re-enters PPM 5.1.1 Directs RPV level be raised to +13 to +54 band with available systems RO Raises RPV level into band as directed TERMINATION POINT - The scenario will be terminated when RPV level has been returned to normal operating band.
COMMENTS:
Page 53 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 TURNOVER INFORMATION Initial conditions: Columbia is operating at reduced power. Yesterday ASD Channel 1A 1 tripped. The problem has been corrected and Channel 1A1 is ready to be re-started.
Turnover: Start ASD Channel 1A1 per SOP-RRC-ASD. Step 5.6.1 is complete.
After the channel is started, raise Reactor Power with flow to exit the OPRM Enabled Region. The SNE is working on a reactivity plan to continue the power increase from that point.
Additionally, RCC Pumps need to be swapped for run time equalization. Start RCC-P-1A and place RCC-P-1C in standby.
Page 54 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SIMULATOR SETUP INSTRUCTIONS Load IC 220.
Page 55 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SCHEDULE
<SCHEDULE>
<ITEM row = 1>
<ACTION>Insert malfunction MAL-CRD007A1</ACTION>
<DESCRIPTION>HYDRAULIC ATWS EAST SDV BLOCKAGE</DESCRIPTION>
</ITEM>
<ITEM row = 2>
<ACTION>Insert malfunction MAL-CRD007A2 to 90</ACTION>
<DESCRIPTION>HYDRAULIC ATWS EAST SDV</DESCRIPTION>
</ITEM>
<ITEM row = 3>
<ACTION>Insert malfunction MAL-CRD007B1</ACTION>
<DESCRIPTION>HYDRAULIC ATWS WEST SDV BLOCKAGE</DESCRIPTION>
</ITEM>
<ITEM row = 4>
<ACTION>Insert malfunction MAL-CRD007B2 to 90</ACTION>
<DESCRIPTION>HYDRAULIC ATWS WEST SDV</DESCRIPTION>
</ITEM>
<ITEM row = 5>
<ACTION>Insert malfunction PMP-SLC001F to 75</ACTION>
<DESCRIPTION>SLC-P-1A SLC PUMP 1A REDUCED FLOW (25% of normal)</DESCRIPTION>
</ITEM>
<ITEM row = 6>
<ACTION>Insert malfunction PMP-SLC002F to 75</ACTION>
<DESCRIPTION>SLC-P-1B SLC PUMP 1B REDUCED FLOW (25% of normal)</DESCRIPTION>
</ITEM>
<ITEM row = 9>
<EVENT>1</EVENT>
<ACTION>Insert malfunction MAL-NIS006B to INOP on event 1</ACTION>
<DESCRIPTION>APRM FLOW UNIT B FAIL</DESCRIPTION>
</ITEM>
<ITEM row = 10>
<ACTION>Insert override OVR-FPC003E to OFF</ACTION>
<DESCRIPTION>FPC-P-1A FAILS TO AUTO START</DESCRIPTION>
</ITEM>
<ITEM row = 11>
<ACTION>Insert malfunction PMP-FPC002B on event 2</ACTION>
<DESCRIPTION>FPC-P-1B SHAFT BREAK</DESCRIPTION>
Page 56 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009
</ITEM>
<ITEM row = 13>
<EVENT>3</EVENT>
<ACTION>Insert malfunction AOV-FWH059F to CLOSE on event 3</ACTION>
<DESCRIPTION>HD-LCV-9A1 HD-TK-1A LEVEL CONTROL VALVE</DESCRIPTION>
</ITEM>
<ITEM row = 14>
<EVENT>3</EVENT>
<ACTION>Insert malfunction AOV-FWH060F to CLOSE on event 3</ACTION>
<DESCRIPTION>HD-LCV-9A2 HD-TK-1A LEVEL CONTROL DUMP VLV</DESCRIPTION>
</ITEM>
</SCHEDULE>
Page 57 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Raise Power with Flow; Start CW-P-1C; Control Rod Exercise Surveillance Finds an Uncoupled Rod That Wont Re-Couple; SGT LESSON TITLE Surveillance - Controller Failure; Minimum Seismic EQ; CW Rupture -
Causes Back Pressure To Rise Requiring a Manual Scram; OBE; Loss of Offsite Power; DW Floor Rupture; RHR-P-2A Breaker Fails to Close, RHR-V-16B Fails Closed; Emergency Depressurize on exceeding High Drywell Temp LENGTH OF LESSON 1.5 Hours S INCLUDED Lesson Plan PQD Code Rev. No.
Simulator Guide PQD Code LO001679 Rev. No. 0 JPM PQD Code Rev. No.
Exam PQD Code Rev. No.
DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/31/09 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE APPROVED DATE Page 58 of 22
Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use Page 59 of 22
Appendix D NRC Scenario No. 3 FORM ES-D-1 Columbia Generating Station ILC NRC Exam October, 2009 Facility: Columbia NRC Scenario No: 3 Examiners: _______________ Operators: _______________
Initial conditions: Reactor Power is 90%. Power was reduced due to CW-P-1C not being available. The work on CW-P-1C has just been completed.
Turnover: Start CW-P-1C. After the pump start, raise reactor power with Flow to 95% power. The reactivity brief has been performed. At that time stop the power increase and perform OSP-CRD-W701, Control Rod Exercise of Fully Withdrawn Rods (MODE 1) starting with rod 18-59 and working across from left to right and then from top to bottom until all fully withdrawn control rods have been exercised. After CW-P-1C is started perform the Standby Gas Treatment B System Monthly Operability surveillance, OSP-SGT-M702.
Event Timeline Event Event Description No. Type*
- 1. T=0 N (BOP) Start CW-P-1C
- 2. T=0 R (ATC) Raise power with Flow
- 3. T = 10 R (ATC) Perform Control Rod Exercise surveillance - OSP-CRD-W701 C (ATC)
TS (SRO) Second rod is uncoupled and will not re-couple when attempted
- 4. T = 10 C (BOP) Perform SGT B System Operability surveillance - OSP-SGT-M702 TS (SRO)
Controller Fails when SGT flow is raised
- 5. T = 35 M (All) Minimum Seismic Earthquake CW Pipe Rupture outside Protected Area MT Back Pressure rise requiring Reactor scram and MT Trip
- 6. T = 50 M (All) Operating Basis Earthquake Loss of Offsite Power
- 7. T = 55 LOCA Drywell Floor Rupture
RHR-V-16B Control Power trips and valve still closed
- 9. T = 70 Emergency Depressurize due to High Drywell Temperature GT 330°F
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 60 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SCENARIO DESCRIPTION EVENT 1 - Start CW-P-1C EVENT 2 - Power will be raised to 95% with Flow EVENT 3 - Perform OSP-CRD-W701 (Control Rod Exercise Surveillance). Control Rod 22-59 will be uncoupled when checked. When Recoupling is attempted the rod will not recouple. Tech Specs will be referenced and the rod should be driven full in and isolated with cooling flow maintained EVENT 4 - Perform OSP-SGT-M702 (Standby Gas treatment System B Operability Surveillance). The controller will fail as is when flow reaches 3100 cfm. The unit may be shut down. Tech Specs will be referenced EVENT 5 - Minimum Seismic Earthquake results in a CW Line rupture outside the protected area. As a result, Main Turbine back pressure will start to rise. The crew should recognize that the event is not recoverable and insert a manual scram and remove the MT from service EVENT 6 - After the immediate scram actions have been performed, a OBE will occur causing a loss of Startup Power, then a loss of Backup Power (and the Drywell Floor Ruptures and a LOCA starts - refer to Event 7)
EVENT 7 - Drywell Floor Rupture and LOCA EVENT 8 - Inability to Spray (RHR-P-2A Breaker Fails and RHR-V-16B will not open)
EVENT 9 - Emergency Depressurize due to Drywell Temperature when it cannot be restored and maintained LT 330°F The scenario will be terminated when RPV level is being returned to normal or as directed by the scenario coordinator Page 61 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 1
==
Description:==
Start CW-P-1C per SOP-CW-START This event is initiated by shift turnover Time Position Applicants Actions or Behavior T=0 SRO Directs the start of CW-P-1C per SOP-CW-START BOP Performs SOP-CW-START Section 5.2:
- 5.2.1 - Step is N/A
- 5.2.2 - Contacts OPS4 to verify
- 5.2.3 - Contacts OPS4 to verify
- Makes plant announcement of CW-P-1C start
- 5.2.5 - Verifies bay level is GT 441 (is reading 442)
- 5.2.6 - Places C/S for CW-V-13C and TSW-V-115C to OPEN and when valves start to open releases switch
- 5.2.7 - Verifies CW-P-1C Blue ready to start light is illuminates
- 5.2.8 - Verifies 6 towers on line per P&L 4.2
- 5.2.9 - Step is N/A
- 5.2.10 - Places CW-P-1C C/S to START and verifies pump starts, discharge valve opens, and CW-V-13C and TSW-V-115C close Informs CRS that CW-P-1C is running COMMENTS:
Page 62 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 2
==
Description:==
Raise Power with Flow This event is initiated by shift turnover Time Position Applicants Actions or Behavior T=0 SRO Directs ATC to raise power with flow to achieve 95% reactor power at a rate not to exceed 10MWE/min ATC Notes Reactor Power and Main Generator Output Verifies both RRC pumps individual controllers are in AUTO and depresses Master Controller Raise P/B to increase flow/power as directed COMMENTS:
Page 63 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 3
==
Description:==
Control Rod Exercise. Control Rod 22-59 is not coupled and will not re-couple This event is initiated by shift turnover and started after Reactor Power is 95%
Time Position Applicants Actions or Behavior T = 10 SRO Directs performance of OSP-CRD-W701 ATC Performs OSP-CRD-W701 section 7.8 for rod 18-59 with coupling check OK:
- Selects the rod
- Inserts rod 1 notch
- Verifies position changes
- Continuously withdraws rod
- Verifies position change
- Verifies coupling integrity (no alarm)
- Verifies position 48
- Repeats for next rod ATC Performs for rod 22-59 and receives ROD OVERTRAVEL annunciator (P603.A7.1-8)
ATC Acknowledges alarm and refers to ARP:
- Insert control rod 22-59 to position 00 to accomplish recouping
- Continuous withdraws 22-59 and receives ROD OVERTRAVEL alarm again Page 64 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 3 SRO Declares Control Rod 22-59 inoperable Refers to Tech Spec 3.1.3 Condition C and verifies total number of slow or inop rods is LE 8 immediately AND Fully insert the inop rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND disarm the associated CRD within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Directs control rod 22-59 be fully inserted SRO May direct SOP-CRD-HCU section 5.4 be performed for rod 22-59 ROLEPLAY: If directed to isolate rod acknowledge task only - no manipulations need to be done.
ROLEPLAY: If asked, there are no slow or inop control rods.
ROLEPLAY: If asked, conditions allow control rod 22-59 to be inserted and then withdrawn.
COMMENTS:
Page 65 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 4
==
Description:==
Perform SGT B Monthly Surveillance OSP-SGT-M702 The event is initiated by the turnover and is performed after CW-P-1C is started Time Position Applicants Actions or Behavior BOOTH OPERATOR: Have SGT Flow displayed on computer and when flow reaches 3100 CFM ACTIVATE TRIGGER 1 T = 10 SRO Directs Standby Gas Treatment System B monthly operability surveillance, OSP-SGT-M702 be performed ROLEPLAY - If asked there are no paint fumes, etc. in SGT area and SGT integrity is done BOP Performs OSP-SGT-M702 as directed:
- 7.1.1 - Contacts OPS 2 and verifies no paint fumes
- 7.1.3 - Records moisture reading on SGT-MI-4B (reads zero)
- 7.1.4 - Verifies SGT-V-2B is open (Rx Bldg inlet)
- 7.1.5 - Verifies SGT-V-3B1 is open (fan 1B2 inlet)
- 7.1.6 - Depresses BISI Manual Out of Service pushbutton
- 7.1.7 - Informs CRS to enters SGT system B as inoperable in the TS surveillance log
- 7.1.8 - Places SGT-DPIC-1B2 in MANUAL
- 7.1.9 - Adjusts SGT-DPIC-1B2 output to minimum (100%)
- 7.1.10 - Places SGT-EHC-1B2 control switch to ON
- 7.1.11 - Verifies SGT-FN-1B2 auto starts 10 sec. after heaters energize
- 7.1.12 - Promptly opens SGT-V-5B2 (exhaust to stack)
- 7.1.13 - Slowly adjusts SGT-DPIC-1B2 to obtain 4800 CFM +/-
480CFM BOOTH OPERATOR: When flow reaches 3100 CFM ACTIVATE TRIGGER 1 Page 66 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 4 BOP Observes and reports to the CRS that the DPIC cannot be adjusted and appears to have failed-as-is with SGT flow at about 3100 CFM SRO May directs BOP to shutdown the SGT system and restore the lineup Refers to Tech Specs due to DPIC failure and determines TS 3.6.4.3 Condition A applies as SGT-FN-1A-1 is already tagged out - Restore SGT B within 7 Days May contact Production/Work Control/SSS ROLEPAY: If asked to secure or leave SGT-B running ask the crew to leave it running so mechanics can go check it out.
BOP May use SOP-SGT-SHUTDOWN to secure SGT or use surveillance and do steps in reverse order Per SOP-SGT-SHUTDOWN Section 5.1.2:
Take the following switches to PULL TO LOCK:
- SGT-EHC-1B2
- SGT-V-2B
- SGT-V-3B1
- SGT-V-2B2
- SGT-V-5B1
- SGT-V-5B2 When SGT-EHC-1B1 and SGT-FN-1B1 starts then place SGT-EHC-1B1 to OFF COMMENTS:
Page 67 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 5
==
Description:==
Minimum Seismic Earthquake results in Circ Water Rupture Outside Protected Area requiring a Reactor Scram and Main Turbine Trip This event is initiated when the two surveillances are completed and Tech Specs have been reviewed by ACTIVATING TRGGER 2 - BOOTH OPERATOR SEE BELOW INSTRUCTIONS Time Position Applicants Actions or Behavior BOOTH OPERATOR: Start EQ track on lowest volume and run for 5 seconds and then ACTIVATE TRIGGER 2. Allow EQ track to run another 5 seconds then stop it T = 35 BOP Acknowledges Minimum Seismic Alarm, pulls ARP and refers CRS to ABN-EARTHQUAKE Investigates and reports indications on Bd. L (16 Amber and no red lights)
ROLEPLAY: 30 seconds after EQ contact Control Room as OPS 4 and report that you felt the earth shake just a minute ago SRO Directs announcement per ABN-EARTHQUAKE be performed BOP Makes announcement and directs SAS (meets booth operator at booth door) to repeat on the Maintenance and Security radio channels ROLEPLAY: When EQ announcement has been performed contact the control room as OPS 4 and report a large piping break between the cooling towers has resulted in a large volume of water flowing away form the plant into the desert SRO May direct announcement concerning pipe rupture be performed BOP Makes announcement if directed Reports lowering MWe output and rising MT Back Pressure NOTE: It takes about 9 minutes to get to a back pressure reading of 5.7 and MWe to be 948 MWe -
longer if power is reduced in an attempt to keep plant/Main Turbine on line longer SRO Determines that it is necessary to trip the Main Turbine due to rising back pressure Conducts a brief on scram and MT trip Page 68 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 5 SRO May direct a RRC flow reduction prior to directing the Reactor Scram Directs ATC to insert a manual scram ATC Lowers Core Flow if directed Announces Listen up for the scram report Performs immediate scram actions:
- Places Reactor Mode Switch in SHUTDOWN
- Monitors Power, Pressure, and Level
- Verifies all rods inserted
- Inserts IRMs and SRMs by depressing INSERT P/B Reports EOP entry on low RPV water level SRO May direct MT Trip prior to its auto trip Enters PPM 5.1.1 on Low RPV Level and directs restoration of RPV level to +13 inches to +54 inches (a -40 to +50 band should be given) with RCIC and/or Condensate and Feed system COMMENTS:
Page 69 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 6
==
Description:==
Operating Basis Earthquake; Loss of Startup Power (10 sec. TD); Loss of Backup Power (120 sec. TD)
This event is initiated by ACTIVATING TRIGGER 3 AFTER the scram report and after EOPs have been entered - BOOTH OPERATOR SEE BELOW INSTRUCTIONS Time Position Applicants Actions or Behavior BOOTH OPERATOR: Start EQ track on lowest volume and take 19 seconds to get to full volume. After 4 seconds ACTIVATE TRIGGER 3. Allow EQ track to run another 5 seconds after reaching max volume and then stop it Critical step is to initiate systems required to restore RPV level back to +13 to =54 T = 55 BOP Reports OBE annunciator, pulls ARP and refers SRO to ABN-EARTHQUAKE.
Investigates and reports indications on Bd. L (all red and yellow lights illuminated)
BOP Investigates electrical boards when the Startup Transformer locks out and updates crew that Startup power is locked out and Backup power is on SM-7 and SM-8. SM-4 is powered from DG-3 SRO Due to the loss of feedwater directs RPV level restoration with RCIC and/or HPCS and/or CRD ATC Initiates RCIC and or HPCS using quick cards Restarts CRD pump Uses RCIC and/or HPCS to maintain RPV Level BOP Investigates electrical board when Backup Transformer locks out and updates crew that Backup power is locked out and SM-7 and SM-8 are powered from Diesel Generators SRO Directs RPV Pressure be maintained with SRVs with a band of 800 to 1000 psig Page 70 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 BOP/ATC Cycles SRVs as necessary to maintain RPV Pressure between 800 and 1000 psig (When LOCA starts SRVs will not have to be cycled to control RPV pressure)
SRO Directs actuations for low RPV level be verified BOP Verifies and reports actuations complete BOP/ATC Recognizes that CAS compressors and TSW are not running.
Directs OPS 3 to place FW on CAS Heat Exchanger cooling and reset and restart CAS compressors A and B BOOTH OPERATOR: When directed and after appropriate time delay, place firewater on CAS and reset and restart the CAS compressors and report results to control room COMMENTS:
Page 71 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 7
==
Description:==
LOCA (on a 120 sec. TD); Drywell Floor Failure; RHR-P-2A Breaker Fails to Close This event is initiated from trigger 3 which has already been activated Time Position Applicants Actions or Behavior T = 55 BOP Reports Drywell Pressure rising and at 1.68 psig reports EOP entry into PPM 5.2.1 (reports others as they occur - SP/T, SP/L, DW/T)
SRO Directs actuations for 1.68 psig DW/P be verified BOP Verifies actuations for 1.68 psig and notes RHR-P-2A is not running Attempts to manually close RHR-P-2A breaker and notes it does not close Reports 1.68 actuation findings to CRS BOP Observes that Wetwell and Drywell pressures are approximately the same and informs the CRS Reports Wetwell pressure when GT 2 psig SRO Directs Wetwell Sprays be initiated with RHR-P-2B May direct SP Cooling be initiated Directs sprays be terminated when WW/P drops below 1.68 psig BOP Initiates Wetwell sprays using quick card and opens RHR-V-27B Initiates Suppression Pool Cooling using quick card if directed Reports Wetwell sprays initiated COMMENTS:
Page 72 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 8
==
Description:==
Inability to Spray Drywell This event is initiated from trigger 3 which has already been activated Time Position Applicants Actions or Behavior T = 65 BOP Reports Drywell Temperature as it approaches 285°F (It takes 6 minutes to reach 285°F after trigger 3 is initiated)
SRO Ensures parameters are within DSIL, WW/L LT 51, RRC pumps are stopped and directs Drywell Cooling Fans be secured ATC/BOP Stops Drywell Cooling Fans and reports completion to CRS SRO Directs Drywell sprays be initiated with RHR-P-2B BOP Using quick card, verifies within DSIL and opens RHR-V-17B and attempts to open RHR-V-16B Notes and reports that RHR-V-16B will not open with C/S was turned to start SRO May contact Production/Work Control/OPS1/OPS2 to manually open RHR-V-16B ROLEPLAY: If asked to manually open RHR-V-16B wait 10 minutes and inform the Control Room that it will not open SRO Sets Drywell Temperature as a KEY parameters due to inability to spray drywell ATC/BOP Reports Drywell temperature as it rises towards 330°F Reports trend of parameters as it approaches PSP limits COMMENTS:
Page 73 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 Event No. 9
==
Description:==
EMERGENCY DEPRESSURIZATION when Drywell Temperature reaches 330°F (It takes 10 minutes to get to 330°F from trigger 3 initiation)
This event is initiated when it is determined that Drywell Temperature cannot be restored and maintained LT 330°F Time Position Applicants Actions or Behavior Critical step is to initiate an EMERGENCY DEPRESSURIZATION when drywell Temperature cannot be restored and maintained LT 330°F T = 60 BOP Reports Drywell Temperature as it approaches 330°F SRO When Drywell Temperature cannot be restored and maintained below 330°F, determines that an Emergency Depressurization is required:
Takes PPM 5.1.1override to PPM 5.1.3, Emergency RPV Depressurization ATC/BOP Stops ECCS injection as necessary to maintain RPV level Directs ECCS pumps not required for adequate core cooling be stopped from injecting SRO Requests Wetwell Level and when reported GT 17 foot, directs seven SRVs, ADS preferred, be opened ATC/BOP Opens seven ADS SRVs as directed and reports completion to CRS Page 74 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SRO Directs RPV/L maintenance +13 inches to +54 inches.
Termination Cue: The scenario can be terminated when the reactor has been Emergency Depressurized and RPV level is under control in the band of +13 inches to +54 inches or as directed by the scenario coordinator COMMENTS:
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Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 TURNOVER INFORMATION Initial conditions: Reactor Power is 90%. Power was reduced due to CW-P-1C not being available. The work on CW-P-1C has just been completed. SGT-FN-1A-1 is tagged out due to a failed shaft coupling.
Turnover: BOP - Start CW-P-1C.
The following tasks are to be performed concurrently:
ATC - After the pump start, raise reactor power with Flow to 95% power. The reactivity brief has been performed.
ATC - After the power increase has been stopped, perform OSP-CRD-W701, Control Rod Exercise of Fully Withdrawn Rods (MODE 1) starting with rod 18-59 and working across from left to right and then from top to bottom until all fully withdrawn control rods have been exercised.
BOP - After CW-P-1C has been started perform the Standby Gas Treatment B System Monthly Operability surveillance, OSP-SGT-M702.
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Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SIMULATOR SETUP INSTRUCTIONS Reset to IC 219 Ensure components are de-energized and hang tags on: SGT-V-3A2, SGT-V-4A-1, SGT-V-5A-1 and SGT-EHC-1A-1 Set up earthquake machine on lowest volume and paused Ensure all events and schedules windows are closed Place Simulator in Run Page 77 of 21
Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009 SCHEDULE
<SCHEDULE>
<ITEM row = 1>
<ACTION>Insert malfunction MAL-RMC006-2259</ACTION>
<DESCRIPTION>ROD 2259 UNCOUPLED</DESCRIPTION>
</ITEM>
<ITEM row = 2>
<ACTION>Insert malfunction BKR-RHR001 to FA_AS_IS</ACTION>
<DESCRIPTION>RHR-P-2A Breaker Fails As Is</DESCRIPTION>
</ITEM>
<ITEM row = 3>
<ACTION>Insert malfunction MOV-RHR009F to FAIL_AS_IS</ACTION>
<DESCRIPTION>RHR-V-16B Fails closed</DESCRIPTION>
</ITEM>
<ITEM row = 5>
<EVENT>1</EVENT>
<ACTION>Insert malfunction CNH-SCN007A on event 1</ACTION>
<DESCRIPTION>SGT-DPIC-1B2 FAN 1B-2 FLOW CONTROLLER FAIL AS IS</DESCRIPTION>
</ITEM>
<ITEM row = 7>
<EVENT>2</EVENT>
<ACTION>Insert malfunction MAL-RWB001 to 0.1 on event 2</ACTION>
<DESCRIPTION>Minimum Seismic EQ</DESCRIPTION>
</ITEM>
<ITEM row = 8>
<EVENT>2</EVENT>
<ACTION>Insert malfunction MAL-CFW003 to 2400 in 600 on event 2</ACTION>
<DESCRIPTION>CONDENSER AIR LEAK</DESCRIPTION>
</ITEM>
<ITEM row = 10>
<EVENT>3</EVENT>
<ACTION>Insert malfunction MAL-RWB001 to 0.2 on event 3</ACTION>
<DESCRIPTION>EARTHQUAKE</DESCRIPTION>
</ITEM>
<ITEM row = 11>
<EVENT>3</EVENT>
<ACTION>Insert malfunction MAL-OED001 after 10 on event 3</ACTION>
<DESCRIPTION>LOCKOUT TR-S 10 seconds after OBE</DESCRIPTION>
</ITEM>
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Appendix D NRC Scenario No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam October, 2009
<ITEM row = 12>
<EVENT>3</EVENT>
<ACTION>Insert malfunction MAL-OED003 after 120 on event 3</ACTION>
<DESCRIPTION>LOCKOUT TR-B 120 seconds after OBE</DESCRIPTION>
</ITEM>
<ITEM row = 13>
<EVENT>3</EVENT>
<ACTION>Insert malfunction MAL-PCN006 on event 3</ACTION>
<DESCRIPTION>Drywell Floor Failure</DESCRIPTION>
</ITEM>
<ITEM row = 14>
<EVENT>3</EVENT>
<ACTION>Insert malfunction MAL-RRS009A after 240 to 500000 in 1200 on event 3</ACTION>
<DESCRIPTION>Steam Line break in Drywell 2 minutes after OBE</DESCRIPTION>
</ITEM>
</SCHEDULE>
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