ML050690411
| ML050690411 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/27/2005 |
| From: | Gody A Operations Branch IV |
| To: | Forbes J Entergy Operations |
| References | |
| -RFPFR, 50-368/05-301 50-368/05-301 | |
| Download: ML050690411 (188) | |
Text
JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 1 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A1a Conduct of Operations TASK: Perform offsite power availability and vital electrical availability checklist.
JTA#: ANO2-RO-ELECD-SURV-25 KA VALUE RO: 4.2 SRO: 3.9 KA
REFERENCE:
2.1.31 APPROVED FOR ADMINISTRATION TO:
RO: X SRO: TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2107.001 Supplement 4 Rev. 049-00-0 EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 2 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE
JPM INITIAL TASK CONDITIONS: 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted. Low grid voltage is expected to be restored to normal by 2000 today. No further grid degradation is expected.
Actions are being reviewed in OP 2107.001 for degraded offsite power voltage. 2VEF56A and B are operable.
TASK STANDARD: Supplement 4 complete and 2B5 voltage determined to be low and the bus inoperable.
TASK PERFORMANCE AIDS: Copy of OP 2107.001 Supplement 4.
SIMULATOR SETUP: Degrade Offsite voltage to ~ 490KV. Degrade 2B5 voltage to ~ 431VAC and 2B6 voltage to ~ 440VAC.
JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 3 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Using OP 2107.001, Supplement 4, Electrical system breaker alignment and power availability checklist, perform sections 1.0 through 3.3 due to degraded offsite voltage."
CRITICAL STEPS: 33, 34, 38, 39, 41 PERFORMANCE CHECKLIST STANDARDS (Circle One) EXAMINER'S NOTE:
The steps of this surveillance may be performed in any order.
- 1. Verify SU-2 status.
Verified only SU #2 to 2A2, 2H1, 2H2 are in PTL and SU #2 to 2A1 is NOT in PULL-TO-LOCK.
On Supplement 4, step 2, initialed step 2.1and 2.3 and NA'd the rest. On Supplement 4, 3.0 table 1 circled NA for UA to 2A1 and UA to 2A2.
N/A SAT UNSAT 2. Verify SU-2 To 2A1 (2A-111) status. Verified 2A-111 green and white lights lit.
On Supplement 4, Table 2 placed a check in 2A-111 "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for 2A-111 WITHIN ACCEPTABLE NORMAL
RANGE. N/A SAT UNSAT 3. Verify SU-2 To 2A2 (2A-211) status.
Verified 2A-211 green and white lights lit.
On Supplement 4, Table 2, placed a check in 2A-211 "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for 2A-211 WITHIN
ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 4 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 4. Verify 2A3 Supply Breaker (2A-309) CLOSED.
Verified 2A-309 CLOSED.
Observed red light ON for 2A-309. On Supplement 4, Table 2, placed a check in 2A-309 "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for 2A-309 WITHIN ACCEPTABLE NORMAL
RANGE. N/A SAT UNSAT 5. Verify 2A4 Supply breaker (2A-409) CLOSED.
Verified 2A-409 CLOSED.
Observed red light ON for 2A-409. On Supplement 4, Table 2, placed a check in 2A-409 "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for 2A-409 WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT 6. Verify SU-2 voltage.
EXAMINER's CUE: ER-ANO-2004-0548 is not installed.
Using SPDS-EST2R OR PMS E4013, verified SU-2 voltage
> 154 KV.
On Supplement 4, Table 2, recorded SU-2 voltage in "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for SU-2 voltage WITHIN ACCEPTABLE
NORMAL RANGE. N/A SAT UNSAT Note to Examiner: The answers to the System Dispatcher calls should be given by the Examiner.
JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 5 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 7. Contact dispatcher to determine if ANO switchyard capacitors "in service" or not required.
EXAMINER'S CUE:
Dispatcher reports ANO switchyard capacitors "in service". Contacted dispatcher to determine if ANO switchyard capacitors "in service" or not
required.
On Supplement 4, Table 2, placed a check in ANO switchyard capacitor "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for ANO switchyard capacitor WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT 8. Contact dispatcher to determine if Russellville East Substation capacitors "in service" or not required.
EXAMINER'S CUE:
Dispatcher reports Russellville East Substation capacitors "in service".
Contacted dispatcher to determine if Russellville East Substation capacitors "in service" or not required.
On Supplement 4, Table 2, placed a check in Russellville East Substation capacitor "Measured Value" column.
On Supplement 4, Table 2, circled "YES" for Russellville East Substation capacitor status WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT 9. Contact dispatcher to determine if any other condition that could degrade offsite power sources
is known.
EXAMINER'S CUE:
Dispatcher reports NO conditions which could degrade offsite are power known. Contacted dispatcher to determine if any other condition that could degrade offsite power sources was known.
On Supplement 4, Table 2, placed a check in "Measured Value" column for other conditions known which could degrade offsite power.
On Supplement 4, Table 2, circled "YES" for other conditions known which could degrade offsite power WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 6 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 10. Contact Dispatcher to determine if SU-2 automatic voltage regulator is in service or not required.
EXAMINER'S CUE:
SU-2 Automatic Voltage Regulator is in service.
Contacted dispatcher to determine if SU-2 Automatic Voltage Regulator is in service or if it is not required.
On Supp 4 Table 2, placed check in status column for SU-2 Voltage Regulator in service.
On Supp 4 Table 2, circled YES for SU-2 voltage regulator WITHIN ACCEPTABLE
NORMAL RANGE. N/A SAT UNSAT 11. Verify SU-3 To 2A1 (2A-113) status.
Checked 2A-113 green and white lights lit.
On Supplement 4, Table 3, placed a check in 2A-113 "Measured Value" column.
On Supplement 4, Table 3, circled "YES" for 2A-113 WITHIN
ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT 12. Verify SU-3 To 2A2 (2A-213) status. Verified 2A-213 green and white lights lit.
On Supplement 4, Table 3, placed a check in 2A-213 "Measured Value" column.
On Supplement 4, Table 3, circled "YES" for 2A-213 WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT 13. Verify 2A3 Supply breaker (2A-309) CLOSED.
Verified 2A-309 CLOSED. Observed red light ON for 2A-309. On Supplement 4, Table 3, placed a check in 2A-309 "Measured Value" column. On Supplement 4, Table 3, circled "YES" for 2A-309 WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 7 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 14. Verify 2A4 Supply breaker (2A-409) CLOSED.
EXAMINER'S CUE:
Red light ON for 2A409 to 2A4. Verified 2A-409 CLOSED. Observed red light ON for 2A-409. On Supplement 4, Table 3, placed a check in 2A-409 "Measured Value" column. On Supplement 4, Table 3, circled "YES" for 2A-409 WITHIN ACCEPTABLE NORMAL
RANGE. N/A SAT UNSAT 15. Verify SU-3 Voltage.
Using SPDS point E2ST3R, OR using PMS E9664, OR on panel 2C10 using SU3 regulated voltage indication verified SU-3 voltage > 21.7 KV. On Supplement 4, Table 3, recorded SU-3 voltage in "Measured Value" column. On Supplement 4, Table 3, circled "YES" for SU-3 voltage WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT 15. Contact dispatcher to determine Auto-Transformer status.
EXAMINER'S CUE:
Dispatcher reports 500 KV source connected to AUTO transformer.
Contacted dispatcher to determine if Auto-Transformer 500 KV source was connected. On Supplement 4, Table 3, placed a check in Auto-Transformer 500 KV source "Measured Value" column. On Supplement 4, Table 3, circled "YES" for Auto-Transformer 500 KV source WITHIN ACCEPTABLE NORMAL RANGE. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 8 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 16. Contact Dispatcher to determine if SU-3 automatic voltage regulator is in service or not required.
EXAMINER'S CUE:
SU-3 Automatic Voltage Regulator is in service.
Contacted dispatcher to determine if SU-3 Automatic Voltage Regulator is in service or if it is not required. On Supp 4 Table 3, placed check in status column for SU-3 Voltage Regulator in service. On Supp 4 Table 3, circled YES for SU-3 voltage regulator WITHIN ACCEPTABLE NORMAL RANGE.. N/A SAT UNSAT 17. Verify both SU-2 and SU-3 operable. Verified both SU-2 and SU-3 operable as shown in Table 2 and Table 3. Circled "YES" in step 3.1.1. N/A SAT UNSAT 18. Mark step 3.1.2 & 3.1.3 "N/A".
Marked step 3.1.2 & 3.1.3 "N/A". N/A SAT UNSAT 19. Evaluate steps 3.1.1 through 3.1.3 for "NO" answers.
Evaluated steps 3.1.1 through 3.1.2 for "NO" answers. Determined that there were no "NO" answers NA'd bullets below 3.1.4. N/A SAT UNSAT EXAMINER's NOTE: This starts section 3.2, of electrical checklist.
Verified 2A-310 OPEN.
Observed green light ON for 2A-310. On Supplement 4, Table 4, placed a check in 2A-310 "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2A-310 status agreeing with limiting condition
for operability. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 9 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 21. Verify 2A3-2A4 Tie Breaker (2A-410) OPEN.
Verified 2A-410 OPEN.
Observed green light ON for 2A-410. On Supplement 4, Table 4, placed a check in 2A-410 "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2A-410 status agreeing with limiting condition
for operability. N/A SAT UNSAT 22. Verify 2A3 voltage.
On panel 2C33 OR using SPDS point E2A3, verified 2A3 voltage > 3640v and < 4440v.
On Supplement 4, Table 4, recorded 2A3 voltage in "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2A3 voltage agreeing with limiting condition for operability. N/A SAT UNSAT 23. Determine 2A3 Operability Knowing the status of 2VEF-56B, weather data and Table 4 data, USED the flow chart to verify 2A3 operable. N/A SAT UNSAT 24. Verify 2A3-2A4 Tie Breaker (2A-310) OPEN.
Verified 2A-310 OPEN. Observed green light ON for 2A-310. On Supplement 4, Table 5, placed a check in 2A-310 "Measured Value" column. On Supplement 4, Table 5, circled "YES" for 2A-310 status agreeing with limiting condition for operability. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 10 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 25. Verify 2A3-2A4 Tie Breaker (2A-410) OPEN.
Verified 2A-410 OPEN. Observed green light ON for 2A-410. On Supplement 4, Table 5, placed a check in 2A-410 "Measured Value" column. On Supplement 4, Table 5, circled "YES" for 2A-410 status agreeing with limiting condition
for operability. N/A SAT UNSAT 26. Verify 2A4 voltage.
On panel 2C33 OR using SPDS point E2A4, verified 2A4 voltage > 3640v and < 4440v. On Supplement 4, Table 5, recorded 2A4 voltage in "Measured Value" column. On Supplement 4, Table 5, circled "YES" for 2A3 voltage agreeing with limiting condition
for operability. N/A SAT UNSAT 27. Determine 2A4 Operability Knowing the status of 2VEF-56A, weather data and Table 4 data, USED the flow chart to verify 2A4
operable. N/A SAT UNSAT 28. Verify both 2A3 and 2A4 operable.
Verified both 2A3 and 2A4 operable as shown in Table 4 and Table 4.
Circled "YES" in step 3.2.1. N/A SAT UNSAT 29. Mark step 3.2.2 "N/A".
Marked step 3.2.2 "N/A". N/A SAT UNSAT 30. Evaluate steps 3.2.1 and 3.2.2 for "NO" answers.
Evaluated steps 3.2.1 and 3.2.2 for "NO" answers.
Determined 2A3 and 2A4 to be operable.
And NA'd initialed step 3.2.3. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 11 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 31. Verify 2B5-2B6 Tie Breaker (2B-513) OPEN.
Verified 2B-513 OPEN.
Observed green light ON for 2B-513. On Supplement 4, Table 4, placed a check in 2B-513 "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2B-513 status agreeing with limiting condition
for operability. N/A SAT UNSAT 32. Verify 2B5-2B6 Tie Breaker (2B-613) OPEN.
Verified 2B-613 OPEN.
Observed green light ON for 2B-613. On Supplement 4, Table 4, placed a check in 2B-613 "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2B-613 status agreeing with limiting condition for operability. N/A SAT UNSAT (C) 33. Verify 2B5 voltage.
On panel 2C33 OR using SPDS point E2B5, verified 2B5 voltage is NOT > 436v.
On Supplement 4, Table 4, recorded 2B5 voltage in "Measured Value" column.
On Supplement 4, Table 4, circled "NO" for 2B5 voltage agreeing with limiting condition
for operability. N/A SAT UNSAT (C) 34. Determine 2B5 Operability Using the Low voltage recorded in Table 6, used flow chart to determine that 2B5 is INOPERBLE. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 12 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 35. Verify 2B5-2B6 Tie Breaker (2B-513) OPEN.
Verified 2B-513 OPEN.
Observed green light ON for 2B-513. On Supplement 4, Table 4, placed a check in 2B-513 "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2B-513 status agreeing with limiting condition
for operability. N/A SAT UNSAT 36. Verify 2B5-2B6 Tie Breaker (2B-613) OPEN.
Verified 2B-613 OPEN.
Observed green light ON for 2B-613. On Supplement 4, Table 4, placed a check in 2B-613 "Measured Value" column.
On Supplement 4, Table 4, circled "YES" for 2B-613 status agreeing with limiting condition for operability. N/A SAT UNSAT 37. Verify 2B6 voltage.
On panel 2C33 OR using SPDS point E2B6, verified 2B6 voltage is > 436v. On Supplement 4, Table 4, recorded 2B6 voltage in "Measured Value" column. On Supplement 4, Table 4, circled "YES" for 2B6 voltage agreeing with limiting condition for operability. N/A SAT UNSAT (C) 38. Determine 2B6 Operability Using the status of 2VEF-56A, weather data, the status of ESF Switchgear Room Coolers 2VUC-2A and 2VUC-2B, and Table 5 data, used the flow chart to verify 2B6 OPERABLE. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 13 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 39. Verify 2B5 INOPERABLE and 2B6 OPERABLE.
Verified 2B5 INOPERABLE and 2B6 OPERABLE as shown in Table 6 and Table 7.
Circled "NO" in step 3.3.1. N/A SAT UNSAT 40. Mark step 3.3.2 "N/A".
Marked step 3.3.2 "N/A". N/A SAT UNSAT (C) 41. Evaluate steps 3.3.1 and 3.3.2 for "NO" answers.
EXAMINER's CUE:
"Do not refer to Tech Specs the SM will perform that for you." "SM has been informed."
"Initiating Condition Report has been simulated complete."
NOTE CRITICAL PART OF THIS STEP IS DECLARING
2B5 INOPERABLE.
Evaluated steps 3.3.1 and 3.3.2 for "NO" answers. Determined 2B5 to be INOPERABLE and 2B6 to be operable.
Inform the SM Initiate CR
Initialed steps 3.3.3.
N/A SAT UNSAT END JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 14 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL PLANT CONDITIONS 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted. Low grid voltage is expected to be restored to normal by 2000 today. No further grid degradation is expected. Actions are being reviewed in OP 2107.001 for degraded offsite power voltage. 2VEF56A and B are operable.
Initiating CUE:
The SM/CRS directs, "Using OP 2107.001, Supplement 4, Electrical system breaker alignment and power availability checklist, perform sections 1.0 through 3.3 due to degraded offsite voltage."
JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 15 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL PLANT CONDITIONS 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted. Low grid voltage is expected to be restored to normal by 2000 today. No further grid degradation is expected. Actions are being reviewed in OP 2107.001 for degraded offsite power voltage. 2VEF56A and B are operable.
Initiating CUE:
The SM/CRS directs, "Using OP 2107.001, Supplement 4, Electrical system breaker alignment and power availability checklist, perform sections 1.0 through 3.3 due to degraded offsite voltage."
JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A1a Conduct of Operations
TASK: Review and approve offsite power availability and vital electrical availability checklist.
JTA#: ANO-SRO-ADMIN-NORM-152 KA VALUE RO: 4.2 SRO: 3.9 KA
REFERENCE:
2.1.31 APPROVED FOR ADMINISTRATION TO:
RO: SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2107.001 Supplement 4 Rev. 049-00-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE
JPM INITIAL TASK CONDITIONS: 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted. Low grid voltage is expected to be restored to normal by 2300 today. 2VEF-56A and 2VEF56B are both operable.
TASK STANDARD: Review Supplement 4 data and identify the following:
- 1) Voltage recorded in table 3, Startup 3 for SU3 regulated voltage was less than acceptable.
- 2) Declared SU3 INOPERBLE.
- 3) Identified TS 3.8.1.1 to be applicable and performance of a complete OP 2107.001 Supplement 4 must be done within one hour.
- 4) Initiated Condition Report to correct problem.
TASK PERFORMANCE AIDS: Completed copy of OP 2107.001 Supplement 4.
SIMULATOR SETUP:
N/A.
JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
The SM directs, "Perform section 4.0, Supervisor review and identify the errors in the partial completion of OP 2107.001, Supplement 4 (sections 2, 3.0, 3.1, 3.2, and 3.3.)"
Critical Steps: 1,2,3 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 1. Review completed copy of OP 2107.001 Supplement 4 and identify Table3, startup 3 has been completed incorrectly.
Review Table 3, startup 3 and identified that SU #3 voltage is lower than acceptable.
N/A SAT UNSAT (C) 2. Declared SU #3 inoperable.
Determined that SU #3 should be declared inoperable due to low voltage. N/A SAT UNSAT (C) 3. Identified Technical Specification 3.8.1.1 is
applicable.
Identified that Technical Specification 3.8.1.1 LCO is applicable and that action A.1, performance of OP 2107.001 Supplement 4 must be performed within one hour. N/A SAT UNSAT 4. Initiate Condition report. EXAMINER's CUE:
Condition report will be initiated by Shift Engineer.
Identified need to initiate condition report. N/A SAT UNSAT END STOP TIME:
JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL PLANT CONDITIONS 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted. Low grid voltage is expected to be restored to normal by 2300 today. 2VEF-56A and 2VEF56B are both operable.
Initiating CUE:
The SM directs, "Perform section 4.0, Supervisor review and identify the errors in the partial completion of OP 2107.001, Supplement 4 (sections 2, 3.0, 3.1, 3.2, and 3.3.)"
JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL PLANT CONDITIONS 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted. Low grid voltage is expected to be restored to normal by 2300 today. 2VEF-56A and 2VEF56B are both operable.
Initiating CUE:
The SM directs, "Perform section 4.0, Supervisor review and identify the errors in the partial completion of OP 2107.001, Supplement 4 (sections 2, 3.0, 3.1, 3.2, and 3.3.)"
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A1b C onduct of Operations TASK: Spent Fuel Pool Makeup
JTA#:
REFERENCE:
2.1.23 APPROVED FOR ADMINISTRATION TO:
RO: X SRO: TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
20 Minutes REFERENCE(S):
OP 2104.006, Rev 021-06-0, Attachment F
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
SYSTEM/DUTY AREA:
THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
Plant is at 100% power. PMS computer is out of service. Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb
TASK STANDARD:
RO candidates should calculate required SFP makeup vo lume to be within 1828 to 1928 gallons, determine Boric acid volume to be within 910 gallons to 960 gallons, det ermine DI water volume to be within 918 gallons to 968 gallons.
TASK PERFORMANCE AIDS:
OP 2104.006, Rev 021-06-0, Attachment F JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
Chemistry has just notified the Contro l Room that when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM/CRS directs, "Per OP 2104.006 step 10.3, manually calculate the total volume, the amount of boric acid and the amount of DI water required to raise the Spent Fuel Pool level four (4) inches due to cask loading pit operations using OP 2104.006, Attachment F."
CRITICAL ELEMENTS (C): 5, 7, 8 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. Record initial Spent Fuel Pool Level. On 2104.006, Attachment F recorded initial Spent Fuel Pool
level of 401' 0" given in initial
conditions.
N/A SAT UNSAT Examiner's Note:
It is not necessary for the candidate to fill in every blank on OP 2104.005, attachment F to arrive at the correct total volume to be added to the SFP. 2. Calculate initial Spent Fuel Pool Volume.
Obtained Gal/Ft value for Fuel Pool - Top of racks to Elev 401'6"
(5634.4 gal/ft).
Divided 5634.4 gal/ft by 12 in/ft to obtain 469.5 gal/in.
Multiplied 469.5 by 6 inches to obtain 2817 gallons.
Obtained value for Total Volume (Gal) of Fuel Pool - Top of racks
to Elev 401'6" (133,817 gal)
Subtracted 1878 gal from 133,817 gal to obtain 131000
gallons total volume above top of racks. Added 131000 gal and 84,255 gal to find initial pool volume of
215255 gallons.
N/A SAT UNSAT 3. Record desired Spent Fuel Pool Level.
On 2104.006, Attachment F recorded desired Spent Fuel
Pool level of 401' 4".
N/A SAT UNSAT JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 4. Calculate desired Spent Fuel Pool Volume.
Obtained Gal/Ft value for Fuel Pool - Top of racks to Elev 401'6"
(5634.4 gal/ft).
Divided 5634.4 gal/ft by 12 in/ft to obtain 469.5 gal/in.
Multiplied 469.5 by 2 inches to obtain 939 gallons.
Obtained value for Total Volume (Gal) of Fuel Pool - Top of racks
to Elev 401'6" (133,817 gal)
Subtracted 939 gal from 133,817 gal to obtain 132878 gallons total
volume above top of racks.
Added 132878 gal and 84,255 gal to find desired pool volume of
217133 gallons.
N/A SAT UNSAT C 5. Calculate volume of makeup required to raise Spent Fuel
Pool level to desired level.
Total Volume within 1828 to 1928. Subtracted initial Spent Fuel Pool volume from desired Spent Fuel
Pool volume and determined
amount of makeup needed to be
1878 gallons.
N/A SAT UNSAT 6. Record 'A' BAMT boron concentration.
On 2104.006, Attachment F, recorded value of 5950 ppm for
'A' BAMT concentration.
N/A SAT UNSAT C 7. Calculate feed volume of boric acid required to raise pool level.
Volume within 910 gallons to
960 gallons.
Inserted values into formula and determined Boric acid volume to
be 935.53 gallons.
N/A SAT UNSAT C 8. Calculate the feed volume of DI water required to raise pool
level. Volume within 918
gallons to 968 gallons.
Inserted values into formula and determined DI water volume to
be 942.47 gallons.
N/A SAT UNSAT END STOP TIME:
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER'S COPY JPM INITIAL TASK CONDITIONS:
Plant is at 100% power. PMS computer is out of service. Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb INITIATING CUE:
Chemistry has just notified the Control Room t hat when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM/CRS directs, "Per OP 2104.006 step 10.3, manually calculate the total volume, the am ount of boric acid and the amount of DI water required to raise the Spent Fuel Pool level f our (4) inches due to cask loading pit operations using OP 2104.006, Attachment F."
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:
Plant is at 100% power. PMS computer is out of service. Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb INITIATING CUE:
Chemistry has just notified the Control Room t hat when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM/CRS directs, "Per OP 2104.006 step 10.3, manually calculate the total volume, the am ount of boric acid and the amount of DI water required to raise the Spent Fuel Pool level f our (4) inches due to cask loading pit operations using OP 2104.006, Attachment F."
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A1b C onduct of Operations TASK: Spent Fuel Pool Makeup
JTA#:
REFERENCE:
2.1.23 APPROVED FOR ADMINISTRATION TO:
RO: SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2104.006, Rev 021-06-0, Attachment F
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
SYSTEM/DUTY AREA:
THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
Plant is at 100% power. PMS computer is out of service. Initial Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3. Final Spent Fuel Pool Level = 401' 4"
TASK STANDARD:
SRO candidates should identify the following: 1) Boron Concentration of the feed source should be 5950 NOT 4950.
- 2) The Feed volume (F) calculated previously was tr ansposed into the feed volumes calc as 1788 gallons not the 1878 gallons correctly calculated.
Therefore both the calculated Boric acid and DI water volumes are wrong. And calculate the following correct feed volumes:
- 3) Boric acid volume calculated to be within 910 gallons to 960 gallons. 4) Determine DI water volume to be within 918 gallons to 968 gallons.
TASK PERFORMANCE AIDS:
OP 2104.006, Rev 021-06-0, Attachment F JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
Chemistry has just notified the Contro l Room that when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM directs, "Review for accuracy and correct any errors in the completed OP 2104.006, Attachment F."
CRITICAL ELEMENTS (C): 3, 4, 5, 6 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. Reviewed the completed form OP 2104.006, Attachment F.
Reviewed the completed form OP 2104.006, Attachment F.
N/A SAT UNSAT 2. Determined the calculated volume of solution to be correct.
Calculated the feed volume to be added to the SFP, F, to be 1878
gallons. N/A SAT UNSAT C 3. Determined that the boron concentration of the feed source was in error.
Recognized the boron concentration of the feed source
was recorded as 4950 ppm
instead of the given value of
5940 ppm.
N/A SAT UNSAT C 4. Determined the calculated volume of solution used in the
calculation of the feed volumes
of boric acid Recognized that the feed volume to be added to the SFP, F, was
recorded in error as 1788 gallons
NOT the 1878 gallons calculated
on the previous page.
N/A SAT UNSAT Examiner's Note: the candidate may need to be prompted to calculate the volume of Boric acid and DI water. C 5. Determined the Boron volume to be added as calculated was
in error and determined the
correct volume to be 910
gallons to 960 gallons.
Recognized the Boron volume to be added as calculated was in
error and determined the correct
volume to be 935.5 gallons.
N/A SAT UNSAT C 6. Determined the DI water volume to be added as
calculated was in error and
determined the correct volume
to be within 918 gallons to 968
gallons. Recognized the DI water volume to be added as calculated was in
error and determined the correct
volume to be 942.5 gallons.
N/A SAT UNSAT END STOP TIME:
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER'S COPY JPM INITIAL TASK CONDITIONS:
Plant is at 100% power. PMS computer is out of service. Initial Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3. Final Spent Fuel Pool Level = 401' 4" INITIATING CUE:
Chemistry has just notified the Control Room t hat when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM directs, "Review for accuracy and
correct any errors in the completed OP 2104.006, Attachment F."
JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:
Plant is at 100% power. PMS computer is out of service. Initial Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3. Final Spent Fuel Pool Level = 401' 4"
INITIATING CUE:
Chemistry has just notified the Control Room t hat when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM directs, "Review for accuracy and
correct any errors in the completed OP 2104.006, Attachment F."
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A.2: Equipment Control TASK: Review completed 2P89B surveillance and determine 2P-89B operability JTA#: KA VALUE RO: 3.5 SRO: 3.9 KA
REFERENCE:
2.2.12 APPROVED FOR ADMINISTRATION TO:
RO: X SRO: TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2104.039 Supplement 2 Rev. 042-04-0 EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS
Plant is at 100% power and all ESF equipment is in normal alignment. 2P89C is aligned to the GREN side.
The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.
TASK STANDARD: (Identification of three of the four errors is required and one of the three must be the Pump D/P)
Pump P is out of LIMITING RANGE FOR OPERABILITY. Calculation for determining lower pump P limit is in error. Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY. Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.
TASK PERFORMANCE AIDS: marked-up copy of Supplement 2 2P-89B quarterly test
SIMULATOR SETUP:
NA JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:
The Control Room Supervisor/Shift Manager directs determination of the operability of the 'B' HPSI pump, 2P89B, by reviewing the completed surveillance data OP 2104.039 Supplement 2, complete all reviews for operability, calculations performed and identify all errors.
CRITICAL STEPS: 2, 3, 4, 5 START TIME:
PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide a marked-up copy of Supplement 2, 2P-89B quarterly test
- 1. Perform review of the surveillance procedure results. Reviews the surveillance procedure provided.
N/A (C) 2. Pump P is out of LIMITING RANGE FOR OPERABILITY.
Pump D/P is out of LIMITING RANGE FOR OPERABILITY.
N/A SAT UNSAT (C) 3. Calculation for determining lower pump P limit is in error. This calculation is below the table in supplement 2 section 3 and recorded in the table on the
line for pump P. Calculation for determining lower pump P limit should be 1380.81 psid.
N/A SAT UNSAT (C) 4. Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY.
Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY.
N/A SAT UNSAT (C) 5. Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.
Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.
N/A SAT UNSAT EXAMINER's CUE: The Shift Engineer will enter the pump data into the database. 6. Report to CRS that the results of the surveillance are unsatisfactory and 2P89B is inoperable. Reports to CRS that results of the surveillance are unsatisfactory and 2P89B is inoperable.
N/A SAT UNSAT END STOP TIME:
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment. 2P89C is aligned to the GREEN side. The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.
Initiating CUE:
The Control Room Supervisor/Shift Manager direct s determination of the operability of the 'B' HPSI pump, 2P89B, by reviewing the comple ted surveillance data OP 2104.039 Supplement 2, complete all reviews for operability, calc ulations performed and identify all errors.
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment. 2P89C is aligned to the GREEN side. The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.
Initiating CUE:
The Control Room Supervisor/Shift Manager direct s determination of the operability of the 'B' HPSI pump, 2P89B, by reviewing the comple ted surveillance data OP 2104.039 Supplement 2, complete all reviews for operability, calc ulations performed and identify all errors.
PROC./WORK PLAN NO.
2104.039 PROCEDURE/WORK PLAN TITLE:
HPSI SYSTEM OPERATION PAGE: 61 of 148 CHANGE: SUPPLEMENT 2 PAGE 7 OF 9 3.0 ACCEPTANCE CRITERIA 3.1 Record values observed during 2P-89B operation below AND compare with limiting range of values for operability.
Record date and time Test begins TODAY's DATE / 0800 TABLE 1 TEST QUANTITY INSTRUMENT (INCLUDE TEST INST)
MEASURED VALUE ACCEPTABLE NORMAL RANGE LIMITING RANGE FOR OPERABILITY IS DATA IN LIMITING RANGE? Running Suct.
Pressure 2PI-5100 (local) 33.5 psig 8 psig 8 psig YES NO 2PI-5101 (local) 1389 psig N/A N/A N/A Discharge Pressure 2PI-5109 (2C16) 1379 psig N/A N/A N/A RWT Temperature 2TIS-5675 (2C17) 90 F 40 to 110 F N/A N/A Pump P {4.3.1} 2PI-5101 - 2PI-5100 1355.5 psid N/A 1360.81 (1)to 1612.8 psid YES NO 34 33 35 Motor Running Amps (CR-1-96-0272-07)Ammeter at 2A-406 A B C Amps Amps AmpsN/A N/A N/A Inboard Brg Radial #1 Vibes VIB001 0.825 in/sec 0.325 in/sec 0.700 in/sec YES NO Inboard Brg Radial #2 Vibes VIB001 0.22 in/sec 0.325 in/sec 0.700 in/sec YES NO Inboard Brg Axial Vibes VIB001 0.073 in/sec 0.325 in/sec 0.700 in/sec YES NO Outboard Brg Radial #1 Vibes VIB001 0.187 in/sec 0.325 in/sec 0.700 in/sec YES NO Outboard Brg Radial #2 Vibes VIB001 0.207 In/sec 0.325 in/sec 0.700 in/sec YES NO Outboard Brg Axial Vibes VIB001 0.610 In/sec 0.232 in/sec 0.558 in/sec YES NO Record date and time Test completed TODAY's DATE 0930 Vibration Instrument Cal Due Date 7 days from TODAY Vibration Data Collected By Eddy Electrician Note 1: For RWT temperature (T), minimum acceptable pump P is: 1372.9 + 20.41 (Instrument error) - [(T-40)/4] psid Minimum P = 1393.31 - [( 90 - 40)/4] = 1360.81 psid 3.2 Independently verify pump P calculation.
PROC./WORK PLAN NO.
2104.039 PROCEDURE/WORK PLAN TITLE:
HPSI SYSTEM OPERATION PAGE: 62 of 148 CHANGE: SUPPLEMENT 2 PAGE 8 OF 9 3.3 Document observation of check valve stroke in Table 2.
TABLE 2 CHECK VALVE TEST DIRECTION TEST CRITERIA IS PROPER VALVE STROKE INDICATED? 2SI-10C Closed 2P-89C NOT rotating YES NO N/A 2SI-10B Closed 2P-89B NOT rotating YES NO N/A 3.4 IF NO circled in Table 1 OR 2, THEN perform the following: Declare affected component inoperable. Refer to Tech Spec 3.5.2 OR 3.5.3. Notify Shift Manager. Initiate WR/WO as applicable.
NOTE If HPSI pump 2P-89A OR 2P-89C inoperable, then 2SI-10C/2SI-10B testing may be deferred until inoperable HPSI pump restored to operable as per
IST Coordinator.
3.5 IF 2SI-10C AND/OR 2SI-10B NOT tested (N/A circled in Table 2),
THEN perform the following: Initiate notification to perform test during current quarter OR as directed by IST Coordinator. N/A Annotate on status board. N/A Annotate in Work Exceptions section of WR/WO. N/A 3.6 Pump Data recorded in database AND reviewed by SRO.
3.7 IF this surveillance performed as PMT, THEN complete Unit 2 IST Data Collection (1015.016O). N/A Comments ________________________________________________________________ ________________________________________________________________ ________________________________________________________________ ________________________________________________________________
Performed By Jimmy Reactor Date TODAY_____
____________________________________________
PROC./WORK PLAN NO.
2104.039 PROCEDURE/WORK PLAN TITLE:
HPSI SYSTEM OPERATION PAGE: 63 of 148 CHANGE: SUPPLEMENT 2 PAGE 9 OF 9 4.0 SUPERVISOR REVIEW AND ANALYSIS 4.1 Do all measured values recorded in ACCEPTANCE CRITERIA fall within specified LIMITING RANGE FOR OPERABILITY?
4.2 Do all measured values recorded in ACCEPTANCE CRITERIA fall within ACCEPTABLE NORMAL RANGE? (N/A if all results outside normal range also outside limiting range.)
4.3 IF NO answered to 4.1, THEN perform the following corrective actions: Verify Inoperable Equipment Checklist (1015.001, Conduct of Operations) completed. Verify Condition Report initiated.
4.4 IF NO circled in 4.2, THEN perform the following corrective actions: Verify WR/WO has been initiated. Complete Surveillance Test Schedule Change Request (1000.009D) to double test frequency.
Comments ________________________________________________________________ ________________________________________________________________
________________________________________________________________ ________________________________________________________________
4.5 Are all administrative requirements of this test satisfied?
Supervisor ______________________________________________ Date __________
YES NO YES NO N/A YES NO JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A.2: Equipment Control TASK: Review and approve as a supervisor the completed 2P89B surveillance.
JTA#: KA VALUE RO: 3.5 SRO: 3.9 KA
REFERENCE:
2.2.12 APPROVED FOR ADMINISTRATION TO:
RO: SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2104.039 Supplement 2 Rev. 042-04-0 EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS
Plant is at 100% power and all ESF equipment is in normal alignment. 2P89C is aligned to the GREEN side.
The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.
TASK STANDARD:
(Identification of Five of the Six errors is required and two of the six must be the Pump D/P and the tech spec applicabiltiy)
Pump P is out of LIMITING RANGE FOR OPERABILITY. Calculation for determining lower pump P limit is in error. Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY. Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY. Determine TS 3.5.2 applicability Yes is circled on parameters that do not meet acceptance criteria
TASK PERFORMANCE AIDS: marked-up copy of Supplement 2 2P-89B quarterly test
SIMULATOR SETUP:
NA
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:
The Shift Manager directs "perform supervisor review and analysis of the 'B' HPSI pump, 2P89B, by reviewing and identifying all errors on the completed surveillance data OP 2104.039 Supplement 2." CRITICAL STEPS: 2, 3, 4, 5, 6, 7 START TIME:
PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide a marked-up copy of Supplement 2, 2P-89B quarterly test
- 1. Perform supervisor review of the surveillance procedure results and determine errors. Reviews the surveillance acceptance criteria provided.
N/A EXAMINER's NOTE: the following are the errors in the form provided. (C) 2. Pump P is out of LIMITING RANGE FOR OPERABILITY.
Pump D/P is out of LIMITING RANGE FOR OPERABILITY.
N/A SAT UNSAT (C) 3. Calculation for determining lower pump P limit is in error. This calculation is below the table in supplement 2 section 3 and recorded in the table on the line for pump P. Calculation for determining lower pump P limit should be 1380.81 psid.
N/A SAT UNSAT (C) 4. Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY.
Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY.
N/A SAT UNSAT (C) 5. Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.
Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.
N/A SAT UNSAT (C) 6. Identify the technical specification applicability error. Identifies TS 3.5.2 applicability.
N/A SAT UNSAT (C) 7. Identified that YES was circled on parameters that did not meet acceptance criteria.
Identifies that YES was circled on parameters that did not meet acceptance criteria.
N/A SAT UNSAT EXAMINER's NOTE: The candidate will probably require another RO to review the data table before proceeding. Ask the candidate to continue on with completing section 4.0 as though that review matched the same errors previously identified. 8. Inoperable equipment checklist needed. EXAMINER's CUE: The SRO ADMIN will perform the inoperable equipment checklist. Identifies need to perform inoperable equipment checklist must be completed.
N/A SAT UNSAT 9. Condition Report needed.
EXAMINER's CUE:
The SE will initiate the condition report. Identifies need to generate condition report. N/A SAT UNSAT JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE END STOP TIME:
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment. 2P89C is aligned to the GREEN side.
The 2P-89B Quarterly test has been comp leted using OP 2104.039 Supplement 2.
Initiating CUE:
The Shift Manager directs "perform supervisor review and analysis of the 'B' HPSI pump, 2P89B, by reviewing and identifying all errors on the completed surveillance data OP 2104.039 Supplement 2."
JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 6 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment. 2P89C is aligned to the GREEN side.
The 2P-89B Quarterly test has been comp leted using OP 2104.039 Supplement 2.
Initiating CUE:
The Shift Manager directs "perform supervisor review and analysis of the 'B' HPSI pump, 2P89B, by reviewing and identifying all errors on the completed surveillance data OP 2104.039 Supplement 2."
PROC./WORK PLAN NO.
2104.039 PROCEDURE/WORK PLAN TITLE:
HPSI SYSTEM OPERATION PAGE: 61 of 148 CHANGE: SUPPLEMENT 2 PAGE 7 OF 9 3.0 ACCEPTANCE CRITERIA 3.1 Record values observed during 2P-89B operation below AND compare with limiting range of values for operability.
Record date and time Test begins TODAY's DATE / 0800 TABLE 1 TEST QUANTITY INSTRUMENT (INCLUDE TEST INST)
MEASURED VALUE ACCEPTABLE NORMAL RANGE LIMITING RANGE FOR OPERABILITY IS DATA IN LIMITING RANGE? Running Suct.
Pressure 2PI-5100 (local) 33.5 psig 8 psig 8 psig YES NO 2PI-5101 (local) 1389 psig N/A N/A N/A Discharge Pressure 2PI-5109 (2C16) 1379 psig N/A N/A N/A RWT Temperature 2TIS-5675 (2C17) 90 F 40 to 110 F N/A N/A Pump P {4.3.1} 2PI-5101 - 2PI-5100 1355.5 psid N/A 1360.81 (1)to 1612.8 psid YES NO 34 33 35 Motor Running Amps (CR-1-96-0272-07)Ammeter at 2A-406 A B C Amps Amps AmpsN/A N/A N/A Inboard Brg Radial #1 Vibes VIB001 0.825 in/sec 0.325 in/sec 0.700 in/sec YES NO Inboard Brg Radial #2 Vibes VIB001 0.22 in/sec 0.325 in/sec 0.700 in/sec YES NO Inboard Brg Axial Vibes VIB001 0.073 in/sec 0.325 in/sec 0.700 in/sec YES NO Outboard Brg Radial #1 Vibes VIB001 0.187 in/sec 0.325 in/sec 0.700 in/sec YES NO Outboard Brg Radial #2 Vibes VIB001 0.207 In/sec 0.325 in/sec 0.700 in/sec YES NO Outboard Brg Axial Vibes VIB001 0.610 In/sec 0.232 in/sec 0.558 in/sec YES NO Record date and time Test completed TODAY's DATE 0930 Vibration Instrument Cal Due Date 7 Days from TODAY Vibration Data Collected By Eddy Electrician Note 1: For RWT temperature (T), minimum acceptable pump P is: 1372.9 + 20.41 (Instrument error) - [(T-40)/4] psid Minimum P = 1393.31 - [( 90 - 40)/4] = 1360.81 psid 3.2 Independently verify pump P calculation. JJB PROC./WORK PLAN NO.
2104.039 PROCEDURE/WORK PLAN TITLE:
HPSI SYSTEM OPERATION PAGE: 62 of 148 CHANGE: SUPPLEMENT 2 PAGE 8 OF 9 3.3 Document observation of check valve stroke in Table 2.
TABLE 2 CHECK VALVE TEST DIRECTION TEST CRITERIA IS PROPER VALVE STROKE INDICATED? 2SI-10C Closed 2P-89C NOT rotating YES NO N/A 2SI-10B Closed 2P-89B NOT rotating YES NO N/A 3.4 IF NO circled in Table 1 OR 2, THEN perform the following: Declare affected component inoperable. N/A Refer to Tech Spec 3.5.2 OR 3.5.3. N/A Notify Shift Manager. N/A Initiate WR/WO as applicable. N/A NOTE If HPSI pump 2P-89A OR 2P-89C inoperable, then 2SI-10C/2SI-10B testing may be deferred until inoperable HPSI pump restored to operable as per
IST Coordinator.
3.5 IF 2SI-10C AND/OR 2SI-10B NOT tested (N/A circled in Table 2),
THEN perform the following: Initiate notification to perform test during current quarter OR as directed by IST Coordinator. N/A Annotate on status board. N/A Annotate in Work Exceptions section of WR/WO. N/A 3.6 Pump Data recorded in database AND reviewed by SRO. SBR
3.7 IF this surveillance performed as PMT, THEN complete Unit 2 IST Data Collection (1015.016O). N/A Comments ________________________________________________________________ ________________________________________________________________ ________________________________________________________________ ________________________________________________________________
Performed By Sammy Reactor Date TODAY Jimmy Reactor
PROC./WORK PLAN NO.
2104.039 PROCEDURE/WORK PLAN TITLE:
HPSI SYSTEM OPERATION PAGE: 63 of 148 CHANGE: SUPPLEMENT 2 PAGE 9 OF 9 4.0 SUPERVISOR REVIEW AND ANALYSIS 4.1 Do all measured values recorded in ACCEPTANCE CRITERIA fall within specified LIMITING RANGE FOR OPERABILITY?
4.2 Do all measured values recorded in ACCEPTANCE CRITERIA fall within ACCEPTABLE NORMAL RANGE? (N/A if all results outside normal range also outside limiting range.)
4.3 IF NO answered to 4.1, THEN perform the following corrective actions: Verify Inoperable Equipment Checklist (1015.001, Conduct of Operations) completed. Verify Condition Report initiated.
4.4 IF NO circled in 4.2, THEN perform the following corrective actions: Verify WR/WO has been initiated. Complete Surveillance Test Schedule Change Request (1000.009D) to double test frequency.
Comments ________________________________________________________________ ________________________________________________________________
________________________________________________________________ ________________________________________________________________
4.5 Are all administrative requirements of this test satisfied?
Supervisor ______________________________________________ Date __________
YES NO YES NO N/A YES NO JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: A.3 Radiation Control TASK: Review the emergency RWP and determine stay time based on radiation levels expected.
JTA#: KA VALUE RO: 2.9 SRO: 3.3 KA
REFERENCE:
2.3.10 APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
Perform SIMULATOR:
LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
2004-0009; emergency RWP and status board printout of Aux Building 354'.
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS
- 1. Plant is DEFUELED and all FUEL HANDLING operations are secured. 2. Power has been lost to both SFP cooling pumps and 2K11-K5 "FUEL POOL TEMP HI" is in alarm. 3. A Site Area Emergency has been declared on Unit 2 due to a station blackout. Power has been restored to 2A3 and 2B5 from the Alternate AC Generator, AACG. 4. Service water must be aligned to the SFP due to boiling and loss of inventory through the tilt pit gate. 5. Fuel Pool low level alarm is in and SFP level is lowering.
- 6. RP coverage will not be available.
TASK STANDARD:
Using Emergency RWP: Identify General Area, GA, dose rates in SFP valve gallery are ~ 500 MR/HR. Determine a maximum stay time of 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> based on EAD alarm set-points. Using normal inspection RWP: Determine appropriate dosimeter Entered RCA Observed proper radiological controls while in RCA Properly uses the PCM-1 Properly scans loose items in TCM JPM time is based on the review of the emergency RWP and the calculation of the stay time.
TASK PERFORMANCE AIDS: Emergency RWP 2004-0009
SIMULATOR SETUP:
NA
JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:
The Shift Manager directs that Service water from loop I must be aligned to the SFP, use the Emergency Radiological Work Permit, RWP, and identify the maximum allowable time before you would be required to leave the Auxiliary Building 354' elevation SFP valve gallery, excluding entry and exit times to and from the area. Critical Steps: 2, 3, 4, 5, 6 START TIME:
PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide Emergency RWP. EXAMINER's CUE: The candidate may attempt to check out a radiation survey meter per monitoring step 7.0. It is not a part of this JPM to check out the survey meter, but that the candidate knows one is needed.
- 1. Review Emergency RWP for limits. Determines that the alarming dosimeter is set to alarm in an 800mr/hr field and that the Dose alarm is set at 800 mrem.
N/A (C) 2. Determine stay time in SFP valve gallery to be a maximum of 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Using the status board printout provided determined that the General Area (GA) field is 500 MR/HR so the maximum stay time will be 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
N/A SAT UNSAT EXAMINER's NOTE: The rest of these steps determine the candidate's ability to enter and exit controlled access correctly using the Actual RWP for inspections, DO NOT allow the candidate to use the emergency RWP to enter controlled access.
(C) 3. Determined that an alarming dosimeter will be required for entry into the Radiologically Controlled Area, RCA, using the normal inspection RWP. Obtained an alarming dosimeter from rack. N/A SAT UNSAT (C) 4. Entered appropriate information into the log in screen and successfully entered the RCA. Entered the RCA under the general inspection RWP.
N/A SAT UNSAT (C) 5. While in the RCA the examinee observes and adheres to all applicable postings and entry requirements.
While in the RCA the examinee observes and adheres to all applicable postings and entry requirements.
N/A SAT UNSAT (C) 6. When exiting the RCA the examinee enters the control point area and enters a PCM-1 monitor.Enters and exits PCM-1.
N/A SAT UNSAT 7. All loose materials will be cleared through the tool contamination monitor (TCM) Examinee places loose items in the TCM for counting.
N/A SAT UNSAT 8. After clearing the PCM-1 monitor, the examinee exits through the Portal Monitor Examinee clears the Portal Monitor N/A SAT UNSAT 9. Examinee deactivates EAD at final exit of session Examinee deactivates his EAD and returns it to the Health Physics rack.
N/A SAT UNSAT END STOP TIME:
JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL PLANT CONDITIONS
- 1. Plant is DEFUELED and all FUEL HANDLING operations are secured. 2. Power has been lost to both SFP cooling pumps and 2K11-K5 "FUEL POOL TEMP HI" is in alarm. 3. A Site Area Emergency has been declared on Unit 2 due to a station blackout. Power has been restored to 2A3 and 2B5 from the Alternate AC Generator, AACG. 4. Service water must be aligned to the SFP due to boiling and loss of inventory through the tilt pit gate. 5. Fuel Pool low level alarm is in and SF P level is lowering.
- 6. RP coverage will NOT be available.
Initiating CUE:
The Shift Manager directs that Service water fr om loop I must be aligned to the SFP, use the Emergency RWP and identify the ma ximum allowable time before you would be required to leave the Auxiliary Building 354' elevation SFP valve gallery, excluding entry and exit times to and from the area.
JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL PLANT CONDITIONS
- 1. Plant is DEFUELED and all FUEL HANDLING operations are secured. 2. Power has been lost to both SFP cooling pumps and 2K11-K5 "FUEL POOL TEMP HI" is in alarm. 3. A Site Area Emergency has been declared on Unit 2 due to a station blackout. Power has been restored to 2A3 and 2B5 from the Alternate AC Generator, AACG. 4. Service water must be aligned to the SFP due to boiling and loss of inventory through the tilt pit gate. 5. Fuel Pool low level alarm is in and SF P level is lowering.
- 6. RP coverage will NOT be available.
Initiating CUE:
The Shift Manager directs that Service water fr om loop I must be aligned to the SFP, use the Emergency RWP and identify the ma ximum allowable time before you would be required to leave the Auxiliary Building 354' elevation SFP valve gallery, excluding entry and exit times to and from the area.
RWP for TRAINING USE ONLY RWP ANO Page 1 of 5
______________________________________________________________________________
l l l Status: Active RADIOLOGICAL WORK PERMIT Rev 0 Unit C RWP 2004-0009l l______________________________________________________________________________
l l l l SECTION I RWP DESCRIPTION l
l______________________________________________________________________________
l l l l l l START DATE: 01-jan-2004 l END DATE: 31-dec-2004 l RWP TYPE: General l l__________________________l_________________________l_________________________l l l
l DESCRIPTION: l
l l
l Emergencies l l l l SYSTEM COMPONENT BLDG LOCATION l
l l
l NA Various A1/A2 Non LHRA's l
l NA Various OSCA Non LHRA's l l NA Various A1/A2 LHRA's l l l
l JOB CONTACTS..Shift Manager ALARA CODE....C0007014 l
l JOB CODE......ROS- ALARA CAT.....Level III l
l______________________________________________________________________________l
______________________________________________________________________________
l l l SECTION II
TASK LIST l l______________________________________________________________________________
l l l l l l l l l l ESTIMATED l
l TASKl STATUS l TASK DESCRIPTION l PR-HR lPER-REMl
l_____l_________l______________________________________________l_______l_______l
l l l l l l l 1 lActive lEmergency Response in Non LHRA's l 1000.0l 5.000l l l l l l l
l 2 lActive lEmergency Response in LHRA's l 200.0l 6.000l
l_____l_________l______________________________________________l_______l_______l
l l l l l TOTALS l 1200.0l 11.000l l______________________________________________________________l_______l_______l
______________________________________________________________________________
l l l SECTION III
RWP REVIEWS AND APPROVAL l
l______________________________________________________________________________
l l l l Originator ELLISON PW 18-dec-2003 Development ELLISON PW 19-dec-2003 l
l ALARA Eval ELLISON PW 19-dec-2003 HP Supv. DORAN GA 19-dec-2003 l l Terminated ____________ ___________ Completed ____________ ___________ l l Withdrawn ____________ ___________ l
l______________________________________________________________________________l
Tue Oct 19 13:59:58 2004 working RWP 2004-0009 RWP for TRAINING USE ONLY RWP ANO Page 2 of 5
_______________________________________________________________________
l l l SECTION IV PROTECTIVE REQUIREMENTS BY TASK Rev 0 RWP 2004-0009l l______________________________________________________________________________
l l l l TASK TASK DESCRIPTION
( Task# 1 ) l l______________________________________________________________________________l l l l 1) Emergency Response in Non LHRA's l l______________________________________________________________________________
l l l l
RADIOLOGICAL CONDITIONS
( Task# 1 ) l l______________________________________________________________________________l l l l l l l l l l l (mrem/Hr) l dpm l l l l l l Component/Location l Gen Max l100cm2l l Yr/DANI# l l l
l______________________l_____l_____l______l________l____________l_______l______l
l l l l l l l l l
lUnit 1&2 Aux. Bldgs l 1 l 200 l <1K l lMonthly Pkg l l l lOutside Controlled Ac l 1 l 80 l <1K l lMonthly Pkg l l l lVarious / Aux. Bldgs l 1 l1000 l <1K l lANTICIPATED l l l
l______________________l_____l_____l______l________l____________l_______l______l
l l l Dosimetry
- Whole body TLD required, and Alarming Dosimeter. l l l l ------------------------- SPECIAL INSTRUCTIONS ------------------------- l l ALARA Actions: l l 1) Utilize low dose waiting areas whenever possible to minimize l l exposure. l l l l Monitoring: l l 1) Notify the zone coverage RP or the duty shift RP when Emergency l l Conditions exist. l
l 2) Unless otherwise directed by RP Supervision, Electronic Alarming l l Dosimeter (EAD) set points will be 800 mrem dose and 800 mrem/hr l l dose rate. l l 3) During Emergency conditions the possibility of changing l
l radiological conditions is increased. Radiological information l
l should be obtained from in plant monitors, Rads Telmetry devices in l l the field or RP personnel. l l 4) Periodically check your Electronic Alarming Dosimeter (EAD). This l
l check should be more frequent in areas where your ability to hear l
l the alarm is diminished. l
l 5) If an EAD dose alarm occurs: l l 1. Secure work. l l 2. Immediately leave Controlled Access. l
l 3. Notify RP. l
l 6) If an EAD dose rate alarm occurs: l
l 1. Secure work. l l 2. Back out of the immediate area until alarm clears. l l 3. Notify others in work crew. l
l 4. Immediately contact RP for further instructions. l
l 7) Initial/Intermittent RP coverage is required for High Radiation l
l Areas unless the individual is "Category 3 Advanced Radworker" l l qualified and has an appropriate radiation survey meter at all l l times during the entry. l
l NOTE: An EAD is not an appropriate survey meter. l l 8) Access to the overhead
>8ft. is allowed with the following l l l l --Continued on next page-- l l______________________________________________________________________________l
Tue Oct 19 13:59:58 2004 working RWP 2004-0009 RWP for TRAINING USE ONLY RWP ANO Page 3 of 5
______________________________________________________________________________
l l l SECTION IV PROTECTIVE REQUIREMENTS BY TASK Rev 0 RWP 2004-0009l l______________________________________________________________________________
l l l l TASK TASK DESCRIPTION
( Task# 1 ) l l______________________________________________________________________________l l l
l --Continued from previous page-- l l l l provisions: l
l A.) Use a ladder to climb directly below the valve to be l
l operated. l
l B.) Do not touch any interferences or components in the overhead. l l C.) Use your survey meter to obtain dose rates of all areas l l entered. l
l D.) Wear rubber gloves while operating the valve but remove them l
l prior to descending the ladder. l
l E.) Upon completion, perform a large area masslin survey of the l l ladder to determine if any cross contamination has occurred. l l l
l 9) Accessing the top of partial walls separating Radiation/High l
l Radiation areas from Locked High Radiation areas is not permitted l
l on this RWP. l l l l Work Controls: l l l l 1) Ensure the proper surveys are performed prior to removing any l
l items from the RCA. l l l l Respiratory: l l l l 1) Airborne Activity will be assessed based on process monitor's and l
l continuous air monitor activity. l l l l Anti-C's: l l l l 1) Use Anti-C's appropriate for the area to be entered. l
l l l Additional: l l l l 1) Radiological Conditions are ANTICIPATED and must be determined l
l prior to beginning work in the area. l
l______________________________________________________________________________l Tue Oct 19 13:59:58 2004 working RWP 2004-0009 RWP for TRAINING USE ONLY RWP ANO Page 4 of 5
______________________________________________________________________________
l l l SECTION IV PROTECTIVE REQUIREMENTS BY TASK Rev 0 RWP 2004-0009l l______________________________________________________________________________
l l l l TASK TASK DESCRIPTION
( Task# 2 ) l l______________________________________________________________________________l l l l 2) Emergency Response in LHRA's l l______________________________________________________________________________
l l l l
RADIOLOGICAL CONDITIONS
( Task# 2 ) l l______________________________________________________________________________l l l l l l l l l l l (mrem/Hr) l dpm l l l l l l Component/Location l Gen Max l100cm2l l Yr/DANI# l l l
l______________________l_____l_____l______l________l____________l_______l______l
l l l l l l l l l
lUnit 1/2 Aux. Bldgs. l 1 l 200 l <1K l lMonthly Pkg l l l lOutside Controlled Ac l 1 l 80 l <1K l lMonthly Pkg l l l lVarious U1/2 Aux. Bld l 1 l1000 l <1K l lANTICIPATED l l l
l______________________l_____l_____l______l________l____________l_______l______l
l l l Dosimetry
- Whole body TLD required, and Alarming Dosimeter. l l l l______________________________________________________________________________l
Tue Oct 19 13:59:58 2004 working RWP 2004-0009 RWP for TRAINING USE ONLY RWP ANO Page 5 of 5
______________________________________________________________________________
l l l SECTION IV PROTECTIVE REQUIREMENTS BY TASK Rev 0 RWP 2004-0009l l______________________________________________________________________________
l l l l TASK TASK DESCRIPTION
( Task# 2 ) l l______________________________________________________________________________l l ------------------------- SPECIAL INSTRUCTIONS ------------------------- l
l l l ALARA Actions: l l l l 1) A pre-job-brief is required for this task. l
l l
l 2) RP staff and or Shift Manager will conduct the pre-job-brief. l l l l 3) Utilize low dose waiting areas whenever possible to minimize l
l exposure. l
l l l Monitoring: l l l l 1) Contiuous RP coverage is required for this task. l
l l
l 2) Periodically check Electronic Alarming Dosimeter (EAD). This check l
l should be more frequent in areas where your ability to hear the l l alarm is deminished. If any (EAD) alarm is received secure work, l l find as low a dose rate area as possible and contact RP supervision l
l for further guidance. l
l l
l 3) Unless otherwise directed by RP Supervision, Electronic Alarming l l Dosimeter set points will be 800 mrem dose and 4000 mrem/hr dose l l rate. l l l
l 4) During Emergency conditions the possibility of changing l
l radiological conditions is increased. Radiological information l l should be obtained from in plant radiation monitors, Rads Telemetry l l devices in the field or RP personnel. l
l l l Work Controls: l l l l 1) Ensure the proper surveys are preformed prior to removing any l l items from the RCA l
l l l Respiratory: l l l l 1) Airborne Activity will be assessed based on process monitor's and l l continuous air monitor's activity. l
l l l Anti-C's: l l l l 1) Use Anti-C's appropriate for the area to be entered. l l l l Additional: l l l l 1) Radiological conditions are ANTICIPATED and must be determined l l prior to beginning work in the area. l l______________________________________________________________________________l
Tue Oct 19 13:59:59 2004 working RWP 2004-0009 JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:
SYSTEM/DUTY AREA: A4 Emergency Plan TASK: Determine Emergency Action Level JTA#: KA VALUE RO: 2.3 SRO: 4.1 KA
REFERENCE:
2.4.41 APPROVED FOR ADMINISTRATION TO:
RO: SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 1903.010 Rev 037-02-0 EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
Plant had been operating fo r 150 days at 100% power. A reactor trip occurred two hours ago. A reactor trip has occurred due to Loss of Coolant Accident estimated to be 700 gpm. Containment Spray Actuation Signal (CSAS) has actuated. Containment high range radiation monitors, 2RE8925-1 and 2RE8925-2 ar e reading 2400 R/HR. Chemists have been notified to sample the RCS.
TASK STANDARD:
Declared a Site Area Emergency (bas ed on EAL 1.4, Containment radi ation readings which indicate LOCA and >1% fuel cladding failure). Also acceptable is a review of the 1903.010 paragraph 4.10, Fission Product Barrier Failure and 4.11, Fission Product Barrier Challenge criteria and determine that two fission product barriers are challenged or failed and classi fy the event as a Site Area Emergency based on criteria 9.3,Plant conditions exist that warrant activation of the Emergency Response Facility.
TASK PERFORMANCE AIDS: OP 1903.010 Rev. 037-02-0
SIMULATOR SETUP:
N/A.
JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE
INITIATING CUE:
As Shift Manager, determine the EAL classification based on the given plant conditions.
Critical Steps: 2, 3, 4 PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. Review E-Plan procedure 1903.010 to determine classification.
Review 1903.010 index and EAL classification tabs.
N/A SAT UNSAT (C) 2. Reviewed 1903.010 attachment 6 containment radiation EAL plot to determine that containment radiation levels exceed the Site area emergency criteria.
Determined that the containment radiation reading exceeds the Site Area Emergency Criteria. N/A SAT UNSAT (C) 3. Reviewed initial conditions and determined that a LOCA inside containment was in progress.
Determined LOCA inside containment was in progress. N/A SAT UNSAT (C) 4. Reviewed EAL 1.4., Site Area Emergency based on a LOCA and > 1% failed fuel.
Or Also acceptable is a review of the 1903.010 paragraph 4.10, Fission Product Barrier Failure and 4.11, Fission Product Barrier Challenge criteria and determine that two fission product barriers are challenged or failed and classify the event as a Site Area Emergency based on criteria 9.3,Plant conditions exist that warrant activation of the Emergency
Response Facility.
Classified EAL as a Site Area Emergency (SAE) based on EAL 1.4, Containment Radiation readings which indicate LOCA and > 1% fuel cladding failure.
OR Classified EAL as a Site Area Emergency (SAE) based on EAL 9.3, Plant conditions exist that warrant activation of the Emergency Response Facility.
N/A SAT UNSAT END JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL PLANT CONDITIONS Plant had been operating fo r 150 days at 100% power. A reactor trip occurred two hours ago. A reactor trip has occurred due to Loss of Coolant Accident estimated to be 700 gpm. Containment Spray Actuation Signal (CSAS) has actuated. Containment high range radiation monitors, 2RE8925-1 and 2RE8925-2 ar e reading 2400 R/HR. Chemists have been notified to sample the RCS.
INITIATING CUE:
As Shift Manager, determine the EAL classification based on the given plant conditions.
JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL PLANT CONDITIONS Plant had been operating fo r 150 days at 100% power. A reactor trip occurred two hours ago. A reactor trip has occurred due to Loss of Coolant Accident estimated to be 700 gpm. Containment Spray Actuation Signal (CSAS) has actuated. Containment high range radiation monitors, 2RE8925-1 and 2RE8925-2 ar e reading 2400 R/HR. Chemists have been notified to sample the RCS.
INITIATING CUE:
As Shift Manager, determine the EAL classification based on the given plant conditions.
JPM- ANO-2-JPM-NRC-AOP2 PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA:
Containment Cooling Water System
TASK: Reset CIAS and establish cooling water to containment
JTA#: KA VALUE RO: 3.1 SRO: 3.2 KA
REFERENCE:
022 A4.04
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
AOP 2203.0039 Rev 03-02-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-AOP2 PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
An inadvertent CIAS has occurred.
Steps 1-10 of AOP 2203.039 have been completed.
TASK STANDARD:
CIAS has been reset and containment Chilled water has been realigned.
TASK PERFORMANCE AIDS:
Copy of AOP 2203.039 Revision 003-02-0 is available.
AOP 2203.039 Steps 1-10 have been completed.
SIMULATOR SETUP:
Inadvertent CIAS present. Containm ent parameters and RCS parameters
are above setpoints, contai nment pressure < 18.3 psia. Verify CBO to VCT
valves, 2CV-4847-2 and 2CV 4846-1 handswitc hes are in CLOSE.
JPM- ANO-2-JPM-NRC-AOP2 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Perform actions in I nadvertent CIAS, AOP 2203.039, steps 11 through 15." CRITICAL ELEMENTS (C):
1, 2, 6, 7, 8
START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 1. (Proc step 11) Reset CIAS on 2C23B.
Examiners note:
Only one channel of PPS is modeled on simulator
completely. Correctly resetting
of this channel will reset CIAS
trip paths.
Examiners Cue @ Step 11.D:
All four PPS trip path channels have been reset.
Obtained key 15 from Shift Manager.
On panel 2C23B placed key in trip path keyswitch to UNLK.
Depressed CIAS pushbutton for
trip path.
Placed trip path keyswitch to LK
and removed key.
N/A SAT UNSAT (C) 2. (Proc step 12) Reset ESF CIAS actuation on 2C40.
Examiners note:
Only one channel of ESF actuation path is modeled on
simulator completely. Correctly
resetting of this channel will
reset CIAS ESF actuation.
Examiners Cue @ Step 12.B:
2C39 ESF CIAS actuation has been reset.
Depressed CIAS lockout reset pushbutton on 2C40-7 and
observed "CIAS ON "light lit and
observed trip paths lights on
panel above 2C23 lit.
N/A SAT UNSAT 3. (Proc step1 2.c) Go to step 14.
Using procedure 2203.039, transition to step 14.
N/A SAT UNSAT 4. (Proc step 14) Open RCP Bleedoff to VCT valve, 2CV-4846-1.
On panel 2C17, Placed handswitches for RCP bleedoff to
VCT valve 2CV-4846-1 to OPEN.
Observed RED light ON and
GREEN light OFF above hand switch. N/A SAT UNSAT JPM- ANO-2-JPM-NRC-AOP2 PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 5. (Proc step 14) Open RCP Bleedoff to VCT valve, 2CV-4847-2.
On panel 2C16, Placed handswitches for RCP bleedoff to
VCT valve 2CV-4847-2 to OPEN.
Observed RED light ON and
GREEN light OFF above hand switch. N/A SAT UNSAT (C) 6. (Proc step 15.a) Open Chilled water to CNTMT valve 2CV-3851-1.
On panel 17, placed handswitches for Chilled Water to
CNTMT Isolation valve
2CV-3851-1 to OPEN.
Observed RED light ON and
GREEN light OFF above hand switch. N/A SAT UNSAT (C) 7. (Proc step 15a) Open Chilled water to CNTMT valve 2CV-3852-1.
On panel 17, placed handswitches for Chilled Water to
CNTMT Isolation valve
2CV-3852-1 to OPEN.
Observed RED light ON and
GREEN light OFF above hand switch. N/A SAT UNSAT (C) 8. (Proc step 15a) Open Chilled water to CNTMT valve 2CV-3850-2.
On panel 16, placed handswitches for Chilled Water to
CNTMT Isolation valve
2CV-3850-2 to OPEN.
Observed RED light ON and
GREEN light OFF above hand switch. N/A SAT UNSAT 9. (Proc step 15b) Verify Main Chiller (2VCH1A) running.
Examiner's note: The red light above hand switch for 2VCH-1A indicates
the chiller is running.
Examiner's note:
The red light label for 2HS-3810 for 2VCH-1A indicates
the 2A1 breaker is closed.
On panel 22, verified hand switch for 2VCH1A is in normal after
start (RED flagged).
Observed RED light ON and GREEN light OFF above hand switch for 2VCH-1A.
Observed RED light ON and GREEN light OFF above label for
Observed all chilled water alarms are clear on annunciator 2K13 (Lights slow flashing or clear).
N/A SAT UNSAT JPM- ANO-2-JPM-NRC-AOP2 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)
EXAMINER's NOTE:
JPM standard does not require completi on of steps past procedure step 15.
END STOP TIME:
JPM- ANO-2-JPM-NRC-AOP2 PAGE 6 OF 7 JOB PERFORMANCE MEASURE
EXAMINER'S COPY
JPM INITIAL TASK CONDITIONS:
An inadvertent CIAS has occurred. Steps 1-10 of AOP 2203.039 have been
completed.
INITIATING CUE:
The SM/CRS directs, "Perform actions in Inadvertent CIAS, AOP 2203.039, steps 11 through 15."
JPM- ANO-2-JPM-NRC-AOP2 PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEE'S COPY
JPM INITIAL TASK CONDITIONS:
An inadvertent CIAS has occurred. Steps 1-10 of AOP 2203.039 have been
completed.
INITIATING CUE:
The SM/CRS directs, "Perform actions in Inadvertent CIAS, AOP 2203.039, steps 11 through 15."
JPM- ANO-2-JPM-NRC-CVCS010 PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA:
Chemical and Volume Control System
TASK: Perform Emergency Boration (Alternate Success Path)
JTA#: KA VALUE RO: 3.9 SRO: 3.7 KA
REFERENCE:
004 A4.07
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
12 Minutes REFERENCE(S):
OP 2203.032 Rev. 008-06-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-RO-CVCS010 PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" porti on of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
Mode 3. 'B' CCP tagged out for low pressure operat ions. 'C' CCP tagged out for gear box repair.
TRM 3.1.2.4 entered for only 1 CCP availabl e with 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> remaining on the action.
A Shutdown Margin is calculated following a reactor trip.
Shutdown Margin is found to be less than required.
TASK STANDARD:
Greater than or equal to 40 gallons per minute boric acid solution being injected into the RCS using HPSI pump and HPSI injection MOV's.
This is an alternate success path JPM>
TASK PERFORMANCE AIDS:
AOP 2203.032 Steps 2 through 16. OP 4104.039 secti on 9, Starting any HPSI pump on recirc.
SIMULATOR SETUP:
A mode 3 IC will be set up for this JPM. RCS cooldow n in progress, PZR pressure ~ 1200psia, RCS temp
~480°F. 'A' CCP running. 'B' CCP t agged out for low pressure operations. 'C' CCP tagged out for gear box repair. TRM 3.1.2.4 entered for only 1 CCP ava ilable with 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> remaining on the action.
Set T1=2CV-4873-1a < 75% (this will trigger T1 when the VCT outlet gets to 75% open.)
T1 = 'A' CCP plunger failure (flow out of pump ~ 30gpm).
JPM- ANO-2-JPM-RO-CVCS010 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Initiate Emergency Boration using BAMT gravity feed to Charging Pump suction beginning with AOP 2203.032, Step 2."
CRITICAL ELEMENTS (C): 2, 5, 9, 10, 14, 15
START TIME:
PERFORMANCE CHECKLIST STANDARD (Circle One) 1. (Proc Step 2) Verify at least one charging Pump (CCP) running with flow
greater than 40 GPM.
On panel 2C09, verified CCP(s) running.
Observed red light ON; green light
OFF above at least one of the
following handswitch(es):
2HS-4832-1, "A" CCP
2HS-4852-1, "C" CCP (red)
2HS-4853-2, "C" CCP (green)
2HS-4842-2, "B" CCP
Observed flow greater than 40
gpm on Charging Header Flow
(2FIS-4863).
N/A SAT UNSAT (C) 2. (Proc Step 3A1) Align boric acid supply to CCP suction.
On panel 2C09, opened BAMT gravity feed valves 2CV-4920-1 and/or 2CV-4921-1
Observed red light ON and green
light OFF above handswitch(es):
2HS-4920-1 for 2CV-4920-1 2HS-4921-1 for 2CV-4921-1 N/A SAT UNSAT 3. (Proc Step 4) Close volume control tank (VCT) outlet valve (2CV-4873-
1).
On panel 2C09, observed that 2CV-4873-1 closed.
Observed green light ON; red light
OFF above VCT Outlet valve
handswitch (2HS-4873-1).
N/A SAT UNSAT 4. (Proc Step 5) Check Reactor Makeup Water Flow Control valve (2CV-4927)
or 2CV 4941-2 closed.
On panel 2C09, verified 2CV-4927 or 2CV-4941-2 closed.
Observed green light ON; red light
OFF above Reactor Makeup Water
Flow Controller (2FIC-4927) or
above 2CV-4941-2 handswitch.
N/A SAT UNSAT (C) 5. (Proc Step 6) Check charging header flow.
On panel 2C09 (upright portion), observed flow about 30 gpm on
Charging Header Flow indicator
(2FIS-4863).
N/A SAT UNSAT JPM- ANO-2-JPM-RO-CVCS010 PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One) 6. (Proc Step 2) GO to step 2 and verify TCB's open and then transition to
step 8. On panel 2C14, verifies that the TCB's are open by observing the
green lights ON and red lights
OFF. N/A SAT UNSAT 7. (Proc Step 8) Check RCS pressure less than 1265 psia.
On panel 2C04, SPDS, PMS or PDS verified that PZR pressure is
less than 1265 psia.
N/A SAT UNSAT 8. (Proc Step 9A) Verify RWT level greater than 7.5%. On panel 2C16 or 2C17, verified RWT level greater than 7.5%.
N/A SAT UNSAT (C) 9. (Proc Step 9B) Verify 2CV-5631-2 is OPEN.
EXAMINER'S CUE: When asked as CRS, in step 9, which HPSI pump to start, state that 'B' HPSI pump is
to be used. If not asked and goes to 2C17 to verify RWT outlet valve open and start
'A' HPSI pump, state that 'B'
HPSI pump is to be started.
On panel 2C16 verified RWT outlet valve 2CV-5631-2 is OPEN.
N/A SAT UNSAT NOTE: If Examinee in procedure step 9C, goes to use OP2104.039 section 9.0 then gi ve the following cue.
EXAMINER's CUE: CRS directs to start 'B' HPSI pump first and then verify steps in appropriate section in OP 2104.039. (C) 10. (Proc Step 9C) Start 2P89B, 'B' HPSI Pump. On panel 2C16 rotated handswitch for 2P89B to start position.
Observed Red light ON and Green light OFF.
N/A SAT UNSAT 11. (Proc Step 10) Verify SDC secured. On panel 2C16 and 2C17 verified LPSI (SDC) pumps secured.
N/A SAT UNSAT 12. (Proc Step 11) Check RCS temperature greater than 450°F.
On panel 2C04, SPDS, PMS or PDS verified RCS temperature
greater than 450°F.
N/A SAT UNSAT JPM- ANO-2-JPM-RO-CVCS010 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One) 13. (Proc step 12) Commence RCS cooldown to allow a makeup rate of 40
GPM. Note: applicant will not perform this procedure step.
EXAMINER'S CUE: The RCS cooldown will be controlled by another operator and the rate is sufficient to allow 40
GPM makeup rate.
Verify conditions will allow for a makeup rate of 40 gpm. (Step 12)
N/A SAT UNSAT (C) 14. (Proc step 13A) Use one HPSI train B injection MOV to maintain PZR level. (Note these are contingency action steps.)
Throttled open ONE of the following HPSI injection MOV:
2CV5056-2
Observed Red light ON and Green light ON above handswitch.
N/A SAT UNSAT (C) 15. (Proc step 13B) Verified HPSI to RCS flow greater than 40 GPM using SPDS computer.
Adjust valve position to maintain greater than 40 GPM HPSI flow
using indications on SPDS
computer.
N/A SAT UNSAT Procedure steps 14, 15 and 16 are not required to be completed.
END STOP TIME:
JPM- ANO-2-JPM-RO-CVCS010 PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINER's COPY
JPM INITIAL TASK CONDITIONS:
Mode 3. 'B' CCP tagged out for low pressure operations. 'C' CCP tagged out for gear box repair. TRM 3.1.2.4 entered for only 1 CCP available with 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> remaining on the action.
A Shutdown Margin is calculated following a reactor trip. Shutdown Margin is found to be less than required.
INITIATING CUE:
The SM/CRS directs, "Initiate Emergency Boration using BAMT gravity feed to
Charging Pump suction beginning with AOP 2203.032, Step 2."
JPM- ANO-2-JPM-RO-CVCS010 PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEE's COPY
JPM INITIAL TASK CONDITIONS:
Mode 3. 'B' CCP tagged out for low pressure operations. 'C' CCP tagged out for gear box repair. TRM 3.1.2.4 entered for only 1 CCP available with 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> remaining on the action.
A Shutdown Margin is calculated following a reactor trip. Shutdown Margin is found to be less than required.
INITIATING CUE:
The SM/CRS directs, "Initiate Emergency Boration using BAMT gravity feed to
Charging Pump suction beginning with AOP 2203.032, Step 2."
JPM- ANO-2-JPM-NRC-PZR02 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 010 DATE:
SYSTEM/DUTY AREA:
Pressurizer Pressure Control System
TASK: Equalize RCS and PZR Boron (ALTERNATE SUCCESS PATH)
JTA#: ANO2-RO-PZR-NORM-3
REFERENCE:
010 A4.01
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2103.005 Rev. 024-00-0 and AOP 2203.028 Rev 06-00-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-PZR02 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist -
System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
100% Power Operation. A power escalation has been completed.
Chemistry reports that RCS boron is 500 PPM and PZR boron is 575 PPM.
TASK STANDARD:
Spray Valve (2CV-4651) is isolated.
THIS IS AN ALTERNATE SUCCESS PATH JPM.
TASK PERFORMANCE AIDS:
OP 2103.005 section 7.0 and AOP 2203.028.
SIMULATOR SETUP:
Run CAE FILE JPM03. This will open 'A' spray valve 100% and trip the breaker when
the valve indicates intermediate position.
The following malfunctions/overrides need to be triggered (cae file JPM03 w ill do all of them):
Set T5 file to 'GH4R651A' this will tri gger T5 when 2CV-4651 red light is energized.
T5 '2CV-4651_a' value = 1.0
T5 '2HS-4651-3' false (green light)
T5 '2HS-4651-5' false (red light)
JPM- ANO-2-JPM-NRC-PZR02 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
EXAMINER's NOTE: Do not hand out procedure until asked.
The SM/CRS directs: "Equalize RCS and PZR boron c oncentration using RCP 'A' spray valve, 2CV-4651." CRITICAL ELEMENTS (C):
2, 3, 4, 6 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 7.1.1) Verify spray valve, 2CV-4651, isolation valves 2CV-4655
AND 2CV-4656 are OPEN.
On panel 2C04 verified red lights ON, green lights OFF for
N/A SAT UNSAT (C) 2. (Proc step 7.1.2) Place RCP 'A' spray valve MAN/AUTO select switch
(2HS-4651B) to MANUAL.
On panel 2C04, rotated 2HS-4651B in the CCW direction
to MANUAL.
N/A SAT UNSAT (C) 3. (Proc step 7.1.3) Energize all available Backup Heaters.
On panel 2C04 verified the following hand switches to ON:
Place 2HS-4643 to ON
Place 2HS-4644 to ON
Place 2HS-4645 to ON
Place 2HS-4646 to ON AND Observed the red light ON and green light OFF above each of
the above backup heater hand switches.
N/A SAT UNSAT EXAMINER'S NOTE:
When 2CV-4651 is taken to open, the valv e will open 100% and then trip the breaker. (C) 4. (Proc step 7.1.4) Partially open 2CV-4651 to stabilize pressure within +/- 10
psia of desired setpoint.
When RCS pressure starts rising, then on panel 2C04, throttled
open 2CV-4651 by taking the
hand switch for 2CV-4651 to the
open position.
N/A SAT UNSAT EXAMINER'S NOTE:
The following step may be completed after enteri ng the AOP 2203.028, but entering the AOP is NOT critical for successful completion of this JPM.
JPM- ANO-2-JPM-NRC-PZR02 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)
- 5. (AOP Proc step 1) Recognizes that 2CV4651 is deenergized open.
Attempts to close 2CV4651
may be made, but is not
necessary.
On panel 2C04, observed that light position indications above
2CV-4651 are out and PZR
pressure is lowering.
N/A SAT UNSAT (C) 6. (AOP Proc step 1.B.3) Close PZR Spray Block Valves.
On panel 2C04, placed hand-switch for 2CV-4655 and 2CV-
4656 to "CLOSE".
Observed green lights ON, red
lights OFF for 2CV-4655 and
N/A SAT UNSAT END STOP TIME:
JPM- ANO-2-JPM-NRC-PZR02 PAGE 5 OF 6 JOB PERFORMANCE MEASURE
EXAMINER'S COPY NOTE: Do not hand out procedure until Examinee asks for it.
JPM INITIAL TASK CONDITIONS:
100% Power Operation. A power escalation has been completed. Chemistry reports that RCS boron is 500 PPM and PZR boron is 575 PPM.
INITIATING CUE:
The SM/CRS directs: "Equalize RCS and PZR boron concentration using RCP 'A' spray valve, 2CV-4651."
JPM- ANO-2-JPM-NRC-PZR02 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEE'S COPY
JPM INITIAL TASK CONDITIONS:
100% Power Operation. A power escalation has been completed. Chemistry reports that RCS boron is 500 PPM and PZR boron is 575 PPM.
INITIATING CUE:
The SM/CRS directs: "Equalize RCS and PZR boron concentration using RCP 'A' spray valve, 2CV-4651."
JPM- ANO-2-JPM-NRC-SIT05 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 003 DATE:
SYSTEM/DUTY AREA:
Safety Injection System
TASK: Adjust SIT Pressure (Incr ease) ALTERNATE SUCCESS PATH JTA#: ANO2-RO-ECCS-NORM-10
REFERENCE:
006 A1.13
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
8 Minutes REFERENCE(S): OP 2104.001
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-SIT05 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist -
System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
Safety Injection Tank (2T2A) level is between 80.1% and 87.9%.
Pressure is approximately 606 psig.
TASK STANDARD:
Safety Injection Tank (2T2A) pressure raised to 615 psig. Nitrogen Isolated to 'A' SIT.
2T2A pressure is < 700 psig. THIS IS AN ALTERNATE SUCCESS PATH JPM.
TASK PERFORMANCE AIDS:
OP 2104.001 Section 11.0
SIMULATOR SETUP:
Ensure 'A' SIT pressure is ~606 psig and 'A
' SIT level is ~ 84%. Run CAE file JPM05.
CAE file JPM05 will do the following:
Set trigger T5=PD4R5005 (trigger when 2SV-5005 red light energized)
Set 2SV5005 to stick open (Hand switch for the valve faulty) (IMF CV5005_(5 0) 1.0 0 0.0)
JPM- ANO-2-JPM-NRC-SIT05 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Raise Safety Injection Tank (2 T2A) pressure to 615 psig using OP 2104.001 Section 11.0." CRITICAL ELEMENTS (C):
2, 3, 6 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 1) Verify nitrogen supply is aligned.
Examiner's Cue:
Unit-1 (or Unit-2 operator)
reports high pressure N 2 is aligned. Using the gaitronics, plant telephone system, or radio;
contacted Unit-1 OR contacted Unit-2 operator.
Requested alignment of high
pressure N
(2CV-6207-2).
On panel 2C16, placed handswitch for 2CV-6207-2 to
OPEN.
Observed red light ON above
handswitch.
N/A SAT UNSAT EXAMINER'S NOTE:
2SV-5005A and B are both operated by handswitch for 2SV-5005. (C) 3. (Proc step 3) Open SIT N 2 Supply valves (2SV-5005A/B).
On panel 2C33, placed handswitch 2SV-5005 for
2SV-5005A/B to OPEN.
Observed red light ON; green
light OFF above handswitch.
N/A SAT UNSAT 4. (Proc step 5) Verify SIT (2T2A) at desired pressure.
Verified SIT (2T2A) pressure between 615 and 620 psig.
Observed SIT (2T2A) pressure
on any of the following:
2PIS-5012 (2C17)
2PI-5013 (2C17)
2PIS-5011 (2C16)
OR:
Observed SIT (2T2A) pressure
points/trend for 2T2A pressure.
N/A SAT UNSAT JPM- ANO-2-JPM-NRC-SIT05 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 5. (Proc step 5) Close SIT N 2 Supply valves (2SV-5005A/B).
On panel 2C33, placed hand switch 2SV-5005 for
2SV-5005A/B to CLOSE.
Observed green light OFF; red
light ON above handswitch.
Reports that valve hand switch will not close the valve and SIT
pressure is continuing to
increase.
N/A SAT UNSAT EXAMINER'S NOTE:
SIT high and high-high pressure alarms may come in. These will not influence the passing of the following step. If the operator does not isolate N 2 from 2C16 and pressurizes the SIT to 700psig, the following step should be considered UNSAT. (C) 6. (Proc step 7) Close Supply Header to Containment Isolation valve
(2CV-6207-2).
On panel 2C16, placed handswitch for 2CV-6207-2 to
CLOSE.
Observed green light ON above
handswitch.
Isolated N 2 from 2C16 with SIT pressure less than 700psig, N/A SAT UNSAT 7. (Proc step 8) Isolate the nitrogen supply.
Examiner's Cue:
Unit-1 (or Unit-2 operator)
reports high pressure N 2 is isolated.
Using the gaitronics, plant telephone system, or radio;
contacted Unit-1 OR contacted Unit-2 operator.
Requested isolation of high
pressure N
- 2. N/A SAT UNSAT END STOP TIME:
JPM- ANO-2-JPM-NRC-SIT05 PAGE 5 OF 6 JOB PERFORMANCE MEASURE
EXAMINER'S COPY
JPM INITIAL TASK CONDITIONS:
Safety Injection Tank (2T2A) level is betw een 80.1% and 87.9%. Pressure is approximately 606 psig.
INITIATING CUE:
The SM/CRS directs, "RAISE Safety Injection Tank (2T2A) pressure to 615 psig using OP 2104.001 Section 11.0."
JPM- ANO-2-JPM-NRC-SIT05 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEE'S COPY
JPM INITIAL TASK CONDITIONS:
Safety Injection Tank (2T2A) level is betw een 80.1% and 87.9%. Pressure is approximately 606 psig.
INITIATING CUE:
The SM/CRS directs, "RAISE Safety Injection Tank (2T2A) pressure to 615 psig using OP 2104.001 Section 11.0."
JPM- ANO-2-JPM-NRC-EOP03 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA:
Emergency Operating Procedures
TASK: Verify Natural Circulation Condi tions exist (ALTERNATE SUCCESS PATH)
JTA#:
REFERENCE:
002 A4.02
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
10 Minutes REFERENCE(S): EOP 2202.006 Rev. 006-01-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
JPM- ANO-2-JPM-NRC-EOP03 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist -
System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
A Loss of Feedwater is in progress. EOP 2202.006 has been
entered and steps through step 25 have been completed.
Feed to SG's has been established via 'B' EFW.
TASK STANDARD:
Take required actions to restore Natu ral Circulation conditions per Loss of Feedwater procedure.
THIS IS AN ALTERNATE SUCCESS PATH JPM.
TASK PERFORMANCE AIDS:
EOP 2202.006 Step 26.
SIMULATOR SETUP:
Loss of feedwater in progress. SDBC S is in auto (setpoint ~ 1000 psia).
Ensure that actions completed in EOP 2202.006 up to step 26 have been completed. RCS Tc < 500°F.
Ensure MTS on SPDS is less than 30°. All other steps in 26 are satisfied. PZR level ~ 40%.
All Backup Heater hand switches are in OFF. Both banks of proportional heaters have NOT been reset from
PZR level heater cutout. Ensure SG levels are gr eater than 25% and levels are slowly restoring.
JPM- ANO-2-JPM-NRC-EOP03 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Verify Natu ral Circulation Conditions are met using EOP 2202.006, Loss of Feedwater Step 26."
CRITICAL ELEMENTS (C):
3, 5 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 26) Verify Loop T is Less than 50°F. Using SPDS 'SFD' Screen, PMS, PDS or 2C04 indications, determine Loop T to be less than 50°F.
N/A SAT UNSAT 2. (Proc step 26) Verify RCS loop T H and T C constant or lowering.
Using SPDS 'SFD' Screen, PMS, PDS or 2C04 indications, determine that RCS loop T H and T C are constant.
N/A SAT UNSAT (C) 3. (Proc step 26) Verify RCS MTS 30°F or greater.
Using SPDS 'SFD' Screen, PMS, PDS or 2C04 indications, determine that RCS MTS is less
than 30°F.
N/A SAT UNSAT 4. (Proc step 26) Contingency column step 26.A, verify SG levels being
maintained 10% to 90%.
Using SPDS 'SFD' Screen, PMS, PDS or 2C04 indications, determine that Steam Generator
levels are above 10% and less
than 90%.
N/A SAT UNSAT If examinee asks for direction, then provide the following cue: EXAMINER's CUE: CRS asks why are we not meeting the >30°F MTS requirement? (C) 5. (Proc step 26.B) Contingency column step 26.B, verify RCS pressure within limits
of Attachment 1, P-T Limits.
Examiner's note: Critical element is that examinee
recognizes that PZR pressure
is LOW due to all heaters de-
energized and this is causing
MTS problems. The number
of heaters re-energized is discretionary. Candidate may consider a plant cooldown after raising
PZR pressure. Refer to Attachment 1, P-T Limits and verify that MTS is less than
30°F.
Take PZR Backup heaters out of OFF. Verify that red light ON
above hand switch(es).
Take Proportional heaters hand switches to ON. Verify that Red
light is ON above associated
hand switch.
Verify P-T limits of Attachment 1 are restored.
N/A SAT UNSAT JPM- ANO-2-JPM-NRC-EOP03 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 6. (Proc step 26) Verify T between T H and CETs less than 10°F.
Using SPDS 'SFD' Screen, PMS, PDS or 2C04 indications, determine that T between T H and CETs is less than 10°F.
N/A SAT UNSAT END STOP TIME:
JPM- ANO-2-JPM-NRC-EOP03 PAGE 5 OF 6 JOB PERFORMANCE MEASURE
EXAMINER'S COPY
JPM INITIAL TASK CONDITIONS:
A Loss of Feedwater is in progress. EO P 2202.006 has been entered and steps through step 25 have been completed. Feed to SG's has been established via 'B' EFW.
INITIATING CUE:
The SM/CRS directs, "Verify Natural Circu lation Conditions are met using EOP 2202.006, Loss of Feedwater Step 26."
JPM- ANO-2-JPM-NRC-EOP03 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEE'S COPY
JPM INITIAL TASK CONDITIONS:
A Loss of Feedwater is in progress. EO P 2202.006 has been entered and steps through step 25 have been completed. Feed to SG's has been established via 'B' EFW.
INITIATING CUE:
The SM/CRS directs, "Verify Natural Circu lation Conditions are met using EOP 2202.006, Loss of Feedwater Step 26."
ANO-2-JPM-NRC-ELECXT PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE: SYSTEM/DUTY AREA:
A. C. Electrical Distribution TASK: Perform Synchronized Cross Connect of 480 VAC load-centers 2B1 and 2B2 JTA#: ANO2-RO-480VAC-NORM-15 KA VALUE RO: 3.3 SRO: 3.1 KA
REFERENCE:
062 A4.01 APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
10 Minutes REFERENCE(S):
OP 2107.001 Revision 049-00-0 EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAI NST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLIC ABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
ANO-2-JPM-NRC-ELECXT PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL R EVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed
on 2B2 transformer. Plant is in mode 5.
TASK STANDARD:
Cross connect 480VAC non-vital busses 2B1 and 2B2 with 2B1 supplying and 2B2 supply breakers
open. Maintain 2B1 amperage less than 130 amps.
TASK PERFORMANCE AIDS:
OP 2107.001 Section 12.0.
SIMULATOR SETUP: Any power level or mode.
All Non-Vital 4160VAC and 480VAC Busses energized.
Summed 2B1 and 2B2 bus currents are greater than 130 amps (REMOTE malfunctions 480CURR2B1 And 480CURR2B2).
ANO-2-JPM-NRC-ELECXT PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0." CRITICAL ELEMENTS (C): 2, 3, 4, 6, 7
PERFORMANCE CHECKLIST STANDARDS (Circle One)
Examiner's note:
If the initial plant conditions are in Mode 3, 4 or 5, then the first step is N/A.
- 1. (Proc step 1) Check that Operations Manager approval obtained.
EXAMINER'S CUE:
"The Operations Manager has given permission to perform
Cross Connect of 2B1 and
2B2." Ask if Operations Manager has given approval to cross connect
2B1 and 2B2 at power.
N/A SAT UNSAT Examiner's note: The following two steps may be completed after cross-connecting the busses. The resolution on the meters is low at the low end. (C) 2. (Proc step 2) Determine combined load of 2B1 an 2B2.
On Panel 2C10, summed the current reading of 2B1 and 2B2.
Observed that the summed load
is greater than 130 amps.
N/A SAT UNSAT (C) 3. (Proc step 2) Reduce loads on 2B1 and 2B2 so that combined loading is less
than 130 amps when cross
connected.
EXAMINERS CUE:
"AO has been directed to secure non-essential loads
on 2B1 and 2B2 to reduce
loading on 2B1 and 2B2 to
less than 130 amps."
EXAMINERS NOTE:
Direct operator in simulator instructor's station to reduce
loading on 2B1 and 2B2 so
that loading is less than 130 amps (use REMOTE malfunctions 480CURR2B1
and 480CURR2B2).
Direct the AO or inform CRS of need to reduce non-essential
loads on 2B1 and 2B2 so that
combined loading is less than
130 amps.
N/A SAT UNSAT ANO-2-JPM-NRC-ELECXT PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 4. (Proc step 4) Synchroscope switch inserted in 2B1/2B2 cross-tie slot and
placed in ON.
On Panel 2C10, Placed Synchroscope switch into
2B1/2B2 cross-tie slot and
rotated clockwise to the ON
position.
N/A SAT UNSAT 5. (Proc step 5) Observed that the Synchroscope is at the 12
o'clock position.
On Panel 2C10, Observed that the Synchroscope is at the 12
o'clock position with the
Synchroscope switch in the ON
position.
N/A SAT UNSAT (C) 6. (Proc step 6) Close the 2B1/2B2 Cross Tie breaker.
On panel 2C10, rotate the Cross Tie handswitch for 2B1/2B2 clockwise.
Observed that the Green light
turns OFF and the Red light turns
ON above the Cross Tie
handswitch.
N/A SAT UNSAT (C) 7. (Proc step 7) Open normal supply breaker on 2B2, 480VAC bus.
AND Open Transformer feeder
breaker from 2A2 to 2B2.
On Panel 2C10, rotate the normal feeder supply breaker on
2B2 counter clockwise to the
open position. (2B212)
Observed that the RED light went OFF and the GREEN light went
ON.
On Panel 2C10, rotate the
transformer feeder breaker on
2A2 to 2B2 counter clockwise to
the open position. (2A202)
Observed that the RED light went OFF and the GREEN light went
ON. N/A SAT UNSAT 8. (Proc step 8) Verify that the amperage indicated on 2B1 is less than
130 amps.
On panel 2C10, observe that the current is less than 130 amps on
2B1.
N/A SAT UNSAT
- 9. (Proc step 9) Turn sync switch to OFF. On Panel 2C10, turn sync switch counter clockwise to the OFF
position.
N/A SAT UNSAT Examiner's Note Step 12.10 in procedure is not applicable for this JPM as both busses remained energized and the loads removed to reduce amperage on 2B1 will remain deenergized.
ANO-2-JPM-NRC-ELECXT PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)
- 10. (Proc step 11) Notified AO to monitor 2B1 transformer during cross
connected operation and
maintain temperature less than
220°C.
EXAMINER'S CUE:
"AO has been notified to monitor 2B1 transformer and notify the control room if
temperature exceeds 220°C
during cross connected
operations."
Notify AO to monitor 2B1 transformer during cross
connected operation and
maintain temperature less than
220°C. N/A SAT UNSAT END ANO-2-JPM-NRC-ELECXT PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINER'S COPY
JPM INITIAL TASK CONDITIONS:
Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer. Plant is in mode 5.
INITIATING CUE:
The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."
ANO-2-JPM-NRC-ELECXT PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEE'S COPY
JPM INITIAL TASK CONDITIONS:
Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer. Plant is in mode 5.
INITIATING CUE:
The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."
ANO-2-JPM-NRC-BMSRM PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:
SYSTEM/DUTY AREA:
Process Radiation Monitoring System
TASK: Perform BMS Liquid Discharge Radiation Monitor Functional Check
JTA#: ANO2WCOLRWBMSNORM21
REFERENCE:
068 A3.02
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
Simulate SIMULATOR:
LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
10 Minutes REFERENCE(S):
2104.014 Rev 034-00-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
ANO-2-JPM-NRC-BMSRM PAGE 2 OF 8 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
2T21A Liquid Radwaste Release Permit, 2104.014 Supplem ent 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112. Use 2CV2330A to perform release.
TASK STANDARD:
Functional Test has been completed on 2RITS-2330.
TASK PERFORMANCE AIDS:
2104.014 Supplement 1
EXAMINER'S NOTE:
JPM-ANO-2-JPM-NRC-EOP02 Page 1 of 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:
SYSTEM/DUTY AREA: Abnormal/Emergency Operations
TASK: Restore SDC Flow following an instrument failure - inadvertent Auto-Closure Initiation (ACI)
JTA#: ANO2-RO-EOPAOP-OFFNORM
REFERENCE:
016 A2.01
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
SIMULATOR:
Perform LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
AOP 2203.029
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
JPM-ANO-2-JPM-NRC-EOP02 Page 2 of 7 JOB PERFORMANCE MEASURE
THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
AOP 2203.029 has been entered due to 2PI-4623-2 failing "High". SDC pump secured, fuse for 2PS-4623-2 removed, and Loss of SDC AOP, 2203.029, has been completed up to contingency step 13.C.
TASK STANDARD: Shutdown Cooling Flow has been restored per Loss of SDC AOP, 2203.029.
TASK PERFORMANCE AIDS: Loss of SDC AOP, 2203.029
SIMULATOR SETUP:
Mode 5, SDC aligned for the "A" LPSI Pu mp through the "A" SDC Heat Exchanger.
2P-60 A & B secured, All LPSI Injection MOVs are OPEN, and 2CV-5086-2 is CLOSED. ACI actuation is clear due to de-energizing 2PS-4623-2 by fuse removal.
JPM-ANO-2-JPM-NRC-EOP02 Page 3 of 7 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "The fuse has been removed for failed RCS pressure instrument 2PI-4623-2; Restore Shutdown Cooling Flow using AOP 2203.029 beginning with contingency step 13.C."
CRITICAL ELEMENTS (C): 2, 6, 9,10
START TIME: PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 7.13.C) Verify SDC RCS isolation valves open.
On panels 2C16 and 2C17, checked indications for:
Observed 2CV-5086-2 closed by green light ON, red light OFF above hand switch.
N/A SAT UNSAT (C) 2. (Proc step 7.13.C) Determine that 2CV-5086-2 is shut due to the Auto-Closure
Initiation (ACI) and Open 2CV-
5086-2.
On panel 2C16, placed hand switch for 2CV-5086-2 to "OPEN".
Observed red light ON; green light OFF above hand switch.
N/A SAT UNSAT 3. (Proc step 7.14) Verify RAS has not actuated.
On panel 2C03, verified Alarms cleared on Annunciator panels 2K04 and 2K07 or verified red lights ON at 2C03 above the
RAS placard.
N/A SAT UNSAT 4. (Proc step 7.15) Verify RCS indicators functioning properly using
OP 2103.011.
EXAMINER's CUE: CRS
reports that OP 2103.011 attachment 'M', RCS level transmitter and tygon tube alignment has been completed and all RCS level
indicators are functioning properly.
Requests that CRS verify OP 2103.011 Attachment 'M' is
complete.
N/A SAT UNSAT JPM-ANO-2-JPM-NRC-EOP02 Page 4 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) 5. (Proc step 7.16) Check SDC pump running.
On 2C17, determined That no SDC pumps are running.
Observed 2C-16 and 2C-17 that 2P-60 A & B were secured.
Observed green light ON; red light OFF above hand switches.
N/A SAT UNSAT (C) 6. (Proc step 7.16.A) Close ALL LPSI Injection MOVs.
On 2C16 & 17, placed hand switches for Safety Injection MOVs to "CLOSE".
Observed green light ON; red light OFF above Hand switch for all valves.
N/A SAT UNSAT 7. (Proc step 7.16.B) Partially open ONE LPSI Injection.
On 2C-16 or 17, held 1 LPSI Injection MOV hand switch in
the open direction for about 2
seconds.
Observed green and red light ON above associated hand switch. N/A SAT UNSAT 8. (Proc step 7.16.C) Verify RCS level of 40% in PZR is adequate; refer to Attachment A, RCS Level.
(Verifies that PZR level is well above the required level of 24 inches above the bottom of the hot leg (40% PZR is ~
286" above the bottom of the
hot leg.)
Referred to Attachment "A" and verified RCS Level adequate for SDC, shutdown cooling (Low Pressure Safety
Injection), Pump restart.
N/A SAT UNSAT JPM-ANO-2-JPM-NRC-EOP02 Page 5 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)
NOTE: If 2CV-5091 is not in Automatic, the candidate may have to transverse from 2C-16 & 17 back to 2C-04 multiple times to control flow. 2CV-5091 should be monitored to ensure that it has control of flow when placed in automatic.
(C) 9. (Proc step 7.16.D) Start SDC pump, refer to 2104.004, Shutdown Cooling System.
On 2C17 placed hand switch for 2P-60A to "START".
Observed red light ON; green light OFF above hand switch.
N/A SAT UNSAT (C) 10. (Proc step 7.16.E) Raise SDC flow to greater than 2400 gpm by opening
On 2C-16 & 17 placed hand-switches for Safety Injection MOVs to "OPEN) as necessary to achieve > 2400 gpm flow.
2FIC-5091 indicates > 2400
gpm. N/A SAT UNSAT Examiner's note/CUE: Inform candidate that the CRS and CBOR will control RCS cool down.
END STOP TIME:
JPM-ANO-2-JPM-NRC-EOP02 Page 6 of 7 JOB PERFORMANCE MEASURE EXAMINER'S COPY JPM INITIAL TASK CONDITIONS:
Loss of Shutdown Cooling AOP, 2203.029, h as been entered due to 2PS-4623-2 failing "High". The resulting ACI caused 2CV-5086-2 to close. The "A" SDC pump was secured and AOP completed up to contingency step 13.C.
INITIATING CUE:
The SM/CRS directs, "The fuse has been removed for failed RCS pressure instrument 2PI-4623-2; Restore Shutdown Cooling Flow using AOP 2203.029 beginning with contingency step 13.C."
JPM-ANO-2-JPM-NRC-EOP02 Page 7 of 7 JOB PERFORMANCE MEASURE EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:
Loss of Shutdown Cooling AOP, 2203.029, has been entered due to 2PS-4623-2 failing "High". The resulting ACI caused 2CV-5086-2 to close. The "A" SDC pump was secured and AOP completed up to contingency step 13.C.
INITIATING CUE:
The SM/CRS directs, "The fuse has been removed for failed RCS pressure instrument 2PI-4623-2; Restore Shutdown Cooling Flow using AOP 2203.029 beginning with contingency step 13.C."
ANO-2-JPM-NRC-BMSRM PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:
SYSTEM/DUTY AREA:
Process Radiation Monitoring System
TASK: Perform BMS Liquid Discharge Radiation Monitor Functional Check
JTA#: ANO2WCOLRWBMSNORM21
REFERENCE:
068 A3.02
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
X OUTSIDE CR:
BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
Simulate SIMULATOR:
LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
10 Minutes REFERENCE(S):
2104.014 Rev 034-00-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
ANO-2-JPM-NRC-BMSRM PAGE 2 OF 8 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
2T21A Liquid Radwaste Release Permit, 2104.014 Supplem ent 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112. Use 2CV2330A to perform release.
TASK STANDARD:
Functional Test has been completed on 2RITS-2330.
TASK PERFORMANCE AIDS:
2104.014 Supplement 1
EXAMINER'S NOTE:
ANO-2-JPM-NRC-BMSRM PAGE 3 OF 8 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Perform the f unctional test of the BMS Liquid Disc harge Radiation Monitor beginning with 2104.014 Supplement 1, Step 7.1 and use 2CV 2330A only."
CRITICAL ELEMENTS (C):
4, 6, 11, 12
START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 7.1) Direct WCO to verify 2P-53A/B Discharge to Circ Water Flume
(2LRW-13) is closed.
EXAMINER's CUE:
WCO reports 2LRW-13 is
closed. Directed the WCO to verify 2LRW-13 is closed.
N/A SAT UNSAT 2. (Proc step 7.1) Direct WCO to verify 2P47A/B Discharge to Circ Water Flume
(2BM-35) is closed.
EXAMINER's CUE:
WCO reports 2BM-35 is
closed. Directed the WCO to verify 2BM-35 is closed.
N/A SAT UNSAT 3. (Proc step 7.1) Direct WCO to verify 2F11/11A Disch to CW Flume (2LRW-24)
is closed.
EXAMINER's CUE:
WCO reports 2LRW-24 is
closed. Directed the WCO to verify 2LRW-24 is closed.
N/A SAT UNSAT (C) 4. (Proc step 7.2.1) Hold 2RITS-2330 Selector Switch in CHECK SOURCE.
EXAMINER's CUE:
Switch in CHECK SOURCE.
On panel 2C25, held 2RITS-2330 Selector Switch in CHECK
SOURCE. N/A SAT UNSAT 5. (Proc step 7.2.1) Verify 2RITS-2330 meter moves up scale.
EXAMINER's CUE:
Meter moved up scale.
On panel 2C25, verified 2RITS-2330 indication moved up scale. N/A SAT UNSAT (C) 6. (Proc step 7.2.3) Return 2RITS-2330 Selector Switch to OPERATE.
EXAMINER's CUE:
Switch to OPERATE.
On panel 2C25, placed 2RITS-2330 Selector Switch to
OPERATE. N/A SAT UNSAT
ANO-2-JPM-NRC-BMSRM PAGE 4 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One) 7. (Proc step 7.2.4) Verify 2RITS-2330 meter reading returns to normal.
EXAMINER's CUE:
Meter returns to normal.
On panel 2C25, verified 2RITS-2330 meter reading
returned to original level.
N/A SAT UNSAT 8. (Proc step 7.3.2.A)
(Proc step 7.3.2.B) Direct WCO to open LRW/BMS Discharge to Circ
Water Flume valve
EXAMINER's CUE:
WCO reports that 2HS-2331
is in position 1.
WCO reports that 2HS-2330 is in position 1.
NA step Procedure step 7.3.1
Direct WCO to verify 2HS-2331 in position 1. Initial step 7.3.2.A.
Direct WCO to verify 2HS-2330 in position 1. Initial step 7.3.2.B.
NA step 7.3.2.
C and 7.3.2.D.
N/A SAT UNSAT 9. (Proc step 7.4.1) Record setpoint value from prerelease report EXAMINERs CUE:
2RE2330 alarm setpoint
from Prerelease Report is
"3E3". Request alarm setpoint from prerelease report and record in
step 7.4.1.
N/A SAT UNSAT 10. (Proc step 7.4.2) Determine dial setting to be used from "Radiation Monitor
Alarm Setpoint Table" using
setpoint from Prerelease
Report. From "Radiation Monitor Alarm Setpoint Table" determined that
Prerelease Report setpoint of 3E3
equals dial setpoint of 4.78.
N/A SAT UNSAT (C) 11. (Proc step 7.4.3) Release 2RE-2330 potentiometer stop AND
adjust dial to setting of 4.78.
EXAMINER's CUE:
Potentiometer dial setting is
set at 4.78. Potentiometer is
locked. On panel 2C25, released 2RE-2330 potentiometer stop AND adjusted dial setting of 4.78. Locks
potentiometer stop.
N/A SAT UNSAT (C) 12. (Proc step 7.4.4) Place 2RE-2330 Selector Switch in PULSE CAL.
EXAMINER's CUE:
Switch in PULSE CAL and meter deflection is above
alarm setpoint.
On panel 2C25, placed 2RE-2330 Selector Switch in PULSE CAL.
N/A SAT UNSAT ANO-2-JPM-NRC-BMSRM PAGE 5 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One) 13. (Proc step 7.4.5) Direct WCO to verify annunciator 2K14 B1 is
actuated on Panel 2C112.
This is located on the 335'
elevation of the auxiliary
building.
EXAMINER's CUE:
2K14-B1, "Liquid Radwaste
Discharge Radiation Hi" is
in alarm. Directed WCO to verify annunciator 2K14-B1, "Liquid
Radwaste Discharge Radiation
Hi", is actuated on 2C112.
N/A SAT UNSAT 14. (Proc step 7.4.5) Verify annunciator 2K11-J9 BORON MGMT SYS
TROUBLE" is actuated on
Panel 2C14.
EXAMINER's CUE:
SYS TROUBLE", is in
alarm. On panel 2C14, verified 2K11-J9 is actuated on Panel 2C14.
N/A SAT UNSAT 15. (Proc step 7.4.5) Verify annunciator 2K11-C10 "PROC LIQUID RADIATION
HI/LO" is actuated on Panel
2C14.
EXAMINER's CUE:
2K11-C10, "PROC LIQUID
RADIATION HI/LO" is in
alarm. On panel 2C14, verified 2K11-C10 is actuated on Panel 2C14.
N/A SAT UNSAT 16. (Proc step 7.4.5) Direct WCO to verify LRW/BMS Discharge to Circ
Water Flume (2CV-2330A) is
closed.
EXAMINER's CUE:
WCO reports 2CV-2330A is
closed. Directed WCO to verify 2CV-2330A is closed.
N/A SAT UNSAT 17. (Proc step 7.5) Reset 2RE-2330 and place in OPERATE.
EXAMINER's CUE:
Switch in OPERATE.
On panel 2C25, placed the Operation Selector switch to
RESET.
Placed the Operation Selector switch to OPERATE.
N/A SAT UNSAT 18. (Proc step 7.5) Verify valve(s) tested have reopened.
EXAMINER's CUE:
WCO reports 2CV-2330A is open. Directed WCO to verify 2CV-2330A open.
ANO-2-JPM-NRC-BMSRM PAGE 6 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One) 19. (Proc step 7.5) Check associated alarms clear.
EXAMINER's CUE:
2K11-C10, 2K11-J9 and 2K14-B1 are in "slow flash".
On panel 2C14, verified 2K11-C10 and 2K11-J9 are in "slow flash" OR NOT illuminated.
Directed WCO to verify
annunciator 2K14-B1 on 2C112 is in "slow flash" OR NOT
illuminated.
N/A SAT UNSAT END STOP TIME:
ANO-2-JPM-NRC-BMSRM PAGE 7 OF 8 JOB PERFORMANCE MEASURE EXAMINER'S COPY JPM INITIAL TASK CONDITIONS:
2T21A Liquid Radwaste Release Permit, OP 2104.014 Supplement 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112.
INITIATING CUE:
The SM/CRS directs, "Perform the functional test of the BMS Liquid Discharge Radiation Monitor beginning with 2104.014 Supplement 1, Step 7.1 and use 2CV 2330A only."
ANO-2-JPM-NRC-BMSRM PAGE 8 OF 8 JOB PERFORMANCE MEASURE EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:
2T21A Liquid Radwaste Release Permit, OP 2104.014 Supplement 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112.
INITIATING CUE:
The SM/CRS directs, "Perform the functional test of the BMS Liquid Discharge Radiation Monitor beginning with 2104.014 Supplement 1, Step 7.1 and use 2CV 2330A only."
JPM-ANO-2-JPM-NRC-EFWRS PAGE 1 of 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 014 DATE:
SYSTEM/DUTY AREA: Emergency Feedwater System
TASK: Reset the EFW pump trip throttle valve
JTA#: ANO2AOEFWEMERG1
REFERENCE:
061 A2.04
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
X BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
Simulate SIMULATOR:
LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
14 Minutes REFERENCE(S):
OP 2106.006 Rev 055-04-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
JPM-ANO-2-JPM-NRC-EFWRS PAGE 2 of 6 JOB PERFORMANCE MEASURE The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
- 1. EFW pump (2P7A) started automatically following a reactor trip.
TASK STANDARD:
The trip throttle valve for EFW pump(2P7A) has been reset and is open.
TASK PERFORMANCE AIDS: OP 2106.006 Exhibit 1 and Exhibit 2
JPM-ANO-2-JPM-NRC-EFWRS PAGE 3 of 6 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Reset the EFW pump (2P7A) overspeed trip device usi ng OP 2106.006, Exhibit 1."
CRITICAL ELEMENTS (C): 2, 3, 4, 6 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 1) Verify 2CV0340-2 and 2CV-205-2 are closed.
EXAMINER'S CUE:
Control room reports that 2CV034-2 and 2CV205-2 are
CLOSED. Called the control room to verify that 2CV0340-2 and 2CV-205-2
are closed.
N/A SAT UNSAT (C) 2. (Proc step 2) Position the latch lever to engage the trip hook.
EXAMINER'S CUE:
Latch lever positioned to engage with the trip hook.
Turned the trip throttle valve handwheel clockwise so that the
rotation of the screw raised the
sliding nut and latch lever to
where it could engage with the trip
hook.
Observed latch lever positioned to engage with the trip hook.
N/A SAT UNSAT EXAMINER's NOTE:
This linkage and the indications for steps 2, 3, and 4 are underneath a walkway. Have the examinee point to the lever and tappet then discuss acti ons using Exhibit 2 located on the wall in the 'A' emergency feed-water pump room. (C) 3. (Proc step 3) Reset the mechanical trip linkage manually.
EXAMINER'S CUE:
Mechanical trip linkage is in TRIP RESET.
Locally manually, pulled the spring loaded emergency
connecting rod against the spring force.
Moved the emergency head lever away from the emergency tappet
and tappet nut to allow tappet to
move downward to TRIP RESET.
N/A SAT UNSAT JPM-ANO-2-JPM-NRC-EFWRS PAGE 4 of 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 4. (Proc step 3/4) Verify emergency tappet is in TRIP RESET.
EXAMINER'S CUE:
The tappet is in TRIP RESET.
EXAMINER's Note:
The emergency tappet is located on the turbine not the trip throttle valve. Failure to
ensure this is in the TRIP
RESET position might defeat the O/S trip device.
Verified the tappet is in TRIP RESET. OR Pressed downward on the emergency tappet to place it in
TRIP RESET and;
Submitted a Condition Report
N/A SAT UNSAT 5. (Proc step 5) Verify tappet nut/emergency head lever positioning.
EXAMINER'S CUE:
The flat side of the tappet nut is to the flat side of the emergency head lever.
Verified the flat side of the tappet nut is to the flat side of the
emergency head lever.
N/A SAT UNSAT (C) 6. (Proc step 6) Open the trip throttle valve.
EXAMINER'S CUE:
The trip throttle valve is fully open. With latch and trip hook engaged, turned trip throttle valve
handwheel CCW until valve was
full open.
Observed stem at full travel.
N/A SAT UNSAT 7. (Proc step 7) Close trip throttle valve 1/4 turn.
EXAMINER'S CUE:
The trip throttle valve is closed 1/4 turn.
Turned the trip throttle valve handwheel Counter clockwise 1/4
turn. N/A SAT UNSAT 8. (Proc step 8) Verify 2P7A turbine overspeed trip (2K05-A9) alarm is clear EXAMINER'S CUE:
The control room reports 2K05-A9 is clear.
Contacted the control room to determine 2K05-A9 alarm status.
N/A SAT UNSAT END STOP TIME:
JPM-ANO-2-JPM-NRC-EFWRS PAGE 5 of 6 JOB PERFORMANCE MEASURE Examiner's Copy
JPM INITIAL TASK CONDITIONS
- EFW pump (2P7A) started automatically following a reactor trip. During the speed ramp the Turbine for 2P-7A tripped on overspeed.
INITIATING CUE
The SM/CRS directs, "Reset the EFW pump (2P7A) overspeed trip device using
OP 2106.006, Exhibit 1."
JPM-ANO-2-JPM-NRC-EFWRS PAGE 6 of 6 JOB PERFORMANCE MEASURE Examinee's Copy
JPM INITIAL TASK CONDITIONS
- EFW pump (2P7A) started automatically following a reactor trip. During the speed ramp the Turbine for 2P-7A tripped on overspeed.
INITIATING CUE
The SM/CRS directs, "Reset the EFW pump (2P7A) overspeed trip device using
OP 2106.006, Exhibit 1."
JPM-ANO-2-JPM-NRC-IA01 PAGE 1 of 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 09 DATE:
SYSTEM/DUTY AREA: Emergency & Abnormal Operations
TASK: Isolate the instrument air supply to the MSIV's (locally)
JTA#: ANO2-A0-EP-PAOP-OFFNORM-127
REFERENCE:
067 AA2.04
APPROVED FOR ADMINISTRATION TO:
RO: X SRO: X TASK LOCATION:
INSIDE CR:
OUTSIDE CR:
X BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
PLANT SITE:
Simulate SIMULATOR:
LAB: POSITION EVALUATED:
RO: SRO: ACTUAL TESTING ENVIRONMENT:
SIMULATOR:
PLANT SITE:
LAB: TESTING METHOD:
SIMULATE:
PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
15 Minutes REFERENCE(S):
OP 2203.049, Rev. 001-01-0
EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
THE EXAMINEE'S PERFORMANCE WA S EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time Stop Time Total Time SIGNED: DATE: SIGNATURE INDICATES THIS JPM HAS BEEN CO MPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)
AND IS CURRENT WITH THAT REVISION.
THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
JPM-ANO-2-JPM-NRC-IA01 PAGE 2 of 7 JOB PERFORMANCE MEASURE The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
A severe fire has occurred in t he 'Corridor Behind Door 340 (Zone 2109-U)'.
Control room supervisor has entered AOP 2203.049, Fires in Areas Affecting Safe Shutdown.
TASK STANDARD:
Main Turbine Generator has been locally tripped and Instrument air has been isolated and air bled off the MSIV's.
TASK PERFORMANCE AIDS:
- 1) OP 2203.049 EOP actions for Corridor Behind Door 340 (Zone 2109-U) pages 1-3 (page 31 of 91).
- 2) Flashlight and gloves
- 3) RWP and dosimeter.
JPM-ANO-2-JPM-NRC-IA01 PAGE 3 of 7 JOB PERFORMANCE MEASURE INITIATING CUE:
The SM/CRS directs, "Perform AOP 2203.049, Fires in Ar eas Affecting Safe Shutdown, EOP ACTIONS section for severe fire in area 'Corridor Behind Door 340 (Zone 2109-U)'
to trip the main turbine generator locally and close the MSIV's locally."
CRITICAL ELEMENTS (C): 4, 5, 7, 8 START TIME:
PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 1/2) Obtain equipment from alternate shutdown locker in the entry to the unit 2 control room.
EXAMINER'S CUE:
Simulate obtaining the CRS bag, flashlight and radio with headset.
Radio check is satisfactory
At the remote shutdown locker, obtain Red CRS bag, Flashlight, and
radio with Headset.
Perform radio check N/A SAT UNSAT EXAMINER's NOTE: Access to platform in MSIV room requires an RWP. To save time, the examinee should be prompted to obtain dosimeter and log onto the RWP a nd task for outside controlle d access before starting JPM.
Also a flashlight will be needed. 2. (Proc step 3.A ) Locally trip the Main Turbine EXAMINER'S CUE:
Main Turbine is tripped.
At the north end of the Main Turbine at the front standard, located the red handle and simulates pulling the handle.
N/A SAT UNSAT EXAMINER'S NOTE:
All valves are located in the MSIV room on the first platform above 2T-91. Leather Gloves will be needed for climbing ladder to platform. Care should be taken around the MSIV's to prevent bumping into valves. 3. (Proc step 3.B.1) Close the IA supply from 2T91 "2F-356 I/N" valve (2MS-540)
EXAMINER'S CUE: 2MS-540 valve CLOCKWISE motion stops.
At the "A" MSIV actuator, closed 2MS-540 by rotating hand wheel CLOCKWISE.
Observed valve motion stopped when valve fully closed N/A SAT UNSAT JPM-ANO-2-JPM-NRC-IA01 PAGE 4 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 4. (Proc step 3.B.2) Close IA supply "IA to 2CV-1010-1" valve" (2IA-166)
EXAMINER'S CUE:
2IA-166 valve CLOCKWISE motion stops.
Just south of the "A" MSIV actuator, closed 2IA-166 by rotating its hand wheel CLOCKWISE.
Observed valve motion stopped when valve fully closed N/A SAT UNSAT (C) 5. (Proc step 3.B.3) Open filter vent valve on "A" MSIV point of use air filter
(2F-356).
EXAMINER'S CUE:
Air bleeds off the actuator system and dies away. The 'A' MSIV is slowly closing.
At the "A" MSIV actuator, opened 2F-356 vent valve by turning the petcock valve until air escapes.
Observed valve motion stopped when valve fully open.
N/A SAT UNSAT 6. (Proc step 3.C.1) Close IA supply from 2T91 "2F-357 I/N" valve, (2MS-539)
EXAMINER'S CUE:
2MS-539 valve CLOCKWISE motion stops.
At the "B" MSIV actuator, closed 2MS-539 by rotating hand wheel CLOCKWISE.
Observed valve motion stopped when valve fully closed.
N/A SAT UNSAT (C) 7. (Proc step 3.C.2) Close IA supply "2CV-1060-2 AIR ISOL" valve, (2IA-93)
EXAMINER'S CUE:
2IA-93 valve CLOCKWISE mot
ion stops.
Just south of the "A" MSIV actuator, closed 2IA-93 by rotating its handwheel CLOCKWISE.
Observed valve motion stopped when valve fully closed.
N/A SAT UNSAT (C) 8. (Proc step 3.C.3) Open filter vent on MSIV "IA FILTER 2CV-1060-2 AIR CONTROL VLV" valve (2F-357) (Valve on "B" MSIV point of use air filter (2F-357))
EXAMINER'S CUE:
Air bleeds off the actuator system and dies away. The 'B' MSIV is slowly closing.
At the "B" MSIV actuator, opened 2F-357 vent valve by turning the petcock valve until air escapes. .
Observed valve motion stopped when valve fully open N/A SAT UNSAT Examiner's Note: The next step is to locally secure the ma in feed pumps located in the basement of the turbine building. Stop the JPM before transitioning to this area. Examiner's Cue: Another operator will trip the Main Feed Pumps.
JPM-ANO-2-JPM-NRC-IA01 PAGE 5 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)
END STOP TIME:
___________________
JPM-ANO-2-JPM-NRC-IA01 PAGE 6 of 7 JOB PERFORMANCE MEASURE EXAMINER's COPY INITIAL CONDITIONS:
A severe fire has occurred in the 'Corridor Behind Door 340 (Zone 2109-U)'. Control room supervisor has entered AOP 2203.049, Fires in Areas Affecting Safe Shutdown.
INITIATING CUE:
The SM/CRS directs, "Perform AOP 2203.049, Fire s in Areas Affecting Safe Shutdown, EOP ACTIONS section for severe fire in area 'Co rridor Behind Door 340 (Zone 2109-U)' to trip the main turbine generator locally and close the MSIV's locally."
JPM-ANO-2-JPM-NRC-IA01 PAGE 7 of 7 JOB PERFORMANCE MEASURE EXAMINEE's COPY INITIAL CONDITIONS:
A severe fire has occurred in the 'Corri dor Behind Door 340 (Zone 2109-U)'. Control room supervisor has entered AOP 2203.049, Fires in Areas Affecting Safe Shutdown.
INITIATING CUE:
The SM/CRS directs, "Perform AOP 2203.049, Fire s in Areas Affecting Safe Shutdown, EOP ACTIONS section for severe fire in area 'Co rridor Behind Door 340 (Zone 2109-U)' to trip the main turbine generator locally and close the MSIV's locally."
JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 1 of 8 SYSTEM/DUTY AREA:
Emergency Diesel Generator System TASK: Start an emergency diesel generator wi thout DC control power (2K-4B)
JTA # : ANO2-AO-EDG-OFFNORM-5 KA VALUE RO: 4.1 SRO: 4.5 KA
REFERENCE:
055 EA1.06 APPROVED FOR ADMINISTRATION TO: RO:
X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR:
X BOTH: SUGGESTED TESTING ENVIRONMENT AND ME THOD (PERFORM OR SIMULATE):
PLANT SITE:
Simulate SIMULATOR:
LAB: POSITION EVALUATED: RO: SRO:
ACTUAL TESTING ENVIRONMENT: SIMULATOR:
PLANT SITE:
X LAB: TESTING METHOD: SIMULATE:
X PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES:
16 minutes REFERENCE(S)
OP 2104.036, Exhibit 2, 2107.001, Exhibit 9 EXAMINEE'S NAME:
SSN: EVALUATOR'S NAME:
DATE: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
SATISFACTORY:
UNSATISFACTORY:
PERFORMANCE CHECKLIST COMMENTS:
Start Time: Stop Time: Total Time:
Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.
SIGNED: DATE:
JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 2 of 8 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
JPM INITIAL TASK CONDITIONS:
The following conditions exist:
- 1. The plant is in Mode 3 following an automatic reactor trip
- 2. A Station Blackout exists
- 3. There is no green DC power available.
- 4. Fuses from alternate shutdow n locker are simulated obtained.
TASK STANDARD:
2DG2 [2K-4B] has been started with normal voltage and frequency TASK PERFORMANCE AIDS:
- 1. OP 2104.036 Exhibit 2 JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 3 of 8 INITIATING CUE:
The CRS provides the following direction:
- 1. Perform a loss of DC start of 2DG2 using OP 2104.036, Exhibit 2 2. Due to the timeliness of the actions required, electric al safety requirements may be waived at your discretion.
However, use extreme caution when operat ing any energized electrical components.
CRITICAL ELEMENTS (C):
4, 5, 6, 8 START TIME:
EXAMINER'S NOTE:
Provide examinee with OP2104.036, Exhibit 2.
Have a copy of 2107.001, Exhibit 9, Electrical Safety Requirements available for examinee's review if requested. If examinee states that they will adhere to the electrical safety requirements for steps 1, 2 & 3, have them show what requirements they will be ensuri ng are satisfied then, tell them that the requirements have been satisfied and that they should continue with the JPM. Due to electrical safety concerns, do not allow the examinee to open the door to 2D24. Have them explain what they would do. PERFORMANCE CHECKLIST STANDARDS (Circle One) 1. (Proc step 1) Open one of the following sets of breakers:
- 2C108 breaker (2D24-2)
- 2E21 breaker (2D24-6)
- 2C108 breaker (2D24-8)
- 2E21 breaker (D2E21NA6)
- 2C108 breaker (D2C108NA8)
- 2C108 breaker (D2C108NA2)
POSITIVE CUE:
(For each breaker)
Breaker indicates OPEN.
NEGATIVE CUE:
(For each breaker)
Breaker indicates NOT OPEN.
For the listed breaker, opened panel door and moved breaker
handle to OFF.
N/A SAT UNSAT TRANSITION NOTE:
Go to 2A4 switchgear room.
EXAMINERS NOTE:
For the 4160v breakers in Steps 2 and 3, do NOT open the breaker cubicle doors.
For electrical safety purposes, provide candidate with picture at the end of this JPM, have the candidate explain the indications he would use to determine the following.
- 1. Breaker position
- 2. Closing Spring Status
Standard:
- 1. The student must use mechanical breaker position indication
- 2. The student must use mechanical closing spring status indication.
Both of these indicators are located on the breaker.
JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 4 of 8 Examiners Note:
The following breakers are listed with their respective conditions for the plant conditions that exist. For breakers 2A-402 and 2A-409, provide examinee with picture at the end of this JPM and have them indicate what they would do to open the breakers. 2. (Proc step 2) Verify the following breakers OPEN WITH closing springs charged.
2DG2 Output breaker (2A-408)
NEGATIVE CUE
- 2A-402 is closed with closing
springs charged
POSITIVE CUE:
2A402 opens when the
mechanical trip button is
pushed.
At bus 2A4 at cubicle 2A411, opened cubicle door.
Observed indications for the
following. Mechanical breaker position Mechanical closing spring indication
Operator opened any closed
breaker by pushing the
mechanical breaker trip button on
the breaker N/A SAT UNSAT 3. (Proc step 3) Verify the following breakers OPEN.
2A4 Supply breaker (2A-409)
NEGATIVE CUE:
2A-409 indicates CLOSED
POSITIVE CUE:
2A-409 opens when the
mechanical trip button is
pushed.
For each listed breaker, verified the breaker to be open with the
mechanical breaker indication.
Operator opened any closed
breaker by pushing the
mechanical breaker trip button on
the breaker N/A SAT UNSAT JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 5 of 8 (C) 4. (Proc step 4) Open 2DG2 Service Water Outlet valve (2CV-1504-2).
POSITIVE CUE:
WCO reports Service Water Valve (2CV-1504-2) is OPEN.
Using radio or telephone communications, instructed WCO
to OPEN 2CV-1504-2 locally using
manual operator.
OR Using radio or telephone
communications, contacted
Control Room personnel to have
WCO to OPEN 2DG2 Service
Water valve (2CV-1504-2) using
the manual operator locally.
N/A SAT UNSAT TRANSITION NOTE:
Go to 2DG2 room.
(C) 5. (Proc step 5) Place exciter regulator handswitch in LOCAL.
POSITIVE CUE:
The exciter regulator
handswitch indicates LOCAL.
On panel 2E22, rotated Exciter Regulator handswitch to LOCAL.
N/A SAT UNSAT (C) 6. (Proc step 6) Place Engine Control handswitch to START.
POSITIVE CUE:
The Engine Control handswitch indicates START.
On panel 2E21, inserted key in Engine Control Switch.
Rotated key clockwise to unlock.
Rotated Engine Control
handswitch through LOCKOUT to
START.
N/A SAT UNSAT 7. (Proc step 7.1) Obtain FNM 10 amp fuses from Alternate Shutdown file cabinet.
POSITIVE CUE:
Fuses are in your possession.
Obtained two fuses from the Alternate Shutdown file cabinet.
N/A SAT UNSAT (C) 8. (Proc step 7.2) Open either Air Start Solenoid (2SV-2829-2 or 2SV-2830-2).
POSITIVE CUE:
Engine noise indicates start.
NEGATIVE CUE:
Engine noise does NOT indicate start.
Rotated manual operator stem on either Air Start Solenoid clockwise.
N/A SAT UNSAT 9. (Proc step 7.3) Close Air Start solenoid. Upon 2DG2 start, disengaged manual solenoid operator by
rotating counter-clockwise.
N/A SAT UNSAT 10. (Proc step 7.4) Verify generator 2DG2 voltage.
POSITIVE CUE:
2DG2 voltage is ~ 4160 volts.
On panel 2E21, verified 2DG2 voltage between 3800 and 4400
volts on V-2DG2-3, 2DG2 local AC
voltmeter.
N/A SAT UNSAT JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 6 of 8
- 11. (Proc step 7.7) Verify generator 2DG2 frequency.
POSITIVE CUE:
2DG2 frequency is ~ 60 Hz.
On panel 2E21, verified 2DG2 frequency between 59.5 and
60.5 Hz and maintained as loads
are added.
N/A SAT UNSAT END STOP TIME:
JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 7 of 8 Examiner's Copy JPM INITIAL TASK CONDITIONS
- 1. The plant is in Mode 3 following an automatic reactor trip. 2. A Station Blackout exists. 3. There is no green DC power available. 5. Fuses from alternate shutdown locker are simulated obtained.
INITIATING CUE:
The CRS provides the following direction:
- 1. Perform a loss of DC start of 2DG2 using OP 2104.036, Exhibit 2. 2. Due to the timeliness of the actions required, electrical safety requirements may be waived at your discretion. However, use
extreme caution when operati ng any energized electrical components.
JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 8 of 8 Examinee's Copy JPM INITIAL TASK CONDITIONS
- 4. The plant is in Mode 3 following an automatic reactor trip. 5. A Station Blackout exists. 6. There is no green DC power available. 6. Fuses from alternate shutdown locker are simulated obtained.
INITIATING CUE:
The CRS provides the following direction:
- 3. Perform a loss of DC start of 2DG2 using OP 2104.036, Exhibit 2. 4. Due to the timeliness of the actions required, electrical safety requirements may be waived at your discretion. However, use
extreme caution when operati ng any energized electrical components.
JOB PERFORMANCE MEASURE JPM# A2JPM-RO-EDDCG REV 03 PAGE 9 of 9 MANUAL CLOSE CHGDMANUAL TRIP CLOSE Appendix D Scenario 1 Form ES-D-1 Page 1 of 17 Facility: ANO-2 Scenario No.: 1 Op-Test No.: 2005-1 Page 1 Examiners: Operators:
Initial Conditions: 56% MOL, All Engineered Safety Features (ESF) systems in standby. Condenser outer water box is isolated for tube plugging. 'B' circulating water pump is secured.
Green Train Maintenance Week.
Turnover: 56%. 250 EFPD. Condenser outer water box is isolated for tube plugging. Estimated time to complete repairs is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 'B' circulating water pump is secured. Equipment Out of Service Monitor (EOOS) indicates 'Minimal Risk.' Green Train Maintenance
Week.
Event No. Malf. No. Event Type* Event Description 1 NIBLINEPWR I (CBOT) Safety channel linear power channel 'B' fails low. CBOT must bypass points in Plant Protection System (PPS) channel.
2 CVC2P36AFAL C (CBOR) Running charging pump trips breaker. Abnormal Operating Procedures (AOP) entry start standby charging pump.
3 SGATUBE R(CBOR) N(CBOT) 'A' Steam Generator (SG) tube leak results in power reduction to take unit off line.
4 SGATUBE M(ALL) 'A' Steam Generator tube rupture results in reactor trip and Reactor Coolant System (RCS) cool down.
5 4162A406 C (CBOT) 'B' High Pressure Safety Injection (HPSI) pump trips breaker on start.
6 2CV50151 C (CBOT) 'A' HPSI train injection Motor Operated Valve (MOV) fails to open on actuation. 7 BUHTRS C(CBOR) Back up Heaters fail on due to relay failure and will not shut off when Pressurizer level drops less than set point. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario 1 Form ES-D-1 Page 2 of 17 Scenario #1 Objectives 1) Evaluate individual response to a fa ilure of an Excore nuclear instrument. 2) Evaluate individual response to a failure of a running charging pump. 3) Evaluate individual response to a small Pri-Sec leak.
- 4) Evaluate individual ability to perform a reduction in plant power. 5) Evaluate individual ab ility to mitigate a SGTR. 6) Evaluate individual ability to monitor operation of ESF equipment. 7) Evaluate individual response to a failure of the PZR heaters.
SCENARIO #1 NARRATIVE Simulator session begins with the plant at 56%
power steady state. 'B' circulating water pump is secured and the outer main condenser water boxes are tagged out.
When the crew has completed their control room walk down and brief, 'B' Excore will fail low. This will result in a CPC sensor failure alarm and the NI linear and log power instruments on 'B' channel failing to Zero.
The CRS will enter the Nuclear Instrument Malfunction AOP, AOP 2203.026. The CRS will direct the CBOT to bypass points 1, 2, 3, and 4 on 'B' PPS. TS 3.3.1.1 will be entered due to the excore failure.
About 10 minutes after the excore failure, the 'A
' CCP will trip its breaker. A CCP low flow alarm will alert the operator that the CCP has tripped. If another pump is not started quickly, letdown will be isolated due to high regenerative heat exchanger outlet temperature high (alarm).The CRS will enter the loss of chargi ng AOP, OP 2203.036, Crew will verify that the breaker tripped; then start a backup CCP. The CBOR will assess the proper operation of the pump, PZR level and letdown flow.
10 minutes after the CCP trips, a 5.0 gpm primary to secondary leak will start. The CRS will enter the primary to secondary leak age AOP, OP 2203.038. CBOR and CBOT will perform RCS Leak rate determinations. The CRS will enter Tech Spec 3.4.6.2. The CRS will direct the NLO's to control secondary c ontamination using standar d attachment 19 and direct the chemists to sample the SG's for activity. The CRS will isolate steam to 'A' EFW pump from 'A' SG and enter TS 3.7.1.2. Crew will perform a plant shutdown.
When cued by the lead evaluator after the CBOR has completed the required reactivity manipulation, a 500 gpm SGTR on 'A' SG will start with a ramp of 10 minutes. Secondary System Radiation Hi, SG tube leak detec tion Rate of change Hi, and SG tube leak detection leak rate Hi annunciators will alarm. The CBOR recognize that the SGTR is greater than CCP capacity. The CRS will direct the CBOR will manually trip the reactor.
Post trip, the PZR backup heaters will fail to de-energize when PZR level drops below 29%, the CBOR will manually secure the heaters.
Post SIAS, the 'B' HPSI pump Breaker will trip (green train) and one of the red train HPSI injection MOV's will fail to open on actuation. The CBOT will manually start the swing HPSI pump and open the failed injection MOV. This is Tech Spec 3.0.3 entry.
Appendix D Scenario 1 Form ES-D-1 Page 3 of 17 SCENARIO #1 NARRATIVE (continued)
The Crew will implement SPTA's and secure 2 RCP's when RCS pressure drops below 1400 psia. The CRS will diagnose a SG TR and enter EOP 2202.004, SGTR. The CBOR will rapidly cool down the RCS to less than 535°F using the bypass valves to the condenser. The CBOT will override SW to CCW and ACW. The CBOT will isolate the
'A' SG using standard attachment 10 when RCS Thot is less than 535°F.
Appendix D Scenario 1 Form ES-D-1 Page 4 of 17 Simulator Instructions for Scenario 1 Reset simulator to MOL 56% power IC stead state.
Markup OP 2102.004, power operations up to step 9.22.
Ensure that AACG is secured and annunciators clear. Ensure hotwell level is ~80%. Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11.
Swing ESF equipment aligned to the Green train.
2PCV0231, Gland sealing steam pressure control valve failed closed.
Place permissive hand switches for 2CV 303 and 2CV 0306 to OFF. T1, T2, T3, T5 set to false. T4 set to SIAS1.
T5 set to PZR Pressure < 2000 psia Event No. Malf. No. Value/
Ramp Time Event Description 1 NIBLINEPWR Trigger = T1 0.0 Safety Channel 'B' Excore Linear instrument fails LOW. 2 CVC2P36AFAL Trigger = T2 TRUE 'A' Coolant Charging Pump trips on instantaneous Over Current due to motor fault. 3 SGATUBE Trigger = T3 5.0 'A' SG primary-secondary leak. 4 SGATUBE CUED 500 RAMP= 10 MIN 'A' Steam Generator Tube Rupture (500 gpm ramped over 10 Minutes).
5 4162A406 Trigger = T4 TRUE 'B' HPSI pump trips breaker on start.
6 CV50151 Trigger = T4 TRUE Red train HPSI injection MOV fails to open on SIAS actuation. 7 RCSHTRON Trigger = T5 TRUE PZR Backup heaters fail to de-energize. At T=0 Trigger T1 'B' excore instrument fails low Cue: Report that I & C planner will begin planning work on failed excore instrument.
Appendix D Scenario 1 Form ES-D-1 Page 5 of 17 At T= 10 minutes Trigger T2 'A' CCP trips breaker.
Cue: As WCO report that the 'A' CCP breaker, 2B52-A5, is tripped and will not reset.
At T=20 minutes Trigger T3 'A' Steam Generator 5 gpm tube leak. Cue: As Auxiliary Operator, report that standard attachment 19, control of secondary contamination is in progress.
Cue: When notified of requirement to sample SG's as Chemis t, after 15 minutes report that the sample analysis is in progress and that when frisking sample 'A' SG countrate was higher than 'B' SG.
The CRS will direct the NLO's to and dire ct the chemists to sample the SG's for activity. CUED by Lead Examiner T3 Raise 'A' SG tube leak to 500 gpm ramped over 10 minutes. This will result in a manual reactor trip.
SIAS actuation T4 'B' high pressure safety injection,HPSI, pump trips its breaker on start and one HPSI injection valve, 2CV5015-1 will fail to open but can be manually opened from 2C17.
PZR pressure
<2000psia T5 All backup heaters fail ON and must be manually taken to OFF.
Appendix D Scenario 1 Form ES-D-1 Page 6 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Channel 'B' excore nuclear instrument will fail low. The CRS will enter the NI malfunction AOP, OP 2203.026.
Time Position Applicant's Actions or Behavior ALL Crew will diagnose that 'B' Excore is the only channel that has failed. CRS Enter AOP 2203.026, NI malfunction and perform the following actions: Refer to TS 3.3.1.1 Direct the CBOT to bypass points 1,2,3 and 4 on 'B' PPS Verify that Log channel is also affected Notify maintenance of problem with 'B' Excore CBOT Will perform the following: Obtain Key 12 from SM Notify control room of potential PPS security door and Bypass alarms Open 2C23 door and unlock panel door Push bypass buttons for points :
1 - Hi Linear Power 2 - Hi Log Power 3 - High LPD 4 - Low DNBR Verify that bypass lights illuminated on operator inserts on 2C03 CBOR Will perform the following: PEER check that bypass lights for points 1,2,3 and 4 are illuminated on operator inserts on 2C03 Simulator Operator Cue: When contacted as IC or Work Week Manager, report that you will begin planning work on 'B' Excore.
Termination criteria: When points 1,2,3 and 4 are bypassed on 'B' PPS or at the discretion of the lead examiner.
Appendix D Scenario 1 Form ES-D-1 Page 7 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 2
Event
Description:
'A' CCP trip. The CCP low flow alarm will alert operators of this failure. Letdown will isolate, if backup CCP not started in timely manner.
Time Position Applicant's Actions or Behavior CBOR Announce that 'A' CCP has tripped its breaker (Red and Green lights out on 2C09)
CRS Enter loss of Charging AOP and perform the following actions: Check for proper Charging suction and discharge flow path. Check that 'A' CCP has tripped breaker Direct Starting backup CCP Direct verification of proper operation of running CCP Check for indications of CCP header rupture using control room indications Direct WCO to locally vent 'A' CCP TRM 3.1.2.4 Applicability Simulator Operator Cue: When contacted as WCO to vent 'A' CCP wait a few minutes and report that no air bubbles only water came out vent.
CBOR Verify VCT outlet valve open Verity CCP header isolation valve open Manually start backup CCP by taking hand-switch to start Verify VCT level stable or going up CBOT /CBOR Verify CCP header not ruptured:
- Aux Building or CNTMT radiation level steady
- Waste Tanks 2T20A/B level not rising
- CNTMT Sump level not rising
- Aux Building sump level not rising NOTE: Letdown may have isolated on high temperature. Letdown may be restored at this point. Termination criteria: When backup CCP started or at discretion of lead examiner.
Appendix D Scenario 1 Form ES-D-1 Page 8 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event
Description:
5.0 GPM primary to secondary leak on 'A' SG. The CRS will enter the primary to secondary leakage AOP, OP 2203.038. Crew will perform a plant shutdown Time Position Applicant's Actions or Behavior CBOR Announce annunciators: 2K11-A10 Sec Sys Radiation Hi 2K11-J8 SG Tube Leak Detection Rate of Change Hi 2K11-K8 SG Tube Leak Detection Trouble/LKRT Hi CRS Implement AOP 2203.038, PRI-SEC leakage and perform the following: Direct CBO's to perform RCS leak rates Enter TS 3.4.6.2 Direct AO to perform standard attachment 19, control of secondary contamination Direct the chemists to sample the SG's for activity
Direct CBOT to isolate steam to 'A' EFW pump from 'A' SG Direct CBOR to perform a plant shutdown using normal boration method. CBOT Close 2CV 1000-1, steam from 'A' SG to 'A' EFW pump.
Appendix D Scenario 1 Form ES-D-1 Page 9 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event
Description:
5.0 GPM primary to secondary leak on 'A' SG. The CRS will enter the primary to secondary leakage AOP, OP 2203.038. Crew will perform a plant shutdown. Simulator Operator Cue: When contacted as AO acknowledge requirement to begin working on Standard attachment 19.
CBOR Perform a plant shutdown Use reactivity plans to determine the amount of boron required. Adjust turbine load to maintain Tave within 2°F of Tref.
Insert CEA's as directed by reactivity plan. AOP requires a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> shutdown to Mode 3. The CRS may determine a rapid plant shutdown of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to be in Mode 3 is more conservative and this decision is acceptable.
Termination criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.
Appendix D Scenario 1 Form ES-D-1 Page 10 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
500 gpm Tube Rupture on 'A' Steam Generator ramped over 10 Minutes. This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate 'A' SG.
Time Position Applicant's Actions or Behavior CBOR Report that PZR level is lowering Start all back up CCP's or report that they are running Isolate Letdown CRS Recognize SGTR has exceeded CCP capacity and the ability to maintain PZR level. Direct the CBOR to manually trip the reactor CBOR Manually trip the reactor.
CRS Implement Standard Post Trip Actions, track safety functions, and direct board operators actions. CBOR Check reactivity control:
Reactor power decreasing.
All CEAs inserted.
CBOT Check maintenance of vital auxiliaries:
Main turbine tripped. Generator output and exciter breakers open. All 4160v and 6900 v Non-Vital busses energized. ALL 4160v and 480v vital AC bus energized.
All 125v vital DC bus energized.
Appendix D Scenario 1 Form ES-D-1 Page 11 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
500 gpm Tube Rupture on 'A' Steam Generator ramped over 10 Minutes. This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate 'A' SG.
Time Position Applicant's Actions or Behavior CBOR Check inventory control: PZR level 16 to 80%.
Trend from set point. Report SIAS actuated or manually actuate and verify all PZR heaters off when PZR level less than 29%. (SEE Event 7)
CBOR Check RCS pressure control: RCS pressure 1800 to 2300 psia.
Trend from set point Secure Two RCP's when RCS pressure is less than 1400 psia.
Place spray valve for secured RCPs in manual closed. Verify SIAS when pressure less than 1650 psia.
CBOR Check core heat removal by forced circulation:
RCP 's running Loop T less than 10 F. RCS MTS 30 F or greater. Service water pump suction aligned to Lake. Component cooling water aligned to RCPs.
CBOT Restore SW to ACW per Exhibit 5. (NOTE: This action requires several minutes)
Check SIAS actuated. Maintain SW pressure greater than 85 psig.
Appendix D Scenario 1 Form ES-D-1 Page 12 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
500 gpm Tube Rupture on 'A' Steam Generator ramped over 10 Minutes. This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate 'A' SG.
Time Position Applicant's Actions or Behavior CBOT Check RCS Heat Removal: Report SG levels and main feed water is in RTO. Report feed water line intact. Report SG pressures (May take manual local (ML) control of SDBCS master controller (at CRS direction) and reduce set point to 950-1050 psia).
CBOR Check CNTMT parameters: Temperature less than 140 F. Pressure less than 16 psia.
Status of radiation alarms: CAMS (2K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT in alarm Secondary Sys Radiation Hi (2K11-A10) IN ALARM CBOT Will open 2CV0233, bypass around 2PCV0231 which is simulated closed to match condition of valve at plant. This is in response to low gland seal pressure.
CRS Notify SM to perform the following: SE report to control room. Announce reactor trip on plant page. Refer to Tech Specs and EALs.
Appendix D Scenario 1 Form ES-D-1 Page 13 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
500 gpm Tube Rupture on 'A' Steam Generator ramped over 10 Minutes. This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate 'A' SG.
CRS Direct CBOs to acknowledge all control room annunciators and announce all significant alarms. Diagnose Steam Generator Tube Rupture
CRS Implement Steam Generator Tube Rupture procedure and open place keeping page.
ALL Perform crew brief and review floating steps.
CRS Determine applicable floating steps: Commence cool down to less than 535 F Thot. HPSI Override Criteria.
CRS Direct the following actions: Commence cool down to less than 535 F Thot. Inform SM to contact Chemistry to sample both SG for activity.
Determine ruptured SG
Perform post-SIAS actions: Verify Safety Injection flow to RCS: Isolate 'A' SG when RCS Thot is less than 535°F Verify HPSI override criteria met: RCS MTS 30°F or greater. PZR level greater than 29% and controlled. RVLMS LVL 03 or higher elevation indicates WET. At least ONE intact SG available for Heat Removal Level 10 to 90% with FW available.
Appendix D Scenario 1 Form ES-D-1 Page 14 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
500 gpm Tube Rupture on 'A' Steam Generator ramped over 10 Minutes. This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate 'A' SG.
Time Position Applicant's Actions or Behavior Critical Step CBOR RCS cool down to less than 535°F T-hot : (floating step)
CBOR Reset low SG set points. Commence RCS depressurization to maintain RCS MTS 30 to 45 (When HPSI overridden) Take manual control of SDBCS bypass valves to condenser
(2CV0302/2CV0303)
Place ALL ADV Permissive switches in OFF. Verify EFW feeding SGs.
Secure running MFW pump.
Close ALL MFW Block valves.
Record and plot cool down on Attachments 1 and 8.
CBOR /CBOT Verify Safety Injection flow to RCS: Check HPSI flow using Exhibit 2. Check LPSI flow using Exhibit 3.
Appendix D Scenario 1 Form ES-D-1 Page 15 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
500 gpm Tube Rupture on 'A' Steam Generator ramped over 10 Minutes. This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate 'A' SG.
Time Position Applicant's Actions or Behavior CBOT Perform post-SIAS actions: SW pumps running on each loop.
SW pump suction aligned to Lake.
Report all non-vital buses energized. Verify SG sample valves open.
Critical Step CBOT Use Attachment 10 to isolate Ruptured SG
CBOR CBOT OVERRIDE HPSI: Throttle HPSI flow OR place HPSI pumps in PTL as needed to control RCS pressure, inventory, and heat removal.
Termination criteria: RCS Cool down to less than 535°F and 'A' SG isolated or at examiners discretion.
Appendix D Scenario 1 Form ES-D-1 Page 16 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 5/6 Event
Description:
'B' HPSI pump trips on SIAS start. 2CV5015-1 fails to open on SIAS signal. This will make HPSI flow UNACCEPTABLE. 'C' HPSI pump must be started or
2CV5015-1 must be opened.
Time Position Applicant's Actions or Behavior CBOT 2K05 E-3, 'B' HPSI pump trip alarm announced. Observes green light lit on pump and no discharge pressure.
CBOT Observes 2CV 5015-1 is closed, green light on, red light off, Z-tape reading 0.
CRS Directs starting 'C' HPSI pump Directs opening 2CV 5015-1
Critical Step Critical Part is to either start 2P89C or open 2CV-5015-1 CBOT Starts 'C' HPSI pump Verified proper discharge pressure and flow(depending on RCS pressure)
And/or Opens 2CV 5015-1 by taking hand switch to OPEN and observing red light on green light off and Z-tape reading ~ 100%
Termination criteria: When 'C' HPSI pump started or 2CV5015-1 is opened or at
discretion of lead examiner.
Appendix D Scenario 1 Form ES-D-1 Page 17 of 17 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
Backup heaters fail to de-energize on PZR pressure control signal or PZR level less than 29%. Failure to turn backup heaters off will cause them to fail and potential for loss of PZR pressure control.
Time Position Applicant's Actions or Behavior CBOR Observes the red light 'ON' on the backup heaters when PZR level is less than 29 %
Reports observation to CRS
CRS Directs taking Backup heater hand switches to OFF
CBOR Takes Backup Heater hand switches to OFF Observes green lights 'ON' red lights 'OFF'
Termination criteria: When PZR heater hand switches are taken to 'OFF' or at the discretion of the lead examiner.
Appendix D Scenario 2 Form ES-D-1 Page 1 of 16 Facility: ANO-2 Scenario No.: 2 Op-Test No.: 2005-1 Examiners: Operators:
Initial Conditions: 100% MOL, All ESF systems in standby. 'C' HPSI pump tagged out for oil bubbler replacement. 'C' HPSI is aligned to green train. Green train maintenance week.
Turnover: 100%. 250 EFPD. 'C' HPSI pump tagged out for oil bubbler replacement. EOOS indicates 'Minimal Risk.' Green train maintenance week.
Event No. Malf. No. Event Type* Event Description 1 XRCCHAPLVL I (CBOR) Control Channel "A" Pressurizer Level fails LOW.
2 XSG2PT10412 I (CBOT) Steam Generator safety channel pressure fails LOW. 3 FWPMPATRP R (CBOR) N (CBOT) 'A' Main Feed Pump (MFP) trips due to thrust bearing wear and results in a power reduction to less than 90%.
4 FWAFT5A M (ALL) Feed water line break in containment after 2FW5A, feed water to 'A' Steam Generator (SG) check valve, which results in Excess Steam Demand (ESD) on 'A' SG. 5 ESCSBPMP C (CBOT) Fail 'B' Containment Spray Actuation Signal (CSAS) pump to start on CSAS.
6 ESFCSASFAIL C (CBOR) Fail CSAS channel 1 to actuate auto.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario 2 Form ES-D-1 Page 2 of 16 Scenario #2 Objectives 1) Evaluate individual response to a failure of Pressurizer level cont rol channel failure. 2) Evaluate individual response to a failure of a Plant Protection S ystem Steam Generator Level instrument failure. 3) Evaluate individual response to a Main Feed Pump Trip at 100% power. 4) Evaluate individual ability to perform a reduction in plant power. 5) Evaluate individual abilit y to mitigate an unisolatable Feed water break in containment. 6) Evaluate individual abi lity to monitor operation of Engineered Safety Features equipment. 7) Evaluate individual response to a failu re of required Engineered Safety Features Actuation System actuation.
SCENARIO #2 NARRATIVE Simulator session begins with the plant at 100%
power steady state. 'C' HPSI pump is tagged out to replace a pump oil bubbler.
When the crew has completed their control room walk down and brief, the in service
Pressurizer (PZR) control channel level instrument will fail low. Alarms on control channel 1 level lo and level lo lo will come in. This will result in letdown going to minimum flow, the two backup CCP's will automatically start, all PZR heaters de-energizing and actual PZR level go up. AOP 2203.028, PZR Systems Malfunctions, will be entered and actions directed by the CRS. The CBOR will take the let down flow controller to manual and control PZR level. The CBOR will also verify that the other level control channel is reading
correctly and select that channel for control and place the PZR low low level cutoff switch to the unaffected channel. When the auto and m anual signals are matched, the CBOR will place the letdown flow controller to automatic
About 10 minutes after PZR level control fa ilure, 'A' Steam Generator safety channel pressure instrument, 2PT1041-2, will fail low. This will tr ip one of the four PPS trip channels for low SG pressure trip and MSIS. Alarms for MSIS pre-trip, RPS channel trip/pre-trip, and channel 'B' oper ator insert (2C03) trip and pre-trip lights will be lit. The CRS will refer to the ACA 2203.012D and tech specs 3.3.1.1, 3.
3.2.1 and 3.3.3.6 for guidance. The CBOT will place Channel 'B' PPS in bypass for point 11, SG pressure low, point 19, 'A' SG delta-P for EFAS 1, and point 20, 'B' SG delta-P for EFAS 2 for maintenance and trouble shooting.
The crew will have one hour to place these points in bypass before exceeding the tech spec LCO.
About 10 minutes after the Steam Generator instrum ent failure, 'A' MFP will trip. CRS will enter AOP 2203.037, Loss of Main Feed Pump. This will result in Steam Flow exceeding Feed flow and SG levels dropping. The crew will manually start the fourth condensate pump, reduce turbine load, and borate usin g emergency boration to the RCS until Feed flow is greater than Steam Flow. Then cont inue with a normal boratio n power reduction to less than 90%.
Appendix D Scenario 2 Form ES-D-1 Page 3 of 16 SCENARIO #2 NARRATIVE (continued)
Once the Reactor operator's reactivity manipulations are complete, the main feed line break will occur. This will cause containment pressure, tem perature and sump level to go up. 'A' Steam Generator level will lower. The crew will m anually trip the reactor and complete SPTA's. Once feed (Main and Emergency) is secured to the SG, an Excess Steam Demand will occur on
'A' Steam Generator.
The CRS will diagnose an Excess Steam Demand event and enter OP 2202.005, ESD. The crew will manually control Reactor Coolant Temperature once the 'A' SG boils dry using the upstream Atmospheric Dump Valves on 'B' SG. The crew will manually control PZR pressure using the Auxiliary Spray valve.
When Containment pressure exceeds 23.3 ps ia, the crew will recognize that CSAS, Containment Spray Actuation Signal, has not automatically actuated on Channel 1 and that the Spray pump on channel 2 side did not start. The crew will manually actuate spray on Channel 1 and manually start 'B' CSAS pump.
Appendix D Scenario 2 Form ES-D-1 Page 4 of 16 Simulator Instructions for Scenario 2 Reset simulator to MOL 100% power IC stead state.
Ensure that AACG is secured and annunciators clear.
'C' HPSI pump is tagged out for oil bubbler replacement. Ensure hotwell level is ~80%. Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11. T1, T2, T3, T4 set to false.
Event No. Malf. No. Value/
Ramp Time Event Description 1 XRCCHAPLVL Trigger 1 0.0 Control Channel "A" Pressurizer Level fails LOW. 2 XSG2PT10412 Trigger 2 0.0 Steam Generator safety channel pressure fails LOW. 3 FWPMPATRP Trigger 3 TRUE 'A' Main Feed Pump (MFP) trips due to thrust bearing wear and results in a power reduction to less than 90%. 4 FW2PW5AAFT Trigger 4 1000 Ramp 5 min Feed water line break in containment after 2FW5A, feed water to 'A' Steam Generator (SG) check valve, which results in Excess Steam Demand (ESD) on 'A' SG. 5 BS2P35BFAL TRUE Fail 'B' Containment Spray Actuation Signal (CSAS) pump to start on CSAS.
6 ESFCSASFAIL TRUE Fail CSAS channel 1 to actuate auto.
At T=0 Trigger T1 Control Channel "A" Pressurizer Level fails LOW.
Cue: Report that I & C planner will begin planning work on failed PZR level transmitter.
At T= 10 minutes Trigger T2 Steam Generator safety channel pressure fails LOW, 2PT10412. Cue: Report that I & C planner will begin planning work on failed Steam Generator safety channel pressure transmitter.
Appendix D Scenario 2 Form ES-D-1 Page 5 of 16 At T=20 minutes Trigger T3 'A' Main Feed Pump (MFP) trips. Cue: As Auxiliary Operator, report that
'A' MFP is tripped and no obvious problems noted locally.
CUED by Lead Examiner T4 'A' main feed line break inside containment resulting in a reactor trip and excess steam demand event CSAS actuation True 'B' containment spray pump will fail to start on CSAS signal. Can be manually started.
CSAS actuation True Red Train containment spray actuation signal, CSAS, will not automatically actuate. Can be manually actuated.
Appendix D Scenario 2 Form ES-D-1 Page 6 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event
Description:
Channel A pressurizer level control channel 2LT-4627-1 fails low. The CRS will enter the PZR Systems Malfunction AOP 2203.028.
Time Position Applicant's Actions or Behavior ALL Announce alarms 2K10-G6 CNTRL CH 1 LEVEL LO. 2K10-F6 CNTRL CH 1 LEVEL LO LO.
Report 2LI-4627-2 and 2LR-4625 indicate normal. Report backup charging pumps started.
CRS Refer to PZR Systems Malfunctions AOP 2203.028 and direct board operators actions.
CBOR Determine PZR level Channel A failed. Place Letdown Flow controller (2HIC-4817) in MANUAL.
Place PZR Level Channel Select switch (2HS-4628) to Channel B. Place PZR Low Low Level Cutoff select switch (2HS-4642) to Channel B. Verify PZR heaters and Normal Spray maintaining RCS pressure 2025 to 2275 psia.
The CBOR will take the letdown flow controller to manual and control PZR level.
CRS Enter 3.3.3.6 Post Accident Instrumentation.
Simulator Operator Cue: When contacted as IC or Work Week Manager, report that you will begin planning work on 2LI-4627-1.
Termination criteria: Unaffected PZR level channel selected and letdown in automatic or at the discretion of the lead examiner.
Appendix D Scenario 2 Form ES-D-1 Page 7 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 2
Event
Description:
2PT1041-2, Channel 'B' SG pressure transmitter fails low.
Time Position Applicant's Actions or Behavior CBOT Announce annunciators: 2K04-A4 CH A RPS/ESF/PRETRIP/TRIP 2K04 B3 PPS TRIP 2K04-E4 MSIS PRETRIP Compare all four channels and report 2PI-1041-2 indicates 0 psia.
CRS Implement Annunciator Corrective Action AOP 2203.012D. Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.6.
CBOR Report 'A' SG pressure low pretrip and trip.
CBOT Place the following channels in bypass on Channel B: A SG pressure low - RPS (Bistable 11)
CBOR Verify annunciator 2K04-C3 PPS CHANNEL BYPASSED Verify correct channels in bypass.
CRS Contact maintenance to repair 2PT1041-2.
Simulator Operator Cue: When contacted as WWM, work week manager, of I&C need to troubleshoot and repair 2PT1041-2. Report that planning on repair of 2PT1041-2 is in progress. Termination criteria: When 'B' plant protection system points 11, 19 and 20 are bypassed or at discretion of lead examiner.
Appendix D Scenario 2 Form ES-D-1 Page 8 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
'A' Main Feed Pump Trip. The CRS will enter the loss of MFP AOP, 2203.027.
Time Position Applicant's Actions or Behavior CBOT Announce 'A' MFP trip alarms:
2K03 A8, 'A' MFP trip 2K03 K8, Thrust Bearing Wear Trouble CRS Enter 2203.027, Loss of Main Feed Pump AOP and direct the
following actions:
Verify Recirc valves closed (Condensate and MFP)
Verify Main Feed water regulating valve bypasses are
opening Start standby condensate pump
Commence emergency boration using exhibit 1 Reduce MTG load to establish Feed water Flow > Steam Flow
while maintaining T C < 554.7°F Secure Emergency boration when Feed water Flow > Steam
Flow
CBOT Check tripped MFW pump reci rc and Condensate recirc closed.
Check MFWRV B/P valves open.
Start standby Condensate Pump.
Reduce MTG load to establish Feed water Flow > Steam Flow
while maintaining T C < 554.7°F.
CBOR Commence boration using Exhibit 1.
Appendix D Scenario 2 Form ES-D-1 Page 9 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
'A' Main Feed Pump Trip. The CRS will enter the loss of MFP AOP, 2203.027.
CRS When FF>SF, direct CBOR to commence down power to <
90% using normal boration method.
CBOR Align normal boration to RCS.
Reduce turbine load to maintain Tave within 2° of Tref until power is less than 90%.
Termination criteria: When CBOR has completed reactivity manipulations or at discretion of lead examiner.
Appendix D Scenario 2 Form ES-D-1 Page 10 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Main Feed line break inside containment on 'A' SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.
ALL Announce that 'A' SG level is lowering. Containment temperature and pressure are rising. Announce that radiation levels in containment are steady. Announce that containment sump level is rising quickly. Diagnose that a feed line leak is in progress inside containment.
CRS Direct CBOR to manually trip the reactor.
CBOR CBOR manually trip the reactor.
CRS Implement Standard Post Trip Actions, track safety functions, and direct board operators actions.
CBOR Check reactivity control:
Reactor power decreasing.
All CEAs inserted. CBOT Check maintenance of vital auxiliaries:
Main turbine tripped. Generator output and exciter breakers open.
All 4160 v and 6900 v Non-Vital busses energized. ALL 4160 v and 480 v vital AC bus energized.
All 125 v vital DC bus energized.
Appendix D Scenario 2 Form ES-D-1 Page 11 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Main Feed line break inside containment on 'A' SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.
Time Position Applicant's Actions or Behavior CBOR Check inventory control: PZR level 16 to 80%.
Trend from set point. Report SIAS actuated or manually actuate and verify all PZR heaters off when PZR level less than 29%.
CBOR Check RCS pressure control: RCS pressure 1800 to 2300 psia.
Trend from set point Secure Two RCP's when RCS pressure is less than 1400 psia. Place spray valve for secured RCPs in manual closed. Verify SIAS when pressure less than 1650 psia.
CBOR Check core heat removal by forced circulation:
RCP 's running Loop T less than 10 F. RCS MTS 30 F or greater. Service water pump suction aligned to Lake. Component cooling water aligned to RCPs.
CBOT Restore SW to ACW per Exhibit 5. (NOTE: This action requires several minutes)
Check SIAS actuated.
Maintain SW pressure greater than 85 psig. Restore CCW to RCP's using exhibit 5 (when CIAS actuates).
Appendix D Scenario 2 Form ES-D-1 Page 12 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Main Feed line break inside containment on 'A' SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.
Time Position Applicant's Actions or Behavior CBOT Check RCS Heat Removal: Report SG levels and main feed water is in RTO. Report feed water line is NOT intact. Report SG pressures 'A' SG lower than 'B' SG. Manually actuate EFAS, Emergency Feed water Actuation Signal if not already actuated.
Verify that MSIS is actuated. Verify Feed water is not aligned to 'A' SG CBOR Check CNTMT parameters:
Temperature greater than 140 F. Pressure greater than 16 psia. Status of radiation alarms: CAMS (2K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT in alarm Secondary Sys Radiation Hi (2K11-A10) NOT in alarm Secure ALL RCP's when Containment Spray Actuation Signal (CSAS) occurs.
CRS Notify SM to perform the following: SE report to control room. Announce reactor trip on plant page. Refer to Tech Specs and EALs.
Appendix D Scenario 2 Form ES-D-1 Page 13 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Main Feed line break inside containment on 'A' SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.
CRS Direct CBOs to acknowledge all control room annunciators and announce all significant alarms. Diagnose EXCESS STEAM DEMAND EOP.
CRS Implement EXCESS STEAM DEMAND EOP procedure and open place keeping page.
ALL Perform crew brief and review floating steps.
CRS Determine applicable floating steps: Control post steam generator blow down RCS temperature and
pressure CRS Direct the following actions:
Isolate 'A' SG using Attachment 10.
Control post steam generator blow down RCS temperature using 'B' steam generator upstream atmospheric dump valve.
Control PZR pressure within P-T limits using Auxiliary Spray valve and Attachment 27.
Override HPSI when conditions are met.
RCS MTS 30°F or greater. PZR level greater than 29% [50%] and controlled. RVLMS LVL 03 or higher elevation indicates WET.
At least ONE intact SG available for Heat Removal
Appendix D Scenario 2 Form ES-D-1 Page 14 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Main Feed line break inside containment on 'A' SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.
Time Position Applicant's Actions or Behavior Critical Step CBOT Control post Steam Generator blow down RCS temperature using upstream atmospheric dump valve within 25°F of 'A' Steam Generator Tc when generator boiled dry.
Critical Step CBOR Maintain Post steam generator blow down PZR pressure using auxiliary spray valve and attachment 27 within the Pressure-
Temperature limits of 200°F and 30°F.
CBOR /CBOT Override HPSI flow and charging flow to maintain PZR level.
Termination criteria: When plant temperature and pressures are stabilized after 'A' Steam Generator boils dry or at the discretion of the lead examiner.
Appendix D Scenario 2 Form ES-D-1 Page 15 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event
Description:
'B' Containment Spray pump, 2P35B fails to automatically start. CBOT will manually start the 'B' containment spray pump.
Time Position Applicant's Actions or Behavior CBOT Reports that no flow is indicated on 2C16 for containment spray flow after actuation. Reports that 'B' containment spray pump is not running Reports that the 'B' containment spray containment isolation valve
is open.
Reports Alarm on 2K05 A1, 2P35B failure on ESFAS, Engineered Safety Features Actuation System
CRS Directs manual start of 2P35B, 'B' containment spray pump.
Critical Step (Either start of 2P35B or actuate CSAS 1) CBOT Manually starts 2P35B, 'B' containment spray pump on 2C16. Verifies proper containment spray flow on 2C16.
Termination criteria: 2P35B is manually started or at the discretion of the lead examiner.
Appendix D Scenario 2 Form ES-D-1 Page 16 of 16 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
Channel 1 Containment Spray actuation signal (CSAS-1) fails to automatically actuate.
Time Position Applicant's Actions or Behavior CBOR Observes that containment pressure is greater than 23.3. psia and containment spray actuation signal (CSAS)
(Note this may be completed prior to reaching the 23.3 psia set
point.)
CRS Directs manually actuating CSAS.
Critical Step (Either start of 2P35B or actuate CSAS 1) CBOR On 2C03 manually actuates CSAS and verifies all four operator insert red lights are out above the CSAS label on 2C03.
Termination criteria: When CSAS is manually actuated or at discretion of lead
examiner.
Appendix D Scenario 3 Form ES-D-1 Page 1 of 14 Facility: ANO-2 Scenario No.: 3 Op-Test No.: 2005-1 Page 1 Examiners: Operators:
Initial Conditions: 100% MOL, All ESF systems in standby. Green Train Maintenance Week.
Turnover: 100%. 250 EFPD. EOOS indicates 'Minimal Risk. Green Train Maintenance Week.
Event No. Malf. No. Event Type* Event Description 1 XCV2LT4861 I (CBOR) VCT level instrument fails low resulting in RWT being aligned to CCP suction.
2 XFW2FIS0735 I (CBOT) 'A' MFP suction flow transmitter fails low. Results in condensate and MFP recircs to condenser opening fully and reducing feed water to SG's.
3 CNDVACUUM R (CBOR) N (CBOT) Air leakage into condenser requiring a power reduction to maintain condenser vacuum.
4 CNDVACUUM M (ALL) Air leakage into condenser results in loss of condenser vacuum and turbine and reactor trip.
5 SU#3 lockout 2A111 fails to close N (CBOT) I (CBOR) Loss of offsite power. Must energize non-vital busses. Startup #2 to 2A1 fails OPEN. Loss of power to PZR controllers must be controlled manually or transfer to automatic.
6 2CV1503-1 fails to open C (CBOT) #1 EDG service water outlet MOV. This will result in deenergizing red train vital 4160VAC, 2A3, and 480VAC, 2B5.
7 2CV0340-2 breaker trips C (CBOT) 'A' EFW pump steam inlet valve fails to open. This will result in a loss of all feed water. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario 3 Form ES-D-1 Page 2 of 14 Scenario #3 Objectives 1) Evaluate individual response to a failure of Volume Control Tank level transmitter. 2) Evaluate individual response to a failu re of a Main Feed Pump suction Flow transmitter. 3) Evaluate individual response to a small condenser vacuum leak. 4) Evaluate individual ability to perform a reduction in plant power. 5) Evaluate individual ability to mitigate a loss of all Feed Water. 6) Evaluate individual ability to mitigate a loss of off site power. 7) Evaluate individual response to a failure Loss of power to a vital bus.
SCENARIO #3 NARRATIVE Simulator session begins with the plant at 100% power steady state.
When the crew has completed their control room walk down and brief, one of the two volume control tank (VCT) level transmitters will fail low. The crew will respond to VCT low low level alarm, 2K12 G5. This will result in the VCT outlet valve to the charging pump suction to close and the Refueling Water tank (RWT) suction to the charging pumps to open. RCS temperature and pressure will lower until the CBOR positions the VCT outlet valve manually opened and the RWT valve manually closed.
About 10 minutes after VCT level transmitte r failure, 'A' main feed pump suction transmitter will fail low. This will result in 2K03-D9 (A MFP SUCT FLOW LO) alarm. This will result in both the 'A' MFP and 'A' / 'C' condensate pump recirc valves opening. This will reduce Main feed water flow to 'A' Steam Generator and reduce MFP suction pressure so that the standby condensate pump will automatically start. The CBOT will recognize the instrument failure due to flow on the 'A' MFP c ontroller indicating zero even with the recirc valve open and flow indicated on the Feed water flow transmitters to the steam generator. The CBOT will take manual control of both the MFP and condensate pump recirc valves
and close them.
About 10 minutes after the MFP suction flow instrument failure, air in-leakage into the main condenser will start. This will result in condenser vacuum slowly degrading. The CRS will enter OP 2203.019, Loss of condenser va cuum. The CBOR will begin an emergency boration and the CBOT will reduce main turbine load to restore condenser vacuum. The crew will secure emergency boration and reducing turbine load when vacuum stabilizes. The CBOR will then commence normal boration and reduce turbine load to allow condenser vacuum to be restored to less than ~6.5 in Hg.
Once the Reactor operator's reactivity manipulations are complete, the air in-leakage will be raised to beyond the vacuum pumps capacit y and the plant will be manually tripped.
Upon the reactor trip, Start up transformer #3 will lock-out and startup transformer #2 feeder to 2A1 will fail resulting in a loss of off-site power. When #1 ED G starts, the service water value from the EDG will fail to open. This will result in the CRS directing the #1 EDG to be locally secured resulting in a loss of th e red train vital power (2A3 and 2B5). Also, the CRS will direct selecting channel #2 PZR level and pressure control channel instrumentation due to a loss of power to the selected channel #1 instruments.
Appendix D Scenario 3 Form ES-D-1 Page 3 of 14 SCENARIO #3 NARRATIVE (continued)
When an Emergency Feed water Actuation Signal (EFAS) occurs and 'A' emergency feed water pump attempts to start automatically start, the steam inlet valve, 2CV 0340-2, will trip its breaker when it starts to open. This will result in a loss of all feed water to the steam generators. The CRS will direct that at least one RCP in each loop are secured and Steam Generator blowdown is isolat ed from both steam generators.
When standard post trip actions, SPTA's, are complete, the CRS will diagnose and enter the Loss of Feed EOP OP2202.006. The CBOT will manually start t he Alternate AC Gener ator from 2C14 and energize 2A3, vital 4160 bus or open the Servic e water valve from the #1 EDG and start #1 EDG. Once 2A3 is energized the CBOT wil l manually start the emergency feed water pump, 2P7B, from 2C17 and align feed to bo th steam generators using the Emergency Feed water valves.
Appendix D Scenario 3 Form ES-D-1 Page 4 of 14 Simulator Instructions for Scenario 3 Reset simulator to MOL 100% power IC stead state.
Ensure that AACG is secured and annunciators clear.
Ensure hotwell level is ~80%. Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11. T1, T2, T3, T4, T5 set to false.
T4 set to RXTRP T6 set to EFAS-1 T7 set to EFAS-2 Event No. Malf. No. Value/
Ramp Time Event Description 1 XCV2LT4861 Trigger=T1 0.0 VCT level instrument fails low resulting in RWT being aligned to CCP suction. 2 XFW2FIS0735 Trigger=T2 0.0 'A' MFP suction flow transmitter fails low. Results in condensate and MFP recircs to condenser opening fully and reducing feed water to SG's. 3 CNDVACUUM Trigger=T3 4.6 Ramp 4 min Air leakage into condenser requiring a power reduction to maintain condenser vacuum. 4 CNDVACUUM 10.0 Ramp 5 min Air leakage into condenser results in loss of condenser vacuum and turbine and reactor trip.
5 FailSU3 416A111
Trigger=T4 TRUE Locked-Open Startup 3 lockout results in a loss of offsite power.
Causes EDGs to automatically start/ loose Aux feed water pump and non-vital loads. Loss of power to PZR controllers must be controlled manually or transfer to automatic.
6 CV15031 Trigger=T5 0.0 #1 EDG service water outlet MOV fails to open. This will result in deenergizing red train vital 4160VAC, 2A3, and 480VAC, 2B5. 7 CV0340 Trigger=T6 Trigger=T7 0.0 'A' EFW pump steam inlet valve fails to open. This will result in a loss of all feed water.
Appendix D Scenario 3 Form ES-D-1 Page 5 of 14 At T=0 Trigger T1 VCT level instrument fails low, 2LT4861.
Cue: Report that I & C planner will begin planning work on failed Volume control tank, VCT, level transmitter.
At T= 10 minutes Trigger T2 'A' MFP suction flow transmitter fails low, 2FIS0735. Cue: Report that I & C planner will begin planning work on failed 'A' MFP suction flow transmitter.
At T=20 minutes Trigger T3 Air leakage into condenser requiring a power reduction to maintain condenser vacuum. Cue: As Auxiliary Operator, report that air in-leakage is from 'B' Low pressure turbine west manway cover and you will need mechanical maintenance support to seal the leak.
Cue: As mechanical maintenance report that it will take from 20 to 30 minutes to repair the leak.
CUED by Lead Examiner Raise air leakage into condenser to 10 ramped over 5 minutes.
Cue: After 5 minutes, report as mechanical maintenance report that the manway gasket on 'A' LP turbine has catastrophically failed.
Main turbine trip T4 SU#3 lockout and failure of SU#2 feeder to 2A1 to close, 2A111.
PZR control channel level and pressure controllers will fail to manual on power transfer to #1 EDG and must be transferred to Channel 2 on loss of #1 EDG.
- 1 EDG start T5 #1 EDG service water outlet MOV fails to open, 2CV 1503-1. EFAS-1 T6 'A' EFW pump steam inlet valve fails to open, 2CV 0340-2.
Appendix D Scenario 3 Form ES-D-1 Page 6 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
VCT level transmitter 2LT4861 fails low. This causes the RWT to be aligned to CCP suction and Tave lowering.
Time Position Applicant's Actions or Behavior CBOT Announce annunciator 2K12-G5 VCT 2T4 LEVEL LO LO.
CRS Implement Annunciator Corrective Action AOP 2203.012L.
CBOR Report level indicates normal on 2LIS-4857 but 2LT-4861 reads 0% on computer. Reports charging pump suction swapping to RWT.
CBOR May secure charging to stop boration if have not determined indication is a failed instrument and VCT level is normal. OR When faulty instrument identified, then manually reopen VCT outlet and close the RWT to CCP suction valve.
CBOT /CBOR Reduce turbine load to maintain Tave within 2 F of Tref if Tave lowered. CRS Contact maintenance/PS liaison to troubleshoot failed instrument.
Simulator Operator Cue: When contacted as IC or Work Week Manager, report that you will begin planning work on 2LT-4861.
Termination criteria: Charging suction manually aligned to the VCT and RWT to CCP valve closed or at the discretion of the lead examiner.
Appendix D Scenario 3 Form ES-D-1 Page 7 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event
Description:
2FIS0735, 'A' loop condensate flow fails low. Condensate and MFP recirc valves open. CBOT must take manual control of recircs and control MFP suction pressure.
Time Position Applicant's Actions or Behavior CBOT Announce annunciator 2K03-D9 (A MFP SUCT FLOW LO)
CRS Implement Annunciator corrective action 2203.012C and direct board operator actions.
CBOT Report auto start of condensate pump. Determine instrument 2FIS-0735 failure by use of PMS or control board indications. Place "A" condensate recirc and "A" main feed pump recirc valves in manual to control condensate header pressure. Secure condensate pump that auto started.
(Examiners Note: Crew may elect to leave fourth condensate pump running until a later point in the shutdown.)
CRS Contact maintenance/WWM to investigate failed transmitter.
Simulator Operator Cue: When contacted as WWM, work week manager, of I&C need to troubleshoot and repair 2FIS 0735. Report that planning on repair of 2FIS0735 is in progress. Termination criteria: When condensate and MFP recircs are in manual and secondary plant is stable or at discretion of lead examiner.
Appendix D Scenario 3 Form ES-D-1 Page 8 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
Condenser vacuum slowly degrades. Crew will reduce turbine load Time Position Applicant's Actions or Behavior CBOT Main Condenser lowering vacuum: 2K03 A3, 2E11A Pressure HI 2K03 B3, 2E11A Turb Hood Press HI
2K03 E4, Vacuum pump 2C5B Auto Start 2K02 B14, Condenser Interlock
CRS Enter 2203.019, Loss of condenser vacuum and direct the following actions:
Verify both vacuum pumps running
Verify adequate gland seal steam pressure
Verify both circulating water pumps running Reduce MTG load to maintain Tc less than 554.7°F and condenser vacuum < 6.5 inHg.
Commence emergency boration using exhibit 1 Secure Emergency boration when condenser vacuum is < 6.5
inHg.
CBOT Reduce MTG load to maintain Tc less than 554.7°F and condenser vacuum < 6.5 inHg.
CBOR Commence boration using Exhibit 1.
Appendix D Scenario 3 Form ES-D-1 Page 9 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
Condenser vacuum slowly degrades. Crew will reduce turbine load CRS When vacuum is less than 6.5 inHg. Secure emergency boration.
Contact Ops Management.
Simulator Operator Cue: When contacted as AO report that you can hear the air leak on the vacuum suction piping on the East heater deck under the deck floor. It is
unisolatable.
Simulator Operator Cue: When contacted as Maintenance, report that it will take at
least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to patch the leak.
Simulator Operator Cue: When contacted as OPS Management, tell the CRS to reduce plant power until vacuum alarms are cleared.
CRS Direct CBOR to reduce commence a normal boration at power and reduce turbine load to < 5 inHg (to clear alarms).
CBOR Align normal boration to RCS.
Reduce turbine load to maintain Tave within 2° of Tref until condenser vacuum is less than 5 inHg.
Termination criteria: When CBOR has completed reactivity manipulations or at discretion of lead examiner.
Appendix D Scenario 3 Form ES-D-1 Page 10 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
Condenser air in-leakage exceeds the capacity of the vacuum pumps.
This results in a reactor trip.
ALL Announce that condenser vacuum is degrading.
CRS Direct CBOR to manually trip the reactor.
CBOR CBOR manually trip the reactor.
CRS Implement Standard Post Trip Actions, track safety functions, and direct board operators actions.
CBOR Check reactivity control:
Reactor power decreasing.
All CEAs inserted. CBOT Check maintenance of vital auxiliaries:
Main turbine tripped. Generator output and exciter breakers open. All 4160v and 6900 v Non-Vital busses NOT energized.
All 4160v and 480v vital AC bus energized. (see event 6)
All 125v vital DC bus energized.
Appendix D Scenario 3 Form ES-D-1 Page 11 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
Condenser air in-leakage exceeds the capacity of the vacuum pumps. This results in a reactor trip.
Time Position Applicant's Actions or Behavior CBOR Check inventory control: PZR level 16 to 80%. Trend to set point. (See event 5/6)
CBOR Check RCS pressure control: RCS pressure 1800 to 2300 psia. Trend to set point CBOR Check core heat removal by forced circulation:
RCP 's running Loop T less than 10 F. RCS MTS 30 F or greater. Service water pump suction aligned to Lake.
Component cooling water aligned to RCPs. SW to aligned to CCW and ACW
CBOT Check RCS Heat Removal: Report SG levels Main feed water is secured.
Manually actuate EFW. Report feed water line is NOT intact. Report SG pressures Shut both MSIV's due to 2CV 0400 and 2CV 0460, Main Steam to the moisture separator reheaters, have no power and are open.
Appendix D Scenario 3 Form ES-D-1 Page 12 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
Condenser air in-leakage exceeds the capacity of the vacuum pumps.
This results in a reactor trip.
Time Position Applicant's Actions or Behavior CBOR Check CNTMT parameters: Temperature less than 140 F. Pressure less than 16 psia. Status of radiation alarms: CAMS (2K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT in alarm Secondary Sys Radiation Hi (2K11-A10) NOT in alarm CRS Notify SM to perform the following: SE report to control room. Announce reactor trip on plant page. Refer to Tech Specs, 3.0.3 due to no emergency feedwater available and 3.8.1.1 action C.
Termination criteria: CRS has diagnosed a Loss of All Feed event and transitions to EOP or at discretion of lead examiner.
Appendix D Scenario 3 Form ES-D-1 Page 13 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and 6 Event
Description:
Startup transformer #3 lockout and feeder breaker from Startup transformer #2 to 2A1, non-vital 4160VAC bus fails to open. This will result in a loss of offsite power and automatic start of both emergency diesel generators (#1 and #2 EDG).
CRS Verify Service Water is aligned to #1 EDG and #2 EDG.
CBOT Report that service water is not aligned to #1 EDG and that service water is aligned to #2 EDG and is running with proper voltage.
CRS Direct that AO locally take #1 EDG to lockout.
CRS Direct CBOR to select channel 2 PZR level and pressure controllers.
CBOR Select channel 2 PZR level and pressure controllers and places them in automatic.
Termination criteria: When CBOR has selected channel 2 PZR level and pressure controllers or at discretion of lead examiner.
Appendix D Scenario 3 Form ES-D-1 Page 14 of 14 Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event
Description:
Failure of 'A' Emergency Feed water pump to start due to a failure of the steam admission valve, 2CV-0340-2, to open. This will result in a loss of all feed water and the crew will reenergize 2A3 and start 2P7B, 'B' emergency feed water pump and restore feed to the steam generators.
Time Position Applicant's Actions or Behavior CRS Direct the following from the Loss of All Feed water EOP: Refer to Standard attachment 11 and direct the CBOT to manually start the Alternate AC Generator and energize 2A3.
Direct the CBOT to manually start 2P7B and restore feed water to both steam generators at < 150 GPM for five minutes or until level rise is observed.
Simulator Operator Cue: When contacted as WCO, to open the service water from #1 EDG isolation valve. Report that the hand-wheel spins freely and valve will not move.
Critical Step CBOT Manually starts the Alternate AC Generator and energizes 2A3.
Critical Step CBOT Manually starts 'B' Emergency Feed Pump and restores feed water to both steam generators.
CBOR Monitor control Steam generator pressures less than main steam safety valve lift set point (~1078 psig). Control PZR pressure using auxiliary spray less than 2500 psia.
Termination criteria: When Emergency Feed water is established to both Steam Generators or at the discretion of the lead examiner.