Latest revision as of 02:17, 15 March 2020

Text

01-2005 - Final Operating Exam
	ML050690411
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/27/2005
From:	Gody A; Operations Branch IV
To:	Forbes J; Entergy Operations
References
	-RFPFR, 50-368/05-301 50-368/05-301
	Download: ML050690411 (188)
	v • d • e

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: SRO:

X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH:

X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: LAB:

Perform 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)

EXAMINERS NOTE:

The steps of this surveillance may be performed in any order.

1. Verify SU-2 status. Verified only SU #2 to 2A2, 2H1, N/A SAT UNSAT 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 NAd the rest.

On Supplement 4, 3.0 table 1 circled NA for UA to 2A1 and UA to 2A2.

2. Verify SU-2 To 2A1 (2A-111) Verified 2A-111 green and white N/A SAT UNSAT status. 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.

3. Verify SU-2 To 2A2 (2A-211) Verified 2A-211 green and white N/A SAT UNSAT status. 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.

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 Verified 2A-309 CLOSED. N/A SAT UNSAT (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.

5. Verify 2A4 Supply breaker Verified 2A-409 CLOSED. N/A SAT UNSAT (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.

6. Verify SU-2 voltage. Using SPDS-EST2R OR PMS N/A SAT UNSAT E4013, verified SU-2 voltage

> 154 KV.

EXAMINERs CUE:

On Supplement 4, Table 2, ER-ANO-2004-0548 is not recorded SU-2 voltage in installed. "Measured Value" column.

On Supplement 4, Table 2, circled "YES" for SU-2 voltage WITHIN ACCEPTABLE NORMAL RANGE.

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 Contacted dispatcher to N/A SAT UNSAT if ANO switchyard capacitors "in determine if ANO switchyard service" or not required. capacitors "in service" or not required.

EXAMINERS CUE:

On Supplement 4, Table 2, Dispatcher reports ANO placed a check in ANO switchyard capacitors "in switchyard capacitor "Measured service".

Value" column.

On Supplement 4, Table 2, circled "YES" for ANO switchyard capacitor WITHIN ACCEPTABLE NORMAL RANGE.

8. Contact dispatcher to determine Contacted dispatcher to N/A SAT UNSAT if Russellville East Substation determine if Russellville East capacitors "in service" or not Substation capacitors "in service" required. or not required.

EXAMINERS CUE: On Supplement 4, Table 2, placed a check in Russellville Dispatcher reports East Substation capacitor Russellville East Substation "Measured Value" column.

capacitors "in service".

On Supplement 4, Table 2, circled "YES" for Russellville East Substation capacitor status WITHIN ACCEPTABLE NORMAL RANGE.

9. Contact dispatcher to determine Contacted dispatcher to N/A SAT UNSAT if any other condition that could determine if any other condition degrade offsite power sources that could degrade offsite power is known. sources was known.

EXAMINERS CUE: On Supplement 4, Table 2, placed a check in "Measured Dispatcher reports NO Value" column for other conditions which could conditions known which could degrade offsite are power degrade offsite power.

known.

On Supplement 4, Table 2, circled "YES" for other conditions known which could degrade offsite power WITHIN ACCEPTABLE NORMAL RANGE.

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 Contacted dispatcher to N/A SAT UNSAT determine if SU-2 automatic determine if SU-2 Automatic voltage regulator is in service or Voltage Regulator is in service or not required. if it is not required.

EXAMINERS CUE: On Supp 4 Table 2, placed check in status column for SU-2 Voltage SU-2 Automatic Voltage Regulator in service.

Regulator is in service.

On Supp 4 Table 2, circled YES for SU-2 voltage regulator WITHIN ACCEPTABLE NORMAL RANGE.

11. Verify SU-3 To 2A1 (2A-113) Checked 2A-113 green and white N/A SAT UNSAT status. 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.

12. Verify SU-3 To 2A2 (2A-213) Verified 2A-213 green and white N/A SAT UNSAT status. 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.

13. Verify 2A3 Supply breaker Verified 2A-309 CLOSED. N/A SAT UNSAT (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.

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 Verified 2A-409 CLOSED. N/A SAT UNSAT (2A-409) CLOSED.

Observed red light ON for 2A-409.

EXAMINERS CUE: On Supplement 4, Table 3, placed a check in 2A-409 Red light ON for 2A409 to "Measured Value" column.

2A4.

On Supplement 4, Table 3, circled "YES" for 2A-409 WITHIN ACCEPTABLE NORMAL RANGE.

15. Verify SU-3 Voltage. Using SPDS point E2ST3R, OR N/A SAT UNSAT 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.

15. Contact dispatcher to determine Contacted dispatcher to N/A SAT UNSAT Auto-Transformer status. determine if Auto-Transformer 500 KV source was connected.

On Supplement 4, Table 3, EXAMINERS CUE:

placed a check in Dispatcher reports 500 KV Auto-Transformer 500 KV source source connected to AUTO "Measured Value" column.

transformer.

On Supplement 4, Table 3, circled "YES" for Auto-Transformer 500 KV source WITHIN ACCEPTABLE NORMAL RANGE.

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 Contacted dispatcher to N/A SAT UNSAT determine if SU-3 automatic determine if SU-3 Automatic voltage regulator is in service or Voltage Regulator is in service or not required. if it is not required.

On Supp 4 Table 3, placed check in status column for SU-3 Voltage EXAMINERS CUE:

Regulator in service.

SU-3 Automatic Voltage On Supp 4 Table 3, circled YES Regulator is in service.

for SU-3 voltage regulator WITHIN ACCEPTABLE NORMAL RANGE..

17. Verify both SU-2 and SU-3 Verified both SU-2 and SU-3 N/A SAT UNSAT operable. operable as shown in Table 2 and Table 3.

Circled "YES" in step 3.1.1.

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 Evaluated steps 3.1.1 through N/A SAT UNSAT 3.1.3 for "NO" answers. 3.1.2 for "NO" answers.

Determined that there were no "NO" answers NAd bullets below 3.1.4.

EXAMINERs NOTE: This starts section 3.2, of electrical checklist.

20. Verify 2A3-2A4 Tie Breaker Verified 2A-310 OPEN. N/A SAT UNSAT (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.

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 Verified 2A-410 OPEN. N/A SAT UNSAT (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.

22. Verify 2A3 voltage. On panel 2C33 OR using SPDS N/A SAT UNSAT 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.

23. Determine 2A3 Operability Knowing the status of 2VEF-56B, N/A SAT UNSAT weather data and Table 4 data, USED the flow chart to verify 2A3 operable.

24. Verify 2A3-2A4 Tie Breaker Verified 2A-310 OPEN. N/A SAT UNSAT (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.

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 Verified 2A-410 OPEN. N/A SAT UNSAT (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.

26. Verify 2A4 voltage. On panel 2C33 OR using SPDS N/A SAT UNSAT 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.

27. Determine 2A4 Operability Knowing the status of 2VEF-56A, N/A SAT UNSAT weather data and Table 4 data, USED the flow chart to verify 2A4 operable.

28. Verify both 2A3 and 2A4 Verified both 2A3 and 2A4 N/A SAT UNSAT operable. operable as shown in Table 4 and Table 4.

Circled "YES" in step 3.2.1.

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 Evaluated steps 3.2.1 and 3.2.2 N/A SAT UNSAT for "NO" answers. for "NO" answers.

Determined 2A3 and 2A4 to be operable.

And NAd initialed step 3.2.3.

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 Verified 2B-513 OPEN. N/A SAT UNSAT (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.

32. Verify 2B5-2B6 Tie Breaker Verified 2B-613 OPEN. N/A SAT UNSAT (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 N/A SAT UNSAT 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.

(C) 34. Determine 2B5 Operability Using the Low voltage recorded N/A SAT UNSAT in Table 6, used flow chart to determine that 2B5 is INOPERBLE.

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 Verified 2B-513 OPEN. N/A SAT UNSAT (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.

36. Verify 2B5-2B6 Tie Breaker Verified 2B-613 OPEN. N/A SAT UNSAT (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 N/A SAT UNSAT 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.

(C) 38. Determine 2B6 Operability Using the status of 2VEF-56A, N/A SAT UNSAT 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.

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 Verified 2B5 INOPERABLE and N/A SAT UNSAT 2B6 OPERABLE. 2B6 OPERABLE as shown in Table 6 and Table 7.

Circled "NO" in step 3.3.1.

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 Evaluated steps 3.3.1 and 3.3.2 N/A SAT UNSAT for "NO" answers. for "NO" answers.

Determined 2B5 to be INOPERABLE and 2B6 to be EXAMINERs CUE:

operable.

Do not refer to Tech Specs the SM will perform that for you.

Inform the SM SM has been informed.

Initiate CR Initiating Condition Report has been simulated complete.

Initialed steps 3.3.3.

NOTE CRITICAL PART OF THIS STEP IS DECLARING 2B5 INOPERABLE.

END

JPM- ANO-2-JPM-NRC-ADMIN Electrical System alignment and availability check PAGE 14 OF 15 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs 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 EXAMINEEs 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: LAB:

Perform 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 Review Table 3, startup 3 and N/A SAT UNSAT 2107.001 Supplement 4 and identified that SU #3 voltage is identify Table3, startup 3 has lower than acceptable.

been completed incorrectly.

(C) 2. Declared SU #3 inoperable. Determined that SU #3 should be N/A SAT UNSAT declared inoperable due to low voltage.

(C) 3. Identified Technical Identified that Technical N/A SAT UNSAT Specification 3.8.1.1 is Specification 3.8.1.1 LCO is applicable. applicable and that action A.1, performance of OP 2107.001 Supplement 4 must be performed within one hour.

4. Initiate Condition report. Identified need to initiate N/A SAT UNSAT condition report.

EXAMINERs CUE:

Condition report will be initiated by Shift Engineer.

END STOP TIME:

JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS 100% power; 250 EFPD. All ESF systems are in normal alignment. No severe weather is forecasted.

Low grid voltage is expected to be restored to normal by 2300 today. 2VEF-56A and 2VEF56B are both operable.

Initiating CUE:

The SM directs, Perform section 4.0, Supervisor review and identify the errors in the partial completion of OP 2107.001, Supplement 4 (sections 2, 3.0, 3.1, 3.2, and 3.3.)

JPM- ANO-2-JPM-NRC-ADMIN supervisor review of 2107.001 sup. 4 PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs 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 Conduct 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: LAB:

Perform 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 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.

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 volume 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 On 2104.006, Attachment F N/A SAT UNSAT Level. recorded initial Spent Fuel Pool level of 401 0 given in initial conditions.

Examiners 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 Obtained Gal/Ft value for Fuel N/A SAT UNSAT Volume. Pool - Top of racks to Elev 4016 (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 4016 (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.

3. Record desired Spent Fuel On 2104.006, Attachment F N/A SAT UNSAT Pool Level. recorded desired Spent Fuel Pool level of 401 4.

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 Obtained Gal/Ft value for Fuel N/A SAT UNSAT Pool Volume. Pool - Top of racks to Elev 4016 (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 4016 (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.

C 5. Calculate volume of makeup Subtracted initial Spent Fuel Pool N/A SAT UNSAT required to raise Spent Fuel volume from desired Spent Fuel Pool level to desired level. Pool volume and determined amount of makeup needed to be Total Volume within 1828 to 1878 gallons.

1928.

6. Record A BAMT boron On 2104.006, Attachment F, N/A SAT UNSAT concentration. recorded value of 5950 ppm for A BAMT concentration.

C 7. Calculate feed volume of boric Inserted values into formula and N/A SAT UNSAT acid required to raise pool level. determined Boric acid volume to Volume within 910 gallons to be 935.53 gallons.

960 gallons.

C 8. Calculate the feed volume of DI Inserted values into formula and N/A SAT UNSAT water required to raise pool determined DI water volume to level. Volume within 918 be 942.47 gallons.

gallons to 968 gallons.

END STOP TIME:

JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS 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 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.

JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES 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 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.

JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: A1b Conduct 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: LAB:

Perform 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 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.

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 Reviewed the completed form N/A SAT UNSAT OP 2104.006, Attachment F. OP 2104.006, Attachment F.

2. Determined the calculated Calculated the feed volume to be N/A SAT UNSAT volume of solution to be correct. added to the SFP, F, to be 1878 gallons.

C 3. Determined that the boron Recognized the boron N/A SAT UNSAT concentration of the feed concentration of the feed source source was in error. was recorded as 4950 ppm instead of the given value of 5940 ppm.

C 4. Determined the calculated Recognized that the feed volume N/A SAT UNSAT volume of solution used in the to be added to the SFP, F, was calculation of the feed volumes recorded in error as 1788 gallons of boric acid NOT the 1878 gallons calculated on the previous page.

Examiners Note: the candidate may need to be prompted to calculate the volume of Boric acid and DI water.

C 5. Determined the Boron volume Recognized the Boron volume to N/A SAT UNSAT to be added as calculated was be added as calculated was in in error and determined the error and determined the correct correct volume to be 910 volume to be 935.5 gallons.

gallons to 960 gallons.

C 6. Determined the DI water Recognized the DI water volume N/A SAT UNSAT volume to be added as to be added as calculated was in calculated was in error and error and determined the correct determined the correct volume volume to be 942.5 gallons.

to be within 918 gallons to 968 gallons.

END STOP TIME:

JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS 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 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.

JPM-#- ANO-2-JPM-NRC-ADMIN SFPMU PAGE 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES 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 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.

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: A.2: Equipment Control TASK: Review completed 2P89B surveillance and determine 2P-89B operability JTA#:

KA VALUE RO: 3.5 SRO: 3.9 KA

REFERENCE:

2.2.12 APPROVED FOR ADMINISTRATION TO: RO: SRO:

X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH:

X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: LAB:

Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2104.039 Supplement 2 Rev. 042-04-0 EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment.

2P89C is aligned to the GREN side.

The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.

TASK STANDARD: (Identification of three of the four errors is required and one of the three must be the Pump D/P)

Pump P is out of LIMITING RANGE FOR OPERABILITY.

Calculation for determining lower pump P limit is in error.

Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY.

Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.

TASK PERFORMANCE AIDS: marked-up copy of Supplement 2 2P-89B quarterly test SIMULATOR SETUP: NA

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:

The Control Room Supervisor/Shift Manager directs determination of the operability of the B HPSI pump, 2P89B, by reviewing the completed surveillance data OP 2104.039 Supplement 2, complete all reviews for operability, calculations performed and identify all errors.

CRITICAL STEPS: 2, 3, 4, 5 START TIME:

PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide a marked-up copy of Supplement 2, 2P-89B quarterly test

1. Perform review of the surveillance Reviews the surveillance procedure N/A procedure results. provided.

(C) 2.

Pump P is out of LIMITING Pump D/P is out of LIMITING RANGE RANGE FOR OPERABILITY. FOR OPERABILITY. N/A SAT UNSAT (C) 3. Calculation for determining lower Calculation for determining lower pump pump P limit is in error. P limit should be 1380.81 psid. N/A SAT UNSAT This calculation is below the table in supplement 2 section 3 and recorded in the table on the line for pump P.

(C) 4. Inboard Radial Bearing #1 Vibes Inboard Radial Bearing #1 Vibes is out of is out of LIMITING RANGE FOR LIMITING RANGE FOR OPERABILITY. N/A SAT UNSAT OPERABILITY.

(C) 5. Outboard Bearing AXIAL Vibes is Outboard Bearing AXIAL Vibes is out of out of LIMITING RANGE FOR LIMITING RANGE FOR OPERABILITY. N/A SAT UNSAT OPERABILITY.

EXAMINERs CUE: The Shift Engineer will enter the pump data into the database.

6. Report to CRS that the results of Reports to CRS that results of the the surveillance are unsatisfactory surveillance are unsatisfactory and N/A SAT UNSAT and 2P89B is inoperable. 2P89B is inoperable.

END STOP TIME:

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment.

2P89C is aligned to the GREEN side. The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.

Initiating CUE:

The Control Room Supervisor/Shift Manager directs determination of the operability of the B HPSI pump, 2P89B, by reviewing the completed surveillance data OP 2104.039 Supplement 2, complete all reviews for operability, calculations performed and identify all errors.

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment.

2P89C is aligned to the GREEN side. The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.

Initiating CUE:

The Control Room Supervisor/Shift Manager directs determination of the operability of the B HPSI pump, 2P89B, by reviewing the completed surveillance data OP 2104.039 Supplement 2, complete all reviews for operability, calculations performed and identify all errors.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 61 of 148 2104.039 HPSI SYSTEM OPERATION CHANGE:

SUPPLEMENT 2 PAGE 7 OF 9 3.0 ACCEPTANCE CRITERIA 3.1 Record values observed during 2P-89B operation below AND compare with limiting range of values for operability.

Record date and time Test begins TODAYs DATE / 0800 TABLE 1 TEST QUANTITY INSTRUMENT MEASURED ACCEPTABLE LIMITING IS DATA IN (INCLUDE VALUE NORMAL RANGE FOR LIMITING TEST INST) RANGE OPERABILITY RANGE?

Running Suct. 2PI-5100 33.5 psig 8 psig 8 psig YES NO Pressure (local) 2PI-5101 1389 psig N/A N/A N/A (local)

Discharge 2PI-5109 Pressure 1379 psig N/A N/A N/A (2C16)

RWT 2TIS-5675 Temperature (2C17) 90 °F 40 to 110°F N/A N/A Pump P 2PI-5101 - 1360.81(1)to 1355.5 psid N/A YES NO

{4.3.1} 2PI-5100 1612.8 psid Motor Running Ammeter at A 34 Amps N/A N/A N/A Amps 2A-406 B 33 Amps (CR-1-96-0272- C 35 Amps 07)

Inboard Brg VIB001 0.325 0.700 0.825 in/sec YES NO Radial #1 in/sec in/sec Vibes Inboard Brg VIB001 0.325 0.700 0.22 in/sec YES NO Radial #2 in/sec in/sec Vibes Inboard Brg VIB001 0.325 0.700 0.073 in/sec YES NO Axial Vibes in/sec in/sec Outboard Brg VIB001 0.325 0.700 0.187 in/sec YES NO Radial #1 in/sec in/sec Vibes Outboard Brg VIB001 0.325 0.700 0.207 In/sec YES NO Radial #2 in/sec in/sec Vibes Outboard Brg VIB001 0.232 0.558 0.610 In/sec YES NO Axial Vibes in/sec in/sec Record date and time Test completed TODAYs DATE 0930 Vibration Instrument Cal Due Date 7 days from TODAY Vibration Data Collected By Eddy Electrician Note 1: For RWT temperature (T), minimum acceptable pump P is:

1372.9 + 20.41 (Instrument error) - [(T-40)/4] psid Minimum P = 1393.31 - [( 90 - 40)/4] = 1360.81 psid 3.2 Independently verify pump P calculation.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 62 of 148 2104.039 HPSI SYSTEM OPERATION CHANGE:

SUPPLEMENT 2 PAGE 8 OF 9 3.3 Document observation of check valve stroke in Table 2.

TABLE 2 CHECK TEST TEST CRITERIA IS PROPER VALVE VALVE DIRECTION STROKE INDICATED?

2SI-10C Closed 2P-89C NOT rotating YES NO N/A 2SI-10B Closed 2P-89B NOT rotating YES NO N/A 3.4 IF NO circled in Table 1 OR 2, THEN perform the following:

Declare affected component inoperable.

Refer to Tech Spec 3.5.2 OR 3.5.3.

Notify Shift Manager.

Initiate WR/WO as applicable.

NOTE If HPSI pump 2P-89A OR 2P-89C inoperable, then 2SI-10C/2SI-10B testing may be deferred until inoperable HPSI pump restored to operable as per IST Coordinator.

3.5 IF 2SI-10C AND/OR 2SI-10B NOT tested (N/A circled in Table 2),

THEN perform the following:

Initiate notification to perform test during current quarter OR as directed by IST Coordinator. N/A

Annotate on status board. N/A

Annotate in Work Exceptions section of WR/WO. N/A 3.6 Pump Data recorded in database AND reviewed by SRO.

3.7 IF this surveillance performed as PMT, THEN complete Unit 2 IST Data Collection (1015.016O). N/A Comments ________________________________________________________________

Performed By Jimmy Reactor Date TODAY_____

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 63 of 148 2104.039 HPSI SYSTEM OPERATION CHANGE:

SUPPLEMENT 2 PAGE 9 OF 9 4.0 SUPERVISOR REVIEW AND ANALYSIS 4.1 Do all measured values recorded in ACCEPTANCE CRITERIA fall within specified LIMITING RANGE FOR OPERABILITY? YES NO 4.2 Do all measured values recorded in ACCEPTANCE CRITERIA fall within ACCEPTABLE NORMAL RANGE? (N/A if all results outside YES NO N/A normal range also outside limiting range.)

4.3 IF NO answered to 4.1, THEN perform the following corrective actions:

Verify Inoperable Equipment Checklist (1015.001, Conduct of Operations) completed.

Verify Condition Report initiated.

4.4 IF NO circled in 4.2, THEN perform the following corrective actions:

Verify WR/WO has been initiated.

Complete Surveillance Test Schedule Change Request (1000.009D) to double test frequency.

Comments ________________________________________________________________

4.5 Are all administrative requirements of this test satisfied?

YES NO Supervisor ______________________________________________ Date __________

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: A.2: Equipment Control TASK: Review and approve as a supervisor the completed 2P89B surveillance.

JTA#:

KA VALUE RO: 3.5 SRO: 3.9 KA

REFERENCE:

2.2.12 APPROVED FOR ADMINISTRATION TO: RO: SRO:

X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH:

X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: LAB:

Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2104.039 Supplement 2 Rev. 042-04-0 EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment.

2P89C is aligned to the GREEN side.

The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.

TASK STANDARD:

(Identification of Five of the Six errors is required and two of the six must be the Pump D/P and the tech spec applicabiltiy)

Pump P is out of LIMITING RANGE FOR OPERABILITY.

Calculation for determining lower pump P limit is in error.

Inboard Radial Bearing #1 Vibes is out of LIMITING RANGE FOR OPERABILITY.

Outboard Bearing AXIAL Vibes is out of LIMITING RANGE FOR OPERABILITY.

Determine TS 3.5.2 applicability

Yes is circled on parameters that do not meet acceptance criteria TASK PERFORMANCE AIDS: marked-up copy of Supplement 2 2P-89B quarterly test SIMULATOR SETUP: NA

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:

The Shift Manager directs perform supervisor review and analysis of the B HPSI pump, 2P89B, by reviewing and identifying all errors on the completed surveillance data OP 2104.039 Supplement 2.

CRITICAL STEPS: 2, 3, 4, 5, 6, 7 START TIME:

PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide a marked-up copy of Supplement 2, 2P-89B quarterly test

1. Perform supervisor review of the Reviews the surveillance acceptance N/A surveillance procedure results and criteria provided.

determine errors.

EXAMINERs NOTE: the following are the errors in the form provided.

(C) 2. Pump P is out of LIMITING Pump D/P is out of LIMITING RANGE RANGE FOR OPERABILITY. FOR OPERABILITY. N/A SAT UNSAT (C) 3. Calculation for determining lower Calculation for determining lower pump pump P limit is in error. P limit should be 1380.81 psid. N/A SAT UNSAT This calculation is below the table in supplement 2 section 3 and recorded in the table on the line for pump P.

(C) 4. Inboard Radial Bearing #1 Vibes Inboard Radial Bearing #1 Vibes is out of is out of LIMITING RANGE FOR LIMITING RANGE FOR OPERABILITY. N/A SAT UNSAT OPERABILITY.

(C) 5. Outboard Bearing AXIAL Vibes is Outboard Bearing AXIAL Vibes is out of out of LIMITING RANGE FOR LIMITING RANGE FOR OPERABILITY. N/A SAT UNSAT OPERABILITY.

(C) 6. Identify the technical specification Identifies TS 3.5.2 applicability.

applicability error. N/A SAT UNSAT (C) 7. Identified that YES was circled on Identifies that YES was circled on parameters that did not meet parameters that did not meet acceptance N/A SAT UNSAT acceptance criteria. criteria.

EXAMINERs NOTE: The candidate will probably require another RO to review the data table before proceeding.

Ask the candidate to continue on with completing section 4.0 as though that review matched the same errors previously identified.

8. Inoperable equipment checklist Identifies need to perform inoperable needed. equipment checklist must be completed. N/A SAT UNSAT EXAMINERs CUE:

The SRO ADMIN will perform the inoperable equipment checklist.

9. Condition Report needed. Identifies need to generate condition report. N/A SAT UNSAT EXAMINERs CUE:

The SE will initiate the condition report.

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE END STOP TIME:

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment.

2P89C is aligned to the GREEN side.

The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.

Initiating CUE:

The Shift Manager directs perform supervisor review and analysis of the B HPSI pump, 2P89B, by reviewing and identifying all errors on the completed surveillance data OP 2104.039 Supplement 2.

JPM-ANO-2-JPM-ADMIN-Surveillance review 2P89B PAGE 6 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS Plant is at 100% power and all ESF equipment is in normal alignment.

2P89C is aligned to the GREEN side.

The 2P-89B Quarterly test has been completed using OP 2104.039 Supplement 2.

Initiating CUE:

The Shift Manager directs perform supervisor review and analysis of the B HPSI pump, 2P89B, by reviewing and identifying all errors on the completed surveillance data OP 2104.039 Supplement 2.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 61 of 148 2104.039 HPSI SYSTEM OPERATION CHANGE:

SUPPLEMENT 2 PAGE 7 OF 9 3.0 ACCEPTANCE CRITERIA 3.1 Record values observed during 2P-89B operation below AND compare with limiting range of values for operability.

Record date and time Test begins TODAYs DATE / 0800 TABLE 1 TEST QUANTITY INSTRUMENT MEASURED ACCEPTABLE LIMITING IS DATA IN (INCLUDE VALUE NORMAL RANGE FOR LIMITING TEST INST) RANGE OPERABILITY RANGE?

Running Suct. 2PI-5100 33.5 psig 8 psig 8 psig YES NO Pressure (local) 2PI-5101 1389 psig N/A N/A N/A (local)

Discharge 2PI-5109 Pressure 1379 psig N/A N/A N/A (2C16)

RWT 2TIS-5675 Temperature (2C17) 90 °F 40 to 110°F N/A N/A Pump P 2PI-5101 - 1360.81(1)to 1355.5 psid N/A YES NO

{4.3.1} 2PI-5100 1612.8 psid Motor Running Ammeter at A 34 Amps N/A N/A N/A Amps 2A-406 B 33 Amps (CR-1-96-0272- C 35 Amps 07)

Inboard Brg VIB001 0.325 0.700 0.825 in/sec YES NO Radial #1 in/sec in/sec Vibes Inboard Brg VIB001 0.325 0.700 0.22 in/sec YES NO Radial #2 in/sec in/sec Vibes Inboard Brg VIB001 0.325 0.700 0.073 in/sec YES NO Axial Vibes in/sec in/sec Outboard Brg VIB001 0.325 0.700 0.187 in/sec YES NO Radial #1 in/sec in/sec Vibes Outboard Brg VIB001 0.325 0.700 0.207 In/sec YES NO Radial #2 in/sec in/sec Vibes Outboard Brg VIB001 0.232 0.558 0.610 In/sec YES NO Axial Vibes in/sec in/sec Record date and time Test completed TODAYs DATE 0930 Vibration Instrument Cal Due Date 7 Days from TODAY Vibration Data Collected By Eddy Electrician Note 1: For RWT temperature (T), minimum acceptable pump P is:

1372.9 + 20.41 (Instrument error) - [(T-40)/4] psid Minimum P = 1393.31 - [( 90 - 40)/4] = 1360.81 psid 3.2 Independently verify pump P calculation. JJB

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 62 of 148 2104.039 HPSI SYSTEM OPERATION CHANGE:

SUPPLEMENT 2 PAGE 8 OF 9 3.3 Document observation of check valve stroke in Table 2.

TABLE 2 CHECK TEST TEST CRITERIA IS PROPER VALVE VALVE DIRECTION STROKE INDICATED?

2SI-10C Closed 2P-89C NOT rotating YES NO N/A 2SI-10B Closed 2P-89B NOT rotating YES NO N/A 3.4 IF NO circled in Table 1 OR 2, THEN perform the following:

Declare affected component inoperable. N/A

Refer to Tech Spec 3.5.2 OR 3.5.3. N/A

Notify Shift Manager. N/A

Initiate WR/WO as applicable. N/A NOTE If HPSI pump 2P-89A OR 2P-89C inoperable, then 2SI-10C/2SI-10B testing may be deferred until inoperable HPSI pump restored to operable as per IST Coordinator.

3.5 IF 2SI-10C AND/OR 2SI-10B NOT tested (N/A circled in Table 2),

THEN perform the following:

Initiate notification to perform test during current quarter OR as directed by IST Coordinator. N/A

Annotate on status board. N/A

Annotate in Work Exceptions section of WR/WO. N/A 3.6 Pump Data recorded in database AND reviewed by SRO. SBR 3.7 IF this surveillance performed as PMT, THEN complete Unit 2 IST Data Collection (1015.016O). N/A Comments ________________________________________________________________

Performed By Sammy Reactor Date TODAY Jimmy Reactor

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 63 of 148 2104.039 HPSI SYSTEM OPERATION CHANGE:

SUPPLEMENT 2 PAGE 9 OF 9 4.0 SUPERVISOR REVIEW AND ANALYSIS 4.1 Do all measured values recorded in ACCEPTANCE CRITERIA fall within specified LIMITING RANGE FOR OPERABILITY? YES NO 4.2 Do all measured values recorded in ACCEPTANCE CRITERIA fall within ACCEPTABLE NORMAL RANGE? (N/A if all results outside YES NO N/A normal range also outside limiting range.)

4.3 IF NO answered to 4.1, THEN perform the following corrective actions:

Verify Inoperable Equipment Checklist (1015.001, Conduct of Operations) completed.

Verify Condition Report initiated.

4.4 IF NO circled in 4.2, THEN perform the following corrective actions:

Verify WR/WO has been initiated.

Complete Surveillance Test Schedule Change Request (1000.009D) to double test frequency.

Comments ________________________________________________________________

4.5 Are all administrative requirements of this test satisfied?

YES NO Supervisor ______________________________________________ Date __________

JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: A.3 Radiation Control TASK: Review the emergency RWP and determine stay time based on radiation levels expected.

JTA#:

KA VALUE RO: 2.9 SRO: 3.3 KA

REFERENCE:

2.3.10 APPROVED FOR ADMINISTRATION TO: RO: SRO:

X X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Perform SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 2004-0009; emergency RWP and status board printout of Aux Building 354.

EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS

1. Plant is DEFUELED and all FUEL HANDLING operations are secured.

2. Power has been lost to both SFP cooling pumps and 2K11-K5 FUEL POOL TEMP HI is in alarm.

3. A Site Area Emergency has been declared on Unit 2 due to a station blackout. Power has been restored to 2A3 and 2B5 from the Alternate AC Generator, AACG.

4. Service water must be aligned to the SFP due to boiling and loss of inventory through the tilt pit gate.

5. Fuel Pool low level alarm is in and SFP level is lowering.

6. RP coverage will not be available.

TASK STANDARD:

Using Emergency RWP:

Identify General Area, GA, dose rates in SFP valve gallery are ~ 500 MR/HR.

Determine a maximum stay time of 1.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months based on EAD alarm set-points.

Using normal inspection RWP:

Determine appropriate dosimeter

Entered RCA

Observed proper radiological controls while in RCA

Properly uses the PCM-1

Properly scans loose items in TCM JPM time is based on the review of the emergency RWP and the calculation of the stay time.

TASK PERFORMANCE AIDS: Emergency RWP 2004-0009 SIMULATOR SETUP: NA

JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:

The Shift Manager directs that Service water from loop I must be aligned to the SFP, use the Emergency Radiological Work Permit, RWP, and identify the maximum allowable time before you would be required to leave the Auxiliary Building 354 elevation SFP valve gallery, excluding entry and exit times to and from the area.

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

PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide Emergency RWP.

EXAMINERs CUE: The candidate may attempt to check out a radiation survey meter per monitoring step 7.0. It is not a part of this JPM to check out the survey meter, but that the candidate knows one is needed.

1. Review Emergency RWP for Determines that the alarming dosimeter N/A limits. is set to alarm in an 800mr/hr field and that the Dose alarm is set at 800 mrem.

(C) 2.

Determine stay time in SFP valve Using the status board printout provided gallery to be a maximum of 1.6 determined that the General Area (GA) N/A SAT UNSAT hours. field is 500 MR/HR so the maximum stay time will be 1.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

EXAMINERs NOTE: The rest of these steps determine the candidates ability to enter and exit controlled access correctly using the Actual RWP for inspections, DO NOT allow the candidate to use the emergency RWP to enter controlled access.

(C) 3. Determined that an alarming Obtained an alarming dosimeter from dosimeter will be required for rack. N/A SAT UNSAT entry into the Radiologically Controlled Area, RCA, using the normal inspection RWP.

(C) 4. Entered appropriate information Entered the RCA under the general into the log in screen and inspection RWP. N/A SAT UNSAT successfully entered the RCA.

(C) 5. While in the RCA the examinee While in the RCA the examinee observes observes and adheres to all and adheres to all applicable postings N/A SAT UNSAT applicable postings and entry and entry requirements.

requirements.

(C) 6. When exiting the RCA the Enters and exits PCM-1.

examinee enters the control point N/A SAT UNSAT area and enters a PCM-1 monitor.

7. All loose materials will be cleared Examinee places loose items in the TCM through the tool contamination for counting. N/A SAT UNSAT monitor (TCM)

8. After clearing the PCM-1 monitor, Examinee clears the Portal Monitor the examinee exits through the N/A SAT UNSAT Portal Monitor

9. Examinee deactivates EAD at Examinee deactivates his EAD and final exit of session returns it to the Health Physics rack. N/A SAT UNSAT END STOP TIME:

JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS

1. Plant is DEFUELED and all FUEL HANDLING operations are secured.

2. Power has been lost to both SFP cooling pumps and 2K11-K5 FUEL POOL TEMP HI is in alarm.

3. A Site Area Emergency has been declared on Unit 2 due to a station blackout. Power has been restored to 2A3 and 2B5 from the Alternate AC Generator, AACG.

4. Service water must be aligned to the SFP due to boiling and loss of inventory through the tilt pit gate.

5. Fuel Pool low level alarm is in and SFP level is lowering.

6. RP coverage will NOT be available.

Initiating CUE:

The Shift Manager directs that Service water from loop I must be aligned to the SFP, use the Emergency RWP and identify the maximum allowable time before you would be required to leave the Auxiliary Building 354 elevation SFP valve gallery, excluding entry and exit times to and from the area.

JPM-ANO-2-JPM-ADMIN-RWP and stay times PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS

1. Plant is DEFUELED and all FUEL HANDLING operations are secured.

2. Power has been lost to both SFP cooling pumps and 2K11-K5 FUEL POOL TEMP HI is in alarm.

3. A Site Area Emergency has been declared on Unit 2 due to a station blackout. Power has been restored to 2A3 and 2B5 from the Alternate AC Generator, AACG.

4. Service water must be aligned to the SFP due to boiling and loss of inventory through the tilt pit gate.

5. Fuel Pool low level alarm is in and SFP level is lowering.

6. RP coverage will NOT be available.

Initiating CUE:

The Shift Manager directs that Service water from loop I must be aligned to the SFP, use the Emergency RWP and identify the maximum allowable time before you would be required to leave the Auxiliary Building 354 elevation SFP valve gallery, excluding entry and exit times to and from the area.

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: LAB:

Perform 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 for 150 days at 100% power.

A reactor trip occurred two hours ago.

A reactor trip has occurred due to Loss of Coolant Accident estimated to be 700 gpm.

Containment Spray Actuation Signal (CSAS) has actuated.

Containment high range radiation monitors, 2RE8925-1 and 2RE8925-2 are reading 2400 R/HR.

Chemists have been notified to sample the RCS.

TASK STANDARD:

Declared a Site Area Emergency (based on EAL 1.4, Containment radiation readings which indicate LOCA and >1% fuel cladding failure). Also acceptable is a review of the 1903.010 paragraph 4.10, Fission Product Barrier Failure and 4.11, Fission Product Barrier Challenge criteria and determine that two fission product barriers are challenged or failed and classify 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 Review 1903.010 index and EAL N/A SAT UNSAT 1903.010 to determine classification tabs.

classification.

(C) 2. Reviewed 1903.010 attachment Determined that the containment N/A SAT UNSAT 6 containment radiation EAL radiation reading exceeds the plot to determine that Site Area Emergency Criteria.

containment radiation levels exceed the Site area emergency criteria.

(C) 3. Reviewed initial conditions and Determined LOCA inside N/A SAT UNSAT determined that a LOCA inside containment was in progress.

containment was in progress.

(C) 4. Reviewed EAL 1.4., Site Area Classified EAL as a Site Area N/A SAT UNSAT Emergency based on a LOCA Emergency (SAE) based on EAL and > 1% failed fuel. 1.4, Containment Radiation readings which indicate LOCA Or and > 1% fuel cladding failure.

Also acceptable is a review of the 1903.010 paragraph 4.10, OR Fission Product Barrier Failure Classified EAL as a Site Area and 4.11, Fission Product Emergency (SAE) based on EAL Barrier Challenge criteria and 9.3, Plant conditions exist that determine that two fission warrant activation of the product barriers are challenged Emergency Response Facility.

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.

END

JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS

Plant had been operating for 150 days at 100% power.

A reactor trip occurred two hours ago.

A reactor trip has occurred due to Loss of Coolant Accident estimated to be 700 gpm.

Containment Spray Actuation Signal (CSAS) has actuated.

Containment high range radiation monitors, 2RE8925-1 and 2RE8925-2 are reading 2400 R/HR.

Chemists have been notified to sample the RCS.

INITIATING CUE:

As Shift Manager, determine the EAL classification based on the given plant conditions.

JPM- ANO-2-JPM-NRC-ADMIN Classify Event EAL PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS

Plant had been operating for 150 days at 100% power.

A reactor trip occurred two hours ago.

A reactor trip has occurred due to Loss of Coolant Accident estimated to be 700 gpm.

Containment Spray Actuation Signal (CSAS) has actuated.

Containment high range radiation monitors, 2RE8925-1 and 2RE8925-2 are reading 2400 R/HR.

Chemists have been notified to sample the RCS.

INITIATING CUE:

As Shift Manager, determine the EAL classification based on the given plant conditions.

JPM- ANO-2-JPM-NRC-AOP2 PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Containment Cooling Water System TASK: Reset CIAS and establish cooling water to containment JTA#:

KA VALUE RO: 3.1 SRO: 3.2 KA

REFERENCE:

022 A4.04 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): AOP 2203.0039 Rev 03-02-0 EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE 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-AOP2 PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: An inadvertent CIAS has occurred.

Steps 1-10 of AOP 2203.039 have been completed.

TASK STANDARD: CIAS has been reset and containment Chilled water has been realigned.

TASK PERFORMANCE AIDS: Copy of AOP 2203.039 Revision 003-02-0 is available.

AOP 2203.039 Steps 1-10 have been completed.

SIMULATOR SETUP: Inadvertent CIAS present. Containment parameters and RCS parameters are above setpoints, containment pressure < 18.3 psia. Verify CBO to VCT valves, 2CV-4847-2 and 2CV 4846-1 handswitches are in CLOSE.

JPM- ANO-2-JPM-NRC-AOP2 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Perform actions in Inadvertent CIAS, AOP 2203.039, steps 11 through 15."

CRITICAL ELEMENTS (C): 1, 2, 6, 7, 8 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Reset CIAS on 2C23B. Obtained key 15 from Shift N/A SAT UNSAT Manager.

(Proc step Examiners note: On panel 2C23B placed key in

11) trip path keyswitch to UNLK.

Only one channel of PPS is modeled on simulator Depressed CIAS pushbutton for completely. Correctly resetting trip path.

of this channel will reset CIAS trip paths. Placed trip path keyswitch to LK and removed key.

Examiners Cue @ Step 11.D:

All four PPS trip path channels have been reset.

(C) 2. Reset ESF CIAS actuation on Depressed CIAS lockout reset N/A SAT UNSAT 2C40. pushbutton on 2C40-7 and (Proc observed CIAS ON light lit and step Examiners note: observed trip paths lights on

12) panel above 2C23 lit.

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.

3. Go to step 14. Using procedure 2203.039, N/A SAT UNSAT (Proc transition to step 14.

step1 2.c)

4. Open RCP Bleedoff to VCT On panel 2C17, Placed N/A SAT UNSAT valve, 2CV-4846-1. handswitches for RCP bleedoff to (Proc VCT valve 2CV-4846-1 to OPEN.

step

14) Observed RED light ON and GREEN light OFF above hand switch.

JPM- ANO-2-JPM-NRC-AOP2 PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

5. Open RCP Bleedoff to VCT On panel 2C16, Placed N/A SAT UNSAT valve, 2CV-4847-2. handswitches for RCP bleedoff to (Proc VCT valve 2CV-4847-2 to OPEN.

step

14) Observed RED light ON and GREEN light OFF above hand switch.

(C) 6. Open Chilled water to CNTMT On panel 17, placed N/A SAT UNSAT valve 2CV-3851-1. handswitches for Chilled Water to (Proc CNTMT Isolation valve step 2CV-3851-1 to OPEN.

15.a)

Observed RED light ON and GREEN light OFF above hand switch.

(C) 7. Open Chilled water to CNTMT On panel 17, placed N/A SAT UNSAT valve 2CV-3852-1. handswitches for Chilled Water to (Proc CNTMT Isolation valve step 2CV-3852-1 to OPEN.

15a)

Observed RED light ON and GREEN light OFF above hand switch.

(C) 8. Open Chilled water to CNTMT On panel 16, placed N/A SAT UNSAT valve 2CV-3850-2. handswitches for Chilled Water to (Proc CNTMT Isolation valve step 2CV-3850-2 to OPEN.

15a)

Observed RED light ON and GREEN light OFF above hand switch.

9. Verify Main Chiller (2VCH1A) On panel 22, verified hand switch N/A SAT UNSAT running. for 2VCH1A is in normal after (Proc start (RED flagged).

step 15b)

Observed RED light ON and Examiners note: GREEN light OFF above hand The red light above hand switch for 2VCH-1A.

switch for 2VCH-1A indicates the chiller is running.

Observed RED light ON and GREEN light OFF above label for Examiners note: 2HS-3810.

The red light label for 2HS-3810 for 2VCH-1A indicates Observed all chilled water alarms the 2A1 breaker is closed. are clear on annunciator 2K13 (Lights slow flashing or clear).

JPM- ANO-2-JPM-NRC-AOP2 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERs NOTE:

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

END STOP TIME:

JPM- ANO-2-JPM-NRC-AOP2 PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

An inadvertent CIAS has occurred. Steps 1-10 of AOP 2203.039 have been completed.

INITIATING CUE:

The SM/CRS directs, "Perform actions in Inadvertent CIAS, AOP 2203.039, steps 11 through 15."

JPM- ANO-2-JPM-NRC-AOP2 PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

An inadvertent CIAS has occurred. Steps 1-10 of AOP 2203.039 have been completed.

INITIATING CUE:

The SM/CRS directs, "Perform actions in Inadvertent CIAS, AOP 2203.039, steps 11 through 15."

JPM- ANO-2-JPM-NRC-CVCS010 PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Chemical and Volume Control System TASK: Perform Emergency Boration (Alternate Success Path)

JTA#:

KA VALUE RO: 3.9 SRO: 3.7 KA

REFERENCE:

004 A4.07 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 12 Minutes REFERENCE(S): OP 2203.032 Rev. 008-06-0 EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE 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-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" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Mode 3. B CCP tagged out for low pressure operations. C CCP tagged out for gear box repair.

TRM 3.1.2.4 entered for only 1 CCP available with 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months 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 MOVs. This is an alternate success path JPM>

TASK PERFORMANCE AIDS:

AOP 2203.032 Steps 2 through 16. OP 4104.039 section 9, Starting any HPSI pump on recirc.

SIMULATOR SETUP:

A mode 3 IC will be set up for this JPM. RCS cooldown in progress, PZR pressure ~ 1200psia, RCS temp

~480°F. A CCP running. B CCP tagged out for low pressure operations. C CCP tagged out for gear box repair. TRM 3.1.2.4 entered for only 1 CCP available with 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months remaining on the action.

Set T1=2CV-4873-1a < 75% (this will trigger T1 when the VCT outlet gets to 75% open.)

T1 = A CCP plunger failure (flow out of pump ~ 30gpm).

JPM- ANO-2-JPM-RO-CVCS010 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Initiate Emergency Boration using BAMT gravity feed to Charging Pump suction beginning with AOP 2203.032, Step 2."

CRITICAL ELEMENTS (C): 2, 5, 9, 10, 14, 15 START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

1. Verify at least one charging On panel 2C09, verified CCP(s) N/A SAT UNSAT Pump (CCP) running with flow running.

(Proc greater than 40 GPM.

Step Observed red light ON; green light

2) 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).

(C) 2. Align boric acid supply to CCP On panel 2C09, opened BAMT N/A SAT UNSAT suction. gravity feed valves 2CV-4920-1 (Proc and/or 2CV-4921-1 Step 3A1) 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

3. Close volume control tank On panel 2C09, observed that N/A SAT UNSAT (VCT) outlet valve (2CV-4873- 2CV-4873-1 closed.

(Proc 1).

Step Observed green light ON; red light

4) OFF above VCT Outlet valve handswitch (2HS-4873-1).

4. Check Reactor Makeup Water On panel 2C09, verified 2CV-4927 N/A SAT UNSAT Flow Control valve (2CV-4927) or 2CV-4941-2 closed.

(Proc or 2CV 4941-2 closed.

Step Observed green light ON; red light

5) OFF above Reactor Makeup Water Flow Controller (2FIC-4927) or above 2CV-4941-2 handswitch.

(C) 5. Check charging header flow. On panel 2C09 (upright portion), N/A SAT UNSAT (Proc observed flow about 30 gpm on Step Charging Header Flow indicator

6) (2FIS-4863).

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 TCBs On panel 2C14, verifies that the N/A SAT UNSAT open and then transition to TCBs are open by observing the (Proc step 8. green lights ON and red lights Step OFF.

2)

7. Check RCS pressure less than On panel 2C04, SPDS, PMS or N/A SAT UNSAT 1265 psia. PDS verified that PZR pressure is (Proc less than 1265 psia.

Step 8)

8. Verify RWT level greater than On panel 2C16 or 2C17, verified N/A SAT UNSAT 7.5%. RWT level greater than 7.5%.

(Proc Step 9A)

(C) 9. Verify 2CV-5631-2 is OPEN. On panel 2C16 verified RWT outlet N/A SAT UNSAT EXAMINERS CUE: When valve 2CV-5631-2 is OPEN.

(Proc Step asked as CRS, in step 9, 9B) which HPSI pump to start, state that B HPSI pump is to be used. If not asked and goes to 2C17 to verify RWT outlet valve open and start A HPSI pump, state that B HPSI pump is to be started.

NOTE: If Examinee in procedure step 9C, goes to use OP2104.039 section 9.0 then give the following cue.

EXAMINERs CUE: CRS directs to start B HPSI pump first and then verify steps in appropriate section in OP 2104.039.

(C) 10. Start 2P89B, B HPSI Pump. On panel 2C16 rotated handswitch N/A SAT UNSAT for 2P89B to start position.

(Proc Step Observed Red light ON and Green 9C) light OFF.

11. Verify SDC secured. On panel 2C16 and 2C17 verified N/A SAT UNSAT LPSI (SDC) pumps secured.

(Proc Step 10)

12. Check RCS temperature On panel 2C04, SPDS, PMS or N/A SAT UNSAT greater than 450°F. PDS verified RCS temperature (Proc greater than 450°F.

Step 11)

JPM- ANO-2-JPM-RO-CVCS010 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

13. Commence RCS cooldown to Verify conditions will allow for a N/A SAT UNSAT allow a makeup rate of 40 makeup rate of 40 gpm. (Step 12)

(Proc GPM.

step

12) Note: applicant will not perform this procedure step.

EXAMINERS CUE: The RCS cooldown will be controlled by another operator and the rate is sufficient to allow 40 GPM makeup rate.

(C) 14. Use one HPSI train B injection Throttled open ONE of the N/A SAT UNSAT MOV to maintain PZR level. following HPSI injection MOV:

(Proc step (Note these are contingency 2CV-5016-2 13A) action steps.)

2CV-5036-2 2CV5056-2 2CV-5076-2 Observed Red light ON and Green light ON above handswitch.

(C) 15. Verified HPSI to RCS flow Adjust valve position to maintain N/A SAT UNSAT greater than 40 GPM using greater than 40 GPM HPSI flow (Proc SPDS computer. using indications on SPDS step computer.

13B)

Procedure steps 14, 15 and 16 are not required to be completed.

END STOP TIME:

JPM- ANO-2-JPM-RO-CVCS010 PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

Mode 3. B CCP tagged out for low pressure operations. C CCP tagged out for gear box repair. TRM 3.1.2.4 entered for only 1 CCP available with 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months remaining on the action.

A Shutdown Margin is calculated following a reactor trip. Shutdown Margin is found to be less than required.

INITIATING CUE:

The SM/CRS directs, "Initiate Emergency Boration using BAMT gravity feed to Charging Pump suction beginning with AOP 2203.032, Step 2."

JPM- ANO-2-JPM-RO-CVCS010 PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

Mode 3. B CCP tagged out for low pressure operations. C CCP tagged out for gear box repair. TRM 3.1.2.4 entered for only 1 CCP available with 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months remaining on the action.

A Shutdown Margin is calculated following a reactor trip. Shutdown Margin is found to be less than required.

INITIATING CUE:

The SM/CRS directs, "Initiate Emergency Boration using BAMT gravity feed to Charging Pump suction beginning with AOP 2203.032, Step 2."

JPM- ANO-2-JPM-NRC-PZR02 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 010 DATE:

SYSTEM/DUTY AREA: Pressurizer Pressure Control System TASK: Equalize RCS and PZR Boron (ALTERNATE SUCCESS PATH)

JTA#: ANO2-RO-PZR-NORM-3 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 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-PZR02 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: 100% Power Operation. A power escalation has been completed.

Chemistry reports that RCS boron is 500 PPM and PZR boron is 575 PPM.

TASK STANDARD: Spray Valve (2CV-4651) is isolated. THIS IS AN ALTERNATE SUCCESS PATH JPM.

TASK PERFORMANCE AIDS: OP 2103.005 section 7.0 and AOP 2203.028.

SIMULATOR SETUP: Run CAE FILE JPM03. This will open A spray valve 100% and trip the breaker when the valve indicates intermediate position.

The following malfunctions/overrides need to be triggered (cae file JPM03 will do all of them):

Set T5 file to GH4R651A 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:

EXAMINERs NOTE: Do not hand out procedure until asked.

The SM/CRS directs: Equalize RCS and PZR boron concentration using 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, On panel 2C04 verified red lights N/A SAT UNSAT (Proc isolation valves 2CV-4655 ON, green lights OFF for step AND 2CV-4656 are OPEN. 2CV-4655 and 2CV-4656.

7.1.1)

(C) 2. Place RCP A spray valve On panel 2C04, rotated N/A SAT UNSAT (Proc MAN/AUTO select switch 2HS-4651B in the CCW direction step (2HS-4651B) to MANUAL. to MANUAL.

7.1.2)

(C) 3. Energize all available Backup On panel 2C04 verified the N/A SAT UNSAT (Proc Heaters. following hand switches to ON:

step Place 2HS-4643 to ON 7.1.3)

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.

EXAMINERS NOTE:

When 2CV-4651 is taken to open, the valve will open 100% and then trip the breaker.

(C) 4. Partially open 2CV-4651 to When RCS pressure starts rising, N/A SAT UNSAT (Proc stabilize pressure within +/- 10 then on panel 2C04, throttled step psia of desired setpoint. open 2CV-4651 by taking the 7.1.4) hand switch for 2CV-4651 to the open position.

EXAMINERS NOTE:

The following step may be completed after entering 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 On panel 2C04, observed that N/A SAT UNSAT (AOP deenergized open. light position indications above Proc 2CV-4651 are out and PZR step 1) Attempts to close 2CV4651 pressure is lowering.

may be made, but is not necessary.

(C) 6. Close PZR Spray Block On panel 2C04, placed hand- N/A SAT UNSAT (AOP Valves. switch for 2CV-4655 and 2CV-Proc 4656 to "CLOSE".

step 1.B.3) Observed green lights ON, red lights OFF for 2CV-4655 and 2CV-4656.

END STOP TIME:

JPM- ANO-2-JPM-NRC-PZR02 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY NOTE: Do not hand out procedure until Examinee asks for it.

JPM INITIAL TASK CONDITIONS:

100% Power Operation. A power escalation has been completed. Chemistry reports that RCS boron is 500 PPM and PZR boron is 575 PPM.

INITIATING CUE:

The SM/CRS directs: Equalize RCS and PZR boron concentration using RCP A spray valve, 2CV-4651."

JPM- ANO-2-JPM-NRC-PZR02 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

100% Power Operation. A power escalation has been completed. Chemistry reports that RCS boron is 500 PPM and PZR boron is 575 PPM.

INITIATING CUE:

The SM/CRS directs: Equalize RCS and PZR boron concentration using RCP A spray valve, 2CV-4651."

JPM- ANO-2-JPM-NRC-SIT05 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 003 DATE:

SYSTEM/DUTY AREA: Safety Injection System TASK: Adjust SIT Pressure (Increase) 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 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-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 (2T2A) 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 Using the gaitronics, plant N/A SAT UNSAT (Proc aligned. telephone system, or radio; step contacted Unit-1 OR contacted

1) Examiners Cue: Unit-2 operator.

Unit-1 (or Unit-2 operator) reports high pressure N2 is Requested alignment of high aligned. pressure N2.

(C) 2. Open Supply Header to On panel 2C16, placed N/A SAT UNSAT (Proc Containment Isolation handswitch for 2CV-6207-2 to step (2CV-6207-2). OPEN.

2)

Observed red light ON above handswitch.

EXAMINER'S NOTE:

2SV-5005A and B are both operated by handswitch for 2SV-5005.

(C) 3. Open SIT N2 Supply valves On panel 2C33, placed N/A SAT UNSAT (Proc (2SV-5005A/B). handswitch 2SV-5005 for step 2SV-5005A/B to OPEN.

3)

Observed red light ON; green light OFF above handswitch.

4. Verify SIT (2T2A) at desired Verified SIT (2T2A) pressure N/A SAT UNSAT (Proc pressure. between 615 and 620 psig.

step

5) 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.

JPM- ANO-2-JPM-NRC-SIT05 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

5. Close SIT N2 Supply valves On panel 2C33, placed hand N/A SAT UNSAT (Proc (2SV-5005A/B). switch 2SV-5005 for step 2SV-5005A/B to CLOSE.

5)

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.

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 N2 from 2C16 and pressurizes the SIT to 700psig, the following step should be considered UNSAT.

(C) 6. Close Supply Header to On panel 2C16, placed N/A SAT UNSAT (Proc Containment Isolation valve handswitch for 2CV-6207-2 to step (2CV-6207-2). CLOSE.

7)

Observed green light ON above handswitch.

Isolated N2 from 2C16 with SIT pressure less than 700psig,

7. Isolate the nitrogen supply. Using the gaitronics, plant N/A SAT UNSAT (Proc telephone system, or radio; step Examiners Cue: contacted Unit-1 OR contacted

8) Unit-1 (or Unit-2 operator) Unit-2 operator.

reports high pressure N2 is isolated. Requested isolation of high pressure N2.

END STOP TIME:

JPM- ANO-2-JPM-NRC-SIT05 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS 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 EXAMINEES 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 Conditions 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 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-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 SGs has been established via B EFW.

TASK STANDARD: Take required actions to restore Natural 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 greater 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 Natural 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 Using SPDS SFD Screen, PMS, N/A SAT UNSAT (Proc 50°F. PDS or 2C04 indications, step determine Loop T to be less

26) than 50°F.

2. Verify RCS loop TH and TC Using SPDS SFD Screen, PMS, N/A SAT UNSAT (Proc constant or lowering. PDS or 2C04 indications, step determine that RCS loop TH and

26) TC are constant.

(C) 3. Verify RCS MTS 30°F or Using SPDS SFD Screen, PMS, N/A SAT UNSAT (Proc greater. PDS or 2C04 indications, step determine that RCS MTS is less

26) than 30°F.

4. Contingency column step 26.A, Using SPDS SFD Screen, PMS, N/A SAT UNSAT (Proc verify SG levels being PDS or 2C04 indications, step maintained 10% to 90%. determine that Steam Generator

26) levels are above 10% and less than 90%.

If examinee asks for direction, then provide the following cue:

EXAMINERs CUE: CRS asks why are we not meeting the >30°F MTS requirement?

(C) 5. Contingency column step 26.B, Refer to Attachment 1, P-T Limits N/A SAT UNSAT (Proc verify RCS pressure within limits and verify that MTS is less than step of Attachment 1, P-T Limits. 30°F.

26.B)

Examiners note: Critical Take PZR Backup heaters out of element is that examinee OFF. Verify that red light ON recognizes that PZR pressure above hand switch(es).

is LOW due to all heaters de- Take Proportional heaters hand energized and this is causing switches to ON. Verify that Red MTS problems. The number light is ON above associated of heaters re-energized is hand switch.

discretionary. Verify P-T limits of Attachment 1 Candidate may consider a are restored.

plant cooldown after raising PZR pressure.

JPM- ANO-2-JPM-NRC-EOP03 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

6. Verify T between TH and Using SPDS SFD Screen, PMS, N/A SAT UNSAT (Proc CETs less than 10°F. PDS or 2C04 indications, step determine that T between TH

26) and CETs is less than 10°F.

END STOP TIME:

JPM- ANO-2-JPM-NRC-EOP03 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY 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 SGs has been established via B EFW.

INITIATING CUE:

The SM/CRS directs, "Verify Natural Circulation 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 EXAMINEES COPY 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 SGs has been established via B EFW.

INITIATING CUE:

The SM/CRS directs, "Verify Natural Circulation 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 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.

ANO-2-JPM-NRC-ELECXT 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 with the examinee.

JPM INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer. Plant is in mode 5.

TASK STANDARD:

Cross connect 480VAC non-vital busses 2B1 and 2B2 with 2B1 supplying and 2B2 supply breakers open. Maintain 2B1 amperage less than 130 amps.

TASK PERFORMANCE AIDS:

OP 2107.001 Section 12.0.

SIMULATOR SETUP:

Any power level or mode.

All Non-Vital 4160VAC and 480VAC Busses energized.

Summed 2B1 and 2B2 bus currents are greater than 130 amps (REMOTE malfunctions 480CURR2B1 And 480CURR2B2).

ANO-2-JPM-NRC-ELECXT PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

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

CRITICAL ELEMENTS (C): 2, 3, 4, 6, 7 PERFORMANCE CHECKLIST STANDARDS (Circle One)

Examiners 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 Ask if Operations Manager has N/A SAT UNSAT (Proc approval obtained. given approval to cross connect step 2B1 and 2B2 at power.

1) EXAMINERS CUE:

The Operations Manager has given permission to perform Cross Connect of 2B1 and 2B2.

Examiners note:

The following two steps may be completed after cross-connecting the busses. The resolution on the meters is low at the low end.

(C) 2. Determine combined load of On Panel 2C10, summed the N/A SAT UNSAT (Proc 2B1 an 2B2. current reading of 2B1 and 2B2.

step

2) Observed that the summed load is greater than 130 amps.

(C) 3. Reduce loads on 2B1 and 2B2 Direct the AO or inform CRS of N/A SAT UNSAT (Proc so that combined loading is less need to reduce non-essential step than 130 amps when cross loads on 2B1 and 2B2 so that

2) connected. combined loading is less than EXAMINERS CUE: 130 amps.

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 instructors station to reduce loading on 2B1 and 2B2 so that loading is less than 130 amps (use REMOTE malfunctions 480CURR2B1 and 480CURR2B2).

ANO-2-JPM-NRC-ELECXT PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. Synchroscope switch inserted in On Panel 2C10, Placed N/A SAT UNSAT (Proc 2B1/2B2 cross-tie slot and Synchroscope switch into step placed in ON. 2B1/2B2 cross-tie slot and

4) rotated clockwise to the ON position.

5. Observed that the On Panel 2C10, Observed that N/A SAT UNSAT (Proc Synchroscope is at the 12 the Synchroscope is at the 12 step oclock position. oclock position with the

5) Synchroscope switch in the ON position.

(C) 6. Close the 2B1/2B2 Cross Tie On panel 2C10, rotate the Cross N/A SAT UNSAT (Proc breaker. Tie handswitch for 2B1/2B2 step clockwise.

6)

Observed that the Green light turns OFF and the Red light turns ON above the Cross Tie handswitch.

(C) 7. Open normal supply breaker on On Panel 2C10, rotate the N/A SAT UNSAT (Proc 2B2, 480VAC bus. normal feeder supply breaker on step 2B2 counter clockwise to the

7) AND open position. (2B212)

Open Transformer feeder Observed that the RED light went breaker from 2A2 to 2B2. OFF and the GREEN light went ON.

On Panel 2C10, rotate the transformer feeder breaker on 2A2 to 2B2 counter clockwise to the open position. (2A202)

Observed that the RED light went OFF and the GREEN light went ON.

8. Verify that the amperage On panel 2C10, observe that the N/A SAT UNSAT (Proc indicated on 2B1 is less than current is less than 130 amps on step 130 amps. 2B1.

8)

9. Turn sync switch to OFF. On Panel 2C10, turn sync switch N/A SAT UNSAT (Proc counter clockwise to the OFF step position.

9)

Examiners Note Step 12.10 in procedure is not applicable for this JPM as both busses remained energized and the loads removed to reduce amperage on 2B1 will remain deenergized.

ANO-2-JPM-NRC-ELECXT PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

10. Notified AO to monitor 2B1 Notify AO to monitor 2B1 N/A SAT UNSAT (Proc transformer during cross transformer during cross step connected operation and connected operation and

11) maintain temperature less than maintain temperature less than 220°C. 220°C.

EXAMINERS CUE:

AO has been notified to monitor 2B1 transformer and notify the control room if temperature exceeds 220°C during cross connected operations.

END

ANO-2-JPM-NRC-ELECXT PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer. Plant is in mode 5.

INITIATING CUE:

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

ANO-2-JPM-NRC-ELECXT PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer. Plant is in mode 5.

INITIATING CUE:

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

ANO-2-JPM-NRC-BMSRM PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Process Radiation Monitoring System TASK: Perform BMS Liquid Discharge Radiation Monitor Functional Check JTA#: ANO2WCOLRWBMSNORM21 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 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.

ANO-2-JPM-NRC-BMSRM PAGE 2 OF 8 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

2T21A Liquid Radwaste Release Permit, 2104.014 Supplement 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112. Use 2CV2330A to perform release.

TASK STANDARD:

Functional Test has been completed on 2RITS-2330.

TASK PERFORMANCE AIDS:

2104.014 Supplement 1 EXAMINER'S NOTE:

JPM-ANO-2-JPM-NRC-EOP02 Page 1 of 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Abnormal/Emergency Operations TASK: Restore SDC Flow following an instrument failure - inadvertent Auto-Closure Initiation (ACI)

JTA#: ANO2-RO-EOPAOP-OFFNORM 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 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-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 with the examinee.

JPM INITIAL TASK CONDITIONS:

AOP 2203.029 has been entered due to 2PI-4623-2 failing High. SDC pump secured, fuse for 2PS-4623-2 removed, and Loss of SDC AOP, 2203.029, has been completed up to contingency step 13.C.

TASK STANDARD: Shutdown Cooling Flow has been restored per Loss of SDC AOP, 2203.029.

TASK PERFORMANCE AIDS: Loss of SDC AOP, 2203.029 SIMULATOR SETUP:

Mode 5, SDC aligned for the A LPSI Pump through the A SDC Heat Exchanger.

2P-60 A & B secured, All LPSI Injection MOVs are OPEN, and 2CV-5086-2 is CLOSED.

ACI actuation is clear due to de-energizing 2PS-4623-2 by fuse removal.

JPM-ANO-2-JPM-NRC-EOP02 Page 3 of 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "The fuse has been removed for failed RCS pressure instrument 2PI-4623-2; Restore Shutdown Cooling Flow using AOP 2203.029 beginning with contingency step 13.C."

CRITICAL ELEMENTS (C): 2, 6, 9,10 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify SDC RCS isolation On panels 2C16 and 2C17, N/A SAT UNSAT (Proc valves open. checked indications for:

step - 2CV-5038-1 7.13.C) - 2CV-5084-1

- 2CV-5086-2 Observed 2CV-5086-2 closed by green light ON, red light OFF above hand switch.

(C) 2. Determine that 2CV-5086-2 is On panel 2C16, placed hand N/A SAT UNSAT (Proc shut due to the Auto-Closure switch for 2CV-5086-2 to step Initiation (ACI) and Open 2CV- "OPEN".

7.13.C) 5086-2.

Observed red light ON; green light OFF above hand switch.

3. Verify RAS has not actuated. On panel 2C03, verified Alarms N/A SAT UNSAT (Proc cleared on Annunciator panels step 2K04 and 2K07 or verified red 7.14) lights ON at 2C03 above the RAS placard.

4. Verify RCS indicators Requests that CRS verify OP N/A SAT UNSAT (Proc functioning properly using 2103.011 Attachment M is step OP 2103.011. complete.

7.15)

EXAMINERs CUE: CRS reports that OP 2103.011 attachment M, RCS level transmitter and tygon tube alignment has been completed and all RCS level indicators are functioning properly.

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 N/A SAT UNSAT (Proc SDC pumps are running.

step 7.16)

Observed 2C-16 and 2C-17 that 2P-60 A & B were secured.

Observed green light ON; red light OFF above hand switches.

(C) 6. Close ALL LPSI Injection On 2C16 & 17, placed hand N/A SAT UNSAT (Proc MOVs. switches for Safety Injection step MOVs to CLOSE".

7.16.A) 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.

7. Partially open ONE LPSI On 2C-16 or 17, held 1 LPSI N/A SAT UNSAT (Proc Injection. Injection MOV hand switch in step the open direction for about 2 7.16.B) seconds.

2CV-5017-1 2CV-5037-1 2CV-5057-2 2CV-5077-2 Observed green and red light ON above associated hand switch.

8. Verify RCS level of 40% in Referred to Attachment A N/A SAT UNSAT (Proc PZR is adequate; refer to and verified RCS Level step Attachment A, RCS Level. adequate for SDC, shutdown 7.16.C) (Verifies that PZR level is well cooling (Low Pressure Safety above the required level of 24 Injection), Pump restart.

inches above the bottom of the hot leg (40% PZR is ~

286 above the bottom of the hot leg.)

JPM-ANO-2-JPM-NRC-EOP02 Page 5 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

NOTE:

If 2CV-5091 is not in Automatic, the candidate may have to transverse from 2C-16 & 17 back to 2C-04 multiple times to control flow. 2CV-5091 should be monitored to ensure that it has control of flow when placed in automatic.

(C) 9. Start SDC pump, refer to On 2C17 placed hand switch N/A SAT UNSAT (Proc 2104.004, Shutdown for 2P-60A to "START".

step Cooling System.

7.16.D) Observed red light ON; green light OFF above hand switch.

(C) 10. Raise SDC flow to greater On 2C-16 & 17 placed hand- N/A SAT UNSAT (Proc than 2400 gpm by opening switches for Safety Injection step LPSI Injection MOVs. MOVs to OPEN) as necessary 7.16.E) to achieve > 2400 gpm flow.

2FIC-5091 indicates > 2400 gpm.

Examiners note/CUE: Inform candidate that the CRS and CBOR will control RCS cool down.

END STOP TIME:

JPM-ANO-2-JPM-NRC-EOP02 Page 6 of 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Loss of Shutdown Cooling AOP, 2203.029, has been entered due to 2PS-4623-2 failing High. The resulting ACI caused 2CV-5086-2 to close. The A SDC pump was secured and AOP completed up to contingency step 13.C.

INITIATING CUE:

The SM/CRS directs, "The fuse has been removed for failed RCS pressure instrument 2PI-4623-2; Restore Shutdown Cooling Flow using AOP 2203.029 beginning with contingency step 13.C."

JPM-ANO-2-JPM-NRC-EOP02 Page 7 of 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Loss of Shutdown Cooling AOP, 2203.029, has been entered due to 2PS-4623-2 failing High. The resulting ACI caused 2CV-5086-2 to close. The A SDC pump was secured and AOP completed up to contingency step 13.C.

INITIATING CUE:

The SM/CRS directs, "The fuse has been removed for failed RCS pressure instrument 2PI-4623-2; Restore Shutdown Cooling Flow using AOP 2203.029 beginning with contingency step 13.C."

ANO-2-JPM-NRC-BMSRM PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Process Radiation Monitoring System TASK: Perform BMS Liquid Discharge Radiation Monitor Functional Check JTA#: ANO2WCOLRWBMSNORM21 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 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.

ANO-2-JPM-NRC-BMSRM PAGE 2 OF 8 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

2T21A Liquid Radwaste Release Permit, 2104.014 Supplement 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112. Use 2CV2330A to perform release.

TASK STANDARD:

Functional Test has been completed on 2RITS-2330.

TASK PERFORMANCE AIDS:

2104.014 Supplement 1 EXAMINER'S NOTE:

ANO-2-JPM-NRC-BMSRM PAGE 3 OF 8 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Perform the functional test of the BMS Liquid Discharge Radiation Monitor beginning with 2104.014 Supplement 1, Step 7.1 and use 2CV 2330A only."

CRITICAL ELEMENTS (C): 4, 6, 11, 12 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Direct WCO to verify 2P-53A/B Directed the WCO to verify N/A SAT UNSAT (Proc Discharge to Circ Water Flume 2LRW-13 is closed.

step (2LRW-13) is closed.

7.1)

EXAMINERs CUE:

WCO reports 2LRW-13 is closed.

2. Direct WCO to verify 2P47A/B Directed the WCO to verify N/A SAT UNSAT (Proc Discharge to Circ Water Flume 2BM-35 is closed.

step (2BM-35) is closed.

7.1)

EXAMINERs CUE:

WCO reports 2BM-35 is closed.

3. Direct WCO to verify 2F11/11A Directed the WCO to verify N/A SAT UNSAT (Proc Disch to CW Flume (2LRW-24) 2LRW-24 is closed.

step is closed.

7.1)

EXAMINERs CUE:

WCO reports 2LRW-24 is closed.

(C) 4. Hold 2RITS-2330 Selector On panel 2C25, held 2RITS-2330 N/A SAT UNSAT (Proc Switch in CHECK SOURCE. Selector Switch in CHECK step SOURCE.

7.2.1) EXAMINERs CUE:

Switch in CHECK SOURCE.

5. Verify 2RITS-2330 meter On panel 2C25, verified N/A SAT UNSAT (Proc moves up scale. 2RITS-2330 indication moved up step scale.

7.2.1) EXAMINERs CUE:

Meter moved up scale.

(C) 6. Return 2RITS-2330 Selector On panel 2C25, placed N/A SAT UNSAT (Proc Switch to OPERATE. 2RITS-2330 Selector Switch to step OPERATE.

7.2.3) EXAMINERs CUE:

Switch to OPERATE.

ANO-2-JPM-NRC-BMSRM PAGE 4 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

7. (Proc Verify 2RITS-2330 meter On panel 2C25, verified N/A SAT UNSAT step reading returns to normal. 2RITS-2330 meter reading 7.2.4) returned to original level.

EXAMINERs CUE:

Meter returns to normal.

8. Direct WCO to open NA step Procedure step 7.3.1 N/A SAT UNSAT LRW/BMS Discharge to Circ Water Flume valve (Proc 2CV-2330A.

step 7.3.2.A) EXAMINERs CUE: Direct WCO to verify 2HS-2331 in WCO reports that 2HS-2331 position 1. Initial step 7.3.2.A.

is in position 1.

WCO reports that 2HS-2330 Direct WCO to verify 2HS-2330 in (Proc position 1. Initial step 7.3.2.B.

is in position 1.

step 7.3.2.B) NA step 7.3.2.C and 7.3.2.D.

9. (Proc Record setpoint value from Request alarm setpoint from N/A SAT UNSAT step prerelease report prerelease report and record in 7.4.1) EXAMINERs CUE: step 7.4.1.

2RE2330 alarm setpoint from Prerelease Report is "3E3".

10. Determine dial setting to be From Radiation Monitor Alarm N/A SAT UNSAT (Proc used from Radiation Monitor Setpoint Table determined that step Alarm Setpoint Table using Prerelease Report setpoint of 3E3 7.4.2) setpoint from Prerelease equals dial setpoint of 4.78.

Report.

(C) 11. Release 2RE-2330 On panel 2C25, released 2RE- N/A SAT UNSAT (Proc potentiometer stop AND 2330 potentiometer stop AND step adjust dial to setting of 4.78. adjusted dial setting of 4.78. Locks 7.4.3) potentiometer stop.

EXAMINERs CUE:

Potentiometer dial setting is set at 4.78. Potentiometer is locked.

(C) 12. Place 2RE-2330 Selector On panel 2C25, placed 2RE-2330 N/A SAT UNSAT (Proc Switch in PULSE CAL. Selector Switch in PULSE CAL.

step 7.4.4) EXAMINERs CUE:

Switch in PULSE CAL and meter deflection is above alarm setpoint.

ANO-2-JPM-NRC-BMSRM PAGE 5 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

13. Direct WCO to verify Directed WCO to verify N/A SAT UNSAT annunciator 2K14 B1 is annunciator 2K14-B1, Liquid (Proc actuated on Panel 2C112. Radwaste Discharge Radiation step This is located on the 335 Hi, is actuated on 2C112.

7.4.5) elevation of the auxiliary building.

EXAMINERs CUE:

2K14-B1, Liquid Radwaste Discharge Radiation Hi is in alarm.

14. Verify annunciator 2K11-J9 On panel 2C14, verified 2K11-J9 N/A SAT UNSAT BORON MGMT SYS is actuated on Panel 2C14.

(Proc TROUBLE" is actuated on step Panel 2C14.

7.4.5) EXAMINERs CUE:

2K11-J9, BORON MGMT SYS TROUBLE", is in alarm.

15. Verify annunciator 2K11-C10 On panel 2C14, verified 2K11-C10 N/A SAT UNSAT "PROC LIQUID RADIATION is actuated on Panel 2C14.

(Proc HI/LO" is actuated on Panel step 2C14.

7.4.5)

EXAMINERs CUE:

2K11-C10, "PROC LIQUID RADIATION HI/LO" is in alarm.

16. Direct WCO to verify Directed WCO to verify N/A SAT UNSAT LRW/BMS Discharge to Circ 2CV-2330A is closed.

(Proc Water Flume (2CV-2330A) is step closed.

7.4.5)

EXAMINERs CUE:

WCO reports 2CV-2330A is closed.

17. Reset 2RE-2330 and place in On panel 2C25, placed the N/A SAT UNSAT (Proc OPERATE. Operation Selector switch to step RESET.

7.5)

EXAMINERs CUE: Placed the Operation Selector Switch in OPERATE. switch to OPERATE.

18. Verify valve(s) tested have Directed WCO to verify 2CV-(Proc reopened. 2330A open.

step EXAMINERs CUE:

7.5) WCO reports 2CV-2330A is open.

ANO-2-JPM-NRC-BMSRM PAGE 6 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

19. Check associated alarms On panel 2C14, verified 2K11-C10 N/A SAT UNSAT (Proc clear. and 2K11-J9 are in "slow flash" step OR NOT illuminated.

7.5) EXAMINERs CUE: Directed WCO to verify 2K11-C10, 2K11-J9 and annunciator 2K14-B1 on 2C112 is 2K14-B1 are in "slow flash". in "slow flash" OR NOT illuminated.

END STOP TIME:

ANO-2-JPM-NRC-BMSRM PAGE 7 OF 8 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

2T21A Liquid Radwaste Release Permit, OP 2104.014 Supplement 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112.

INITIATING CUE:

The SM/CRS directs, "Perform the functional test of the BMS Liquid Discharge Radiation Monitor beginning with 2104.014 Supplement 1, Step 7.1 and use 2CV 2330A only."

ANO-2-JPM-NRC-BMSRM PAGE 8 OF 8 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

2T21A Liquid Radwaste Release Permit, OP 2104.014 Supplement 1, is completed through step 7.0. A Waste Control Operator (WCO) is available at 2C112.

INITIATING CUE:

The SM/CRS directs, "Perform the functional test of the BMS Liquid Discharge Radiation Monitor beginning with 2104.014 Supplement 1, Step 7.1 and use 2CV 2330A only."

JPM-ANO-2-JPM-NRC-EFWRS PAGE 1 of 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 014 DATE:

SYSTEM/DUTY AREA: Emergency Feedwater System TASK: Reset the EFW pump trip throttle valve JTA#: ANO2AOEFWEMERG1 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 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.

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.

CRITICAL ELEMENTS (C): 2, 3, 4, 6 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify 2CV0340-2 and 2CV-205- Called the control room to verify N/A SAT UNSAT (Proc 2 are closed. that 2CV0340-2 and 2CV-205-2 step are closed.

1)

EXAMINERS CUE:

Control room reports that 2CV034-2 and 2CV205-2 are CLOSED.

(C) 2. Position the latch lever to Turned the trip throttle valve N/A SAT UNSAT (Proc engage the trip hook. handwheel clockwise so that the step rotation of the screw raised the

2) sliding nut and latch lever to EXAMINERS CUE: where it could engage with the trip hook.

Latch lever positioned to engage with the trip hook.

Observed latch lever positioned to engage with the trip hook.

EXAMINERs 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 actions using Exhibit 2 located on the wall in the A emergency feed-water pump room.

(C) 3. Reset the mechanical trip Locally manually, pulled the N/A SAT UNSAT (Proc linkage manually. spring loaded emergency step connecting rod against the spring EXAMINERS CUE:

3) force.

Mechanical trip linkage is in TRIP RESET.

Moved the emergency head lever away from the emergency tappet and tappet nut to allow tappet to move downward to TRIP RESET.

JPM-ANO-2-JPM-NRC-EFWRS PAGE 4 of 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. Verify emergency tappet is in Verified the tappet is in TRIP N/A SAT UNSAT (Proc TRIP RESET. RESET.

step OR 3/4)

EXAMINERS CUE: Pressed downward on the emergency tappet to place it in The tappet is in TRIP RESET.

TRIP RESET and; EXAMINERs Note:

Submitted a Condition Report 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.

5. Verify tappet nut/emergency Verified the flat side of the tappet N/A SAT UNSAT (Proc head lever positioning. nut is to the flat side of the step emergency head lever.

5)

EXAMINERS CUE:

The flat side of the tappet nut is to the flat side of the emergency head lever.

(C) 6. Open the trip throttle valve. With latch and trip hook engaged, N/A SAT UNSAT (Proc turned trip throttle valve step handwheel CCW until valve was

6) EXAMINERS CUE: full open.

The trip throttle valve is fully open.

Observed stem at full travel.

7. Close trip throttle valve 1/4 turn. Turned the trip throttle valve N/A SAT UNSAT (Proc handwheel Counter clockwise 1/4 step turn.

7) EXAMINERS CUE:

The trip throttle valve is closed 1/4 turn.

8. Verify 2P7A turbine overspeed Contacted the control room to N/A SAT UNSAT (Proc trip (2K05-A9) alarm is clear determine 2K05-A9 alarm status.

step 8)

EXAMINERS CUE:

The control room reports 2K05-A9 is clear.

END STOP TIME:

JPM-ANO-2-JPM-NRC-EFWRS PAGE 5 of 6 JOB PERFORMANCE MEASURE Examiners Copy JPM INITIAL TASK CONDITIONS:

EFW pump (2P7A) started automatically following a reactor trip.

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

INITIATING CUE:

The SM/CRS directs, Reset the EFW pump (2P7A) overspeed trip device using OP 2106.006, Exhibit 1.

JPM-ANO-2-JPM-NRC-EFWRS PAGE 6 of 6 JOB PERFORMANCE MEASURE Examinees Copy JPM INITIAL TASK CONDITIONS:

EFW pump (2P7A) started automatically following a reactor trip.

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

INITIATING CUE:

The SM/CRS directs, Reset the EFW pump (2P7A) overspeed trip device using OP 2106.006, Exhibit 1.

JPM-ANO-2-JPM-NRC-IA01 PAGE 1 of 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 09 DATE:

SYSTEM/DUTY AREA: Emergency & Abnormal Operations TASK: Isolate the instrument air supply to the MSIVs (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 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.

THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

JPM-ANO-2-JPM-NRC-IA01 PAGE 2 of 7 JOB PERFORMANCE MEASURE The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: A severe fire has occurred in the 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 MSIVs.

TASK PERFORMANCE AIDS:

1) OP 2203.049 EOP actions for Corridor Behind Door 340 (Zone 2109-U) pages 1-3 (page 31 of 91).

2) Flashlight and gloves

3) RWP and dosimeter.

JPM-ANO-2-JPM-NRC-IA01 PAGE 3 of 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, Perform AOP 2203.049, Fires in Areas 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 MSIVs locally.

CRITICAL ELEMENTS (C): 4, 5, 7, 8 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Obtain equipment from alternate N/A SAT UNSAT (Proc shutdown locker in the entry to the step unit 2 control room.

1/2)

EXAMINERS CUE:

At the remote shutdown locker, Simulate obtaining the CRS bag, obtain Red CRS bag, Flashlight, and flashlight and radio with headset.

radio with Headset.

Radio check is satisfactory Perform radio check EXAMINERs 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 and task for outside controlled access before starting JPM. Also a flashlight will be needed.

2. Locally trip the Main Turbine At the north end of the Main Turbine N/A SAT UNSAT (Proc at the front standard, located the red step handle and simulates pulling the 3.A ) EXAMINERS CUE: handle.

Main Turbine is tripped.

EXAMINERS 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 MSIVs to prevent bumping into valves.

3. Close the IA supply from 2T91 At the A MSIV actuator, closed N/A SAT UNSAT (Proc 2F-356 I/N valve (2MS-540) 2MS-540 by rotating hand wheel step CLOCKWISE.

3.B.1)

EXAMINERS CUE:

2MS-540 valve CLOCKWISE Observed valve motion stopped when motion stops. valve fully closed

JPM-ANO-2-JPM-NRC-IA01 PAGE 4 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. Close IA supply IA to Just south of the A MSIV actuator, N/A SAT UNSAT (Proc 2CV-1010-1 valve (2IA-166) closed 2IA-166 by rotating its hand step wheel CLOCKWISE.

3.B.2)

EXAMINERS CUE:

2IA-166 valve CLOCKWISE Observed valve motion stopped when motion stops. valve fully closed (C) 5. Open filter vent valve on A At the A MSIV actuator, opened N/A SAT UNSAT (Proc MSIV point of use air filter 2F-356 vent valve by turning the step (2F-356). petcock valve until air escapes.

3.B.3)

EXAMINERS CUE: Observed valve motion stopped when Air bleeds off the actuator valve fully open.

system and dies away. The A MSIV is slowly closing.

6. Close IA supply from 2T91 At the B MSIV actuator, closed N/A SAT UNSAT (Proc 2F-357 I/N valve, (2MS-539) 2MS-539 by rotating hand wheel step CLOCKWISE.

3.C.1)

EXAMINERS CUE:

2MS-539 valve CLOCKWISE Observed valve motion stopped when motion stops. valve fully closed.

(C) 7. Close IA supply 2CV-1060-2 Just south of the A MSIV actuator, N/A SAT UNSAT (Proc AIR ISOL valve, (2IA-93) closed 2IA-93 by rotating its step handwheel CLOCKWISE.

3.C.2)

EXAMINERS CUE:

2IA-93 valve CLOCKWISE mot Observed valve motion stopped when ion stops. valve fully closed.

(C) 8. Open filter vent on MSIV IA At the B MSIV actuator, opened N/A SAT UNSAT (Proc FILTER 2CV-1060-2 AIR 2F-357 vent valve by turning the step CONTROL VLV valve (2F-357) petcock valve until air escapes.

3.C.3)

(Valve on B MSIV point of use .

air filter (2F-357))

Observed valve motion stopped when EXAMINERS CUE: valve fully open Air bleeds off the actuator system and dies away. The B MSIV is slowly closing.

Examiners 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.

Examiners Cue: Another operator will trip the Main Feed Pumps.

JPM-ANO-2-JPM-NRC-IA01 PAGE 5 of 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

END STOP TIME: ___________________

JPM-ANO-2-JPM-NRC-IA01 PAGE 6 of 7 JOB PERFORMANCE MEASURE EXAMINERs 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, Fires in Areas 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 MSIVs locally.

JPM-ANO-2-JPM-NRC-IA01 PAGE 7 of 7 JOB PERFORMANCE MEASURE EXAMINEEs 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, Fires in Areas 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 MSIVs locally.

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 1 of 8 SYSTEM/DUTY AREA: Emergency Diesel Generator System TASK: Start an emergency diesel generator without DC control power (2K-4B)

JTA # : ANO2-AO-EDG-OFFNORM-5 KA VALUE RO: 4.1 SRO: 4.5 KA

REFERENCE:

055 EA1.06 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: X LAB:

TESTING METHOD: SIMULATE: X PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 16 minutes REFERENCE(S) OP 2104.036, Exhibit 2, 2107.001, Exhibit 9 EXAMINEES NAME: SSN:

EVALUATORS NAME: DATE THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time: Stop Time: Total Time:

Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

SIGNED: DATE:

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 2 of 8 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The following conditions exist:

1. The plant is in Mode 3 following an automatic reactor trip

2. A Station Blackout exists

3. There is no green DC power available.

4. Fuses from alternate shutdown locker are simulated obtained.

TASK STANDARD:

2DG2 [2K-4B] has been started with normal voltage and frequency TASK PERFORMANCE AIDS:

1. OP 2104.036 Exhibit 2

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 3 of 8 INITIATING CUE: The CRS provides the following direction:

1. Perform a loss of DC start of 2DG2 using OP 2104.036, Exhibit 2

2. Due to the timeliness of the actions required, electrical safety requirements may be waived at your discretion.

However, use extreme caution when operating any energized electrical components.

CRITICAL ELEMENTS (C): 4, 5, 6, 8 START TIME:

EXAMINERS NOTE:

Provide examinee with OP2104.036, Exhibit 2.

Have a copy of 2107.001, Exhibit 9, Electrical Safety Requirements available for examinees review if requested. If examinee states that they will adhere to the electrical safety requirements for steps 1, 2 & 3, have them show what requirements they will be ensuring are satisfied then, tell them that the requirements have been satisfied and that they should continue with the JPM.

Due to electrical safety concerns, do not allow the examinee to open the door to 2D24. Have them explain what they would do.

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Open one of the following sets For the listed breaker, opened N/A SAT UNSAT (Proc of breakers: panel door and moved breaker step handle to OFF.

1) - 2C108 breaker (2D24-2)

- 2E21 breaker (2D24-6)

- 2C108 breaker (2D24-8)

OR

- 2E21 breaker (D2E21NA6)

- 2C108 breaker (D2C108NA8)

- 2C108 breaker (D2C108NA2)

POSITIVE CUE:

(For each breaker)

Breaker indicates OPEN.

NEGATIVE CUE:

(For each breaker)

Breaker indicates NOT OPEN.

TRANSITION NOTE:

Go to 2A4 switchgear room.

EXAMINERS NOTE:

For the 4160v breakers in Steps 2 and 3, do NOT open the breaker cubicle doors.

For electrical safety purposes, provide candidate with picture at the end of this JPM, have the candidate explain the indications he would use to determine the following.

1. Breaker position

2. Closing Spring Status Standard:

1. The student must use mechanical breaker position indication

2. The student must use mechanical closing spring status indication.

Both of these indicators are located on the breaker.

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 4 of 8 Examiners Note:

The following breakers are listed with their respective conditions for the plant conditions that exist. For breakers 2A-402 and 2A-409, provide examinee with picture at the end of this JPM and have them indicate what they would do to open the breakers.

2. Verify the following breakers At bus 2A4 at cubicle 2A411, N/A SAT UNSAT (Proc OPEN WITH closing springs opened cubicle door.

step charged.

2) Observed indications for the SW Pump 2P4C (2A-402) following.

Mechanical breaker position SW Pump 2P4B (2A-403) Mechanical closing spring indication 2DG2 Output breaker (2A-408)

Operator opened any closed NEGATIVE CUE: breaker by pushing the 2A-402 is closed with closing mechanical breaker trip button on springs charged the breaker POSITIVE CUE:

2A402 opens when the mechanical trip button is pushed.

3. Verify the following breakers For each listed breaker, verified N/A SAT UNSAT (Proc OPEN. the breaker to be open with the step mechanical breaker indication.

3) CS Pump 2P35B (2A-404)

Operator opened any closed LPSI Pump 2P60B (2A-405) breaker by pushing the mechanical breaker trip button on HPSI Pump 2P89B (2A-406) the breaker HPSI Pump 2P89C (2A-407) 2A4 Supply breaker (2A-409) 2A3-2A4 Tie (2A-410)

NEGATIVE CUE:

2A-409 indicates CLOSED POSITIVE CUE:

2A-409 opens when the mechanical trip button is pushed.

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 5 of 8 (C) 4. Open 2DG2 Service Water Using radio or telephone N/A SAT UNSAT (Proc Outlet valve (2CV-1504-2). communications, instructed WCO step to OPEN 2CV-1504-2 locally using

4) POSITIVE CUE: manual operator.

WCO reports Service Water Valve (2CV-1504-2) is OPEN. OR Using radio or telephone communications, contacted Control Room personnel to have WCO to OPEN 2DG2 Service Water valve (2CV-1504-2) using the manual operator locally.

TRANSITION NOTE:

Go to 2DG2 room.

(C) 5. Place exciter regulator On panel 2E22, rotated Exciter N/A SAT UNSAT (Proc handswitch in LOCAL. Regulator handswitch to LOCAL.

step

5) POSITIVE CUE:

The exciter regulator handswitch indicates LOCAL.

(C) 6. Place Engine Control On panel 2E21, inserted key in N/A SAT UNSAT (Proc handswitch to START. Engine Control Switch.

step

6) POSITIVE CUE: Rotated key clockwise to unlock.

The Engine Control handswitch indicates START. Rotated Engine Control handswitch through LOCKOUT to START.

7. Obtain FNM 10 amp fuses from Obtained two fuses from the N/A SAT UNSAT (Proc Alternate Shutdown file cabinet. Alternate Shutdown file cabinet.

step 7.1) POSITIVE CUE:

Fuses are in your possession.

(C) 8. Open either Air Start Solenoid Rotated manual operator stem on N/A SAT UNSAT (Proc (2SV-2829-2 or 2SV-2830-2). either Air Start Solenoid clockwise.

step 7.2) POSITIVE CUE:

Engine noise indicates start.

NEGATIVE CUE:

Engine noise does NOT indicate start.

9. Close Air Start solenoid. Upon 2DG2 start, disengaged N/A SAT UNSAT (Proc manual solenoid operator by step rotating counter-clockwise.

7.3)

10. Verify generator 2DG2 voltage. On panel 2E21, verified 2DG2 N/A SAT UNSAT (Proc voltage between 3800 and 4400 step POSITIVE CUE: volts on V-2DG2-3, 2DG2 local AC 7.4) 2DG2 voltage is ~ 4160 volts. voltmeter.

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 6 of 8

11. Verify generator 2DG2 On panel 2E21, verified 2DG2 N/A SAT UNSAT (Proc frequency. frequency between 59.5 and step 60.5 Hz and maintained as loads 7.7) POSITIVE CUE: are added.

2DG2 frequency is ~ 60 Hz.

END STOP TIME:

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 7 of 8 Examiners Copy JPM INITIAL TASK CONDITIONS

1. The plant is in Mode 3 following an automatic reactor trip.

2. A Station Blackout exists.

3. There is no green DC power available.

5. Fuses from alternate shutdown locker are simulated obtained.

INITIATING CUE: The CRS provides the following direction:

1. Perform a loss of DC start of 2DG2 using OP 2104.036, Exhibit 2.

2. Due to the timeliness of the actions required, electrical safety requirements may be waived at your discretion. However, use extreme caution when operating any energized electrical components.

JOB PERFORMANCE MEASURE JPM# A2JPM-NRC-EDDCG REV 01 PAGE 8 of 8 Examinees Copy JPM INITIAL TASK CONDITIONS

4. The plant is in Mode 3 following an automatic reactor trip.

5. A Station Blackout exists.

6. There is no green DC power available.

6. Fuses from alternate shutdown locker are simulated obtained.

INITIATING CUE: The CRS provides the following direction:

3. Perform a loss of DC start of 2DG2 using OP 2104.036, Exhibit 2.

4. Due to the timeliness of the actions required, electrical safety requirements may be waived at your discretion. However, use extreme caution when operating any energized electrical components.

JOB PERFORMANCE MEASURE JPM# A2JPM-RO-EDDCG REV 03 PAGE 9 of 9 CLOSE MANUAL TRIP CHGD MANUAL CLOSE

Appendix D Scenario 1 Form ES-D-1 Facility: ANO-2 Scenario No.: 1 Op-Test No.: 2005-1 Page 1 Examiners: Operators:

Initial Conditions:

56% MOL, All Engineered Safety Features (ESF) systems in standby. Condenser outer water box is isolated for tube plugging. B circulating water pump is secured.

Green Train Maintenance Week.

Turnover:

56%. 250 EFPD. Condenser outer water box is isolated for tube plugging. Estimated time to complete repairs is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . B circulating water pump is secured. Equipment Out of Service Monitor (EOOS) indicates Minimal Risk. Green Train Maintenance Week.

Event Malf. No. Event Event No. Type* Description 1 NIBLINEPWR I (CBOT) Safety channel linear power channel B fails low.

CBOT must bypass points in Plant Protection System (PPS) channel.

2 CVC2P36AFAL C (CBOR) Running charging pump trips breaker. Abnormal Operating Procedures (AOP) entry start standby charging pump.

3 SGATUBE R(CBOR) A Steam Generator (SG) tube leak results in N(CBOT) power reduction to take unit off line.

4 SGATUBE M(ALL) A Steam Generator tube rupture results in reactor trip and Reactor Coolant System (RCS) cool down.

5 4162A406 C (CBOT) B High Pressure Safety Injection (HPSI) pump trips breaker on start.

6 2CV50151 C (CBOT) A HPSI train injection Motor Operated Valve (MOV) fails to open on actuation.

7 BUHTRS C(CBOR) Back up Heaters fail on due to relay failure and will not shut off when Pressurizer level drops less than set point.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 17

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

1) Evaluate individual response to a failure of an Excore nuclear instrument.

2) Evaluate individual response to a failure of a running charging pump.

3) Evaluate individual response to a small Pri-Sec leak.

4) Evaluate individual ability to perform a reduction in plant power.

5) Evaluate individual ability to mitigate a SGTR.

6) Evaluate individual ability to monitor operation of ESF equipment.

7) Evaluate individual response to a failure of the PZR heaters.

SCENARIO #1 NARRATIVE Simulator session begins with the plant at 56% power steady state. B circulating water pump is secured and the outer main condenser water boxes are tagged out.

When the crew has completed their control room walk down and brief, B Excore will fail low. This will result in a CPC sensor failure alarm and the NI linear and log power instruments on B channel failing to Zero. The CRS will enter the Nuclear Instrument Malfunction AOP, AOP 2203.026. The CRS will direct the CBOT to bypass points 1, 2, 3, and 4 on B PPS. TS 3.3.1.1 will be entered due to the excore failure.

About 10 minutes after the excore failure, the A CCP will trip its breaker. A CCP low flow alarm will alert the operator that the CCP has tripped. If another pump is not started quickly, letdown will be isolated due to high regenerative heat exchanger outlet temperature high (alarm).The CRS will enter the loss of charging AOP, OP 2203.036, Crew will verify that the breaker tripped; then start a backup CCP. The CBOR will assess the proper operation of the pump, PZR level and letdown flow.

10 minutes after the CCP trips, a 5.0 gpm primary to secondary leak will start. The CRS will enter the primary to secondary leakage AOP, OP 2203.038. CBOR and CBOT will perform RCS Leak rate determinations. The CRS will enter Tech Spec 3.4.6.2. The CRS will direct the NLOs to control secondary contamination using standard attachment 19 and direct the chemists to sample the SGs for activity. The CRS will isolate steam to A EFW pump from A SG and enter TS 3.7.1.2. Crew will perform a plant shutdown.

When cued by the lead evaluator after the CBOR has completed the required reactivity manipulation, a 500 gpm SGTR on A SG will start with a ramp of 10 minutes. Secondary System Radiation Hi, SG tube leak detection Rate of change Hi, and SG tube leak detection leak rate Hi annunciators will alarm. The CBOR recognize that the SGTR is greater than CCP capacity. The CRS will direct the CBOR will manually trip the reactor.

Post trip, the PZR backup heaters will fail to de-energize when PZR level drops below 29%, the CBOR will manually secure the heaters.

Post SIAS, the B HPSI pump Breaker will trip (green train) and one of the red train HPSI injection MOVs will fail to open on actuation. The CBOT will manually start the swing HPSI pump and open the failed injection MOV. This is Tech Spec 3.0.3 entry.

Page 2 of 17

Appendix D Scenario 1 Form ES-D-1 SCENARIO #1 NARRATIVE (continued)

The Crew will implement SPTAs and secure 2 RCPs when RCS pressure drops below 1400 psia. The CRS will diagnose a SGTR and enter EOP 2202.004, SGTR.

The CBOR will rapidly cool down the RCS to less than 535°F using the bypass valves to the condenser. The CBOT will override SW to CCW and ACW. The CBOT will isolate the A SG using standard attachment 10 when RCS Thot is less than 535°F.

Page 3 of 17

Appendix D Scenario 1 Form ES-D-1 Simulator Instructions for Scenario 1 Reset simulator to MOL 56% power IC stead state.

Markup OP 2102.004, power operations up to step 9.22.

Ensure that AACG is secured and annunciators clear.

Ensure hotwell level is ~80%.

Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11.

Swing ESF equipment aligned to the Green train.

A CCP lead charging pump.

2PCV0231, Gland sealing steam pressure control valve failed closed.

Place permissive hand switches for 2CV 303 and 2CV 0306 to OFF.

T1, T2, T3, T5 set to false.

T4 set to SIAS1.

T5 set to PZR Pressure < 2000 psia Event Malf. No. Value/ Event No. Ramp Description Time 1 NIBLINEPWR 0.0 Safety Channel B Excore Linear instrument fails Trigger = T1 LOW.

2 CVC2P36AFAL TRUE A Coolant Charging Pump trips on instantaneous Trigger = T2 Over Current due to motor fault.

3 SGATUBE 5.0 A SG primary-secondary leak.

Trigger = T3 4 SGATUBE 500 A Steam Generator Tube Rupture (500 gpm ramped CUED RAMP= over 10 Minutes).

10 MIN 5 4162A406 TRUE B HPSI pump trips breaker on start.

Trigger = T4 6 CV50151 TRUE Red train HPSI injection MOV fails to open on SIAS Trigger = T4 actuation.

7 RCSHTRON TRUE PZR Backup heaters fail to de-energize.

Trigger = T5 At T=0 Trigger T1 B excore instrument fails low Cue: Report that I & C planner will begin planning work on failed excore instrument.

Page 4 of 17

Appendix D Scenario 1 Form ES-D-1 At T= 10 Trigger T2 A CCP trips breaker.

minutes Cue: As WCO report that the A CCP breaker, 2B52-A5, is tripped and will not reset.

At T=20 Trigger T3 A Steam Generator 5 gpm tube leak.

minutes Cue: As Auxiliary Operator, report that standard attachment 19, control of secondary contamination is in progress.

Cue: When notified of requirement to sample SGs as Chemist, after 15 minutes report that the sample analysis is in progress and that when frisking sample A SG countrate was higher than B SG.

The CRS will direct the NLOs to and direct the chemists to sample the SGs for activity.

CUED by T3 Raise A SG tube leak to 500 gpm ramped over 10 minutes.

Lead This will result in a manual reactor trip.

Examiner SIAS T4 B high pressure safety injection,HPSI, pump trips its breaker on actuation start and one HPSI injection valve, 2CV5015-1 will fail to open but can be manually opened from 2C17.

PZR T5 All backup heaters fail ON and must be manually taken to OFF.

pressure

<2000psia Page 5 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event

Description:

Channel B excore nuclear instrument will fail low. The CRS will enter the NI malfunction AOP, OP 2203.026.

Time Position Applicant's Actions or Behavior ALL Crew will diagnose that B Excore is the only channel that has failed.

CRS Enter AOP 2203.026, NI malfunction and perform the following actions:

Refer to TS 3.3.1.1 Direct the CBOT to bypass points 1,2,3 and 4 on B PPS Verify that Log channel is also affected Notify maintenance of problem with B Excore CBOT Will perform the following:

Obtain Key 12 from SM Notify control room of potential PPS security door and Bypass alarms Open 2C23 door and unlock panel door Push bypass buttons for points :

1 - Hi Linear Power 2 - Hi Log Power 3 - High LPD 4 - Low DNBR Verify that bypass lights illuminated on operator inserts on 2C03 CBOR Will perform the following:

PEER check that bypass lights for points 1,2,3 and 4 are illuminated on operator inserts on 2C03 Simulator Operator Cue: When contacted as IC or Work Week Manager, report that you will begin planning work on B Excore.

Termination criteria: When points 1,2,3 and 4 are bypassed on B PPS or at the discretion of the lead examiner.

Page 6 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event

Description:

A CCP trip. The CCP low flow alarm will alert operators of this failure.

Letdown will isolate, if backup CCP not started in timely manner.

Time Position Applicant's Actions or Behavior CBOR Announce that A CCP has tripped its breaker (Red and Green lights out on 2C09)

CRS Enter loss of Charging AOP and perform the following actions:

Check for proper Charging suction and discharge flow path.

Check that A CCP has tripped breaker Direct Starting backup CCP Direct verification of proper operation of running CCP Check for indications of CCP header rupture using control room indications Direct WCO to locally vent A CCP TRM 3.1.2.4 Applicability Simulator Operator Cue: When contacted as WCO to vent A CCP wait a few minutes and report that no air bubbles only water came out vent.

CBOR Verify VCT outlet valve open Verity CCP header isolation valve open Manually start backup CCP by taking hand-switch to start Verify VCT level stable or going up CBOT Verify CCP header not ruptured:

/CBOR

Aux Building or CNTMT radiation level steady

Waste Tanks 2T20A/B level not rising

CNTMT Sump level not rising

Aux Building sump level not rising NOTE: Letdown may have isolated on high temperature. Letdown may be restored at this point.

Termination criteria: When backup CCP started or at discretion of lead examiner.

Page 7 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

5.0 GPM primary to secondary leak on A SG. The CRS will enter the primary to secondary leakage AOP, OP 2203.038. Crew will perform a plant shutdown Time Position Applicant's Actions or Behavior CBOR Announce annunciators:

2K11-A10 Sec Sys Radiation Hi

2K11-J8 SG Tube Leak Detection Rate of Change Hi

2K11-K8 SG Tube Leak Detection Trouble/LKRT Hi CRS Implement AOP 2203.038, PRI-SEC leakage and perform the following:

Direct CBOs to perform RCS leak rates Enter TS 3.4.6.2 Direct AO to perform standard attachment 19, control of secondary contamination Direct the chemists to sample the SGs for activity Direct CBOT to isolate steam to A EFW pump from A SG Direct CBOR to perform a plant shutdown using normal boration method.

CBOT Close 2CV 1000-1, steam from A SG to A EFW pump.

Page 8 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

5.0 GPM primary to secondary leak on A SG. The CRS will enter the primary to secondary leakage AOP, OP 2203.038. Crew will perform a plant shutdown.

Simulator Operator Cue: When contacted as AO acknowledge requirement to begin working on Standard attachment 19.

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

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

Insert CEAs as directed by reactivity plan.

AOP requires a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months shutdown to Mode 3.

The CRS may determine a rapid plant shutdown of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to be in Mode 3 is more conservative and this decision is acceptable.

Termination criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.

Page 9 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

500 gpm Tube Rupture on A Steam Generator ramped over 10 Minutes.

This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate A SG.

Time Position Applicant's Actions or Behavior CBOR Report that PZR level is lowering Start all back up CCPs or report that they are running Isolate Letdown CRS Recognize SGTR has exceeded CCP capacity and the ability to maintain PZR level.

Direct the CBOR to manually trip the reactor CBOR Manually trip the reactor.

CRS Implement Standard Post Trip Actions, track safety functions, and direct board operators actions.

CBOR Check reactivity control:

Reactor power decreasing.

All CEAs inserted.

CBOT Check maintenance of vital auxiliaries:

Main turbine tripped.

Generator output and exciter breakers open.

All 4160v and 6900 v Non-Vital busses energized.

ALL 4160v and 480v vital AC bus energized.

All 125v vital DC bus energized.

Page 10 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

500 gpm Tube Rupture on A Steam Generator ramped over 10 Minutes.

This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate A SG.

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

PZR level 16 to 80%.

Trend from set point.

Report SIAS actuated or manually actuate and verify all PZR heaters off when PZR level less than 29%.

(SEE Event 7)

CBOR Check RCS pressure control:

RCS pressure 1800 to 2300 psia.

Trend from set point Secure Two RCPs when RCS pressure is less than 1400 psia.

Place spray valve for secured RCPs in manual closed.

Verify SIAS when pressure less than 1650 psia.

CBOR Check core heat removal by forced circulation:

RCP s running Loop T less than 10° F.

RCS MTS 30° F or greater.

Service water pump suction aligned to Lake.

Component cooling water aligned to RCPs.

CBOT Restore SW to ACW per Exhibit 5. (NOTE: This action requires several minutes)

Check SIAS actuated.

Maintain SW pressure greater than 85 psig.

Page 11 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

500 gpm Tube Rupture on A Steam Generator ramped over 10 Minutes.

This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate A SG.

Time Position Applicant's Actions or Behavior CBOT Check RCS Heat Removal:

Report SG levels and main feed water is in RTO.

Report feed water line intact.

Report SG pressures (May take manual local (ML) control of SDBCS master controller (at CRS direction) and reduce set point to 950-1050 psia).

CBOR Check CNTMT parameters:

Temperature less than 140° F.

Pressure less than 16 psia.

Status of radiation alarms:

CAMS (2K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT in alarm Secondary Sys Radiation Hi (2K11-A10) IN ALARM CBOT Will open 2CV0233, bypass around 2PCV0231 which is simulated closed to match condition of valve at plant. This is in response to low gland seal pressure.

CRS Notify SM to perform the following:

SE report to control room.

Announce reactor trip on plant page.

Refer to Tech Specs and EALs.

Page 12 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

500 gpm Tube Rupture on A Steam Generator ramped over 10 Minutes.

This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate A SG.

CRS Direct CBOs to acknowledge all control room annunciators and announce all significant alarms.

Diagnose Steam Generator Tube Rupture CRS Implement Steam Generator Tube Rupture procedure and open place keeping page.

ALL Perform crew brief and review floating steps.

CRS Determine applicable floating steps:

Commence cool down to less than 535° F Thot.

HPSI Override Criteria.

CRS Direct the following actions:

Commence cool down to less than 535° F Thot.

Inform SM to contact Chemistry to sample both SG for activity.

Determine ruptured SG Perform post-SIAS actions:

Verify Safety Injection flow to RCS:

Isolate A SG when RCS Thot is less than 535°F Verify HPSI override criteria met:

RCS MTS 30°F or greater.

PZR level greater than 29% and controlled.

RVLMS LVL 03 or higher elevation indicates WET.

At least ONE intact SG available for Heat Removal Level 10 to 90% with FW available.

Page 13 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

500 gpm Tube Rupture on A Steam Generator ramped over 10 Minutes.

This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate A SG.

Time Position Applicant's Actions or Behavior Critical CBOR RCS cool down to less than 535°F T-hot : (floating step)

Step CBOR Reset low SG set points.

Commence RCS depressurization to maintain RCS MTS 30 to 45° (When HPSI overridden)

Take manual control of SDBCS bypass valves to condenser (2CV0302/2CV0303)

Place ALL ADV Permissive switches in OFF.

Verify EFW feeding SGs.

Secure running MFW pump.

Close ALL MFW Block valves.

Record and plot cool down on Attachments 1 and 8.

CBOR Verify Safety Injection flow to RCS:

Check HPSI flow using Exhibit 2.

/CBOT Check LPSI flow using Exhibit 3.

Page 14 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

500 gpm Tube Rupture on A Steam Generator ramped over 10 Minutes.

This will result in a manual reactor trip, SIAS and CCAS actuations. Crew will perform a cool down of the RCS and manually Isolate A SG.

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

SW pumps running on each loop.

EDG SW outlet valves open.

SW pump suction aligned to Lake.

Report all non-vital buses energized.

Verify SG sample valves open.

Critical CBOT Use Attachment 10 to isolate Ruptured SG Step CBOR OVERRIDE HPSI:

CBOT Throttle HPSI flow OR place HPSI pumps in PTL as needed to control RCS pressure, inventory, and heat removal.

Termination criteria: RCS Cool down to less than 535°F and A SG isolated or at examiners discretion.

Page 15 of 17

Appendix D Scenario 1 Form ES-D-1 Op-Test No.: 1 Scenario No.: 1 Event No.: 5/6 Event

Description:

B HPSI pump trips on SIAS start. 2CV5015-1 fails to open on SIAS signal. This will make HPSI flow UNACCEPTABLE. C HPSI pump must be started or 2CV5015-1 must be opened.

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

Observes green light lit on pump and no discharge pressure.

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

CRS Directs starting C HPSI pump Directs opening 2CV 5015-1 Critical CBOT Starts C HPSI pump Step Verified proper discharge pressure and flow(depending on RCS pressure)

Critical And/or Part is Opens 2CV 5015-1 by taking hand switch to OPEN and to observing red light on green light off and Z-tape reading ~

either 100%

start 2P89C or open 2CV-5015-1 Termination criteria: When C HPSI pump started or 2CV5015-1 is opened or at discretion of lead examiner.

Page 16 of 17

Appendix D Scenario 1 Form ES-D-1 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.

Page 17 of 17

Appendix D Scenario 2 Form ES-D-1 Facility: ANO-2 Scenario No.: 2 Op-Test No.: 2005-1 Examiners: Operators:

Initial Conditions:

100% MOL, All ESF systems in standby. C HPSI pump tagged out for oil bubbler replacement. C HPSI is aligned to green train. Green train maintenance week.

Turnover:

100%. 250 EFPD. C HPSI pump tagged out for oil bubbler replacement. EOOS indicates Minimal Risk. Green train maintenance week.

Event Malf. No. Event Event No. Type* Description 1 XRCCHAPLVL I (CBOR) Control Channel A Pressurizer Level fails LOW.

2 XSG2PT10412 I (CBOT) Steam Generator safety channel pressure fails LOW.

3 FWPMPATRP R (CBOR) A Main Feed Pump (MFP) trips due to thrust N (CBOT) bearing wear and results in a power reduction to less than 90%.

4 FWAFT5A M (ALL) Feed water line break in containment after 2FW5A, feed water to A Steam Generator (SG) check valve, which results in Excess Steam Demand (ESD) on A SG.

5 ESCSBPMP C (CBOT) Fail B Containment Spray Actuation Signal (CSAS) pump to start on CSAS.

6 ESFCSASFAIL C (CBOR) Fail CSAS channel 1 to actuate auto.

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

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

1) Evaluate individual response to a failure of Pressurizer level control channel failure.

2) Evaluate individual response to a failure of a Plant Protection System Steam Generator Level instrument failure.

3) Evaluate individual response to a Main Feed Pump Trip at 100% power.

4) Evaluate individual ability to perform a reduction in plant power.

5) Evaluate individual ability to mitigate an unisolatable Feed water break in containment.

6) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.

7) Evaluate individual response to a failure of required Engineered Safety Features Actuation System actuation.

SCENARIO #2 NARRATIVE Simulator session begins with the plant at 100% power steady state. C HPSI pump is tagged out to replace a pump oil bubbler.

When the crew has completed their control room walk down and brief, the in service Pressurizer (PZR) control channel level instrument will fail low. Alarms on control channel 1 level lo and level lo lo will come in. This will result in letdown going to minimum flow, the two backup CCPs will automatically start, all PZR heaters de-energizing and actual PZR level go up. AOP 2203.028, PZR Systems Malfunctions, will be entered and actions directed by the CRS. The CBOR will take the letdown flow controller to manual and control PZR level. The CBOR will also verify that the other level control channel is reading correctly and select that channel for control and place the PZR low low level cutoff switch to the unaffected channel. When the auto and manual signals are matched, the CBOR will place the letdown flow controller to automatic About 10 minutes after PZR level control failure, A Steam Generator safety channel pressure instrument, 2PT1041-2, will fail low. 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 B operator insert (2C03) trip and pre-trip lights will be lit. The CRS will refer to the ACA 2203.012D and tech specs 3.3.1.1, 3.3.2.1 and 3.3.3.6 for guidance. The CBOT will place Channel B PPS in bypass for point 11, SG pressure low, point 19, A SG delta-P for EFAS 1, and point 20, B SG delta-P for EFAS 2 for maintenance and trouble shooting. The crew will have one hour to place these points in bypass before exceeding the tech spec LCO.

About 10 minutes after the Steam Generator instrument failure, A MFP will trip. CRS will enter AOP 2203.037, Loss of Main Feed Pump. This will result in Steam Flow exceeding Feed flow and SG levels dropping. The crew will manually start the fourth condensate pump, reduce turbine load, and borate using emergency boration to the RCS until Feed flow is greater than Steam Flow. Then continue with a normal boration power reduction to less than 90%.

Page 2 of 16

Appendix D Scenario 2 Form ES-D-1 SCENARIO #2 NARRATIVE (continued)

Once the Reactor operators reactivity manipulations are complete, the main feed line break will occur. This will cause containment pressure, temperature and sump level to go up. A Steam Generator level will lower. The crew will manually trip the reactor and complete SPTAs. Once feed (Main and Emergency) is secured to the SG, an Excess Steam Demand will occur on A Steam Generator.

The CRS will diagnose an Excess Steam Demand event and enter OP 2202.005, ESD.

The crew will manually control Reactor Coolant Temperature once the A SG boils dry using the upstream Atmospheric Dump Valves on B SG. The crew will manually control PZR pressure using the Auxiliary Spray valve.

When Containment pressure exceeds 23.3 psia, the crew will recognize that CSAS, Containment Spray Actuation Signal, has not automatically actuated on Channel 1 and that the Spray pump on channel 2 side did not start. The crew will manually actuate spray on Channel 1 and manually start B CSAS pump.

Page 3 of 16

Appendix D Scenario 2 Form ES-D-1 Simulator Instructions for Scenario 2 Reset simulator to MOL 100% power IC stead state.

Ensure that AACG is secured and annunciators clear.

C HPSI pump is tagged out for oil bubbler replacement.

Ensure hotwell level is ~80%.

Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11.

T1, T2, T3, T4 set to false.

Event Malf. No. Value/ Event No. Ramp Description Time 1 XRCCHAPLVL 0.0 Control Channel A Pressurizer Level fails LOW.

Trigger 1 2 XSG2PT10412 0.0 Steam Generator safety channel pressure fails LOW.

Trigger 2 3 FWPMPATRP TRUE A Main Feed Pump (MFP) trips due to thrust bearing Trigger 3 wear and results in a power reduction to less than 90%.

4 FW2PW5AAFT 1000 Feed water line break in containment after 2FW5A, Trigger 4 Ramp feed water to A Steam Generator (SG) check valve, which results in Excess Steam Demand (ESD) on A 5 min SG.

5 BS2P35BFAL TRUE Fail B Containment Spray Actuation Signal (CSAS) pump to start on CSAS.

6 ESFCSASFAIL TRUE Fail CSAS channel 1 to actuate auto.

At T=0 Trigger T1 Control Channel A Pressurizer Level fails LOW.

Cue: Report that I & C planner will begin planning work on failed PZR level transmitter.

At T= 10 Trigger T2 Steam Generator safety channel pressure fails LOW, minutes 2PT10412.

Cue: Report that I & C planner will begin planning work on failed Steam Generator safety channel pressure transmitter.

Page 4 of 16

Appendix D Scenario 2 Form ES-D-1 At T=20 Trigger T3 A Main Feed Pump (MFP) trips.

minutes Cue: As Auxiliary Operator, report that A MFP is tripped and no obvious problems noted locally.

CUED by T4 A main feed line break inside containment resulting in a reactor Lead trip and excess steam demand event Examiner CSAS True B containment spray pump will fail to start on CSAS signal.

actuation Can be manually started.

CSAS True Red Train containment spray actuation signal, CSAS, will not actuation automatically actuate. Can be manually actuated.

Page 5 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event

Description:

Channel A pressurizer level control channel 2LT-4627-1 fails low. The CRS will enter the PZR Systems Malfunction AOP 2203.028.

Time Position Applicant's Actions or Behavior ALL Announce alarms 2K10-G6 CNTRL CH 1 LEVEL LO.

2K10-F6 CNTRL CH 1 LEVEL LO LO.

Report 2LI-4627-2 and 2LR-4625 indicate normal.

Report backup charging pumps started.

CRS Refer to PZR Systems Malfunctions AOP 2203.028 and direct board operators actions.

CBOR Determine PZR level Channel A failed.

Place Letdown Flow controller (2HIC-4817) in MANUAL.

Place PZR Level Channel Select switch (2HS-4628) to Channel B.

Place PZR Low Low Level Cutoff select switch (2HS-4642) to Channel B.

Verify PZR heaters and Normal Spray maintaining RCS pressure 2025 to 2275 psia.

The CBOR will take the letdown flow controller to manual and control PZR level.

CRS Enter 3.3.3.6 Post Accident Instrumentation.

Simulator Operator Cue: When contacted as IC or Work Week Manager, report that you will begin planning work on 2LI-4627-1.

Termination criteria: Unaffected PZR level channel selected and letdown in automatic or at the discretion of the lead examiner.

Page 6 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

2PT1041-2, Channel B SG pressure transmitter fails low.

Time Position Applicant's Actions or Behavior CBOT Announce annunciators:

2K04-A4 CH A RPS/ESF/PRETRIP/TRIP 2K04 B3 PPS TRIP 2K04-E4 MSIS PRETRIP Compare all four channels and report 2PI-1041-2 indicates 0 psia.

CRS Implement Annunciator Corrective Action AOP 2203.012D.

Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.6.

CBOR Report A SG pressure low pretrip and trip.

CBOT Place the following channels in bypass on Channel B:

A SG pressure low - RPS (Bistable 11)

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 2PT1041-2.

Simulator Operator Cue: When contacted as WWM, work week manager, of I&C need to troubleshoot and repair 2PT1041-2. Report that planning on repair of 2PT1041-2 is in progress.

Termination criteria: When B plant protection system points 11, 19 and 20 are bypassed or at discretion of lead examiner.

Page 7 of 16

Appendix D Scenario 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 Behavior CBOT Announce A MFP trip alarms:

2K03 A8, A MFP trip 2K03 K8, Thrust Bearing Wear Trouble CRS Enter 2203.027, Loss of Main Feed Pump AOP and direct the following actions:

Verify Recirc valves closed (Condensate and MFP)

Verify Main Feed water regulating valve bypasses are opening Start standby condensate pump Commence emergency boration using exhibit 1 Reduce MTG load to establish Feed water Flow > Steam Flow while maintaining TC < 554.7°F Secure Emergency boration when Feed water Flow > Steam Flow CBOT Check tripped MFW pump recirc and Condensate recirc closed.

Check MFWRV B/P valves open.

Start standby Condensate Pump.

Reduce MTG load to establish Feed water Flow > Steam Flow while maintaining TC < 554.7°F.

CBOR Commence boration using Exhibit 1.

Page 8 of 16

Appendix D Scenario 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.

CRS When FF>SF, direct CBOR to commence down power to <

90% using normal boration method.

CBOR Align normal boration to RCS.

Reduce turbine load to maintain Tave within 2° of Tref until power is less than 90%.

Termination criteria: When CBOR has completed reactivity manipulations or at discretion of lead examiner.

Page 9 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line break inside containment on A SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.

ALL Announce that A SG level is lowering.

Containment temperature and pressure are rising.

Announce that radiation levels in containment are steady.

Announce that containment sump level is rising quickly.

Diagnose that a feed line leak is in progress inside containment.

CRS Direct CBOR to manually trip the reactor.

CBOR CBOR manually trip the reactor.

CRS Implement Standard Post Trip Actions, track safety functions, and direct board operators actions.

CBOR Check reactivity control:

Reactor power decreasing.

All CEAs inserted.

CBOT Check maintenance of vital auxiliaries:

Main turbine tripped.

Generator output and exciter breakers open.

All 4160 v and 6900 v Non-Vital busses energized.

ALL 4160 v and 480 v vital AC bus energized.

All 125 v vital DC bus energized.

Page 10 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line break inside containment on A SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.

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

PZR level 16 to 80%.

Trend from set point.

Report SIAS actuated or manually actuate and verify all PZR heaters off when PZR level less than 29%.

CBOR Check RCS pressure control:

RCS pressure 1800 to 2300 psia.

Trend from set point Secure Two RCPs when RCS pressure is less than 1400 psia.

Place spray valve for secured RCPs in manual closed.

Verify SIAS when pressure less than 1650 psia.

CBOR Check core heat removal by forced circulation:

RCP s running Loop T less than 10° F.

RCS MTS 30° F or greater.

Service water pump suction aligned to Lake.

Component cooling water aligned to RCPs.

CBOT Restore SW to ACW per Exhibit 5. (NOTE: This action requires several minutes)

Check SIAS actuated.

Maintain SW pressure greater than 85 psig.

Restore CCW to RCPs using exhibit 5 (when CIAS actuates).

Page 11 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line break inside containment on A SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.

Time Position Applicant's Actions or Behavior CBOT Check RCS Heat Removal:

Report SG levels and main feed water is in RTO.

Report feed water line is NOT intact.

Report SG pressures A SG lower than B SG.

Manually actuate EFAS, Emergency Feed water Actuation Signal if not already actuated.

Verify that MSIS is actuated.

Verify Feed water is not aligned to A SG CBOR Check CNTMT parameters:

Temperature greater than 140° F.

Pressure greater than 16 psia.

Status of radiation alarms:

CAMS (2K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT in alarm Secondary Sys Radiation Hi (2K11-A10) NOT in alarm Secure ALL RCPs when Containment Spray Actuation Signal (CSAS) occurs.

CRS Notify SM to perform the following:

SE report to control room.

Announce reactor trip on plant page.

Refer to Tech Specs and EALs.

Page 12 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line break inside containment on A SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.

CRS Direct CBOs to acknowledge all control room annunciators and announce all significant alarms.

Diagnose EXCESS STEAM DEMAND EOP.

CRS Implement EXCESS STEAM DEMAND EOP procedure and open place keeping page.

ALL Perform crew brief and review floating steps.

CRS Determine applicable floating steps:

Control post steam generator blow down RCS temperature and pressure CRS Direct the following actions:

Isolate A SG using Attachment 10.

Control post steam generator blow down RCS temperature using B steam generator upstream atmospheric dump valve.

Control PZR pressure within P-T limits using Auxiliary Spray valve and Attachment 27.

Override HPSI when conditions are met.

RCS MTS 30°F or greater.

PZR level greater than 29% [50%] and controlled.

RVLMS LVL 03 or higher elevation indicates WET.

At least ONE intact SG available for Heat Removal Page 13 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

Main Feed line break inside containment on A SG. This will result in a reactor trip, SIAS, CCAS, CIAS and CSAS engineered safety features actuations.

Time Position Applicant's Actions or Behavior Critical CBOT Control post Steam Generator blow down RCS temperature Step using upstream atmospheric dump valve within 25°F of A Steam Generator Tc when generator boiled dry.

Critical CBOR Maintain Post steam generator blow down PZR pressure using Step auxiliary spray valve and attachment 27 within the Pressure-Temperature limits of 200°F and 30°F.

CBOR Override HPSI flow and charging flow to maintain PZR level.

/CBOT Termination criteria: When plant temperature and pressures are stabilized after A Steam Generator boils dry or at the discretion of the lead examiner.

Page 14 of 16

Appendix D Scenario 2 Form ES-D-1 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

B Containment Spray pump, 2P35B fails to automatically start. CBOT will manually start the B containment spray pump.

Time Position Applicant's Actions or Behavior CBOT Reports that no flow is indicated on 2C16 for containment spray flow after actuation.

Reports that B containment spray pump is not running Reports that the B containment spray containment isolation valve is open.

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

Critical CBOT Manually starts 2P35B, B containment spray pump on 2C16.

Step Verifies proper containment spray flow on 2C16.

(Either start of 2P35B or actuate CSAS 1)

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

Page 15 of 16

Appendix D Scenario 2 Form ES-D-1 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 CBOR On 2C03 manually actuates CSAS and verifies all four operator Step insert red lights are out above the CSAS label on 2C03.

(Either start of 2P35B or actuate CSAS 1)

Termination criteria: When CSAS is manually actuated or at discretion of lead examiner.

Page 16 of 16

Appendix D Scenario 3 Form ES-D-1 Facility: ANO-2 Scenario No.: 3 Op-Test No.: 2005-1 Page 1 Examiners: Operators:

Initial Conditions:

100% MOL, All ESF systems in standby. Green Train Maintenance Week.

Turnover:

100%. 250 EFPD. EOOS indicates Minimal Risk. Green Train Maintenance Week.

Event Malf. No. Event Event No. Type* Description 1 XCV2LT4861 I (CBOR) VCT level instrument fails low resulting in RWT being aligned to CCP suction.

2 XFW2FIS0735 I (CBOT) A MFP suction flow transmitter fails low. Results in condensate and MFP recircs to condenser opening fully and reducing feed water to SGs.

3 CNDVACUUM R (CBOR) Air leakage into condenser requiring a power N (CBOT) reduction to maintain condenser vacuum.

4 CNDVACUUM M (ALL) Air leakage into condenser results in loss of condenser vacuum and turbine and reactor trip.

5 SU#3 lockout N (CBOT) Loss of offsite power. Must energize non-vital 2A111 fails to busses.

close Startup #2 to 2A1 fails OPEN.

I (CBOR) Loss of power to PZR controllers must be controlled manually or transfer to automatic.

6 2CV1503-1 fails to C (CBOT) #1 EDG service water outlet MOV. This will result open in deenergizing red train vital 4160VAC, 2A3, and 480VAC, 2B5.

7 2CV0340-2 C (CBOT) A EFW pump steam inlet valve fails to open. This breaker trips will result in a loss of all feed water.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 14

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

1) Evaluate individual response to a failure of Volume Control Tank level transmitter.

2) Evaluate individual response to a failure of a Main Feed Pump suction Flow transmitter.

3) Evaluate individual response to a small condenser vacuum leak.

4) Evaluate individual ability to perform a reduction in plant power.

5) Evaluate individual ability to mitigate a loss of all Feed Water.

6) Evaluate individual ability to mitigate a loss of off site power.

7) Evaluate individual response to a failure Loss of power to a vital bus.

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

When the crew has completed their control room walk down and brief, one of the two volume control tank (VCT) level transmitters will fail low. The crew will respond to VCT low low level alarm, 2K12 G5. This will result in the VCT outlet valve to the charging pump suction to close and the Refueling Water tank (RWT) suction to the charging pumps to open. RCS temperature and pressure will lower until the CBOR positions the VCT outlet valve manually opened and the RWT valve manually closed.

About 10 minutes after VCT level transmitter failure, A main feed pump suction transmitter will fail low. This will result in 2K03-D9 (A MFP SUCT FLOW LO) alarm. This will result in both the A MFP and A / C condensate pump recirc valves opening. This will reduce Main feed water flow to A Steam Generator and reduce MFP suction pressure so that the standby condensate pump will automatically start. The CBOT will recognize the instrument failure due to flow on the A MFP controller indicating zero even with the recirc valve open and flow indicated on the Feed water flow transmitters to the steam generator.

The CBOT will take manual control of both the MFP and condensate pump recirc valves and close them.

About 10 minutes after the MFP suction flow instrument failure, air in-leakage into the main condenser will start. This will result in condenser vacuum slowly degrading. The CRS will enter OP 2203.019, Loss of condenser vacuum. The CBOR will begin an emergency boration and the CBOT will reduce main turbine load to restore condenser vacuum. The crew will secure emergency boration and reducing turbine load when vacuum stabilizes.

The CBOR will then commence normal boration and reduce turbine load to allow condenser vacuum to be restored to less than ~6.5 in Hg.

Once the Reactor operators reactivity manipulations are complete, the air in-leakage will be raised to beyond the vacuum pumps capacity and the plant will be manually tripped.

Upon the reactor trip, Startup transformer #3 will lock-out and startup transformer #2 feeder to 2A1 will fail resulting in a loss of off-site power. When #1 EDG starts, the service water value from the EDG will fail to open. This will result in the CRS directing the #1 EDG to be locally secured resulting in a loss of the red train vital power (2A3 and 2B5). Also, the CRS will direct selecting channel #2 PZR level and pressure control channel instrumentation due to a loss of power to the selected channel #1 instruments.

Page 2 of 14

Appendix D Scenario 3 Form ES-D-1 SCENARIO #3 NARRATIVE (continued)

When an Emergency Feed water Actuation Signal (EFAS) occurs and A emergency feed water pump attempts to start automatically start, the steam inlet valve, 2CV 0340-2, will trip its breaker when it starts to open. This will result in a loss of all feed water to the steam generators. The CRS will direct that at least one RCP in each loop are secured and Steam Generator blowdown is isolated from both steam generators. When standard post trip actions, SPTAs, are complete, the CRS will diagnose and enter the Loss of Feed EOP OP2202.006. The CBOT will manually start the Alternate AC Generator from 2C14 and energize 2A3, vital 4160 bus or open the Service water valve from the #1 EDG and start

1 EDG. Once 2A3 is energized the CBOT will manually start the emergency feed water pump, 2P7B, from 2C17 and align feed to both steam generators using the Emergency Feed water valves.

Page 3 of 14

Appendix D Scenario 3 Form ES-D-1 Simulator Instructions for Scenario 3 Reset simulator to MOL 100% power IC stead state.

Ensure that AACG is secured and annunciators clear.

Ensure hotwell level is ~80%.

Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11.

T1, T2, T3, T4, T5 set to false.

T4 set to RXTRP T6 set to EFAS-1 T7 set to EFAS-2 Event Malf. No. Value/ Event No. Ramp Description Time 1 XCV2LT4861 0.0 VCT level instrument fails low resulting in RWT Trigger=T1 being aligned to CCP suction.

2 XFW2FIS0735 0.0 A MFP suction flow transmitter fails low. Results in Trigger=T2 condensate and MFP recircs to condenser opening fully and reducing feed water to SGs.

3 CNDVACUUM 4.6 Air leakage into condenser requiring a power Trigger=T3 Ramp reduction to maintain condenser vacuum.

4 min 4 CNDVACUUM 10.0 Air leakage into condenser results in loss of Ramp condenser vacuum and turbine and reactor trip.

5 min 5 FailSU3 TRUE Startup 3 lockout results in a loss of offsite power.

Causes EDGs to automatically start/ loose Aux feed water pump and non-vital loads.

416A111 Locked

-Open Loss of power to PZR controllers must be controlled manually or transfer to automatic.

Trigger=T4 6 CV15031 0.0 #1 EDG service water outlet MOV fails to open. This Trigger=T5 will result in deenergizing red train vital 4160VAC, 2A3, and 480VAC, 2B5.

7 CV0340 0.0 A EFW pump steam inlet valve fails to open. This Trigger=T6 will result in a loss of all feed water.

Trigger=T7 Page 4 of 14

Appendix D Scenario 3 Form ES-D-1 At T=0 Trigger T1 VCT level instrument fails low, 2LT4861.

Cue: Report that I & C planner will begin planning work on failed Volume control tank, VCT, level transmitter.

At T= 10 Trigger T2 A MFP suction flow transmitter fails low, 2FIS0735.

minutes Cue: Report that I & C planner will begin planning work on failed A MFP suction flow transmitter.

At T=20 Trigger T3 Air leakage into condenser requiring a power reduction to minutes maintain condenser vacuum.

Cue: As Auxiliary Operator, report that air in-leakage is from B Low pressure turbine west manway cover and you will need mechanical maintenance support to seal the leak.

Cue: As mechanical maintenance report that it will take from 20 to 30 minutes to repair the leak.

CUED by Raise air leakage into condenser to 10 ramped over 5 minutes.

Lead Examiner Cue: After 5 minutes, report as mechanical maintenance report that the manway gasket on A LP turbine has catastrophically failed.

Main T4 SU#3 lockout and failure of SU#2 feeder to 2A1 to close, turbine trip 2A111.

PZR control channel level and pressure controllers will fail to manual on power transfer to #1 EDG and must be transferred to Channel 2 on loss of #1 EDG.

1 EDG T5 #1 EDG service water outlet MOV fails to open, 2CV 1503-1.

start EFAS-1 T6 A EFW pump steam inlet valve fails to open, 2CV 0340-2.

Page 5 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event

Description:

VCT level transmitter 2LT4861 fails low. This causes the RWT to be aligned to CCP suction and Tave lowering.

Time Position Applicant's Actions or Behavior CBOT Announce annunciator 2K12-G5 VCT 2T4 LEVEL LO LO.

CRS Implement Annunciator Corrective Action AOP 2203.012L.

CBOR Report level indicates normal on 2LIS-4857 but 2LT-4861 reads 0% on computer.

Reports charging pump suction swapping to RWT.

CBOR May secure charging to stop boration if have not determined indication is a failed instrument and VCT level is normal.

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

CBOT Reduce turbine load to maintain Tave within 2° F of Tref if Tave

/CBOR lowered.

CRS Contact maintenance/PS liaison to troubleshoot failed instrument.

Simulator Operator Cue: When contacted as IC or Work Week Manager, report that you will begin planning work on 2LT-4861.

Termination criteria: Charging suction manually aligned to the VCT and RWT to CCP valve closed or at the discretion of the lead examiner.

Page 6 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

2FIS0735, A loop condensate flow fails low. Condensate and MFP recirc valves open. CBOT must take manual control of recircs and control MFP suction pressure.

Time Position Applicant's Actions or Behavior CBOT Announce annunciator 2K03-D9 (A MFP SUCT FLOW LO)

CRS Implement Annunciator corrective action 2203.012C and direct board operator actions.

CBOT Report auto start of condensate pump.

Determine instrument 2FIS-0735 failure by use of PMS or control board indications.

Place A condensate recirc and A main feed pump recirc valves in manual to control condensate header pressure.

Secure condensate pump that auto started.

(Examiners Note: Crew may elect to leave fourth condensate pump running until a later point in the shutdown.)

CRS Contact maintenance/WWM to investigate failed transmitter.

Simulator Operator Cue: When contacted as WWM, work week manager, of I&C need to troubleshoot and repair 2FIS 0735. Report that planning on repair of 2FIS0735 is in progress.

Termination criteria: When condensate and MFP recircs are in manual and secondary plant is stable or at discretion of lead examiner.

Page 7 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Condenser vacuum slowly degrades. Crew will reduce turbine load Time Position Applicant's Actions or Behavior CBOT Main Condenser lowering vacuum:

2K03 A3, 2E11A Pressure HI 2K03 B3, 2E11A Turb Hood Press HI 2K03 E4, Vacuum pump 2C5B Auto Start 2K02 B14, Condenser Interlock CRS Enter 2203.019, Loss of condenser vacuum and direct the following actions:

Verify both vacuum pumps running Verify adequate gland seal steam pressure Verify both circulating water pumps running Reduce MTG load to maintain Tc less than 554.7°F and condenser vacuum < 6.5 inHg.

Commence emergency boration using exhibit 1 Secure Emergency boration when condenser vacuum is < 6.5 inHg.

CBOT Reduce MTG load to maintain Tc less than 554.7°F and condenser vacuum < 6.5 inHg.

CBOR Commence boration using Exhibit 1.

Page 8 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Condenser vacuum slowly degrades. Crew will reduce turbine load CRS When vacuum is less than 6.5 inHg. Secure emergency boration.

Contact Ops Management.

Simulator Operator Cue: When contacted as AO report that you can hear the air leak on the vacuum suction piping on the East heater deck under the deck floor. It is unisolatable.

Simulator Operator Cue: When contacted as Maintenance, report that it will take at least 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to patch the leak.

Simulator Operator Cue: When contacted as OPS Management, tell the CRS to reduce plant power until vacuum alarms are cleared.

CRS Direct CBOR to reduce commence a normal boration at power and reduce turbine load to < 5 inHg (to clear alarms).

CBOR Align normal boration to RCS.

Reduce turbine load to maintain Tave within 2° of Tref until condenser vacuum is less than 5 inHg.

Termination criteria: When CBOR has completed reactivity manipulations or at discretion of lead examiner.

Page 9 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event

Description:

Condenser air in-leakage exceeds the capacity of the vacuum pumps.

This results in a reactor trip.

ALL Announce that condenser vacuum is degrading.

CRS Direct CBOR to manually trip the reactor.

CBOR CBOR manually trip the reactor.

CRS Implement Standard Post Trip Actions, track safety functions, and direct board operators actions.

CBOR Check reactivity control:

Reactor power decreasing.

All CEAs inserted.

CBOT Check maintenance of vital auxiliaries:

Main turbine tripped.

Generator output and exciter breakers open.

All 4160v and 6900 v Non-Vital busses NOT energized.

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

All 125v vital DC bus energized.

Page 10 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event

Description:

Condenser air in-leakage exceeds the capacity of the vacuum pumps. This results in a reactor trip.

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

PZR level 16 to 80%.

Trend to set point.

(See event 5/6)

CBOR Check RCS pressure control:

RCS pressure 1800 to 2300 psia.

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

RCP s running Loop T less than 10° F.

RCS MTS 30° F or greater.

Service water pump suction aligned to Lake.

Component cooling water aligned to RCPs.

SW to aligned to CCW and ACW CBOT Check RCS Heat Removal:

Report SG levels Main feed water is secured.

Manually actuate EFW.

Report feed water line is NOT intact.

Report SG pressures Shut both MSIVs due to 2CV 0400 and 2CV 0460, Main Steam to the moisture separator reheaters, have no power and are open.

Page 11 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event

Description:

Condenser air in-leakage exceeds the capacity of the vacuum pumps.

This results in a reactor trip.

Time Position Applicant's Actions or Behavior CBOR Check CNTMT parameters:

Temperature less than 140° F.

Pressure less than 16 psia.

Status of radiation alarms:

CAMS (2K10-B6) NOT in alarm Area radiation (2K11-B10) NOT in alarm Process liquid (2K11-C10) NOT in alarm Secondary Sys Radiation Hi (2K11-A10) NOT in alarm CRS Notify SM to perform the following:

SE report to control room.

Announce reactor trip on plant page.

Refer to Tech Specs, 3.0.3 due to no emergency feedwater available and 3.8.1.1 action C.

Termination criteria: CRS has diagnosed a Loss of All Feed event and transitions to EOP or at discretion of lead examiner.

Page 12 of 14

Appendix D Scenario 3 Form ES-D-1 Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and 6 Event

Description:

Startup transformer #3 lockout and feeder breaker from Startup transformer #2 to 2A1, non-vital 4160VAC bus fails to open. This will result in a loss of offsite power and automatic start of both emergency diesel generators (#1 and #2 EDG).

CRS Verify Service Water is aligned to #1 EDG and #2 EDG.

CBOT Report that service water is not aligned to #1 EDG and that service water is aligned to #2 EDG and is running with proper voltage.

CRS Direct that AO locally take #1 EDG to lockout.

CRS Direct CBOR to select channel 2 PZR level and pressure controllers.

CBOR Select channel 2 PZR level and pressure controllers and places them in automatic.

Termination criteria: When CBOR has selected channel 2 PZR level and pressure controllers or at discretion of lead examiner.

Page 13 of 14

Appendix D Scenario 3 Form ES-D-1 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 CBOT Manually starts the Alternate AC Generator and energizes 2A3.

Step Critical CBOT Manually starts B Emergency Feed Pump and restores feed Step water to both steam generators.

CBOR Monitor control Steam generator pressures less than main steam safety valve lift set point (~1078 psig).

Control PZR pressure using auxiliary spray less than 2500 psia.

Termination criteria: When Emergency Feed water is established to both Steam Generators or at the discretion of the lead examiner.

Page 14 of 14

ML050690411: Difference between revisions

Latest revision as of 02:17, 15 March 2020

Text

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Navigation menu

Search