ML050690390

01-2005 - Draft Operating Exam

ML050690390
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: ML050690390 (176)

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.

20. Verify 2A3-2A4 Tie Breaker (2A-310) OPEN.

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.

(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.

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-A D MIN supervisor re v i e w o f 2107.001 sup. 4 PAGE 5 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E 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#: KA VALUE RO: 3.9 SRO: 4.0 KA

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, 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 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Chemistry has just notified the Control 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" given in initial conditions.

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#: KA VALUE RO: 3.9 SRO: 4.0 KA

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 transposed 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 Control 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-ADMI N-Sur v eillance re v i e w 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-ADMI N-Sur v eillance re v i e w 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 Vi bes 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-ADMI N-Sur v eillance re v i e w 2P89B PAGE 3 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E Initiating CUE:

The Co ntrol Room Su perv i sor/Shift Man ager di re cts d e te rmin ation of the opera b i lity of the 'B' HPSI pump, 2P89B, by reviewing the completed su rveillance data OP 2104.03 9 Supplem en t 2, complete all reviews for operability, calcul ation s pe rforme d and i dentify all errors.

CRITI CAL S T EPS: 2, 3, 4, 5 START TIME:

PERFO RMA NCE CHE C K L IST STA NDA RD C I R C L E ON E NOTE: Provi de a marke d-up co py of Suppl eme n t 2, 2P-89B qua rte r ly test 1. Perform review of the surveillance pro c ed ure re sults. Revie w s the surveill an ce p r ocedu re provide d. N/A (C) 2. Pump P is out of LIMITING RANGE FOR OPERABILITY.

Pump D/P is out of LIMITING RA NGE FOR OPE R ABILITY. N/A SAT UN SAT (C) 3. Cal c ulation fo r determining lowe r pump P lim it is in error.

Cal c ulation fo r determining lowe r pum p P limit should be 1380.8 1 p s id. N/A SAT UN SAT (C) 4. Inboard Ra di al Bearin g #1 Vibes is out of LIMITING RA NG E FOR OPERABILITY.

Inboard Ra di al Bearin g #1 Vibes is out of LIMITING RA NGE FO R O PERABILITY.

N/A SAT UN SAT (C) 5. Outboa rd Be aring AXIAL Vibes is out of LIMITING RA NGE FOR OPERABILITY.

Outboa rd Be aring AXIAL Vibes is o u t of LIMITING RA NGE FO R O PERABILITY.

N/A SAT UN SAT EXAMIN E R's CUE: The Shift Engineer w ill enter th e pump data into the data base. 6. Rep o rt to CRS that the results of the surveill an ce are un sati sfacto ry and 2P89B i s inoperable.

Rep o rts to CRS that results of the surveill an ce a r e un satisfa c t o ry and 2P89B is ino pera b le. N/A SAT UN SAT END STOP TIME:

JPM-ANO-2-JPM-ADMI N-Sur v eillance re v i e w 2P89B PAGE 4 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E EXAMINER's CO PY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipm ent 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-ADMI N-Sur v eillance re v i e w 2P89B PAGE 5 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E EXAMINEE's CO PY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipm ent 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./W ORK P L A N N O. 2104.0 39 PROCED URE/W ORK P L A N TIT L E: HPSI SYSTE M OPERATI O N PA G E: 61 of 14 8 CH A N GE: 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.

R e c o r d d a t e a n d t i m e T e s t b e g i n s T O D A Y's D A T E / 0 8 0 0 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 Amps N/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 R e c o r d d a t e a n d t i m e T e s t c o m p l e t e d T O D A Y's D A T E 0 9 3 0 V i b r a t i o n I n s t r u m e n t C a l D u e D a t e 7 d a y s f r o m T O D A Y V i b r a t i o n D a t a C o l l e c t e d B y E d d y E l e c t r i c i a n Note 1: For RWT temperature (T), minimum acceptable pump P is: 1372.9 + 20.41 (Instrument error) - [(T-40)/4] psid Minimum P = 1 3 9 3.3 1 - [( 9 0 - 4 0)/4] = 1 3 6 0.8 1 psid 3.2 Independently verify pump P calculation.

JJB PROC./W ORK P L A N N O. 2104.0 39 PROCED URE/W ORK P L A N TIT L E: HPSI SYSTE M OPERATI O N PA G E: 62 of 14 8 CH A N GE: 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 ____________________________________________ Date __________

____________________________________________

PROC./W ORK P L A N N O. 2104.0 39 PROCED URE/W ORK P L A N TIT L E: HPSI SYSTE M OPERATI O N PA G E: 63 of 14 8 CH A N GE: 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?

YES NO 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.)

YES NO N/A 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?

YES NO Supervisor ______________________________________________ Date __________

JPM-ANO-2-JPM-ADMI N-Sur v eillance re v i e w 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-ADMI N-Sur v eillance re v i e w 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 Vi bes 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-ADMI N-Sur v eillance re v i e w 2P89B PAGE 3 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E Initiating CUE:

The Shift Manage r direct s "pe r form sup e rviso r revie w and a nalysi s of the 'B' HPSI pump, 2P89B, by reviewin g and ide n tifying all errors on the complete d surveill an ce data OP 210 4.039 Suppl e m ent 2." CRITI CAL S T EPS: 2, 3, 4, 5, 6, 7 START TIME:

PERFO RMA NCE CHE C K L IST STA NDA RD C I R C L E ON E NOTE: Provi de a marke d-up co py of Suppl eme n t 2, 2P-89B qua rte r ly test 1. Perform sup e r viso r revie w of the surveill an ce p r ocedu re results and determi ne errors.

Revie w s the surveill an ce a c ceptan ce crite r ia provid ed. 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 RA NGE FOR OPE R ABILITY. N/A SAT UN SAT (C) 3. Cal c ulation fo r determining lowe r pump P lim it is in error.

Cal c ulation fo r determining lowe r pum p P limit should be 1380.8 1 p s id. N/A SAT UN SAT (C) 4. Inboard Ra di al Bearin g #1 Vibes is out of LIMITING RA NG E FOR OPERABILITY.

Inboard Ra di al Bearin g #1 Vibes is out of LIMITING RA NGE FO R O PERABILITY.

N/A SAT UN SAT (C) 5. Outboa rd Be aring AXIAL Vibes is out of LIMITING RA NGE FOR OPERABILITY.

Outboa rd Be aring AXIAL Vibes is o u t of LIMITING RA NGE FO R O PERABILITY.

N/A SAT UN SAT (C) 6. Identify the te chni cal spe c if ication appli c ability erro

r. Identifies TS 3.5.2 appli c a b ility. N/A SAT UN SAT (C) 7. Identified that YES was circled on para m eters that did not meet accepta n ce criteria.

Identifies that YES was circled on para m eters that did not meet accepta n c e criteria.

N/A SAT UN SAT EXAMIN E R's NOTE: The c andidate will probably require ano ther R O to review th e data table b e fore proceed ing. Ask the candidate to contin ue on with completing section 4.0 as tho ugh tha t revie w matched th e same errors previously ide n tified. 8. Inoperable e q u ipment che c klist need ed. EXAMINER's CUE: The SRO A D MIN will perform the inope rabl e eq uipment che c klist. Identifies ne e d to perform inope rabl e equipm ent ch ecklist mu st b e compl e ted. N/A SAT UN SAT 9. Con d ition Re port nee ded. EXAMINER's CUE: The SE will initiate the condition repo rt. Identifies ne e d to generate conditio n repo rt. N/A SAT UN SAT END STOP TIME:

JPM-ANO-2-JPM-ADMI N-Sur v eillance re v i e w 2P89B PAGE 4 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E EXAMINER's CO PY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipm ent 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 analys is of the 'B' HPSI pump , 2P89B, by reviewing a nd identifying all erro rs on the completed surveilla nce d a ta OP 2104.039 Supplement 2."

JPM-ANO-2-JPM-ADMI N-Sur v eillance re v i e w 2P89B PAGE 5 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E EXAMINEE's CO PY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipm ent 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 analys is of the 'B' HPSI pump , 2P89B, by reviewing a nd identifying all erro rs on the completed surveilla nce d a ta OP 2104.039 Supplement 2."

PROC./W ORK P L A N N O. 2104.0 39 PROCED URE/W ORK P L A N TIT L E: HPSI SYSTE M OPERATI O N PA G E: 61 of 14 8 CH A N GE: 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.

R e c o r d d a t e a n d t i m e T e s t b e g i n s T O D A Y's D A T E / 0 8 0 0 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 Amps N/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 R e c o r d d a t e a n d t i m e T e s t c o m p l e t e d T O D A Y's D A T E 0 9 3 0 V i b r a t i o n I n s t r u m e n t C a l D u e D a t e 7 D a y s f r o m T O D A Y V i b r a t i o n D a t a C o l l e c t e d B y E d d y E l e c t r i c i a n Note 1: For RWT temperature (T), minimum acceptable pump P is: 1372.9 + 20.41 (Instrument error) - [(T-40)/4] psid Minimum P = 1 3 9 3.3 1 - [( 9 0 - 4 0)/4] = 1 3 6 0.8 1 psid 3.2 Independently verify pump P calculation.

JJB PROC./W ORK P L A N N O. 2104.0 39 PROCED URE/W ORK P L A N TIT L E: HPSI SYSTE M OPERATI O N PA G E: 62 of 14 8 CH A N GE: 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 ________________________________________________________________

________________________________________________________________

________________________________________________________________

________________________________________________________________

P e r f o r m e d B y S a m m y R e a c t o r D a t e T O D A Y Jimmy Reactor

PROC./W ORK P L A N N O. 2104.0 39 PROCED URE/W ORK P L A N TIT L E: HPSI SYSTE M OPERATI O N PA G E: 63 of 14 8 CH A N GE: 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?

YES NO 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.)

YES NO N/A 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?

YES NO Supervisor ______________________________________________ Date __________

JPM-ANO-2-JPM-ADMI N-RWP an d sta y t i mes 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-ADMI N-RWP an d sta y t i mes 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-ADMI N-RWP an d sta y t i mes PAGE 3 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E Initiating CUE:

The Shift Manage r direct s that Service water from lo op I must be aligne d to the SFP, use the Emergen cy Radi ologi cal Wo rk Pe rmit, RWP, an d identify the maxi mum allowa ble time before you woul d be req u ired to leave the Auxiliary Building 354' elevatio n SFP valve ga llery, exclu d ing entry an d exit times to and from th e area. Critical Steps:

2 , 3, 4, 5, 6 START TIME:

PERFO RMA NCE CHE C K L IST STA NDA RD C I R C L E ON E NOTE: Provi de Emerg e n cy RWP. EXAMINER's CUE: T he ca ndidate may attempt to ch eck out a radi at ion su rvey meter pe r mo nitoring step 7.0. It is not a part o f this JPM to che c k out the survey mete r, but that the can d idate kn ows one i s ne eded. 1. Revie w Emergen cy RWP f o r limits. Determine s that the alarmi ng do simete r is set to ala r m in an 800m r/hr field an d that the Dose alarm is set at 800 mrem.

N/A (C) 2. Determine s t ay time in SFP valve gallery to be a maximum o f 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Usi ng the stat us bo ard p r int out provide d determi ned th at the Gene ra l Area (GA

) field is 500 M R/HR so the maximum sta y 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 UN SAT EXAMIN E R's NOTE: The r est of these steps determine the cand i date's ab ilit y to enter and exit contr o lle d access corre ctl y us ing th e Actual RWP for inspect ions , DO NO T allo w the c a ndidate to u se the e m erg e nc y RWP to ente r contro lled access. (C) 3. Determine d that an alarmi ng dosim eter will be requi re d for entry into the Radi ologi call y Controlled Area, RCA, u s ing the norm a l inspe c tion RWP.

Obtaine d an alarmi ng do si meter from rac k. N/A SAT UN SAT (C) 4. Entered a ppropriate info rm ation into the log in screen a nd su ccessfully entere d the RC A. Entered the RCA un de r the gene ral ins p ec tion RWP.

N/A SAT UN SAT (C) 5. While in the RCA the exa m inee observe s and adheres to al l appli c able p o s ting s and e n t ry requi rem ents. While in the RCA the exa m inee ob se rv es and ad heres t o all appli c abl e postin g s and entry req u irem ents. N/A SAT UN SAT (C) 6. Whe n exiting the RCA the examinee e n ters the cont ro l point area a nd ent ers a P C M-1 monitor.

Enters a nd e x its PCM-1.

N/A SAT UN SAT 7. All loose mat e rial s will be cleared throug h the tool co ntamin ation monitor (T CM) Examinee pla c e s loo s e ite m s in the TCM for c o unting. N/A SAT UN SAT 8. After clea ring the PCM-1 monitor, the examinee exits through the Portal Monito r Examinee cl e a rs the Po rtal Monitor N/A SAT UN SAT 9. Examinee de activates EA D at final exit of sessi on Examinee de activates hi s EAD and returns it to the Health Phy s ics rack. N/A SAT UN SAT END STOP TIME:

JPM-ANO-2-JPM-ADMI N-RWP an d sta y t i mes PAGE 4 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E EXAMINER's CO PY INITIAL PLANT CONDITIONS

1. Pl ant is D E FU ELED a nd a ll F U E L HA NDLING operations are s e cured. 2. Power has been los t to bot h SF P c o oling pumps and 2K11-K5 "F UEL POOL TEMP HI" is in alarm. 3. A Sit e Area Emer genc y has been dec l ar ed on Unit 2 due to a station blac kout. Power has been r e stor ed to 2A3 and 2B5 from the Alt e r nat e AC G e n e rat o r, AACG. 4. Serv ice wat e r must be alig ned t o the SFP due to boiling and los s of in ventor y through t he tilt pit gat

e. 5. Fuel Pool low le vel alarm is in and SF P level is lowering.

6. RP coverage will NOT be av ailable. 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 SF P valve gallery, excluding entry and exit times to and from the area.

JPM-ANO-2-JPM-ADMI N-RWP an d sta y t i mes PAGE 5 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E EXAMINEE's CO PY INITIAL PLANT CONDITIONS

1. Pl ant is D E FU ELED a nd a ll F U E L HA NDLING operations are s e cured. 2. Power has been los t to bot h SF P c o oling pumps and 2K11-K5 "F UEL POOL TEMP HI" is in alarm. 3. A Sit e Area Emer genc y has been dec l ar ed on Unit 2 due to a station blac kout. Power has been r e stor ed to 2A3 and 2B5 from the Alt e r nat e AC G e nerat o r, AACG. 4. Serv ice wat e r must be alig ned t o the SFP due to boiling and los s of in ventor y through t he tilt pit gat

e. 5. Fuel Pool low le vel alarm is in and SF P level is lowering.

6. RP coverage will NOT be av ailable. 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 SF P 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, 2R E8925-1 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 accept able 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, 2R E8925-1 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-A D MIN Classif y Ev ent EAL PAGE 5 OF 5 ADMI N ISTR ATIVE JOB PERFO RMA NCE MEAS U R E 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, 2R E8925-1 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 6 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 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:

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, containment pr essure < 18.3 psia, PZR pressure > 1650psia. 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 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Perform actions in I nadvertent CIAS, AOP 2203.039, beginning with step 11." CRITICAL ELEMENTS (C):

1, 2, 6, 7, 8 PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 1. 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 and observed trip paths lights on panel above 2C23 lit.

Placed trip path keyswitch to LK and removed key.

N/A SAT UNSAT (C) 2. 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.

N/A SAT UNSAT

3. (Step 12.c) Go to step 14.

Using procedure 2203.039, transition to step 14.

N/A SAT UNSAT

4. 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 above hand switch.

N/A SAT UNSAT JPM- ANO-2-JPM-NRC-AOP2 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

5. 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 above hand switch.

N/A SAT UNSAT (C) 6. 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 above

hand switch.

N/A SAT UNSAT (C) 7. 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 above

hand switch.

N/A SAT UNSAT (C) 8. 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 above

hand switch.

N/A SAT UNSAT

9. 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 above hand switch for 2VCH-1A.

Observed RED light ON above

label for 2HS-3810.

Observed all chilled water alarms

are clear on annunciator 2K13 (Lights slow flashing or clear).

N/A SAT UNSAT EXAMINER's NOTE:

JPM standard does not require completi on of steps past procedure step 15.

END JPM- ANO-2-JPM-NRC-AOP2 PAGE 5 OF 6 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, beginning with step 11."

JPM- ANO-2-JPM-NRC-AOP2 PAGE 6 OF 6 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, beginning with step 11."

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 usi ng BAMT gravity feed to Charging Pump suction beginning with AOP 2203.032, Step 2." CRITICAL ELEMENTS (C): 5, 10, 15 PERFORMANCE CHECKLIST STANDARD (Circle One)

1. 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

2. 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. 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. 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. 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. 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. 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. Verify RWT level greater than 7.5%. On panel 2C16 or 2C17, verified RWT level greater than 7.5%.

N/A SAT UNSAT EXAMINER'S CUE: When asked as CRS which HPSI pump to start, state that 'B' HPSI pump is to be started.

9. Verify 2CV-5631-2 is OPEN.

On panel 2C16 verified RWT outlet

valve 2CV-5631-2 is OPEN.

N/A SAT UNSAT NOTE: If Examinee goes to use OP2104.039 section 9.0 then give the following cue.

EXAMINER's CUE: CRS directs to start 'B' HPSI pump and verify steps in appropriate section in OP 2104.039 after Emergency boration is established. (C) 10. Start 2P89B.

On panel 2C16 rotated handswitch for 2P89B to start postion.

Observed Red light ON and Green light OFF.

N/A SAT UNSAT

11. Verify SDC secured.

On panel 2C16 and 2C17 verified LPSI pumps secured.

N/A SAT UNSAT

12. 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

13. Commence RCS cooldown to allow a makeup rate of 40 GPM.

EXAMINER'S CUE: CRS has verified RCS cooldown rate is sufficient to allow make-up rate greater than 40 gpm. The CRS and CBOR will monitor and control RCS Cooldown.

Verify conditions will allow for a makeup rate of 40 gpm. (Step 12)

N/A SAT UNSAT

14. Use one HPSI train B injection MOV to maintain PZR level.

Opened ONE of the following HPSI injection MOV:

2CV-5016-2 2CV-5036-2 2CV5056-2 2CV-5076-2 Observed Red light ON and Green

light ON above handswitch.

N/A SAT UNSAT JPM- ANO-2-JPM-RO-CVCS010 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One) (C) 15. 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 END 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 av ailable 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 reac tor 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 av ailable 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 reac tor 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

KA VALUE RO: 3.7 SRO: 3.5 KA

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 (case file JPM03 will do all of them):

Set T5 file to 'sprayvlv' this will trigger 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:

The SM/CRS directs: "Equalize RCS and PZR boron concentration using OP 2103.005 step 7.1, RCP 'A' spray valve, 2CV-4651." CRITICAL ELEMENTS (C):

2, 3, 4, 6 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

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 2CV-4655 and 2CV-4656.

N/A SAT UNSAT (C) 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. 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 valve will open 100% and then trip the breaker. (C) 4 Partially open 2CV-4651.

On panel 2C04, took hand switch for 2CV-4651 to the open position when PZR pressure rises. 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. 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. 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 2CV-4656.

N/A SAT UNSAT END STOP TIME:

JPM- ANO-2-JPM-NRC-PZR02 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINER'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 PZ R boron concentration using OP 2103.005 step 7.1, 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 PZ R boron concentration using OP 2103.005 step 7.1, 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

KA VALUE RO: 3.5 SRO: 3.7 KA

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. 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

2. N/A SAT UNSAT (C) 2. Open Supply Header to Containment Isolation (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. 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. 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

on PMS or SPDS computer 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. 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. 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. 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 between 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 between 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#: KA VALUE RO: 4.3 SRO: 4.5 KA

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.

RCS temperature dropped less than 500°F during transient and cooldown has been stopped per step 25.

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. SDBCS 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. 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. 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. 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. 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 (C) 5. 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, but as CRS report that Tc should remain constant until system engineering completes analysis. 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. 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. RCS temperature dropped less than 500°F during transient and cooldown has been stopped per step 25.

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. RCS temperature dropped less than 500°F during transient and cooldown has been stopped per step 25.

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 rev i ew the "Briefing Checklist - Sy stem Walkthrough" portion of OP 1064.023 Attachment 6 w i th the examinee.

J P M INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer.

TASK STANDARD:

Cross connect 480VAC non-v i tal busses 2B1 and 2B2 w i th 2B1 supply i ng and 2B2 supply breakers open. Maintain 2B1 amperage less than 130 amps.

TASK PERFORMANCE AIDS:

OP 2107.001 Section 12.0.

SIMULATOR SETUP:

Any pow er lev e l 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 2B 2 and open 2B2 supply breakers from 2A2 using OP 2107.001 section 12.0." CRITICAL ELEMENTS (C): 2, 3, 4, 6, 7

PERFORMANCE CHECKLIST ST A N D A R D S (C i r c l e O n e) Examiner's note:

If the initial plant conditions are in Mode 3, 4 or 5, then the first step is N/A.

1. Check that Operations Manager approval obtained.

EXAMINER'S CUE:

"The Operations Manager has giv e n 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 follow i ng tw o steps may be completed after cross-connecting the busses. The resolution on the meters is low at the low end. (C) 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. 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 m a lfunctions 480CURR2B1 and 480CURR2B2).

Direc t 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 ST A N D A R D S (C i r c l e O n e) (C) 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. 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. 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. Open normal supply breaker on 2B2. 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.

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.

Observed that the RED light went OFF and the GREEN light went ON. N/A SAT UNSAT

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. Turn sync switch to OFF.

On Panel 2C10, turn sync switch counter clockwise to the OFF position.

N/A SAT UNSAT

ANO-2-JPM-NRC-ELECXT PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST ST A N D A R D S (C i r c l e O n e) 10. 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.

INITIATING CUE:

The SM/CRS directs, "Cross Connect 2B1 and 2B2 and open 2B2 supply breakers 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.

INITIATING CUE:

The SM/CRS directs, "Cross Connect 2B1 and 2B2 and open 2B2 supply breakers from 2A2 using OP 2107.001 section 12.0."

ANO-2-JPM-NRC-BMSRM PAGE 1 OF 7 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 KA VALUE RO: 3.6 SRO: 3.6 KA

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 7 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 7 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." CRITICAL ELEMENTS (C):

4, 6, 10, 11 PERFORMANCE CHECKLIST STANDARDS (Circle One)

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. 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. 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. 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. 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. 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 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

7. 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. Direct WCO to open LRW/BMS Discharge to Circ Water Flume

valve(s) (2CV-2330A).

EXAMINER's CUE:

WCO reports 2CV-2330A is open. Directed WCO to open 2CV-2330A.

N/A SAT UNSAT EXAMINER'S NOTE: Provide the following cue:

EXAMINERs CUE:

Setpoint from Prerelease Report = "3E3".

9. 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) 10. 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) 11. Place 2RE-2330 Selector Switch in PULSE CAL.

EXAMINER's CUE:

Switch in PULSE CAL.

On panel 2C25, placed

2RE-2330 Selector Switch in PULSE CAL.

N/A SAT UNSAT

12. Direct WCO to verify annunciator 2K14-B1 "LIQUID

RADWASTE DISCHARGE RADIATION HIGH" is actuated on Panel 2C112.

EXAMINER's CUE:

2K14-B1 is actuated.

Directed WCO to verify annunciator 2K14-B1 actuated on 2C112. N/A SAT UNSAT ANO-2-JPM-NRC-BMSRM PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

13. Verify annunciator 2K11-J9 BORON MGMT SYS TROUBLE" is actuated on Panel 2C14.

EXAMINER's CUE:

2K11-J9 is actuated.

On panel 2C14, verified 2K11-J9 is actuated on Panel 2C14.

N/A SAT UNSAT 14 Verify annunciator 2K11-C10 "PROC LIQUID RADIATION

HI/LO" is actuated on Panel 2C14. EXAMINER's CUE:

2K11-C10 is actuated.

On panel 2C14, verified 2K11-C10 is actuated on Panel 2C14. N/A SAT UNSAT 15 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 16 Reset 2RE-2330 and place in OPERATE. EXAMINER's CUE:

High Alarm light OFF EXAMINER's CUE:

Switch in OPERATE.

EXAMINER's CUE:

Channel Test light OFF.

On panel 2C25, placed the

Operation Selector switch to RESET. Observed High Alarm light OFF.

Placed the Operation Selector switch to OPERATE.

Observed the Channel Test light

OFF. N/A SAT UNSAT 17 Verify valve(s) tested have reopened.

EXAMINER's CUE:

WCO reports 2CV-2330A open. Directed WCO to verify 2CV-2330A open.

18 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 ANO-2-JPM-NRC-BMSRM PAGE 6 OF 7 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 O perator (WCO) is available at 2C112. Use 2CV2330A to perform release. 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."

ANO-2-JPM-NRC-BMSRM PAGE 7 OF 7 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. Use 2CV2330A to perform release. 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."

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 KA VALUE RO: 3.0 SRO: 3.1 KA

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 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 Shutdow n Cooling Flow using AOP 2203.029 beginning w i th contingency step 13.C." CRITICAL ELEMENTS (C): 2, 6, 9,10 PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify SDC RCS isolation v a lv es open. On panels 2C16 and 2C17, checked indications for:

- 2CV-5038-1

- 2CV-5084-1

- 2CV-5086-2 Observ e d 2CV-5086-2 closed by green light ON, red light OFF abov e hand sw itch. N/A SAT UNSAT (C) 2. Determine that 2CV-5086-2 is shut due to the Auto-Closure Initiation (ACI) and Open 2CV-5086-2. On panel 2C16, placed hand sw itch for 2CV-5086-2 to "OPEN". Observ e d red light ON; green light OFF abov e hand sw itch. N/A SAT UNSAT

3. Verify RAS has not actuated.

On panel 2C03, v e rified Alarms cleared on Annunciator panels 2K04 and 2K07 or v e rified red lights ON at 2C03 abov e the RAS placard.

N/A SAT UNSAT

4. Verify RCS indicators functioning properly using OP 2103.011.

EXAMINER's CUE: CRS reports that OP 2103.011 attachment 'M', RCS lev e l transmitter and ty gon tube alignment has been completed and all RCS lev e l indicators are functioning properly. Requests that CRS v e rify O P 2103.011 Attachment 'M' i s complete.

N/A SAT UNSAT JPM-ANO-2-JPM-NRC-EOP02 Page 4 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

5. 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. Close ALL LPSI Injection MOVs. POSITIVE CUE:

Green lights ON; red lights

OFF. On 2C16 & 17, placed hand switches for Safety Injection MOVs to "CLOSE".

2CV-5017-1 2CV-5037-1 2CV-5057-2 2CV-5077-2 Observed green light ON; red light OFF above Hand switch for all valves.

N/A SAT UNSAT

7. Partially open ONE LPSI Injection.

On 2C-16 or 17, held 1 LPSI Injection MOV hand switch in the open direction for about 2 second. 2CV-5017-1 2CV-5037-1 2CV-5057-2 2CV-5077-2 Observed green and red light ON above associated hand switch. N/A SAT UNSAT

8. Verify RCS level adequate; refer to Attachment A, RCS Level. Referred to Attachment "A" and verified RCS Level adequate for SDC Pump restart. N/A SAT UNSAT 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.

JPM-ANO-2-JPM-NRC-EOP02 Page 5 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 9. 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. Raise SDC flow to greater than 2400 gpm by opening LPSI Injection MOVs.

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: Inform candidate that the CRS and CBOR will control RCS cool down.

END 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, 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 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 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-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 KA VALUE RO: 3.4 SRO: 3.8 KA

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.

2. During the speed ramp the Turbine for 2P-7A tripped on overspeed.

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 using OP 2106.006, Exhibit 1 starting with step 2.0."

CRITICAL ELEMENTS (C):

1, 2, 3, 5 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One) (C) 1. 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) 2. 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) 3. 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

4. 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) 5. 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

6. 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

7. 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 starting with step 2.0."

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 starting with step 2.0."

JPM-ANO-2-JPM-NRC-IA01 PAGE 1 of 6 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 KA VALUE RO: 3.1 SRO: 4.3 KA

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 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:

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 6 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 beginning with step 3."

CRITICAL ELEMENTS (C): 3, 4, 6, 7 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One) 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. 1. 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.

2. 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 (C) 3. 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) 4. 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 JPM-ANO-2-JPM-NRC-IA01 PAGE 4 of 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

5. 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) 6. Close IA supply "2CV-1060-2 AIR ISOL" valve, (2IA-93)

EXAMINER'S CUE:

2IA-93 valve CLOCKWISE motion 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) 7. 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 main feed pumps located in the basement of the turbine building. Stop the JPM before transitioning to this area.

END STOP TIME:

___________________

JPM-ANO-2-JPM-NRC-IA01 PAGE 5 of 6 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 t he MSIV's locally beginning with step 3."

JPM-ANO-2-JPM-NRC-IA01 PAGE 6 of 6 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 beginning with step 3."

JPM- ANO-2-JPM-RO-XTCEA PAGE 1 of 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 02 DATE: SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Perform CEA#1 Upper Gripper Coil Temperature M easurement JTA#: ANO2-RO-CEDM-NORM-10 KA VALUE RO: 3.7 SRO: 3.9 KA

REFERENCE:

001 A2.14 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 2105.009, Rev. 021-01-0 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-RO-XTCEA 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. Plant is at full power. 2. Both Main Chillers have tripped and cannot be started. 3. I&C is not available to obtain CEDM Coil temperatures. 4. OP 2203.012M, 2K13 ACA, for window C3, Main Chiller 2VCH1A overload is in alarm.

TASK STANDARD:

CEA 01 Upper Gripper coil temperature has been measured and determined to be 360 - 367 o F using Exhibit 2 in 2105.009 (CEDM Control System Operation).

TASK PERFORMANCE AIDS:

1. OP 2105.009 Exhibit 2 2. Digital Voltmeter (DVM) 3. 2OPG-012 for DVM usage.

4. Calculator.

JPM- ANO-2-JPM-RO-XTCEA PAGE 3 of 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "As directed by OP 2203012M, 2K13-C4, CEDM Cooling co ils Water Flow Low ACA, measure the Upper Gripper temperature fo r CEA 01 using 2105.009, Exhibit 2."

CRITICAL ELEMENTS (C):

3, 4, 6, 7 & 8 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERS NOTE:

2OPG-12 contains guidance for using a Digital Volt Meter.

1. Obtain a currently calibrated handheld Digital Voltmeter (DVM). EXAMINER'S NOTE:

Hand examinee DVM.

Obtained a currently calibrated handheld Digital Voltmeter (DVM). N/A SAT UNSAT EXAMINER's Note:

The Hold Bus and 2C72 is in the CEDMCS Room located above the control room. No panel doors are allowed to be opened. Use the photograph' s provided for cables in back of 2C72 and coil monitor connector on the front of 2C72.

2. Verify CEA 01 is NOT on the Hold Bus.

EXAMINER'S CUE:

The Subgroup Maintenance toggle switch for subgroup 12 is pointing down and RED light is OUT above the toggle switch.

Verified that the Subgroup

Maintenance toggle switch for CEA Subgroup 12 is pointing down. Red light is OUT above toggle switch.

N/A SAT UNSAT EXAMINER's NOTE: When examinee identifies panel to be opened in back of 2C72, give examinee picture of cables in back of 2C72 to complete next step. (C) 3. Obtain CEA 01 upper gripper coil voltage.

EXAMINER'S CUE:

CEA 01 upper gripper voltage is 44 VDC.

AT back of panel 2C-72, CEA #1

power cables on TBC4C6 have been located.

Selected DVM scale on 200 and recorded the voltage across the

'black' and 'white' cables located on TBC4C6, terminals #4 and

1. 5. Recorded 44 VDC in Step 3.2.

N/A SAT UNSAT JPM- ANO-2-JPM-RO-XTCEA PAGE 4 of 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINER's NOTE:

When examinee identifies Connector for C EA #1 on front of 2C72, give examinee picture of connector to perform next step. (C) 4. Obtain CEA #01 Upper Gripper shunt voltage (V shunt). EXAMINER'S CUE:

CEA 01 Upper Gripper shunt voltage reads 7.62 millivolts DC.

Located the CEA #01 coil monitor connector on the front side of 2C72. Unscrewed and removed the

connector cap.

Selected the 200 mV scale on

the DVM and measured the voltage across pins 'C' and 'D'.

Divided 7.62 millivolts by 1000 and recorded .00762V in step 4.3.1. N/A SAT UNSAT

5. Install connector cap.

EXAMINER'S CUE:

Connector cap is installed.

Installed the connector cap back

on CEA #01 coil monitor connector.

N/A SAT UNSAT (C) 6. Calculate coil current (I coil). EXAMINER'S CUE:

None Calculated coil current by dividing Shunt voltage by .002.

Recorded 3.81 amps in step 5.2.

N/A SAT UNSAT (C) 7. Calculate coil resistance (Rcoil). EXAMINER'S CUE:

None Calculated coil resistance by dividing Upper Gripper voltage by Upper Gripper current.

Divided 44 VDC by 3.81 amps

and recorded 11.55 ohms in step 6.1 Subtracted .525 from 11.55 and

recorded ~11.02 ohms in step 6.3. N/A SAT UNSAT (C) 8. Obtain CEA #01 coil temperature.

EXAMINER'S CUE:

None Obtained the coil temperature for the CEA #01 Upper Gripper by using the coil resistance from step 6.3 and using the chart.

Using the chart in step 7.1

calculated a coil temperature between 360 o F and 367 o F. N/A SAT UNSAT END STOP TIME:

JPM- ANO-2-JPM-RO-XTCEA PAGE 5 of 6 JOB PERFORMANCE MEASURE EXAMINER's COPY JPM INITIAL TASK CONDITIONS:

Plant is at full power. Both Main Chillers have tripped and cannot be started. I&C is not available to obtain CEDM Coil temperatures. OP 2203.012M, 2K13 ACA, for window C3, Main Chiller 2VCH1A overload is in alarm.

INITIATING CUE:

The SM/CRS directs, "As directed by OP 2203012M , 2K13-C4, CEDM Cooling coils Water Flow Low ACA, measure the Upper Gripper temper ature for CEA 01 using 2105.009, Exhibit 2."

JPM- ANO-2-JPM-RO-XTCEA PAGE 6 of 6 JOB PERFORMANCE MEASURE EXAMINEE's COPY JPM INITIAL TASK CONDITIONS:

Plant is at full power. Both Main Chillers have tripped and cannot be started. I&C is not available to obtain CEDM Coil temperatures. OP 2203.012M, 2K13 ACA, for window C3, Main Chiller 2VCH1A overload is in alarm.

INITIATING CUE:

The SM/CRS directs, "As directed by OP 2203012M , 2K13-C4, CEDM Cooling coils Water Flow Low ACA, measure the Upper Gripper temper ature for CEA 01 using 2105.009, Exhibit 2."

Appendix D Scena rio 1 Form ES-D-1 Facility: ANO-2 Scenario No.: 1 Op-Test No.: 2005-1 Page 1 Exa m iners: Operators:

Initial Condit i ons: 56% MOL, All Engineered Safety Features (ESF) systems in standby. Condenser outer water box is isolat ed for tube plugging. 'B' circulat ing water pump is secured

. Green Train Maintenance Week.

Turnover:

56%. 250 EFPD. Conde nser outer water box is isolated for t ube pluggin

g. 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' circu l ating water pump is secur ed. Equipment Out of Servi c e Monitor (EOOS) indicates 'Minimal Risk.' Gre en Train Maintenance Week. Event No. Malf. No.

Event Type* Event Description 1 NIALINEPW R I (CBOT) Safety channel linear po wer channel 'A' fails low. CBOT must bypass poin t s in Plant P r otection System (PPS) channel.

2 CVC2P36AFAL C (CB O R) Running ch arging pump trips breake

r. Abnormal Operating Procedures (A OP) entry start standb y charging pu mp. 3 SGAT UBE R(CB OR) N(CB OT) 'A' Steam Generator (SG) tube leak results in power reduction to take unit off line.

4 SGAT UBE M(ALL) 'A' Steam Generator tube rupture results in re actor trip and Reactor Coolant System (RCS) cool down.

5 4 1 6 2 A 4 0 6 C (CB O T) 'B' High Pressure Safety Injection (H PSI) pump trips breaker on start.

6 2 C V 5 0 1 5 1 C (CBOT) 'A' HPSI train injection Motor Operated Valve (MOV) fails t o open on a c tuation. 7 BUHTRS C(CBOR) Back up Heaters fail on due to relay failure and will not shut off when Pressurizer level drops less t han set point.

• (N)ormal, (R)eactivity, (I)nstrument, (C)o mponent, (M)ajor Page 1 of 16

Appendix D Scena rio 1 Form ES-D-1 Scenario #1 Objectives

1) Evaluate individual res ponse to a fa ilure of an Excore nuclear instrument.

2) Evaluate individual res ponse to a failure of a running charging pum

p. 3) Evaluate individual res ponse 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 res ponse to a failure of the PZR heat ers. SCE NARI O #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 r oom walk down and br ief, 'A' Exc o re will fail low. This will result in a CPC sen s or failure alarm and the NI linear and log po wer instruments on 'A' ch annel failin g to Zero.

The CRS will enter the Nuclear Instrument Malfunction AOP, AOP 2203.026. The CRS will d i re ct the CBOT to bypass point s 1, 2, 3, and 4 on 'A' PPS. TS 3.3.1.1 will be enter ed due to the excore failu r e. About 10 minutes after the excore failure, the 'A

' CCP will trip its breaker. A CCP low flow alarm will a l ert the operator t hat the CCP has tripped. If another pump is not started quickly, let down will b e isolated d ue to high regenerativ e heat exc h anger outlet temperature high (alar m).The CRS will enter the loss of charging AOP, OP 2203.036, Crew will v e rify that the br eaker 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 C C P trips, a 5.0 gpm pr i m ary to secondary leak will start. The CRS will enter the primary to secondar y leak age AOP, OP 2203.038. CBOR and CBOT will perform R C S 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 ac tivity. The CRS will is olate 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 C B OR 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 le ak rate Hi annunciators will a l arm. The CBOR recogniz e that the SGTR is greater than CCP cap a city. The CRS will dire ct the CB OR will ma nually trip the reactor.

Post trip, the PZR bac kup heaters will fail to de-energiz e when PZ R level dro p s below 29%, the C B OR will manually sec u re the heaters.

Post SIAS, the 'B' HPSI pump Breaker will trip (green train) and on e of the red train HPSI injection MOV's will fail to open on actuation.

The CBOT will manu ally start the swing HPSI pump and open the failed inj e ction MOV.

This is Tech Spec 3.0.3 entry.

Page 2 of 16

Appendix D Scena rio 1 Form ES-D-1 SCE NARI O #1 NARRATIVE (c ontinued)

The Crew will implem ent SPTA's and secure 2 RCP's when RCS pressure drops belo w 1400 psia. The CRS will d i agnos e 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 conden ser. The CBOT will ov erride SW to CCW and ACW. The CBOT will isolate the

'A' SG using standard attachment 10 when RCS Thot is less than 535°F.

Page 3 of 16

Appendix D Scena rio 1 Form ES-D-1 Simulator Instructions for Scenari o 1 Reset simulator to MOL 56% power IC stead stat

e. Markup OP 2102.004, p o wer operations up to st ep 9.22. Ensure that AACG is se cured and a nnunciators clear. Ensure hotwell level is ~

80%. Place MINIMAL RISK a nd Green Train Maintenance Week signs on 2C

11. Swing ESF equipment aligned to the Green train.

'A' CCP lead charging p u mp. 2PCV0231, Gland sealin g steam pressure contro l valve failed closed.

T1, T2, T3, T5 set to false.

T4 set to SI AS1. T5 set to PZ R Pressure < 2000 psia Event No. Malf. No.

Value/ Ramp Time Event Description 1 NIALINEPW R Trigger = T1 0.0 Safety Chan nel 'A' Excore Linear inst rument fails LOW. 2 CVC2P 36AF A L Trigger = T2 TRUE 'A' Coolant Charging Pump trips on instantaneou s Over Curren t due to motor fault.

3 S G A T U B E Trigger = T3 5.0 'A' SG primary-secondary leak.

4 S G A T U B E CUED 500 RAMP= 10 MIN 'A' Steam Generator Tube Rupture (500 gpm ramped over 10 Min u tes). 5 4 1 6 2 A 4 0 6 Trigger = T4 TRUE 'B' HPSI pump trips breaker on start

. 6 C V 5 0 1 5 1 Trigger = T4 TRUE Red train HPSI injection MOV fails t o open on SIAS actuation.

7 R C S H T R O N Trigger = T5 TRUE PZR Backup heaters fail to de-ener gize. Page 4 of 16

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

1 Event

Description:

Cha nnel 'A' excore nuclear i n strument will fai l low. T he CRS will enter the NI malfunction AOP, OP 2203.026.

Time Position Applicant's Actions or B ehavior ALL Crew will diagnose that

'A' Excore is the only channel that h a s failed. CRS Enter AOP 2203.026, NI malfunctio n and perform the following actions: Refer to TS 3.3.1.1 Direct the CBOT to byp a ss point s 1,2,3 and 4 on 'A' PPS Verify that Log channel is also affe ct ed Notify maint enance of pr oblem with 'A' Excore CBOT Will perform the followin g: Obtain Key 12 from SM Notify control room of potential PPS security door and Bypa ss alarms Open 2C23 door and unlock panel d oor 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 2 C 03 CBOR Will perform the followin g: PEER check that bypass lights for points 1,2,3 and 4 are illuminated on operator inserts on 2 C 03 Simulator Operator Cue: When contacted as IC or Work Week Manager, report that y ou w ill be gin planning work on 'A' Excore.

Termination criteria: When points 1,2,3 and 4 are b y pas sed on 'A' PPS or at t he discretion of the lead examiner.

Page 5 of 16

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1 E

v ent No.: 2 Event

Description:

'A' C C P trip. The CCP low flo w alarm will alert operat ors of this fa ilure. Letdown will isolate, if b a ckup CCP not started i n timely ma nner. Time Position Applicant's Actions or B ehavior CBOR Announce that 'A' CCP has tripped its breaker (R ed and Green lights out on 2C09) CRS Enter loss of Charging AOP and perf o rm the following actions:

Check for pr oper Charging suction a nd discharg e flow path.

Check that 'A' CCP has tripped brea ker Direct Starting backup CCP Direct verification of prop er operation of running CCP Check for in dications of CCP header rupture usin g control roo m indication s Direct WCO to locally vent 'A' CCP TRM 3.1.2.4 Applicability Simulator Operator Cue: When contacted as WCO to v ent 'A' CCP wait a fe w minutes and report that no air bubbles onl y water came out vent.

CBOR Verify VCT outlet valve open Verity CCP header isola t ion valve open Manually start backup CCP b y taking hand-switch to start Verify VCT l e vel stable or going up C B O T /CBOR Verify CCP header not ruptured:

• Aux Building or CNTMT radiation level steady

• Waste Tan ks 2T20A/B level not rising

• CNT MT Sump level not rising

• Aux Building sump level not risin g NOTE: Letd o wn ma y have isolated on high temperature. Letdown may be rest ored at this point. Termination criteria: When backup CCP sta r ted or at discretion of lead examiner.

Page 6 of 16

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1 Event No.: 3 Event

Description:

5.0 GPM primary to secondar y leak on 'A' SG.

The CRS will ent er the primary to secondary leakage AO P, OP 2203.038. Crew will perform a plant shutdown Time Position Applicant's Actions or B ehavior C B O R Announce annunciators:

2K11-A10 Sec Sys Ra dia t io n Hi 2K11-J8 SG Tu be L e a k De tec t i o n Rat e of Cha nge Hi 2K11-K8 SG Tu be L e a k De tec t i o n Trou bl e/L K RT Hi CRS Implement AOP 2203.0 38, PRI-SEC leakage a nd 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 c hemists to sample the SG's for activity Direct CBOT to isolate steam to

'A' EFW pu mp from 'A' SG Direct CBOR to perform a plant shut down using normal boration method. C B O T Close 2CV 1000-1, stea m from 'A' SG to 'A' EFW pump.

CBOR Perform a plant shutdown Use reactivity plans to determine the amount of boron required.

Adjust turbin e load to maintain Tave within 2°F of Tref.

Insert CEA's as directed by reactivity plan. Page 7 of 16

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1 Event No.: 3 Event

Description:

5.0 GPM primary to secondar y leak on 'A' SG.

The CRS will ent er the primary to secondary leakage AO P, OP 2203.038. Crew will perform a plant shutdown. Simulator Operator Cue: When contacted as AO ackno w l edge requirement to begin w o rking on Standard attachment 19.

Termination criteria: When reactivity manip u lations are satisfied or at the discretion of the lead examiner.

Page 8 of 16

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

4 Event

Description:

500 gpm Tube Rupture on 'A' Steam Gen e rator ramp ed over 10 Minutes.

This will re sult in a manual reactor t r ip, SIAS and CCAS actuations. Cre w will perform a cool down of the RCS and manually Isola t e 'A' SG.

Time Position Applicant's Actions or B ehavior C B O R Report that PZR level is lowering Start all back up CCP's or report that they are running Isolate Letd o wn CRS Recognize SGTR has e x ceeded CCP capacity and the abilit y to maintain PZR level.

Direct the CBOR to man ually trip the reactor CBOR Manually trip the reacto

r. CRS Implement Standard Post Trip Actio n s, track saf e ty functions, and direct board operators actions.

CBOR Check reactivity control:

Reactor power decreasing.

All CEAs inserted.

CBOT Check maintenance of vital auxiliarie s: Main turbine tripped.

Generator output and exciter breaker s open. All 4160v and 6900 v No n-Vital busses energize

d. ALL 4160v and 480v vit a l AC bus energized.

All 125v vital DC bus energized.

Page 9 of 16

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

4 Event

Description:

500 gpm Tube Rupture on 'A' Steam Gen e rator ramp ed over 10 Minutes.

This will re sult in a manual reactor t r ip, SIAS and CCAS actuations. Cre w will perform a cool down of the RCS and manually Isola t e 'A' SG.

Time Position Applicant's Actions or B ehavior CBOR Check inventory control:

PZR level 1 6 to 80%.

Trend from set point.

Report SIAS actuated or manually actuate a nd verify all PZR heaters off w hen PZR level less than 29

%. (SEE Event

7) CBOR Check RCS pressure co ntrol: RCS pressure 1800 to 2 300 psia.

Trend from set point Secure Two RCP's w h en RCS pre ssure is less than 1400 psia.

Place spra y valve for secured RCPs in manual closed.

Verify SIAS w h en pressure less than 1650 psia.

CBOR Check core heat remova l by forced circulation:

RCP 's running Loop T less than 10 F. RCS MTS 3 0 F or greater.

Service wat e r pump suction aligned to Lake. Component cooling wate r aligned to RCPs. C B O T Restore SW to ACW per Exhibit 5. (NOTE: T h is actio n re quires several minutes)

Check SIAS actuated.

Maintain SW pressure greater than 85 psig.

Page 10 of 1 6

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

4 Event

Description:

500 gpm Tube Rupture on 'A' Steam Gen e rator ramp ed over 10 Minutes.

This will re sult in a manual reactor t r ip, SIAS and CCAS actuations. Cre w will perform a cool down of the RCS and manually Isola t e 'A' SG.

Time Position Applicant's Actions or B ehavior CBOT Check RCS Heat Remo val: Report SG l e vels and main feed water is in RTO.

Report feed water line in tact. Report SG pressures (Ma y take manual local (ML) contro l of SDBCS ma ster controller (at CRS direction) and reduce set point to 950-1050 psia).

CBOR Check CNTMT paramet ers: Temperature less than 140 F. Pressure less than 16 psia.

Status of ra diation alar ms: CAMS (2 K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT i n alarm Seconda ry Sys Radiation Hi (2K11-A10) IN ALARM CBOT Will open 2 C V0233, bypass around 2PCV0231 which is simulated closed to m a tch condit i on of valve at plant. This is in re spo n se to low gland se al pressure.

CRS Notify SM to perform the following:

SE report to control roo

m. Announce reactor trip o n plant page. Refer to Tech Specs and EALs. Page 11 of 1 6

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

4 Event

Description:

500 gpm Tube Rupture on 'A' Steam Gen e rator ramp ed over 10 Minutes.

This will re sult in a manual reactor t r ip, SIAS and CCAS actuations. Cre w will perform a cool down of the RCS and manually Isola t e 'A' SG.

CRS Direct CBOs to acknowle dge all contr o l room annunciators an d announce all signif i cant alarms. Diagnose Steam Genera t or Tube Rupture CRS Implement Steam Gen e rator Tube Rupture procedure and open place keep ing page.

ALL Perform cre w brief and review floating steps.

CRS Determine a pplicable f l o a ting steps:

Commence cool down t o less than 535 F Thot. HPSI Overri de Criteria.

CRS Direct the fo llowing actio n s: Commence cool down t o less than 535 F Thot. Inform SM t o contact C hemistry to sample both SG for activity.

Determine ruptured SG Perform post-SIAS actions:

Verify Safet y Injection flow to RCS:

Isolate 'A' S G when RCS Thot is less than 535°F Verify HPSI override criteria met: RCS MTS 3 0°F or greater. PZR level greater than 2 9% and cont rolled. RVLMS LVL 03 or highe r elevation indicates W E T. At least ONE intact SG available for Heat Remo val Level 10 to 90% with FW available.

Page 12 of 1 6

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

4 Event

Description:

500 gpm Tube Rupture on 'A' Steam Gen e rator ramp ed over 10 Minutes.

This will re sult in a manual reactor t r ip, SIAS and CCAS actuations. Cre w will perform a cool down of the RCS and manually Isola t e 'A' SG.

Time Position Applicant's Actions or B ehavior Critical Step CBOR RCS cool d o w n to less than 535°F T-hot : (floating step)

CBOR Reset low SG set points.

Commence RCS depres surization to maintain RCS MT S 30 to 45 (When HPSI overridden)

Take manual control of S D BCS b y pa ss 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 do wn on Attachments 1 and 8.

C B O R /CBOT Verify Safet y Injection flow to RCS:

Check HPSI flow using Exhibit 2.

Check LPSI flow using E x hibit 3. Page 13 of 1 6

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

4 Event

Description:

500 gpm Tube Rupture on 'A' Steam Gen e rator ramp ed over 10 Minutes.

This will re sult in a manual reactor t r ip, SIAS and CCAS actuations. Cre w will perform a cool down of the RCS and manually Isola t e 'A' SG.

Time Position Applicant's Actions or B ehavior CBOT Perform post-SIAS actions:

SW pumps running on e a ch loop. EDG SW outlet valves open.

SW pump suction alig n ed to Lake.

Report all n on-vital buses energize

d. Verify SG s a mple valve s open. Critical Step CBOT Use Attach ment 10 to isolate Ruptured SG C B O R CBOT OVE RRID E HPSI: Throttle HPSI flow OR place HPSI pumps in PTL as n eeded to co ntrol RCS pressure, in ventory, and heat removal.

Termination criteria: RCS Cool d o w n to less than 535°F and 'A' SG isolated or at examiners discretion.

Page 14 of 1 6

Appendix D Scena rio 1 Form ES-D-1 Op-Test No.: 1

Scenario No.: 1

Event No.:

5/6 Event

Description:

'B' H PSI pump tri p s on SIAS start. 2CV5015-1 fails to open on SIAS signal. Thi s will make HPSI flow UNACCEPTABLE. 'C' HPSI pump must be started o r 2CV5015-1 must be opened.

Time Position Applicant's Actions or B ehavior CBOT 2K05 E-3, 'B' HPSI pu mp trip alarm announced.

Observes green light lit on pump and no dischar ge pressure.

CBOT Observes 2CV 5015-1 is closed , gr een light on, red light off, Z-tape reading 0.

CRS Directs starting 'C' HPSI pump Directs ope ning 2CV 5015-1 Critical Step Critical Part is to either start 2P89C or open 2CV-5015-1 CBOT Starts 'C' HPSI pump Verified pro per discharge pressure and flo w (depending on RCS press ure) And/or Opens 2CV 5015-1 b y 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.

Page 15 of 1 6

Appendix D Scenario 1 Form ES-D-1 Page 16 of 16 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 Scena rio 2 Form ES-D-1 Facility: ANO-2 Scenario No.: 2 Op-Test No.: 2005-1 Exa m iners: Operators:

Initial Condit i ons: 100% MOL, All ESF systems in stan dby. 'C' HPSI pump tag ged out for oil bubbler replacement. 'C' HPSI is aligned to g r een train. Green train maintenance week. Turnover:

100%. 250 EFPD. 'C' HPSI pump ta gged out for oil bubbler r eplacement. EOOS indicates 'Minimal Risk.'

Green train maintenance week.

Event No. Malf. No.

Event Type* Event Description 1 XRCCHAPL VL I (CBOR) Control Channel "A" Pressurizer Lev el fails LOW

. 2 XSG2PT10 411 I (CBOT) Steam Gen e rator safety channel pre ssure fails LOW. 3 FWPMP A T R P R (CB O R) N (CB O T) 'A' Main Feed Pump (MF P) trips due to thrust bearing wear and results in a power reduction to less than 90

%. 4 F W A F T 5 A M (ALL) Feed water line break in containment after 2FW5A, feed water to 'A' Steam Generator (SG) check valve, which results in Excess Steam De mand (ESD) on 'A' SG. 5 E S C S BPMP C (CB O T) Fail 'B' Cont ainment Spray Actuation Signal (CSAS) pump to start on CSAS.

6 ESFCSASF A IL C (CBOR) Fail CSAS channel 1 to actuate auto.

• (N)ormal, (R)eactivity, (I)nstrument, (C)o mponent, (M)ajor Page 1 of 15

Appendix D Scena rio 2 Form ES-D-1 Scenario #2 Objectives

1) Evaluate individual res ponse to a failure of Pressurizer level cont rol channel failure.

2) Evaluate individual res ponse to a failure of a Plant Protection S ystem Steam Generator Level instrument failure.

3) Evaluate individual res ponse 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 res ponse to a failu re of required Engineered Safety Features Actuation System actuation.

SCE NARI O #2 NARRATIVE Simulator session beg ins 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 br ief, the in service Pressurizer (PZR) control channel level instrum ent will fail lo

w. Alarms on control channel 1 level lo a nd level lo lo will come in. This wil l result in letdown goin g to minim u m flow, th e two backup CCP's will automatically start, all PZR heater s de-energizing and ac tual PZR level go up.

AOP 2203.028, PZR Systems Ma lfunctions, will be ent ered and actions directed by the CRS. The CBOR will take the let down flow controller to manual and control PZR leve l. The CBOR will a l so ve rify that the other level control channel is re ading correctly and select that channel for control and place the PZR low low lev e l 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 channe l pressure instrument, 2PT1041-1, will fail lo

w. This will trip 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 'A' oper ator insert (2C03) trip and pr e-trip l i ghts will be lit. The CRS will refer to the A C A 2203.012D and tech specs 3.3.1.1, 3.

3.2.1 and 3.3.3.5 for guida nce. The CBOT will place Channe l 'A' PPS in byp a ss 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 i n strum ent failure, 'A' MFP will trip. CRS will enter AOP 2203.037, Loss of Main Feed Pu mp. Th is will result in Steam Flow exce edin g Feed flow and SG levels dropping. The crew will manually start the fourth condensate pump, reduce turbine load, and borate using emergency boration to the RCS until Feed flow is greater than Steam Flow. Then conti nue with a normal boration power reduction to less than 90%.

Page 2 of 15

Appendix D Scena rio 2 Form ES-D-1 SCE NARI O #2 NARRATIVE (c ontinued)

Once the Reactor operator's reactivity mani pulations ar e complete, the main feed line break will occur. This will c ause c ontainment pressure, tem perature and sump level to go up. 'A' Stea m Generator level will lower. The crew will m anually trip the reactor and complete SPTA's. Once feed (Mai n and Emer gency) is secured to the SG, an Exc e ss Steam Demand will occur on

'A' Steam Generator.

The CRS will d i agnos e an Excess Steam De mand even t and enter OP 2202.005, ESD.

The crew will manua lly control Reactor Coola n t Temperature once the 'A' SG b o ils dry using the upstream Atmospheric Dump Valv es on 'B' SG. The crew will manually control PZR press u re using the Auxiliar y Spray valve.

When Containment pressure exc eeds 23.3 ps ia, the crew will recognize that CSAS, Containment Spray Actuation Signal, has not automati c ally actuated on Channel 1 and that the Spray pump on channel 2 side did n o t start. The crew will manually a c tuate spray on Channel 1 and manually start 'B' CSAS pump.

Page 3 of 15

Appendix D Scena rio 2 Form ES-D-1 Simulator Instructions for Scenari o 2 Reset simulator to MOL 100% power IC stead st ate. Ensure that AACG is se cured and a nnunciators clear. 'C' HPSI pu mp is tagged out for oil bubbler replacement.

Ensure hotwell level is ~

80%. Place MINIMAL RISK a nd Green Train Maintenance Week signs on 2C

11. T1, T2, T3, T4 set to false.

Event No. Malf. No.

Value/ Ramp Time Event Description 1 X R C C H A P L V L Trigger 1 0.0 Control Channel "A" Pressurizer Lev el fails LOW

. 2 X S G 2 P T 1 0 4 1 1 Trigger 2 0.0 Steam Gen e rator safety channel pre ssure fails L O W. 3 F W P M P A T R P Trigger 3 TRUE 'A' Main Feed Pump (MF P) trips due to thrust bea ring wear and results in a po wer reduction to less tha n 90%. 4 F W 2 P W 5 A A F T Trigger 4 1000 Ramp 5 min Feed water line break in containment after 2FW5A, feed water to 'A' Steam Generator (SG) check valve, which result s in Excess Steam De mand (ESD) o n 'A' SG. 5 B S 2 P 3 5 B F A L TRUE Fail 'B' Cont ainment Spray Actuation Signal (CSAS) pump to start on CSAS.

6 E S F C S A S F A I L T R U E Fail CSAS channel 1 to actuate auto.

Page 4 of 15

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2

Event No.:

1 Event

Description:

Cha nnel A pressurizer level control chan nel 2LT-462 7-1 fails low.

The CRS will enter the PZR Systems Malfunction AOP 2203.028.

Time Position Applicant's Actions or B ehavior ALL Announce alarms 2K10-G6 CNT RL 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.

C R S R e f e r t o PZR Sy stems Malfunctio ns AOP 220 3.028 and direct board operators action

s. CBOR Determine PZR level Ch annel A faile

d. Place Letdo wn 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 pre ssure 2025 to 227 5 psia. The CBOR will take the letdown flow controller to manual and control PZR level.

CRS Enter 3.3.3.6 Post Accid ent Instrumentation.

Simulator Operator Cue: When contacted as IC or Work Week Manager, report that y ou w ill be gin planning work on 2LI-4627-1.

Termination criteria: Unaffected PZR level channel selected and letdow n in aut omatic or at the discretion of the lead examiner.

Page 5 of 15

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2 E

v ent No.: 2 Event

Description:

2PT1 041-1, Channel 'A' SG pressure tran smitter fails low.

Time Position Applicant's Actions or B ehavior C B O T Announce annunciators:

2K04-A4 CH A RPS/

E S F/PRET RIP/TRIP 2K04 B3 PPS TRIP 2K04-E4 MSIS PRET RI P Compare all four channe ls and report 2PI-1041-1 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 chan nels in bypa ss on Chan nel A: A SG pressure low - RPS (Bistable

11) A SG P - EFAS 1 (Bistable 19)

B SG P - EFAS 2 (Bistable 20)

CBOR Verify annunciator 2K04-C3 PPS CHANNEL BYPASSED Verify correct channels in bypass.

CRS Contact maintenance to repair 2PT1041-1.

Simulator Operator Cue: When contacted as WWM, w o rk w eek ma nager, of I&C need to troubleshoot and repair 2PT1041-1. Report that planning on repair of 2PT1041-1 is in progress. Termination criteria: When 'A' plant protection s y stem points 11, 19 and 20 are b y passed o r at discretion of lead examiner.

Page 6 of 15

Appendix D Scena rio 2 Form ES-D-1 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 B ehavior C B O T Announce 'A' MFP trip alarms:

2K03 A8, 'A' MFP trip 2K03 K8, T h rust Bearing Wear Trouble C R S Enter 2203.027, Loss of Main Feed Pump AOP and direct the following actions:

Verify Recirc valves closed (Condensate an d MFP) Verify Main Feed water regulating valve bypasses are opening Start standby condens ate pump Commence emergency boration using exhibit 1 Reduce MTG load to establish F eed water Flow > Steam Flow while maintaining T C < 554.7°F Secure Emergency boration when Feed water Flow > Steam Flow C B O T 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 F eed water Flow > Steam Flow while maintaining T C < 554.7°F.

C B O R Commence boration using Exhibit

1. Page 7 of 15

Appendix D Scena rio 2 Form ES-D-1 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.

C R S When FF>SF, direct CBOR to commence down power to <

90% using normal boration method.

C B O R 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 manip u lations or at discretion of lead examiner.

Page 8 of 15

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line br eak inside containment on 'A' SG. This will re sul t in a reactor trip, SIAS, CCAS, CIAS and CSAS engi neered safet y features actuations.

ALL Announce that 'A' SG level is lowering.

Containmen t temperature and pressure are risin

g. Announce that radiation levels in co ntainment are steady.

Announce that contain m ent sump level is rising quickly.

Diagnose th at a feed lin e leak is in p r ogress inside containment.

CRS Direct CBOR to manually trip the reactor.

CBOR CBOR man ually trip the reactor.

CRS Implement Standard Post Trip Actio n s, track saf e ty functions, and direct board operators actions.

CBOR Check reactivity control:

Reactor power decreasing.

All CEAs inserted.

CBOT Check maintenance of vital auxiliarie s: Main turbine tripped.

Generator output and exciter breaker s open. All 4160 v and 6900 v Non-Vital busses energized.

ALL 4160 v and 480 v vi tal AC bus energized.

All 125 v vital DC bus energized.

Page 9 of 15

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line br eak inside containment on 'A' SG. This will re sul t in a reactor trip, SIAS, CCAS, CIAS and CSAS engi neered safet y features actuations.

Time Position Applicant's Actions or B ehavior CBOR Check inventory control:

PZR level 1 6 to 80%.

Trend from set point.

Report SIAS actuated or manually actuate a nd verify all PZR heaters off w hen PZR level less than 29

%. CBOR Check RCS pressure co ntrol: RCS pressure 1800 to 2 300 psia.

Trend from set point Secure Two RCP's w h en RCS pre ssure is less than 1400 psia.

Place spra y valve for secured RCPs in manual closed.

Verify SIAS w h en pressure less than 1650 psia.

CBOR Check core heat remova l by forced circulation:

RCP 's running Loop T less than 10 F. RCS MTS 3 0 F or greater.

Service wat e r pump suction aligned to Lake. Component cooling wate r aligned to RCPs. CBOT Restore SW to ACW per Exhibit 5. (NOTE: This action requir e s several minutes)

Check SIAS actuated.

Maintain SW pressure greater than 85 psig.

Restore CCW to RCP's using exhibit 5 (when CIAS actuates).

Page 10 of 1 5

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line br eak inside containment on 'A' SG. This will re sul t in a reactor trip, SIAS, CCAS, CIAS and CSAS engi neered safet y features actuations.

Time Position Applicant's Actions or B ehavior CBOT Check RCS Heat Remo val: Report SG l e vels and main feed water is in RTO.

Report feed water line is NOT intact.

Report SG p r essures 'A' SG lower th an 'B' SG.

Manuall y a c tuate EFAS, Emergen c y Feed w a ter Actuatio n Signal if not alread y ac tuated. Verify that MSIS is actuated.

Verify Feed water is not aligned to 'A

' SG CBOR Check CNTMT paramet ers: Temperature greater than 140 F. Pressure greater than 1 6 psia. Status of ra diation alar ms: CAMS (2 K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT i n alarm Seconda ry Sys Radiation Hi (2K11-A10) NOT in alarm Secure ALL RCP's w h e n Containment Spra y Actuation Signal (CSAS) occ urs. CRS Notify SM to perform the following:

SE report to control roo

m. Announce reactor trip o n plant page. Refer to Tech Specs and EALs. Page 11 of 1 5

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line br eak inside containment on 'A' SG. This will re sul t in a reactor trip, SIAS, CCAS, CIAS and CSAS engi neered safet y features actuations.

CRS Direct CBOs to acknowle dge all contr o l room annunciators an d announce all signif i cant alarms. Diagnose EXCESS ST EAM DEMAND EOP.

CRS Implement EX CESS STEAM DEMAND EOP p r ocedure an d open place keep ing page.

ALL Perform cre w brief and review floating steps.

CRS Determine a pplicable f l o a ting steps:

Control post steam generator blow down RCS te mperature and pressure CRS Direct the fo llowing actio n s: Isolate 'A' S G using Attachment 10.

Control post steam generator blow down RCS te mperature using 'B' steam generator upstrea m atmosphe ric dump valve.

Control PZR pressure wi thin P-T limits using Auxi liary Spray valve and Attachment 27.

Override HPSI when conditions are met. RCS MTS 3 0°F or greater.

PZR level greater than 2 9% [50%] and controlle

d. RVLMS LVL 03 or highe r elevation indicates W E T. At least ONE intact SG available for Heat Remo val Page 12 of 1 5

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line br eak inside containment on 'A' SG. This will re sul t in a reactor trip, SIAS, CCAS, CIAS and CSAS engi neered safet y features actuations.

Time Position Applicant's Actions or B ehavior Critical Step CBOT Control po st Steam Generator blow do w n R C S tempera t ure using upstream atmospheric dump valve w i t h in 25°F of 'A' Steam Gen e rator Tc when generator boiled dry

. Critical Step CBOR Maintain Post steam generator blow do w n P Z R pressure using auxiliary sp ra y valve a nd attachment 27 w i thi n the Pressure-Temperature limits of 200°F and 30°F.

C B O R /CBOT Override HPSI flow and charging flo w to maintain PZR level.

Termination criteria: When plant temperature and pressures are stabilized aft e r 'A' Steam Gen e rator boils dry or at th e discretion of the lead examiner.

Page 13 of 1 5

Appendix D Scena rio 2 Form ES-D-1 Op-Test No.: 1

Scenario No.: 2

Event No.:

5 Event

Description:

'B' C ontainment Spray pump

, 2P35B fails to automatically start.

CBOT will manually start the 'B' containme n t spray pump.

Time Position Applicant's Actions or B ehavior CBOT Reports that no flow is in dicated on 2 C 16 for containment spray flow after actuation.

Reports that 'B' contain m ent spray pump is not running Reports that the 'B' cont ainment spray containment isolat ion valve is open.

Reports Alarm on 2K05 A1, 2P35B failure on ESFAS, Engineered Safety Features Actuation System CRS Directs manual start of 2 P 35B, 'B' containment spray pump.

Critical Step (Either start of 2P35B or actuate CSAS 1) CBOT Manuall y starts 2P35B, 'B' containment spra y pump on 2C16.

Verifies pro per containment spra y flo w on 2C16.

Termination criteria: 2P35B is manuall y started or at the discretion of the lead examiner.

Page 14 of 1 5

Appendix D Scenario 2 Form ES-D-1 Page 15 of 15 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 Scena rio 3 Form ES-D-1 Facility: ANO-2 Scenario No.: 3 Op-Test No.: 2005-1 Page 1 Exa m iners: Operators:

Initial Condit i ons: 100% MOL, All ESF systems in stan dby. 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 XCV2LT48 61 I (CBOR) VCT level instrument fails low resulting in RWT being aligne d to CCP suction.

2 X F W2FIS0 735 I (CBOT) 'A' MFP suction flow tra n smitter fails low. Results in condensate and MFP re circs to con denser open ing fully and reducing feed water to SG'

s. 3 CNDV AC U U M R (CB O R) N (CB O T) Air leakage into condenser requiring a power reduction to maintain co ndenser vacuum.

4 CNDV AC U U M M (ALL) Air leakage into condenser results in loss of condenser vacuum and turbine and r eactor trip.

5 SU#3 locko ut 2A111 fails t o close N (CB O T) I (CBOR) Loss of off s ite power. Must energize non-vital busses. Startup #2 to 2A1 fails OPEN. Loss of pow er to PZR controllers must be contr o lled manually or transfer to a u tomatic. 6 2CV1503-1 fails to open C (CBOT) #1 EDG service water outlet MOV.

This will re sult in deenergizing red train vital 4160VAC, 2A3, an d 480VAC, 2B5.

7 2CV0340-2 breaker trips C (CBOT) 'A' EFW pump steam inlet valve fails to open. T h is will result in a loss of a ll f eed water.

• (N)ormal, (R)eactivity, (I)nstrument, (C)o mponent, (M)ajor Page 1 of 13

Appendix D Scena rio 3 Form ES-D-1 Scenario #3 Objectives

1) Evaluate individual res ponse to a failure of Volume Cont rol Tank level transmitter.

2) Evaluate individual res ponse to a failu re of a Main Feed Pump suction Flow transmitter

. 3) Evaluate individual res ponse 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 res ponse to a failure Loss of power to a vital bus.

SCE NARI O #3 NARRATIVE Simulator session begins with the plant at 100% power steady state.

When the crew has completed their contro l room walk down and br ief, one of the two volume con t rol tank (VCT) level transmitters wil l fail lo w. The crew will respon d to VCT low low lev e l alarm, 2K12 G5. This will result in the VCT out l et valve to the chargin g pump suction to close and the Refueling Water tank (RWT) suction to the charging pumps to open. RCS temperature and pressure will lo wer until the CBOR po sitions the VCT outlet valve manually opened and the RWT valve manually closed.

About 10 minutes after VCT level transmi tter failure, 'A' main feed pump suction transmitter will fail lo

w. This wil l result in 2K0 3-D9 (A MFP SUCT FLOW LO) alarm. This will result in both the 'A' MFP an d 'A' / 'C' c ondensate pump recirc valves opening. This will reduce Main feed water flow to 'A' Steam Generator and reduce MFP sucti on pressure so that the standby condensate p u mp will au tomati cally start. The CBOT will recogniz e 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 contr o l of both the MFP and condens ate pump recirc valves and close them.

About 10 minutes after the MFP suction flow instrument failure, air in-leakage into the main cond enser will start. This will result in condenser v a cuum slowly degrad ing. The CRS will enter OP 2203.019, Loss of condenser va cuum. The CBOR will begin an emergency boration an d the CBOT will reduc e main turbi ne loa d to restore condenser vacuum. The crew will secure emergency boration and reduc ing turbine load wh en vacuum stabilizes.

The CBOR will then c o mmence normal borati on and reduce turbine load to allo w condenser vacuum to be restored to less than ~5 in Hg.

Once the Reactor operator's reactivity manipu lations ar e complete, the air in-l eakage 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 E D G 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 channe l instrumentation due to a loss of power to the selected channel #1 instruments.

Page 2 of 13

Appendix D Scena rio 3 Form ES-D-1 SCE NARI O #3 NARRATIVE (c ontinued)

When an Emergency Feed water Actuation Signal (EF AS) occurs and 'A' emergency feed water pump attempts to star t aut omatically 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, th e CRS will diagnose and enter the Loss of Feed EOP OP2202.00 6. The CBOT will manual ly start the Alternate AC Generator from 2C14 and energize 2A3, vital 4160 bus or open the Servic e water valve from the #1 EDG and start

1. 1 EDG. Once 2A3 is energized t he 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.

Page 3 of 13

Appendix D Scena rio 3 Form ES-D-1 Simulator Instructions for Scenari o 3 Reset simulator to MOL 100% power IC stead st ate. Ensure that AACG is se cured and a nnunciators clear. Ensure hotwell level is ~

80%. Place MINIMAL RISK a nd Green Train Maintenance Week signs on 2C

11. T1, T2, T3, T4, T5 set t o false. T6 set to EF AS-1 T7 set to EF AS-2 Event No. Malf. No.

Value/ Ramp Time Event Description 1 XCV2LT48 6 1 Trigger=T1 0.0 VCT level instrument fail s low resulti ng in RWT being aligne d to CCP suction.

2 X F W2FIS0 7 3 5 Trigger=T2 0.0 'A' M F P suction flow tra n sm itter fail s low. Resul t s in condensate and MFP re circs to con denser open ing fully and reducing feed water to SG'

s. 3 C N D V AC U U M Trigger=T3 3.0 Ramp 2 min Air leakage into condenser requiring a power reduction to maintain co ndenser vacuum.

4 C N D V AC U U M 10.0 Ramp 5 min Air leakage into condenser results in loss of condenser vacuum and turbine and r eactor trip.

5 FailSU3 416A111 Trigger=T4 TRUE Locked-Open Startup 3 lockout resu lt s in a lo ss of offsite pow er. Causes EDGs to automatically start/

loose Aux feed water pump and non-vital loads.

Loss of pow er to PZR controllers must be contr o lled manually or transfer to a u tomatic. 6 CV15031 Trigger=T5 0.0 #1 EDG service water outlet MOV.

This will re sult in deenergizin g red train vital 4160VAC, 2A3, and 480VAC, 2B5.

7 C V 0 3 4 0 Trigger=T6 Trigger=T7 0.0 'A' EFW pump steam inlet valve fails to open. T h is will result in a loss of a ll f eed water.

Page 4 of 13

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3

Event No.:

1 Event

Description:

VCT level transmitter 2LT486 1 fails low. T h is causes t he RWT to be aligned to C C P suction and Tave lowering.

Time Position Applicant's Actions or B ehavior CBOT Announce annunciator 2 K 12-G5 VCT 2T4 LEVEL LO LO.

CRS Implement Annunciator Corrective Action AOP 2203.012L.

CBOR Report level indicate s n o rmal on 2LIS-4857 but 2LT-4861 reads 0% on computer.

Reports cha r ging pump suction swapping to RWT.

CBOR May secure charging to stop boratio n if have not determined indication is a failed in str u ment and VCT level is normal.

OR When faulty instrument identified, th en manually reopen VCT outlet and close the RWT to CCP suction valve.

C B O T /CBOR Reduce turbine load to maintain Tave within 2 F of Tref if T a ve lowered. CRS Contact maintenance/PS liaison to t r oubleshoot failed instru ment. Simulator Operator Cue: When contacted as IC or Work Week Manager, report that y ou w ill be gin planning work on 2LT-4861.

Termination criteria: Charging suction manuall y aligned to the VCT and RWT to CCP valve close d or at the discretion of the lead examiner.

Page 5 of 13

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 E

v ent No.: 2 Event

Description:

2FIS 0735, 'A' loo p condensat e flow fails low. Condensate and MFP recirc valves open. CBOT must take manual control of recircs and control MFP suction pre ssure. Time Position Applicant's Actions or B ehavior CBOT Announce annunciator 2 K 03-D9 (A MFP SUCT FLOW LO) CRS Implement Annunciator corrective a c tion 2203.0 12C and direct board operator actions.

CBOT Report auto start of cond ensate pump.

Determine instrument 2FIS-0735 failure by use of PMS or c ontrol board indica tions. Place "A" co ndensate re circ and "A" main feed pump recirc valves in manual to control con densate hea der pressur

e. Secure con densate pu mp that auto started.

(Examiners Note

Crew may elect to leave fourth condensat e pump running until a late r point in the shutdown.)

CRS Contact maintenance/W W M to investigate failed transmitter.

Simulator Operator Cue: When contacted as WWM, w o rk w eek ma nager, 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 recirc s are in manual and secondary plant is stable or at discretion of lead examiner.

Page 6 of 13

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 Event No.: 3 Event

Description:

Cond enser vacuum slowly de grades. Crew will reduce turbine loa d Time Position Applicant's Actions or B ehavior C B O T Main Condenser lowering vacuum:

2K03 A3, 2E11A Pres sure HI 2K03 B3, 2E11A Turb Hood Pres s HI 2K03 E4, Vacuum pump 2C5B Auto Start 2K02 B14, Condenser Interlock C R S 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 T c less than 554.7°F and condenser vacuum < 6.5 inHg.

Commence emergency boration using exhibit 1 Secure Emergency boration when condens er vacuum is < 6.5 inHg. C B O T Reduce MTG load to maintain T c less than 554.7°F and condenser vacuum < 6.5 inHg.

C B O R Commence boration using Exhibit

1. Page 7 of 13

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 Event No.: 3 Event

Description:

Cond enser vacuum slowly de grades. Crew will reduce turbine loa d C R S When vacuum is less than 6.5 inHg. Secure emergency boration.

Contact Ops Management.

Simulator Operator Cue: When contacted as AO report that y ou ca n 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 w ill t ake 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 Man agement, tell the CRS to reduce plant po w e r until vacuum alarms are cleared.

C R S Direct CBOR to reduce commence a normal boration at power and reduce turbine load to < 5 inHg.

C B O R 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 manip u lations or at discretion of lead examiner.

Page 8 of 13

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 Event No.: 4 Event

Description:

Cond enser air in-leakage exceeds the ca pacity of the vacuum pu mps. This result s in a reactor t r ip. ALL Announce that condenser vacuum i s degrading.

CRS Direct CBOR to manually trip the reactor.

CBOR CBOR man ually trip the reactor.

CRS Implement Standard Post Trip Actio n s, track saf e ty functions, and direct board operators actions.

CBOR Check reactivity control:

Reactor power decreasing.

All CEAs inserted.

CBOT Check maintenance of vital auxiliarie s: Main turbine tripped.

Generator output and exciter breaker s open. All 4160v and 6900 v No n-Vital busses NOT energized.

All 4160v and 480v vital AC bus energized. (see event 6)

All 125v vital DC bus energized.

Page 9 of 13

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 Event No.: 4 Event

Description:

Cond enser air in-leakage exceeds the ca pacity of the vacuum pu mps. This results in a r eactor trip.

Time Position Applicant's Actions or B ehavior CBOR Check inventory control:

PZR level 1 6 to 80%.

Trend to set point. (See event 5/6)

CBOR Check RCS pressure co ntrol: RCS pressure 1800 to 2 300 psia.

Trend to set point CBOR Check core heat remova l by forced circulation:

RCP 's running Loop T less than 10 F. RCS MTS 3 0 F or greater.

Service wat e r pump suction aligned to Lake. Component cooling wate r aligned to RCPs. SW to align ed to CCW and ACW CBOT Check RCS Heat Remo val: Report SG l e vels Main feed water is se cur ed. Manually actuate EFW.

Report feed water line is NOT intact.

Report SG p r essures Shut both MSIV's due to 2CV 0400 and 2CV 0460, Main Steam to the moisture separator reheaters, have no pow er and are open. Page 10 of 1 3

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 Event No.: 4 Event

Description:

Cond enser air in-leakage exceeds the ca pacity of the vacuum pu mps. This result s in a reactor t r ip. Time Position Applicant's Actions or B ehavior CBOR Check CNTMT paramet ers: Temperature less than 140 F. Pressure less than 16 psia.

Status of ra diation alar ms: CAMS (2 K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT i n alarm Seconda ry Sys Radiation Hi (2K11-A10) NOT in alarm CRS Notify SM to perform the following:

SE report to control roo

m. Announce reactor trip o n plant page. Refer to Tech Specs and EALs. Termination criteria: CRS has diagnosed a Loss of All Feed event and transitions to EOP or at d i scretion of lead examiner.

Page 11 of 1 3

Appendix D Scena rio 3 Form ES-D-1 Op-Test No.: 1

Scenario No.: 3 Event No.: 5 and 6 Event

Description:

Start up transfor m er #3 lockout and feed er breaker fr om Startup transformer #2 to 2A1, non-vital 4160VAC bus fails to open.

This will re sult in a lo ss of offsite power and automatic sta r t of both e m ergency di esel generat ors (#1 and

1. 2 EDG). CRS Verify Servi c e Water is aligned to #

1 EDG and #2 EDG. CBOT Report that service water is not align ed to #1 EDG and that service water is alig ned 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 chan nel 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.

Page 12 of 1 3

Appendix D Scenario 3 Form ES-D-1 Page 13 of 13 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 at < 150 GPM for five minutes or until level rise is observed.

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.