Revision as of 01:47, 13 November 2019

Text

AN2-2011-02-DRAFT Operating Test
	ML110820680
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/23/2011
From:	Apger G; Division of Reactor Safety IV
To:	; Entergy Operations
References
	50-368/11-301
	Download: ML110820680 (231)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 01/28/2011 Examination Level: RO X SRO Operating Test Number: 2011-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Apply limit and precautions to transferring Unit Auxiliaries to Start Up Transformer #2.

A1. Conduct of Operations P/R ANO-2-JPM-NRC-ADMIN-SU2LOAD 2.1.32 RO (3.8)

Perform a dilution calculation (Manual method)

A2. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-CVCS6 2.1.37 RO (4.3)

Determine applicable Tech Specs for EFW A3. Equipment Control N/R ANO-2-JPM-NRC-ADMIN-EFWTS 2.2.37 RO (3.6)

Determine Condenser Off gas Radiation monitor setting.

A4. Radiation Control N/R ANO-2-JPM-NRC-ADMIN-CRADMON 2.3.15 RO (2.9)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Revision 0

ANO-2-JPM-NRC-ADMIN-SU2LOAD PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 0 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Perform Transferring Unit Auxiliaries from SU3 or Unit Aux to SU2 JTA#: ANO-RO-ELECD-NORM-026 KA VALUE RO: 3.8 SRO: 4.0 KA

REFERENCE:

2.1.32 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

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

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT CLASSROOM:

SITE:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2107.001 Attachment P EXAMINEE'S NAME: Badge #

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-ADMIN-SU2LOAD PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:

Mode 4; 250 EFPD. All ESF systems are in normal alignment.

Startup Transformer #3 is supplying all AC electrical busses.

Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.

2H2 loading is 4MVA, 2H1 loading is 5 MVA Data from Feeder breaker 2A112: Vab = 4082VAC; Vbc=4050VAC; Vca=4102VAC Data from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps; Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc=4050VAC; Vca=4102VAC Data from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps; TASK STANDARD: Calculate Startup #2 loading to be 22.57 MVA (21.1 MVA to 23 MVA is acceptable) and determine that Startup #2 limits for forced oil and forced air cooling will be exceeded.

TASK PERFORMANCE AIDS: OP 2107.001 limits and precautions, step 11.8, and Attachment P.

SIMULATOR SETUP: N/A.

ANO-2-JPM-NRC-ADMIN-SU2LOAD PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS/SM directs, Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001 Step 11.8.5, Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Calculated average Voltage on Calculated average voltage on 2A1 N/A SAT UNSAT 2A1. to be 4.078 KV (between 4.05 KV and 4.10 KV).

2. Calculate current on 2A1. Calculated average current on 2A1 N/A SAT UNSAT to be 1716.67 amps (between 1712 amps and 1720 amps).

3. Calculated 2A1 loading Calculated loading on 2A1 to be N/A SAT UNSAT 12.11 MVA (from 12 MVA to 13 MVA is acceptable)

4. Calculated average Voltage on Calculated average voltage on 2A2 N/A SAT UNSAT 2A2. to be 4.078 KV (between 4.05 KV and 4.10 KV).

5. Calculate current on 2A2. Calculated current on 2A2 to be N/A SAT UNSAT 1482.67 amps (between 1478 amps and 1486 amps.

6. Calculated 2A2 loading Calculated loading on 2A2 to be N/A SAT UNSAT 10.46 MVA (from 10 MVA to 11 MVA is acceptable)

(C) 7. Total 4160 AC loading. Calculated total 4160 AC loading to N/A SAT UNSAT be 22.57 MVA (21.1 MVA to 23 MVA is acceptable).

(C) 8. Compare calculated loading to Determine that limits for SU#2 N/A SAT UNSAT limit and precaution step 5.1.7. loading with Forced oil and air cooling will be exceeded.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-SU2LOAD PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS Mode 4; 250 EFPD. All ESF systems are in normal alignment.

Startup Transformer #3 is supplying all AC electrical busses.

Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.

2H2 loading is 4MVA, 2H1 loading is 5 MVA Data from Feeder breaker 2A112: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps Initiating CUE:

The CRS/SM directs, Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001 Step 11.8.5, Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P.

ANO-2-JPM-NRC-ADMIN-SU2LOAD PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS Mode 4; 250 EFPD. All ESF systems are in normal alignment.

Startup Transformer #3 is supplying all AC electrical busses.

Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.

2H2 loading is 4MVA, 2H1 loading is 5 MVA Data from Feeder breaker 2A112: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps Initiating CUE:

The CRS/SM directs, Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001 Step 11.8.5, Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P.

ANO-2-JPM-NRC-ADMIN-CVCS6 PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 02 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Perform a dilution calculation (Manual Method)

JTA#: ANO2-RO-CHADD-NORM-3 KA VALUE RO: 4.3 SRO: 4.6 KA

REFERENCE:

2.1.37 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

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

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 minutes REFERENCE(S): OP 2103.004 Attachment A.3 & C , OP 2102.016 EXAMINEE'S NAME: Badge #:

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-ADMIN-CVCS6 PAGE 2 OF 5 JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS: OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value. Mode 3 PZR level = 42%, RCS pressure = 2200 psia, Tave = 545°F, VCT level = 65%,

present boron concentration = 750 ppm, ECB is calculated to be 350 ppm. (handout JPM task initial conditions attachment to examinee)

TASK STANDARD: The amount of water needed to dilute from actual to ECB boron concentration has been calculated using OP 2103.004 Attachment A.3.

TASK PERFORMANCE AIDS: Copy of Plant conditions and OP 2103.004 Attachment A.3and Attachment C.

SIMULATOR INITIAL CONDITIONS: Plant is in hot standby condition.

ANO-2-JPM-NRC-ADMIN-CVCS6 PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution water required to bring RCS boron concentration to the given ECB concentration.

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Recorded data from initial Record the following: N/A SAT UNSAT conditions attachment. - 545°F (Tave)

POSITIVE CUE: - 2200 psia (RCS Press)

Data from initial plant conditions recorded on Attachment A.3. - 42% (PZR Level)

- 65% (VCT Level)

- 750 PPM (initial)

- 350 PPM (final)

(C) 2. Determine RCS mass for 42% Determine RCS mass from OP N/A SAT UNSAT PZR level in attachment C. 2103.004 Attachment C.

481980 lb

(+/- 1%)

(C) 3. Calculated Mass of DI water. Calculate DI water Feed Mass: N/A SAT UNSAT Mf = 481980 ln (750/350)

Mf = 367336.3 lb

(+/- 1%)

(C) 4. Calculate DI water feed volume Calculate DI water feed volume: N/A SAT UNSAT F = 367336.3 (0.1204)

F = 44227.3 gal.

(+/- 1%)

END

ANO-2-JPM-NRC-ADMIN-CVCS6 PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM TASK INITIAL CONDITIONS OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value.

Mode 3 PZR level = 42%

RCS pressure = 2200 psia Tave = 545°F VCT level = 65%

Present RCS boron Concentration = 750 ppm ECB is calculated to be 350 ppm INITIATING CUE:

The CRS directs, Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution water required to bring RCS boron concentration to the given ECB concentration.

ANO-2-JPM-NRC-ADMIN-CVCS6 PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM TASK INITIAL CONDITIONS OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value.

Mode 3 PZR level = 42%

RCS pressure = 2200 psia Tave = 545°F VCT level = 65%

Present RCS boron Concentration = 750 ppm ECB is calculated to be 350 ppm INITIATING CUE:

The CRS directs, Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution water required to bring RCS boron concentration to the given ECB concentration.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 6 of 21 2103.004 SOLUBLE POISON CONCENTRATION CONTROL CHANGE: 010 ATTACHMENT A.3 PAGE 1 OF 1 WORK SHEET FOR MAKEUP IN DILUTE MODE NOTE Changes made affecting the calculation should be coordinated with Computer Support prior to implementation.

The BORON2 program located on the plant computer is the preferred method for performing the calculations in this procedure. Manual calculations include assumptions for simplicity that result in slightly different calculated volumes than those calculated using BORON2 (see Limit and Precaution 5.2) 1.0 Record the following:

RCS Temp. = _______________________°F Pressurizer Level = _______________________%

VCT Level = _______________________________%

Initial RCS Boron Conc.(Cri) = ____________________ppm Final Desired RCS Boron Conc.(CrF) = ______________ppm 2.0 Determine the RC Mass from Attachment C:

Mass of Reactor Coolant (Mr) = _________________lb.

3.0 Calculate the DI Water Feed Mass (Mf):

Cri Mf = Mr ln CrF Mf = (________________) ln (_______________)

( )

Mf = __________________lb.

4.0 Calculate the DI Water Feed Volume (F) that must be fed to change the boron concentration from Cri to CrF:

F = MFVF (7.48)

VF = Specific Volume of Feed @80°F(ft3/lb.)= 0.0161 ft3/lb.

F = (___________________lb.)(0.0161 ft3/lb.) (7.48 gal/ft3)

F = (___________________lb.)(0.1204)

F = ______________gal. DI water Performed By: ______________________________ Time: __________ Date: __________

Supervisor Review: __________________________________________ Date: __________

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 15 of 21 2103.004 SOLUBLE POISON CONCENTRATION CONTROL CHANGE: 010 ATTACHMENT C PAGE 1 OF 2 REACTOR COOLANT MASS TABLE ANO - UNIT 2 MR (MASS OF REACTOR COOLANT AT GIVEN TEMP., LBS.)

PZR PRESSURE 250 psia 250 psia 250 psia 250 psia 1000 psia 2200 psia PZR LEVEL (%) 100 F 140 F 200 F 240 F 300 F 545 F 0 632,303 626,598 614,668 604,785 556,500 462,894 2 633,589 627,885 615,957 606,075 557,617 463,803 4 634,874 629,172 617,246 607,365 558,733 464,711 6 636,160 630,459 618,535 608,656 559,850 465,620 8 637,446 631,746 619,824 609,946 560,966 466,529 10 638,731 633,033 621,113 611,237 562,083 467,438 12 640,017 634,320 622,402 612,527 563,199 468,347 14 641,303 635,607 623,691 613,817 564,315 469,256 16 642,588 636,894 624,980 615,108 565,432 470,165 18 643,874 638,181 626,269 616,398 566,548 471,074 20 645,160 639,468 627,558 617,689 567,665 471,982 22 646,445 640,755 628,847 618,979 568,781 472,891 24 647,731 642,042 630,137 620,270 569,898 473,800 26 649,017 643,329 631,426 621,560 571,014 474,709 28 650,302 644,616 632,715 622,850 572,131 475,618 30 651,588 645,903 634,004 624,141 573,247 476,527 32 652,874 647,190 635,293 625,431 574,364 477,436 34 654,159 648,477 636,582 626,722 575,480 478,345 36 655,445 649,764 637,871 628,012 576,596 479,253 38 656,731 651,051 639,160 629,302 577,713 480,162 40 658,016 652,338 640,449 630,593 578,829 481,071 42 659,302 653,626 641,738 631,883 579,946 481,980 44 660,588 654,913 643,027 633,174 581,062 482,889 46 661,873 656,200 644,316 634,464 582,179 483,798 48 663,159 657,487 645,605 635,754 583,295 484,707

ANO-2-JPM-NRC-ADMIN-EFWTS Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 0 DATE:

SYSTEM/DUTY AREA: Equipment controls TASK: Determine EFW TS applicability.

JTA#: ANO2-RO-EFW-SURV-51 KA VALUE RO: 3.6 SRO: 4.6 KA

REFERENCE:

2.2.37 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

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

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 2106.006, Emergency Feedwater system operation, 2104.036 Emergency Diesel Operations, ANO Unit 2 Tech Specs.

EXAMINEE'S NAME: Badge #:

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-ADMIN-EFWTS Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:

Plant is in Mode 1.

PPS Matrix testing is in progress and all administrative requirements are satisfied including TS entry.

When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing the feeder breaker trips.

The Inside AO reports an oil leak on #2 EDG governor and the oil level is below indicating range.

TASK STANDARD: Determine that TS 3.7.1.2 and TS 3.8.1.1 must be entered.

TASK PERFORMANCE AIDS: OP 2106.006, Emergency Feedwater operations, OP-2104.036 Emergency Diesel operations, Unit 2 Tech Specs.

ANO-2-JPM-NRC-ADMIN-EFWTS Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Determine any additional TS for the given plant conditions.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Review OP 2106.006 Examinee reviewed the attachment D, Emergency Emergency feedwater system Feedwater system operation operation and Tech Specs.

and TS.

N/A SAT UNSAT (C) 2. Using 2104.036 L&P 5.22 Examinee determined that #2 determines #2 EDG EDG is inoperable.

operability.

N/A SAT UNSAT (C) 3. Using attachment D of Examinee determined that 2106.006 determines green green train EFW is not train EFW operability. operable because 2CV-1037-1 is closed in Mode 1.

N/A SAT UNSAT (C) 4. Determine applicable required Determined the following TS actions IAW TS. actions must be entered:

TS 3.8.1.1 is applicable.

TS 3.7.1.2 is applicable.

Examiner note: The examinee may mention TS 3.4.4 for proportional heater and TS 3.6.3.1 for containment isolation but are not required.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-EFWTS Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Plant is in Mode 1.

PPS Matrix testing is in progress and all administrative requirements are satisfied including PPS TS entry.

When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing the feeder breaker trips.

The Inside AO reports an oil leak on #2 EDG governor and the oil level is below indicating range.

INITIATING CUE:

Determine TS applicability for the given plant conditions using 2106.006 Emergency Feedwater operations, 2104.036 Emergency Diesel operations, and Unit 2 Tech Specs.

Do not include PPS Tech Specs.

Applicable Tech Specs: ______TS 3.7.1.2 and TS 3.8.1.1 _______________

ANO-2-JPM-NRC-ADMIN-EFWTS Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Plant is in Mode 1.

PPS Matrix testing is in progress and all administrative requirements are satisfied including PPS TS entry.

When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing the feeder breaker trips.

The Inside AO reports an oil leak on #2 EDG governor and the oil level is below indicating range.

INITIATING CUE:

Determine TS applicability for the given plant conditions using 2106.006 Emergency Feedwater operations, 2104.036 Emergency Diesel operations, and Unit 2 Tech Specs.

Do not include PPS Tech Specs.

Applicable Tech Specs: __________________________________________________

ANO-2-JPM-NRC-ADMIN-CRADMON Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 0 DATE:

SYSTEM/DUTY AREA: Radiation Control TASK: Determine Condenser off gas radiation monitor setting.

JTA#: ANO2-RO-RMS-OFFNORM-13 KA VALUE RO: 2.9 SRO: 3.1 KA

REFERENCE:

2.3.15 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

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

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 2105.016, Radiation Monitoring and Evacuation system.

EXAMINEE'S NAME: Badge #:

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-ADMIN-CRADMON Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:

Unit 2 is in Mode 1.

2K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645 Condenser off gas.

Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.

The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.

TASK STANDARD: Determine the new potentiometer setting for the alarm setpoint of 2RITS-0645 (potentiometer setting: 3.62) and the new voltage setting for 2RR-1057 (1.845)

Secondary Radiation Recorder.

TASK PERFORMANCE AIDS: 2105.016, Radiation Monitoring and Evacuation system, OPS-B2 Log

ANO-2-JPM-NRC-ADMIN-CRADMON Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring and Evacuation System. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer until after the voltage reading is obtained for 2RR-1057.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Determine new high alarm setpoint Examinee reviewed the OPS-B2 and for 2RITS-0645 from CBO Electrical 2105.016 log and determines that and CAMS Log (OPS-B2). the new alarm set point should be Verify setpoint within the following 700 cpm.

limits:

- Minimum high alarm setpoint of 250 cpm

- Smaller of 2 times background or 300 cpm above background N/A SAT UNSAT (C) 2. Determine potentiometer dial setting Examinee determined the new which corresponds to desired high setting for 2RITS-0645 is 3.62 from alarm setpoint from Table 1. the table.

N/A SAT UNSAT (C) 3. Determine voltage setting which Examinee determined the new corresponds to desired high alarm setting for 2RR-1057 is 1.845 from setpoint from Table 2. the table.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-CRADMON Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Unit 2 is in Mode 1.

2K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645 Condenser off gas.

Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.

The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.

INITIATING CUE:

The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring and Evacuation system and OPS-B2 CBO log. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer until after the voltage reading is obtained for 2RR-1057.

2RITS-0645 potentiometer setting: ______3.62_______________________

2RR-1057 voltage setting: _______1.845_______________________

ANO-2-JPM-NRC-ADMIN-CRADMON Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Unit 2 is in Mode 1.

2K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645 Condenser off gas.

Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.

The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.

INITIATING CUE:

The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring and Evacuation system and OPS-B2 log. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer until after the voltage reading is obtained for 2RR-1057.

2RITS-0645 potentiometer setting: ______________________________

2RR-1057 voltage setting: ______________________________

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 01/28/2011 Examination Level: RO SRO X Operating Test Number: 2011-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Review CEA#1 Upper Gripper Coil Temperature Data and determine correct temperature.

A5. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-XTCEA 2.1.23 SRO (4.4)

Review CCW system line up to normal operation.

A6. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-CCWVLVLU 2.1.29 SRO (4.0)

Determine applicable Tech Spec for Control Room Ventilation.

A7. Equipment Control N/R ANO-2-JPM-NRC-ADMIN-CREVSTS 2.2.37 SRO (4.6)

Approve administration of Potassium Iodide.

A8. Radiation Control P/R ANO-2-JPM-NRC-ADMIN-KI 2.3.14 SRO (3.8)

Determine Emergency Action Level for given conditions.

A9. Emergency D/R ANO-2-JPM-NRC-ADMIN-EAL11 Procedures/Plan 2.4.41 SRO (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Revision 0

ANO-2-JPM-NRC-ADMIN-XTCEA PAGE 1of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 01 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Verify and determine CEA#1 Upper Gripper Coil Temperature JTA#: ANO2-RO-CEDM-NORM-10 KA VALUE RO: 4.3 SRO: 4.4 KA

REFERENCE:

2.1.23 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2105.009 EXAMINEE'S NAME: BADGE # :

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-ADMIN-XTCEA PAGE 2of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:

1. Plant is at full power.

2. Both Main Chillers have tripped and cannot be started.

3. I&C is not available to obtain CEDM Coil temperatures.

4. OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.

5. Readings obtained from the CEDM coil using a calibrated DVM are: 1) Upper Gripper coil voltage, Vug = 44V;

2) Upper Gripper Shunt voltage Vshunt = 6.46 mV TASK STANDARD:

Two of the three errors on the completed Exhibit 2 must be identified:

1. 8.46mV was recorded instead of the 6.46mV in step 4.3.1 and 4.23 Amps instead of 3.23 Amps in step 5.2.

2. 10.4 ohms was recorded instead of 9.88 ohms in step 6.3.

3. Temperature of upper gripper coil was recorded as 353.373°F instead of 320.038°F.

NOTE: It is acceptable to correctly calculate and identify the correct values throughout the exhibit instead of identifying errors in calculation execution in given exhibit. Refer to Correct Exhibit 2.

And Correct CEA 01 upper gripper coil temperature of 500.050°F must be calculated.

TASK PERFORMANCE AIDS:

1. OP 2105.009 Exhibit 2 (completed)

2. Calculator.

ANO-2-JPM-NRC-ADMIN-XTCEA PAGE 3of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Verify and identify all errors in the calculation by circling each error and determine the correct temperature.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Review OP 2105.009 Exhibit 2. Review the completed OP N/A SAT UNSAT 2105.009 Exhibit 2.

(C) 2. Specific Errors present on Two of the three errors on the N/A SAT UNSAT Exhibit 2: completed Exhibit 2 must be identified.

1. 8.46mV was recorded instead of the 6.46mV in step 4.3.1 and 4.23 Amps instead of 3.23 Amps in step 5.2.

2. 10.4 ohms was recorded instead of 9.88 ohms in step 6.3. (0.525 should have been subtracted from 10.4.).

3. Temperature of upper gripper coil was recorded as 353.373°F (value for 10.9 ohms) instead of 320.038°F (value for 10.4 ohms).

It is acceptable to correctly calculate and identify the correct values throughout the exhibit instead of identifying errors in calculation execution in given exhibit. Refer to Correct Exhibit 2.

(C) 3. Calculate correct CEA 01 Calculated the correct CEA 01 N/A SAT UNSAT upper gripper coil temperature upper gripper coil temperature to be 506.665°F. as 506.665°F (acceptance criteria is 500.050°F).

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-XTCEA PAGE 4of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

Plant is at full power.

Both Main Chillers have tripped and cannot be started.

I&C is not available to obtain CEDM Coil temperatures.

OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.

Readings obtained from the CEDM coil using a calibrated DVM are:

1) Upper Gripper coil voltage, Vug = 44V

2) Upper Gripper Shunt voltage Vshunt = 6.46 mV INITIATING CUE:

The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Identify all errors in the calculation by circling each error and determine the correct temperature.

ANO-2-JPM-NRC-ADMIN-XTCEA PAGE 5of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

Plant is at full power.

Both Main Chillers have tripped and cannot be started.

I&C is not available to obtain CEDM Coil temperatures.

OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.

Readings obtained from the CEDM coil using a calibrated DVM are:

1) Upper Gripper coil voltage, Vug = 44V

2) Upper Gripper Shunt voltage Vshunt = 6.46 mV INITIATING CUE:

The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Identify all errors in the calculation by circling each error and determine the correct temperature.

ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 1 of 7 Administrative JOB PERFORMANCE MEASURE Unit 2 REV #: 003 DATE:

SYSTEM/DUTY AREA: Conduct of Operation TASK: Review a system lineup to restore the Component Cooling Water system to normal operation following completion of maintenance.

JTA#: ANO-SRO-ADMIN-NORM-260 KA VALUE RO: 4.1 SRO: 4.0 KA

REFERENCE:

2.1.29 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: CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE (S): OP-1015.001, PID for Component Cooling Water System M-2234 sheet 1 & 2 EXAMINEE'S NAME: Badge #:

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-ADMIN-CCWVLVLU Page 2 of 7 Administrative JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS: Component cooling water loop are cross connected.

The CCW system danger tags have been removed following maintenance. The shift manager has directed a partial valve lineup to be performed on the affected parts of the system.

TASK STANDARD: Examinees should identify 5 of the 6 errors on the partial valve line up sheet:

2CV-5217 Loop I CCW Surge Tank Vent: Should not be locked closed 2CCW-1023 Surge Tank 2T-37B Drain: wrong position 2CCW-89 Surge Tank 2T-37B Chem. Recirc wrong position 2CV-5210 Condensate Transfer to 2T-37A: valve cycles automatically based on tank level and should be specified as per 1015.001 Att. A.3 2CV-5218 Loop II CCW Surge Tank Vent: Should not be locked closed 2CCW-1022 Surge Tank 2T-37A Drain: wrong position AND Do not sign partial valve line up sheet and return to SM to redo lineup.

TASK PERFORMANCE AIDS: OP-1015.001, OP-2104.028, and PID for Component Cooling Water System M-2234 sheet 1 & 2

ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 3 of 7 Administrative JOB PERFORMANCE MEASURE Initiating Cue: The component cooling water system is being restored to normal system lineup following completion of maintenance on the system. The Shift Manager has instructed you to review the partial system lineup and verify proper restoration.

Start Time: ____________

NOTE: Provide a marked up copy of the system lineup to the examinee PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Perform final SRO review of the Reviews the system lineup paperwork. system lineup paperwork provided.

(C) 2. 2CV-5217 Loop I CCW Surge Tank Vent: SAT UNSAT should not be locked closed 2CCW-1023 Surge Tank 2T-37B Drain:

SAT UNSAT wrong position 2CCW-89 Surge Tank 2T-37B Chem. SAT UNSAT Recirc wrong position Examinee Identifies 5 of the 6 2CV-5210 Condensate Transfer to SAT UNSAT errors and must 2T-37A: Valve cycles automatically based identify the vent on tank level and should be specified as valves per 1015.001 Att. A.3.

2CV-5218 Loop II CCW Surge Tank Vent:

SAT UNSAT should not be locked closed.

2CCW-1022 Surge Tank 2T-37A Drain: SAT UNSAT wrong position (C) 3. Perform the step required for Informs Shift unsatisfactory results Manager of errors. SAT UNSAT Examiner note: The candidates may put the position for the control valves but it is not required per 1015.001 Att. A.3 TERMINATING CUE:

This JPM is complete.

Stop Time: __________

ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 4 of 7 Administrative JOB PERFORMANCE MEASURE EXAMINERS COPY Initial Conditions:

Component cooling water loop are cross connected. The CCW system danger tags have been removed following maintenance. The shift manager has directed a partial valve lineup to be performed on the affected parts of the system.

Initiating Cue:

The component cooling water system is being restored to normal system lineup following completion of maintenance on the system. The Shift Manager has directed you to review the partial system lineup and verify proper restoration.

ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 5 of 7 Administrative JOB PERFORMANCE MEASURE KEY ARKANSAS NUCLEAR ONE E-DOC TITLE: E-DOC NO. CHANGE NO.

PARTIAL SYSTEM LINEUP SHEET 1015.001G 055-00-0 System: Component Cooling Water Page 1 of 1 Reason for partial lineup, e.g. post maintenance test, clearance no., etc. Describe lineup if needed, e.g., list major components, boundaries, or list components excluded, etc.:

Restore system to normal line up following completion of piping repairs.

Partial lineup approval: Bob Shifty 02/02/2011 SRO Signature Date:

Component Description Required Checked SRO (optional) Position Initial Initial*

2CCW-5214 2LT/LG-5214 Root Valve OPEN JR 2CV-5217 Loop I CCW Surge Tank Vent Per 1015.001, Att. A.3 JR 2CCW-1023 Surge Tank 2T-37B Drain OPEN JR 2CCW-89 Surge Tank 2T-37B Chem. Recirc OPEN JR 2CCW-5031 Surge Tanks 2T-37A/B CLOSED JR X-Connect Drain 2CCW-5030 Surge Tanks 2T-37A/B Drain to LRW CLOSED JR 2CT-651 2FI-5210 Inlet Isol OPEN JR 2CT-650 2FI-5210 Outlet Isol OPEN JR 2CT-652 2FI-5210 Bypass CLOSED JR 2CT-653 2FI-5210 Drain CLOSED JR 2CT-16 Surge Tanks 2T-37A/B Makeup Isol OPEN JR 2CV-5210 Condensate Transfer to 2T-37A Per 1015.001, Att. A.3 JR 2CV-5218 Loop II CCW Surge Tank Vent Per 1015.001, Att. A.3 JR 2CCW-5082 Surge Tank 2T-37A Makeup Line Vent CLOSED JR 2CCW-5083 2LT/LG-5210 Root Valve OPEN JR 2CCW-5210 2LT/LG-5210 Root Valve OPEN JR 2CCW-1022 Surge Tank 2T-37A Drain OPEN JR 2CCW-88 Surge Tank 2T-37A Chem. Recirc OPEN JR 2CV-5214 Condensate Transfer Supply to 2T-37B Per 1015.001, Att. A.3 JR 2CCW-5084 Surge Tank 2T-37B Makeup Line Vent CLOSED JR 2CCW-5085 2LT/LG-5214 Root Valve OPEN JR

SRO Initial signifies review.

Lineup Performed By:

Joe Reactor / JR / 02/02/2011 Signature Initial Date NA / NA / NA Signature Initial Date SRO Review: Date

ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 6 of 7 Administrative JOB PERFORMANCE MEASURE EXAMINEES COPY Initial Conditions:

Component cooling water loop are cross connected. The CCW system danger tags have been removed following maintenance. The shift manager has directed a partial valve lineup to be performed on the affected parts of the system.

Initiating Cue:

The component cooling water system is being restored to normal system lineup following completion of maintenance on the system. The Shift Manager has directed you to review the partial system lineup and verify proper restoration.

ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 7 of 7 Administrative JOB PERFORMANCE MEASURE ARKANSAS NUCLEAR ONE E-DOC TITLE: E-DOC NO. CHANGE NO.

PARTIAL SYSTEM LINEUP SHEET 1015.001G 055-00-0 System: Component Cooling Water Page 1 of 1 Reason for partial lineup, e.g. post maintenance test, clearance no., etc. Describe lineup if needed, e.g., list major components, boundaries, or list components excluded, etc.:

Restore system to normal line up following completion of piping repairs.

Partial lineup approval: Bob Shifty 02/02/2011 SRO Signature Date:

Component Description Required Checked SRO (optional) Position Initial Initial*

2CCW-5214 2LT/LG-5214 Root Valve OPEN JR 2CV-5217 Loop I CCW Surge Tank Vent Per 1015.001, Att. A.3 JR LOCKED CLOSED 2CCW-1023 Surge Tank 2T-37B Drain CLOSED JR 2CCW-89 Surge Tank 2T-37B Chem. Recirc CLOSED JR 2CCW-5031 Surge Tanks 2T-37A/B CLOSED JR X-Connect Drain 2CCW-5030 Surge Tanks 2T-37A/B Drain to LRW CLOSED JR 2CT-651 2FI-5210 Inlet Isol OPEN JR 2CT-650 2FI-5210 Outlet Isol OPEN JR 2CT-652 2FI-5210 Bypass CLOSED JR 2CT-653 2FI-5210 Drain CLOSED JR 2CT-16 Surge Tanks 2T-37A/B Makeup Isol OPEN JR 2CV-5210 Condensate Transfer to 2T-37A OPEN JR 2CV-5218 Loop II CCW Surge Tank Vent Per 1015.001, Att. A.3 JR LOCKED CLOSED 2CCW-5082 Surge Tank 2T-37A Makeup Line Vent CLOSED JR 2CCW-5083 2LT/LG-5210 Root Valve OPEN JR 2CCW-5210 2LT/LG-5210 Root Valve OPEN JR 2CCW-1022 Surge Tank 2T-37A Drain CLOSED JR 2CCW-88 Surge Tank 2T-37A Chem. Recirc OPEN JR 2CV-5214 Condensate Transfer Supply to 2T-37B Per 1015.001, Att. A.3 JR 2CCW-5084 Surge Tank 2T-37B Makeup Line Vent CLOSED JR 2CCW-5085 2LT/LG-5214 Root Valve OPEN JR

SRO Initial signifies review.

Lineup Performed By:

Joe Reactor / JR / 02/02/2011 Signature Initial Date NA / NA / NA Signature Initial Date SRO Review: Date

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 0 DATE:

SYSTEM/DUTY AREA: Equipment controls TASK: Determine CREVS TS applicability and any required actions.

JTA#: ANO-SRO-ADMIN-NORM-103 KA VALUE RO: 3.6 SRO: 4.6 KA

REFERENCE:

2.2.37 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 2104.007, Control Room Emergency Ventilation, Unit 2 Tech Specs.

EXAMINEE'S NAME: Badge #:

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-ADMIN-CREVSTS Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:

Unit 1 is in Mode 6 for a refueling outage and currently de-fueled.

Unit 2 is in Mode 1.

Unit 2 is loading a dry fuel cask.

VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55 bus outage.

Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pump failure.

TASK STANDARD: Determined that 3.0.3 is applicable. Determined that TS 3.7.6.1 action j is also applicable requiring immediately suspending handling of irradiated fuel.

TASK PERFORMANCE AIDS: OP 2104.007, Control Room Emergency Ventilation, Unit 2 Tech Specs.

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The CBOT discovers that 2VSF-9 feeder breaker is trip free.

Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.

Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Include any applicable instrumentation TS/TRM and required actions for the given plant conditions.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Review OP 2104.007 Examinee reviewed the control attachment B and C, Control room ventilation procedure Room Emergency Ventilation and Tech Specs.

and TS 3.7.6.1.

N/A SAT UNSAT

2. Using attachment C of Examinee determined that 2104.007 determine that TRM TRM entry is not required for entry is not required for the chlorine monitors that are inoperable chlorine monitors. inoperable.

N/A SAT UNSAT (C) 3. Using TS and 2104.007 Examinee determined that TS determine applicable TS 3.0.3 and TS 3.7.6.1 action j actions. are applicable.

Examiner Note: The candidate may indicate TS 3.7.6.1 action e is applicable, but is not required. TS 3.7.6.1 action e states to apply the action of TS 3.0.3 N/A SAT UNSAT (C) 4. Determine most restrictive Determined the following required action IAW TS. actions:

Immediately suspend handling of irradiated fuel (action J)

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Unit 1 is in Mode 6 for a refueling outage and currently de-fueled.

Unit 2 is in Mode 1.

Unit 2 is loading a dry fuel cask.

VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55 bus outage.

Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pump failure.

INITIATING CUE:

The CBOT discovers that 2VSF-9 feeder breaker is trip free.

Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.

Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Include any applicable instrumentation TS/TRM and required actions for the given plant conditions.

Applicable Tech Specs: 3.7.6.1 action j, and 3.0.3 (directed by 3.7.6.1 action e).

Most restrictive Required Action:

Action j:

With both CREVS inoperable or with one more CREVS inoperable due to an inoperable CRE boundary, immediately suspend all activities involving the handling or irradiated fuel.

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Unit 1 is in Mode 6 for a refueling outage and currently de-fueled.

Unit 2 is in Mode 1.

Unit 2 is loading a dry fuel cask.

VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55 bus outage.

Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pump failure.

INITIATING CUE:

The CBOT discovers that 2VSF-9 feeder breaker is trip free.

Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.

Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Include any applicable instrumentation TS/TRM and required actions for the given plant conditions.

Applicable Tech Specs: __________________________________________________

Most restrictive Required Action:

________________________________________________________________________

ANO-2-JPM-NRC-ADMIN-KI Page 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Radiation Controls TASK: Approve administration of Potassium Iodide.

JTA#: ANO-SRO-EPLAN-EMERG-292 KA VALUE RO: 3.4 SRO: 3.8 KA

REFERENCE:

2.3.14 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): 1903.035, Administration of Potassium Iodide EXAMINEE'S NAME: Badge #:

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-ADMIN-KI Page 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

Data indicates I-131 concentration of 8.0 E-05 ci/cc in area of work in Upper South Piping Penetration room.

Whole body dose rates in area of work are 1Rem/hr.

Site Area Emergency has been declared.

RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.

Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodide if required.

Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.

EOF, OSC and TSC have NOT been staffed.

TASK STANDARD: Determine that KI should be administered.

TASK PERFORMANCE AIDS: OP 1903.0035, Potassium Iodide Administration, completed form 1903.035C, ANO Medical Questionnaire-Iodine Sensitivity and 1903.035A, Potassium Iodide Administration.

ANO-2-JPM-NRC-ADMIN-KI Page 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE: Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.

START TIME:

Examiner Note: Provide the examinee a blank KI Administration Form 1903.035A and a Medical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completed by Joe Mechanic PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Review OP 1903.035, Examinee determined the Administration of Potassium criteria for administration of KI Iodide to determine criteria for is 10 REM exposure to thyroid administering KI. committed dose equivalent or if concentration is unknown, the possibility exists for receiving large amounts of radioactive airborne iodine.

N/A SAT UNSAT (C) 2. Using graph on 1903.035 Determined that expected Attachment 1 and information exposure will exceed 10 REM provided in initial conditions, threshold.

determine that Joe Mechanic will exceed 10 REM during the maintenance evolution.

N/A SAT UNSAT

3. Complete form 1903.035A. Completed all areas of form 1903.035A, Potassium Iodide Administration, from initial conditions:

Estimated Thyroid dose commitment.

Date.

Respiratory protection.

Signature of Joe Mechanic that he chooses to receive KI.

ANO-2-JPM-NRC-ADMIN-KI Page 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE Examiner Note: Provide the examinee a blank KI Administration Form 1903.035A and a Medical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completed by Joe Mechanic PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT (C) 4. Determine that Joe Mechanic Reviewed 1903.035C form is not sensitive to nor and determined that Joe experienced an allergic Mechanic was not sensitive to reaction to Iodide. nor experienced an allergic reaction to Iodide.

N/A SAT UNSAT (C) 5. Determine that KI may be Examinee approved approved for distribution to distribution of KI to Joe Joe Mechanic during the Mechanic by signing and Upper South Piping dating form.

penetration work.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-KI Page 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

Data indicates I-131 concentration of 8.0 E-05 ci/cc in area of work in Upper South Piping Penetration room.

Whole body dose rates in area of work are 1Rem/hr.

Site Area Emergency has been declared.

RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.

Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodide if required.

Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.

EOF, OSC and TSC have NOT been staffed.

INITIATING CUE:

Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.

ANO-2-JPM-NRC-ADMIN-KI Page 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

Data indicates I-131 concentration of 8.0 E-05 ci/cc in area of work in Upper South Piping Penetration room.

Whole body dose rates in area of work are 1Rem/hr.

Site Area Emergency has been declared.

RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.

Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodide if required.

Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.

EOF, OSC and TSC have NOT been staffed.

INITIATING CUE:

Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.

Page 14 of 16 Potassium Iodide (KI) Administration Form Name of Exposed Individual: , ,

Last First Middle Badge Number:

Duration of Exposure: I-131 Concentration:

Minutes Ci/cc in air Estimated Thyroid Dose Commitment: 10 Rem 10 Rem Unknown, large exposure possible General Emergency Declared Date of Exposure:

Respiratory Protection Worn During Exposure: Yes No Respirator Protection Factor:

Known Iodide Allergy/Previous Allergic Reaction to iodide: Yes No CAUTION If the above box is checked yes, then DO NOT administer Potassium Iodide.

I verify that I have read and understand the precaution leaflet and I understand that taking thyroid blocking agent (KI) is strictly voluntary.

I choose do not choose to take KI.

Signature of Exposed Individual Date Approved:

Shift Manager/EOF Director/TSC Director Date Check if approval is via telecom.

KI Issued By:

Signature Date Notes:

FORM TITLE: CHANGE:. REV.

POTASSIUM IODIDE ADMINISTRATION 1903.035A 011

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE 1 of 5 UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Emergency Plan TASK: Determine Emergency Action Level for given conditions. (Time Critical JPM)

JTA#: ANO-SRO-EPLAN-EMERG-278 KA VALUE RO: 2.9 SRO: 4.6 KA

REFERENCE:

2.4.41 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 5 Minutes - Read initial Conditions 15 Minutes - EAL Classification REFERENCE(S): 1903.010 EXAMINEE'S NAME: BADGE

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.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE 2 of 5 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:

Unit 2 has been operating at 100% for 230 consecutive days.

A plant trip has occurred due to a loss of offsite power with a concurrent Loss of Coolant Accident estimated to be 1500 gpm.

4 hours0.167 days 0.0238 weeks 0.00548 months following the trip, High Range containment radiation monitors read 74450 R/hr and 77730 R/hr respectively.

RCS average Core Exit Thermocouples are reading 430°F PZR pressure is 325 psia Containment Pressure is 20 psia and slowly trending down RDACs indicates NO offsite release in progress All safety systems are responding as designed TASK STANDARD: Determine the following ( Time Critical - 5 minutes to read initial conditions/ 15 minutes to classify event):

1. Determine containment radiation is at GE level

2. Determine EAL classification GE, 1.5, Containment Radiation readings which indicate LOCA and >50% fuel overheat TASK PERFORMANCE AIDS: 1903.010, Emergency Action Levels

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE 3 of 5 INITIATING CUE:

Determine the highest EAL classification from the given initial conditions (list EAL classification event number).

.

START:

PERFORMANCE STANDARD (Circle One)

CHECKLIST N/A SAT UNSAT

1. Determined containment Using OP 1903.010 Attachment radiation readings are not 6, verified power history does not modified due to power require modifying containment history. radiation readings.

N/A SAT UNSAT (C) 2. Determined containment Using OP 1903.010 Attachment radiation is GE level 6, determined containment radiation readings the GE criteria.

(critical element verified by classifying EAL as event 1.5)

3. Determined GE EAL Using OP 1903.010, determined N/A SAT UNSAT (C) classification. GE EAL classification 1.5, Containment Radiation readings which indicate LOCA and >50%

fuel overheat (C) 4. JPM complete in 15 JPM complete in 15 minutes with N/A SAT UNSAT minutes. 5 minutes to read conditions.

END STOP:

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE 4 of 5 Examiners Copy JPM is TIME CRITICAL JPM INITIAL TASK CONDITIONS:

Unit 2 has been operating at 100% for 230 consecutive days.

A plant trip has occurred due to a loss of offsite power with a concurrent Loss of Coolant Accident estimated to be 1500 gpm.

4 hours0.167 days 0.0238 weeks 0.00548 months following the trip, High Range containment radiation monitors read 74,450 R/hr and 77,730 R/hr respectively and trending up.

RCS average Core Exit Thermocouples are reading 430°F PZR pressure is 325 psia Containment Pressure is 20 psia and slowly trending down RDACs indicates NO offsite release in progress All safety systems are responding as designed INITIATING CUE:

Determine the highest EAL classification from the given initial conditions (list EAL classification event number).

ANSWER:

EAL classification and event number: GE, EAL 1.5, Containment Radiation readings which indicate LOCA and >50% fuel overheat

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE 5 of 5 Examinees Copy JPM is TIME CRITICAL JPM INITIAL TASK CONDITIONS:

Unit 2 has been operating at 100% for 230 consecutive days.

A plant trip has occurred due to a loss of offsite power with a concurrent Loss of Coolant Accident estimated to be 1500 gpm.

4 hours0.167 days 0.0238 weeks 0.00548 months following the trip, High Range containment radiation monitors read 74,450 R/hr and 77,730 R/hr respectively and trending up.

RCS average Core Exit Thermocouples are reading 430°F PZR pressure is 325 psia Containment Pressure is 20 psia and slowly trending down RDACs indicates NO offsite release in progress All safety systems are responding as designed INITIATING CUE:

Determine the highest EAL classification from the given initial conditions (list EAL classification event number).

ANSWER:

EAL classification and event number:

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 01/28/2011 Exam Level: RO X SRO-I SRO-U Operating Test No.: 2011-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-AOP3 3 010 A2.02 RO-3.9/SRO-3.9 A/N/S Pressure Control Isolate failed PZR spray valve S2. ANO-2-JPM-NRC-SIT08 2 006 A1.13 RO-3.5/SRO-3.7 D/EN/S Inventory Control Lower SIT level S3. ANO-2-JPM-NRC-EDG06 6 064 A4.06 RO-3.9/SRO-3.9 D/S Electrical Align 2A-2 to 2A-4 S4. ANO-2-JPM-NRC-CEA02 7 012 A4.06 RO-4.3/SRO-4.3 D/S Instrumentation Test a Reactor Trip Circuit Breaker S5. ANO-2-JPM-NRC-CEA01 1 001 A4.03 RO-4.0/SRO-3.7 D/S Reactivity control Perform a CEA exercise S6. ANO-2-JPM-NRC-CNMT2 5 103 A3.01 RO-3.9/SRO-4.2 Drain the containment sump A/N/S Containment Integrity S7. ANO-2-JPM-NRC-RCP02 4 003 A4.08 RO-3.2/SRO-2.9 A/D/L/S Heat Removal Restore CCW to RCPs S8. ANO-2-JPM-NRC-CCW02 8 008 A4.01 RO-3.3/SRO-3.1 P/S Plant service Shift running CCW pumps systems In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-AACLS 6 064 A4.01 RO-4.0/SRO-4.3 A/P/E/L Electrical Start up AAC diesel generator manually locally during a LOOP P2. ANO-2-JPM-NRC-AUADV 4 041 A4.08 RO-3.0/SRO-3.1 D/E/L Heat Removal Operate SDBCS valves locally P3. ANO-2-JPM-NRC-SFPAW 8 033 A2.03 RO-3.1/SRO-3.5 D/R Plant service Fill SFP from RWT systems

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 01/28/2011 Exam Level: RO SRO-I X SRO-U Operating Test No.: 2011-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-AOP3 3 010 A2.02 RO-3.9/SRO-3.9 A/N/S Pressure Control Isolate failed PZR spray valve S2. ANO-2-JPM-NRC-SIT08 2 006 A1.13 RO-3.5/SRO-3.7 D/EN/S Inventory Control Lower SIT level S3. ANO-2-JPM-NRC-EDG06 6 064 A4.06 RO-3.9/SRO-3.9 D/S Electrical Align 2A-2 to 2A-4 S4. ANO-2-JPM-NRC-CEA02 7 012 A4.06 RO-4.3/SRO-4.3 D/S Instrumentation Test a Reactor Trip Circuit Breaker S5. ANO-2-JPM-NRC-CEA01 1 001 A4.03 RO-4.0/SRO-3.7 D/S Reactivity control Perform a CEA exercise S6. ANO-2-JPM-NRC-CNMT2 5 103 A3.01 RO-3.9/SRO-4.2 Drain the containment sump A/N/S Containment Integrity S7. ANO-2-JPM-NRC-RCP02 4 003 A4.08 RO-3.2/SRO-2.9 A/D/L/S Heat Removal Restore CCW to RCPs S8.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-AACLS 6 064 A4.01 RO-4.0/SRO-4.3 A/P/E/L Electrical Start up AAC diesel generator manually locally during a LOOP P2. ANO-2-JPM-NRC-AUADV 4 041 A4.08 RO-3.0/SRO-3.1 D/E/L Heat Removal Operate SDBCS valves locally P3. ANO-2-JPM-NRC-SFPAW 8 033 A2.03 RO-3.1/SRO-3.5 D/R Plant service Fill SFP from RWT systems

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 01/28/2011 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2011-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-AOP3 3 010 A2.02 RO-3.9/SRO-3.9 A/N/S Pressure Control Isolate failed PZR spray valve S2. ANO-2-JPM-NRC-SIT08 2 006 A1.13 RO-3.5/SRO-3.7 D/EN/S Inventory Control Lower SIT level In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-AACLS 6 064 A4.01 RO-4.0/SRO-4.3 A/P/E/L Electrical Start up AAC diesel generator manually locally during a LOOP P2. ANO-2-JPM-NRC-AUADV 4 041 A4.08 RO-3.0/SRO-3.1 D/E/L Heat Removal Operate SDBCS valves locally P3. ANO-2-JPM-NRC-SFPAW 8 033 A2.03 RO-3.1/SRO-3.5 D/R Plant service Fill SFP from RWT systems

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Revision 0

ANO-2-JPM-NRC-AOP3 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Pressurizer Spray operation TASK: Isolate failed open Pressurizer Spray valve. (Alternate Success Path)

JTA#: ANO2-RO-EOPAOP-OFFNORM-181 KA VALUE RO: 3.9 SRO: 3.9 KA

REFERENCE:

010 A2.02 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 CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 6 Minutes REFERENCE(S): OP-2203.028 PZR System Malfunctions EXAMINEE'S NAME: Badge #:

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 Stop Total Time Time 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-AOP3 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

2CV-4651 PZR spray valve failed open. Mode 1 TASK STANDARD:

Reactor tripped and 2P-32A secured.

TASK PERFORMANCE AIDS:

OP 2203.028 Step 2 SIMULATOR SETUP:

All RCPs running. Mode 1 CV4651 value = 1.

Trigger1: CV4656 value = .9, DO_HS_4656_G = off, & DO_HS_4656_R = off Conditional trigger 1 set gh4g4656.

Have all backup htrs on.

ANO-2-JPM-NRC-AOP3 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions step 2" START TIME:

EXAMINER NOTE: Maintain the simulator in Freeze until the candidate is ready to start.

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. IF ANY PZR Spray valve failed On panel 2C04 placed PZR N/A SAT UNSAT open, spray valve 2HS-4651B in (Step THEN perform the following: manual 2 A)

Placed 2CV-4651 handswitch in A. Place affected PZR Spray closed.

valve in MANUAL and close:

2CV-4651 Observed red and green lights

2CV-4652 flash above handswitch and the red light remains on.

2. IF affected PZR Spray valve On panel 2C04, placed N/A SAT UNSAT did NOT close, THEN perform handswitch for 2CV-4651 in (Step the following: open for 1 sec.

2.B.1)

Observed red light ON above Place associated PZR Spray handswitch valve handswitch to OPEN for 1 second:

2CV-4651

2CV-4652

.

(C) 3. WHEN 5 seconds have On panel 2C04 and 5 sec have N/A SAT UNSAT elapsed, THEN place elapsed, placed handswitch for (Step handswitch in CLOSE until 2CV-4651 in close until lights 2.B.2) flash.

green indicating light flashes.

Observed red and green lights flash above handswitch and the red light remains on.

(C) 4. IF affected PZR Spray valve On panel 2C04, placed 2CV- N/A SAT UNSAT will NOT close, THEN close 4655/2CV-4656 handswitch to (Step 2.B.3) associated energized Block close.

valves:

2CV-4655 Observed 2CV-4656 lights out and PZR pressure lowering.

2CV-4656

ANO-2-JPM-NRC-AOP3 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERS NOTE:

The following is the alternate path portion of this JPM

5. IF associated energized PZR On panel 2C04, observed all N/A SAT UNSAT Spray Block valves will NOT PZR heater on as indicated by (Step 2.B.4.a) close, red lights above the THEN perform the following: handswitches.

a) Verify ALL PZR heaters ON.

(C) 6. IF RCS pressure lowers to When, RCS pressure is N/A SAT UNSAT 2000 psia, observed at 2000 psia or (Step 2.B.4.b.1) THEN perform the following: informed by evaluator RCS is 2000 psia, tripped the reactor.

IF plant in mode 1 or 2, THEN trip Reactor.

EXAMINER CUE:

If desired to speed up JPM then inform examinee that RCS pressure is 2000 psia.

(C) 7. Stop RCP in loop with failed Secured 2P-32A Reactor N/A SAT UNSAT PZR Spray valve. Coolant pump.

(Step 2.B.4.b.2)

END STOP TIME:

ANO-2-JPM-NRC-AOP3 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

Mode 1 2CV-4651 PZR spray valve has failed open during boron equalization.

INITIATING CUE:

The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions starting with step 2".

ANO-2-JPM-NRC-AOP3 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

Mode 1 2CV-4651 PZR spray valve has failed open during boron equalization.

INITIATING CUE:

The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions starting with step 2".

INSTRUCTIONS CONTINGENCY ACTIONS

2. IF ANY PZR Spray valve failed open, THEN perform the following:

A. Place affected PZR Spray valve in MANUAL and close:

2CV-4651

2CV-4652 (Step 2 continued on next page)

PROC NO TITLE REVISION PAGE 2203.028 PZR SYSTEMS MALFUNCTION 010 3 of 10

INSTRUCTIONS CONTINGENCY ACTIONS

2. (continued)

B. IF affected PZR Spray valve did NOT close, THEN perform the following:

1) Place associated PZR Spray valve handswitch to OPEN for 1 second:

2CV-4651

2CV-4652

2) WHEN 5 seconds have elapsed, THEN place handswitch in CLOSE until green indicating light flashes.

3) IF affected PZR Spray valve will NOT close, THEN close associated energized Block valves:

2CV-4655

2CV-4656

2CV-4653

2CV-4654

4) IF associated energized PZR Spray Block valves will NOT close, THEN perform the following:

a) Verify ALL PZR heaters ON.

b) IF RCS pressure lowers to 2000 psia, THEN perform the following:

1. IF plant in mode 1 or 2, THEN trip Reactor.

2. Stop RCP in loop with failed PZR Spray valve.

3. GO TO 2202.001, Standard Post Trip Actions.

PROC NO TITLE REVISION PAGE 2203.028 PZR SYSTEMS MALFUNCTION 010 4 of 10

ANO-2-JPM-NRC-SIT008 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 009 DATE:

SYSTEM/DUTY AREA: Safety Injection System TASK: Lower Safety Injection Tank level (2T2A)

JTA#: ANO2-RO-ECCS-NORM-5 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 CLASSRROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 8 Minutes REFERENCE(S): OP 2104.001 EXAMINEE'S NAME: Badge#:

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-SIT008 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: A SIT needs to be lowered 0.1%.

TASK STANDARD: SIT (2T2A) level has been lowered at least 0.1%.

TASK PERFORMANCE AIDS: OP 2104.001 Section 7.1 SIMULATOR SETUP: 2T2A level is ~85.2% and pressure is 616 psig.

Use the following as necessary to adjust SIT level/pressure on the monitor screen simn2(1) ~775 and SIM301(1) ~ 97700

ANO-2-JPM-NRC-SIT008 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Open SIT Drain to RDT. On panel 2C33, placed N/A SAT UNSAT (2CV-5081) handswitch for SIT Drain to RDT (Step (2CV-5081) to OPEN.

7.1.4)

Observed red light ON green light OFF above handswitch.

EXAMINERS NOTE: The examinee will close 2CV-5081; then open and close 2SV-5000-1; then open 2CV-5081

2. Close SIT Drain to RDT. On panel 2C33, placed N/A SAT UNSAT 2CV-5081) handswitch for SIT Drain to RDT (Step (2CV-5081) to CLOSED.

7.1.5)

Observed green light ON red light OFF above handswitch.

3. Check for RCS back leakage On panel 2C17 checked N/A SAT UNSAT through Check Valve 2PIS-5000 < 650 psig.

(Step 2SI-15A.

7.1.6)

Examiner note: 2PIS-5000 will be less than 650 psig and the rest of step 7.1.6 will be N/A (C) 4. Open SIT (2T2A) Drain Valve. On panel 2C17, placed N/A SAT UNSAT (2SV-5001-1) handswitch for SIT A Drain Step Valve (2SV-5001-1) to OPEN.

7.1.7)

Observed red light ON green light OFF above handswitch.

ANO-2-JPM-NRC-SIT008 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 5. Verify SIT (2T2A) desired Verified SIT (2T2A) level N/A SAT UNSAT level is achieved. between 84.8% and 85.1%.

Step 7.1.8) Observed SIT (2T2A) control board level instrument(s):

- 2LIS-5008 (2C17)

- 2LI-5010 (2C17)

- 2LIS-5009 (2C16)

OR Observed SIT (2T2A) level on PMS, or SPDS computer point/trend display.

(C) 6. Close SIT (2T2A) Drain On panel 2C17, placed N/A SAT UNSAT Valve. handswitch for SIT A Drain Step (2SV-5001-1) Valve (2SV-5001-1) to CLOSE.

7.1.8)

Observed green light ON above handswitch.

END STOP TIME:

ANO-2-JPM-NRC-SIT008 PAGE 5 OF 6 JOB PERFORMANCE MEASURE Examiners Copy JPM INITIAL TASK CONDITIONS:

SIT (2T2A) level needs to be lowered.

INITIATING CUE:

The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."

ANO-2-JPM-NRC-SIT008 PAGE 6 OF 6 JOB PERFORMANCE MEASURE Examinees Copy JPM INITIAL TASK CONDITIONS:

SIT (2T2A) level needs to be lowered.

INITIATING CUE:

The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."

ANO-2-JPM-NRC-EDG06 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 1 DATE:

SYSTEM/DUTY AREA: Emergency Diesel Generator System TASK: Align 2A2 to 2A4 JTA#: ANO2-RO-EDG-NORM-22 KA VALUE RO: 3.9 SRO: 3.9 KA

REFERENCE:

064 A4.06 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 CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP 2104.036 EXAMINEE'S NAME: BADGE#:

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-EDG06 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: 2DG2 has been supplying 2A4 for 4 hours0.167 days 0.0238 weeks 0.00548 months to allow maintenance on 2A409. Maintenance and PMT are complete on 2A409.

TASK STANDARD: 2A409 closed.

TASK PERFORMANCE AIDS: OP 2104.036 Section 14.0. Sync switch.

SIMULATOR SETUP: 2DG2 supplying 2A4. 2A4 isolated from 2A2 with 2A409 open.

ANO-2-JPM-NRC-EDG06 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify SIAS signal cleared. On panel 2C03, operator insert N/A SAT UNSAT (Step panels, observed that SIAS matrix 14.1) trip lamps are lit and/or SIAS annunciators are clear on 2K04 and 2K05 and/or on 2C23 verify that SIAS trip lamps are clear and the matrix trip lights are lit.

(C) 2. Verify 2A2 available to supply On panel 2C10, verified that 2A2 is N/A SAT UNSAT (Step 2A4. energized by observing either:

14.2.1)

The handswitch from Unit Aux to 2A2 has red light ON and Green light OFF.

Observed voltage on 2A2.

3. Verify Neutral Overvolt alarm On 2C33, observed annunciator N/A SAT UNSAT 2K131-3 clear. 2K09 Window J1 alarm, (Step Engine/Gen trouble is clear by 14.2.2) observing that the annunciator window is not lit.

EXAMINER CUE:

or If asked NLO reports Neutral Contact AO and check locally.

Overvolt alarm on 2K131-3 clear.

(C) 4. Place 2A409 synchronize switch to On panel 2C33, inserted N/A SAT UNSAT (Step "ON". synchronize switch handle into 14.2.3) 2A409, 2A4 supply breaker synchronize switch.

Rotated handle clockwise to "ON".

5. Adjust Generator voltage On 2C33, compare incoming and N/A SAT UNSAT (Step (Incoming) using Voltage Running voltages. Verified 14.2.4) Regulator switch (CS 3) as per incoming is ~100 volts higher than BOTH of the following: running on 2C-33.

Verified incoming voltage is higher Generator voltage (Incoming) ~ than running voltage by SPDS 100 volts higher than System indication.

voltage (Running) by 2C-33 indication.

Generator voltage (Incoming) Adjust EDG voltage using Voltage higher than System voltage regulator switch to match voltages.

(Running) by SPDS indication (NA (If required.)

if SPDS indication not available).

ANO-2-JPM-NRC-EDG06 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 6. Adjust frequency to cause On panel 2C33, adjusted frequency N/A SAT UNSAT (Step synchroscope to rotate slowly in to cause synchroscope to rotate 14.2.5) FAST direction using Governor slowly in the FAST direction using Control switch (CS 4). Governor Control Handswitch (CS4) to raise or lower 2DG2 speed. (If required.)

(C) 7. Perform the following to close 2A- On panel 2C33, placed hand on N/A SAT UNSAT (Step 409: 2A409, 2A4 supply breaker 14.2.6) (152-409).

A. WHEN synchroscope approaches the 12 o'clock position, Observed 2DG2 synchroscope THEN close 2A-409 (152-409/CS). rotation.

B. Immediately raise 2DG2 load to Rotated 152-409 handswitch to

~1400 KW to prevent a reverse "CLOSE" when synchroscope power trip using Governor Control passed through 12 o'clock position.

switch (CS 4).

Verified red light for 2A409, 2A4 supply breaker ON.

Raised load by placing Governor Control switch to raise until load is

~1400 KW.

8. Adjust Generator KVARs between On panel 2C33, observed 2DG2 N/A SAT UNSAT (Step 600 KVARs IN and Kilovar meter.

14.2.7) 1800 KVARs OUT using Voltage Regulator switch (CS 3).

(Preferred range is 0 to 100 OUT) Adjusted Voltage Regulator Handswitch as required to maintain 2DG2 Kilovars between 0 and 100 Kilovars OUT.

9. Place 2A409, 2A4 supply breaker On panel 2C33, rotated 2A409, 2A4 N/A SAT UNSAT (Step Synchroscope switch to "OFF". supply breaker Synchroscope Switch 14.2.8) to "OFF".

EXAMINER NOTE:

This JPM may be stopped once 2A-409 synchroscope switch in OFF.

END START TIME:

ANO-2-JPM-NRC-EDG06 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

2DG2 has been supplying 2A4 for 4 hours0.167 days 0.0238 weeks 0.00548 months to allow maintenance on 2A409.

Maintenance and PMT are complete on 2A409.

INITIATING CUE:

The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."

ANO-2-JPM-NRC-EDG06 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

2DG2 has been supplying 2A4 for 4 hours0.167 days 0.0238 weeks 0.00548 months to allow maintenance on 2A409.

Maintenance and PMT are complete on 2A409.

INITIATING CUE:

The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 38 of 266 2104.036 EMERGENCY DIESEL GENERATOR OPERATIONS CHANGE: 075 14.0 MANUAL SHUTDOWN OF 2DG2 NOTE If 2DG2 is run unloaded for greater than ten minutes OR multiple starts performed, the engine should be operated at full load for one hour prior to securing.

14.1 IF SIAS is actuated, THEN reset SIAS per Attachment 13 of 2202.010, Standard Attachments.

14.2 IF 2A4 Supply breaker (2A-409) open, AND necessary to supply 2A4 from offsite power, THEN perform the following:

14.2.1 Verify 2A2 available to supply 2A4.

NOTE Neutral Overvolt (2K131-3) alarm clears when Engine/Gen Trouble (2K09-J1) is cleared.

14.2.2 Verify Neutral Overvolt (2K131-3) alarm clear.

14.2.3 Place 2A-409 Synchronize switch to ON.

14.2.4 Adjust Generator voltage (Incoming) using Voltage Regulator switch (CS 3) as per BOTH of the following:

Generator voltage (Incoming) ~ 100 volts higher than System voltage (Running) by 2C-33 indication.

Generator voltage (Incoming) higher than System voltage (Running) by SPDS indication (NA if SPDS indication not available).

14.2.5 Adjust frequency to cause synchroscope to rotate slowly in FAST direction using Governor Control switch (CS 4).

CAUTION 2DG2 load will lower when 2A-409 is closed because the governor control circuit shifts to DROOP.

14.2.6 Perform the following to close 2A-409:

A. WHEN synchroscope approaches the 12 o'clock position, THEN close 2A-409 (152-409/CS).

B. Immediately raise 2DG2 load to ~1400 KW to prevent a reverse power trip using Governor Control switch (CS 4).

14.2.7 Adjust Generator KVARs between 600 KVARs IN and 1800 KVARs OUT using Voltage Regulator switch. (Preferred range is 0 to 100 OUT) 14.2.8 Place 2A-409 Synchronize switch in OFF.

ANO-2-JPM-NRC-CEA02 PAGE 1 OF 9 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 9 DATE: ______________

SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Test a Reactor Trip Circuit Breaker.

JTA#: ANO2-RO-CEDM-SURV-15 KA VALUE RO: 4.3 SRO: 4.3 KA

REFERENCE:

012 A4.06 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: Perform CLASSROOM: _______

POSITION EVALUATED: RO: SRO: _________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM: ______

TESTING METHOD: SIMULATE: PERFORM: __________

APPROXIMATE COMPLETION TIME IN MINUTES: 15 minutes REFERENCE(S): OP 2105.009 SUPP. 1 EXAMINEE'S NAME: BADGE: _____________________

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-CEA02 PAGE 2 OF 9 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: TCB-02 has been repaired following a component malfunction. The plant is in Mode 1. Supplement 1 Section 1.0 of 2105.009 is completed. An operator is standing by in the CEDM room.

TASK STANDARD: Reactor trip circuit breaker TCB-2 and TCB-6 operated in accordance with OP 2105.009 Supplement 1.

TASK PERFORMANCE AIDS: OP 2105.009 Supplement 1.0 section 2.1 and 2.2. TCB Close Key.

SIMULATOR SETUP: TCB 9 closed. TCB 2 is open. Mode 1

ANO-2-JPM-NRC-CEA02 PAGE 3 OF 9 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1.0 section 2.1 and 2.2. Leave TCB-2 closed. "

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify undervoltage (UV) trip Contacted operator in CEDM N/A SAT UNSAT device position for Reactor Trip room.

Circuit Breakers TCB-2.

(Step 2.1.1) Requested verification of position EXAMINER CUE: of UV trip device armatures for TCB-2.

CEDM Room operator reports UV Trip Device armatures for TCB-2 is in contact with air gap adjusting screw.

2. Obtain CPC Test/TCB close CPC Test/TCB close key (#15) N/A SAT UNSAT key (#15) from SM key locker. obtained from SM key locker.

(Step 2.1.2)

3. On 2C23, place applicable On 2C23, placed applicable N/A SAT UNSAT Reset Actuation Trip Path Reset Actuation Trip Path keylock keylock in UNLK. in UNLK.

(Step 2.1.3)

(C) 4. Close TCB-2 using pushbutton Depress TCB-2 reset push button. N/A SAT UNSAT on 2C23.

(Step On panel 2C23 or panel 2C14, 2.1.4) verified red light ON for TCB-2.

Placed key in LOCK position and removed key.

(C) 5. On 2C23, place applicable Placed key in LOCK position and N/A SAT UNSAT Reset Actuation Trip Path removed key.

(Step keylock in LK.

2.1.5)

ANO-2-JPM-NRC-CEA02 PAGE 4 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

Perform the following to test Shunt Trip:

6. Verify TCB-2 closed per step Verified TCB-2 closed per step N/A SAT UNSAT 2.1 2.1 (Step 2.2)

7. Hold 2HS/TEST switch in UV Contacted operator in CEDM N/A SAT UNSAT Bypass position (for TCB-2). room.

(Step 2.2) EXAMINER CUE: Requested 2HX/TEST switch be CEDM Room operator held in the UV Bypass position.

reports 2HS/TEST switch is in the UV Bypass Position.

(C) 8. Depress Manual Reactor Trip On panel 2C03, depressed push N/A SAT UNSAT push button (2HS-9071-2). button 2HS-9071-2.

(Step 2.2)

9. Verify TCB-2 open. On panel 2C14, verified TCB-2 N/A SAT UNSAT opens.

(Step 2.2)

10. Check 2K12-A10 alarm comes On annunciator panel 2K12, N/A SAT UNSAT in or reflashes. acknowledged that 2K12-A10 (Step actuated.

2.2)

11. Contact CEDM Room operator Contact CEDM Room operator to N/A SAT UNSAT to release 2HS/TEST switch. release 2HS/TEST switch.

(Step 2.2) EXAMINER CUE:

CEDM Room operator reports that 2HS/TEST switch is released EVALUATORS NOTE: The simulator does not model 2K426. When the examinee attempts to open the door to 2C14, give them the cue on the next step.

ANO-2-JPM-NRC-CEA02 PAGE 5 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

12. Verify reflash Unit 2K426 in Preceded to the back of 2C-14 to N/A SAT UNSAT 2C14 reset. reset 2K426 reflash unit.

(Step 2.2)

EXAMINER CUE: 2K426 reflash unit is reset.

13. Verify undervoltage (UV) trip Contacted operator in CEDM N/A SAT UNSAT device position for Reactor Trip room.

Circuit Breakers TCB-2.

(Step 2.1.1) Requested verification of position EXAMINER CUE: of UV trip device armatures for CEDM Room operator TCB-2.

reports UV Trip Device armatures for TCB-2 is in contact with air gap adjusting screw.

(C) 14. Close TCB-2. On panel 2C23, inserted key in N/A SAT UNSAT ESF reset push button keylock.

(Step 2.1) Placed key in UNLOCK position.

Depress TCB-2 reset push button.

On panel 2C23 or panel 2C14, verified red light ON for TCB-2.

Placed key in LOCK position and removed key.

Perform the following to test UV Trip:

15. Verify TCB-2 closed per step Verified TCB-2 closed per step N/A SAT UNSAT 2.1 2.1 (Step 2.2)

ANO-2-JPM-NRC-CEA02 PAGE 6 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

16. Hold 2HS/TEST switch in Contacted operator in CEDM N/A SAT UNSAT Shunt Bypass position (for room.

(Step TCB-2).

2.2)

EXAMINER CUE:

Requested 2HX/TEST switch be CEDM Room operator held in the Shunt Bypass position.

reports 2HS/TEST switch is in the Shunt Bypass Position.

(C) 17. Depress Manual Reactor Trip On panel 2C03, depressed push N/A SAT UNSAT push button (2HS-9071-2). button 2HS-9071-2.

(Step 2.2)

18. Verify TCB-2 opens. On panel 2C14, verified TCB-2 N/A SAT UNSAT opens.

(Step 2.2) Verified by green lights ON for TCB-2.

19. Check 2K12-A10 alarm comes On annunciator panel 2K12, N/A SAT UNSAT in or reflashes. acknowledged that 2K12-A10 (Step actuated.

2.2)

20. Contact CEDM Room operator Contact CEDM Room operator to N/A SAT UNSAT to release 2HS/TEST switch. release 2HS/TEST switch.

(Step 2.2) EXAMINER CUE:

CEDM Room operator reports that 2HS/TEST switch is released EVALUATORS NOTE: The simulator does not model 2K426. When the examinee attempts to open the door to 2C14, give them the cue below.

21. Reset Reflash unit 2K426 in Preceded to the back of 2C-14 to N/A SAT UNSAT 2C14. reset 2K426 reflash unit.

(Step 2.2)

EXAMINER CUE: 2K426 reflash unit is reset.

ANO-2-JPM-NRC-CEA02 PAGE 7 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

22. Verify undervoltage (UV) trip Contacted operator in CEDM N/A SAT UNSAT device position for Reactor Trip room.

Circuit Breakers TCB-2 and (Step TCB-6.

2.2) Requested verification of position of UV trip device armatures for Examiner Cue: TCB-2 and TCB-6.

CEDM Room operator reports UV Trip Device armatures for TCB-2 and TCB-6 are in contact with air gap adjusting screws.

(C) 23. Close TCB-2 and TCB-6. On panel 2C23, inserted key in N/A SAT UNSAT ESF reset push button keylock.

(Step 2.2.1) Placed key in UNLOCK position.

Depress TCB-2 and TCB-6 reset push button.

On panel 2C23 or panel 2C14, verified red light ON for TCB-2 and TCB-6.

Placed key in LOCK position and removed key.

END Stop Time:

ANO-2-JPM-NRC-CEA02 PAGE 8 OF 9 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM TASK INITIAL CONDITIONS TCB-02 has been repaired following a component malfunction.

The plant is in Mode 1.

Supplement 1 Section 1.0 of 2105.009 CEDM control system operations is completed.

An operator is standing by in the CEDM room.

INITIATING CUE:

The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed. "

ANO-2-JPM-NRC-CEA02 PAGE 9 OF 9 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM TASK INITIAL CONDITIONS TCB-02 has been repaired following a component malfunction.

The plant is in Mode 1.

Supplement 1 Section 1.0 of 2105.009 CEDM control system operations is completed.

An operator is standing by in the CEDM room.

INITIATING CUE:

The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed. "

ANO-2-JPM-NRC-CEA01 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 11 DATE:

SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Perform control element assembly exercise.

JTA#: ANO2-RO-CEDM-SURV-13 KA VALUE RO: 4.0 SRO: 3.7 KA

REFERENCE:

001 A4.03 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 CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 12 minutes REFERENCE(S): OP 2105.009 EXAMINEE'S NAME: BADGE #:

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-CEA01 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: 250 EFPD. OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEAs except CEA #46. No T-alt installed on either RSPT.

TASK STANDARD: CEA #46 has been inserted seven (7) steps (5.25 inches) and withdrawn to the programmed insertion limit.

TASK PERFORMANCE AIDS: OP 2105.009 Supplement 2. Complete Table 2 except for CEA 6-46.

SIMULATOR SETUP: CEAs withdrawn to Programmed insertion limit

ANO-2-JPM-NRC-CEA01 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Complete the CEA Exercise Test for CEA #46 using OP 2105.009 Supplement 2, beginning Step 2.5."

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Select position indication for CEA On panel 2C03, CEA #46 displayed N/A SAT UNSAT (Step

46. on all available CEAC module 2.5.3) displays by one of the following methods:

- Standard OM,

- CEA group plot (Group 6 selected)

- CEA values Page 2

- CEA subgroup plot (Group 6 selected)

(C) 2. Verify Group Select switch On panel 2C03, verified group 6 N/A SAT UNSAT selected to group containing selected.

(Step 2.5.4) individual CEA (C) 1. Place the individual CEA On panel 2C03, selected CEA #46. N/A SAT UNSAT (Step selection switches to CEA #46.

2.5.5) Observed the TENS in "4" and the UNITS in "6".

OR Observed CEA #46 individual light ON.

(C) 4. Place the mode select switch to On panel 2C03, placed mode select N/A SAT UNSAT (Step MANUAL INDIVIDUAL. switch to MI.

2.5.6)

Observed MI (MANUAL INDIVIDUAL) light ON.

(C) 5. Verify CEA #46 at upper On insert 2JC-9058, moved CEA 46 N/A SAT UNSAT (Step electrical limit (UEL). to UEL by going to WITHDRAW on 2.5.7) CEA insert until #46 upper electrical limit (UEL) red light on.

Observed UEL red light ON.

ANO-2-JPM-NRC-CEA01 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 2. Verify CEA #46 position within 7 Observed all Group 6 CEA's within N/A SAT UNSAT (Step inches of CEAs 1, 47, 48 and 49 seven (7) inches using CEAC #1, 2.5.2) throughout exercise. CEAC #2, or PMS indications.

Examiner Note:

This step is a continuous action that must be completed while moving CEAs)

(C) 6. Insert CEA #46 seven steps (>5). Inserted CEA seven steps (>5). N/A SAT UNSAT (Step 2.5.8) Observed insertion of 5.0 inches or greater on CEAC's #1 and #2 displays.

(C) 7 Return CEA to UEL. CEA #46 withdrawn to UEL. N/A SAT UNSAT (Step 2.5.9)

(C) 8. Insert CEA #46 to Programmed CEA #46 inserted to programmed N/A SAT UNSAT (Step insertion limit insertion limit (UEL - 2 steps).

2.5.10)

Observed CEA #46 at 148.5 on Pulse counter (149 on CEACs)

9. Record results. Using OP 2105.009 Supplement A N/A SAT UNSAT (Step Table 1, recorded the results of CEA 2.5.11) #46 exercise.

EXAMINER'S NOTE:

The CEDMCS control may be left in any mode of operation.

10. WHEN all required CEA On insert 2JC-9058, selected off N/A SAT UNSAT (Step movements complete, mode of operation.

2.5.12) THEN verify Mode Select switch in OFF.

END StopTime:

ANO-2-JPM-NRC-CEA01 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

260 EFPD.

OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEAs except CEA #46.

No T-alt installed on either RSPT.

Voltage Traces are not required.

INITIATING CUE:

The CRS directs, "Complete the CEA Exercise Test for CEA # 46 using OP 2105.009 Supplement 2, beginning with Step 2.5."

ANO-2-JPM-NRC-CEA01 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

260 EFPD.

OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEAs except CEA #46.

No T-alt installed on either RSPT.

Voltage Traces are not required.

INITIATING CUE:

The CRS directs, "Complete the CEA Exercise Test for CEA # 46 using OP 2105.009 Supplement 2, beginning with Step 2.5."

ANO-2-JPM-NRC-CMNT2 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Containment TASK: Drain the Containment Sump. (Alternate Success Path)

JTA#: ANO2-WCO-LRWBMS-NORM-7 KA VALUE RO: 3.9 SRO: 4.2 KA

REFERENCE:

103 A3.01 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 CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP-2104.014 LRW/BMS operations EXAMINEE'S NAME: Badge #:

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-CMNT2 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

Containment Sump level ~76%

TASK STANDARD:

2CV-2060-1 closed and Aux building sump level did not trend <100%.

TASK PERFORMANCE AIDS:

OP 2104.014 Section 20 SIMULATOR SETUP:

Any mode, Containment Sump level ~76%

CV20612 value = 1, ramp = 8 sec, set on a Conditional trigger set for rw_2061o.

Using the monitor function the containment sump level can be adjusted using the ctmwtr name and setting the value to 25,000.

ANO-2-JPM-NRC-CMNT2 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting with step 20.1.3" START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Open the following valves to On panel 2C17 placed CMNT N/A SAT UNSAT drain CNTMT sump: sump isolation valve handswitch (Step 2HS-2060-1 to OPEN.

20.1.3) Containment Sump Isolation 2CV-2060-1 (2HS-2060-1)

On panel 2C16 placed CMNT Containment Sump Isolation sump isolation valve handswitch 2CV-2061-2 (2HS-2061-2) 2HS-2061-2 to OPEN.

Observed red lights ON above handswitchs

2. Using level indication or On panel 2C14, monitored Aux N/A SAT UNSAT corresponding computer Building sump level (2LIS-2000 (Step points, monitor the following to or 2LIS-2000B), and 2T-20A 20.1.4) (2LIS-2010) waste tank.

prevent overflow:

Aux Building sump (2LIS-2000 OR or 2LIS-2000B)

In service Waste tank: Monitor Aux Building Sump level and 2T-20A waste tank

- 2T-20A (2LIS-2010) level using PMS computer

- 2T-20B (2LIS-2012)

EXAMINERS NOTE:

The following is the alternate path portion of this JPM (C) 3. Cycle 2CV-2061-2 On panel 2C16 placed CMNT N/A SAT UNSAT (2HS-2061-2) as necessary to sump isolation valve handswitch (Step 20.1.5) prevent overflowing Aux 2HS-2061-2 to CLOSE. And Building sump. observed that the valve did not close.

EXAMINER CUE: If Critical to maintain Aux Building candidate report to the CRS sump level <100%.

2CV-2061-2 has failed open, then instruct candidate to take appropriate action.

ANO-2-JPM-NRC-CMNT2 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. WHEN draining complete, On panel 2C17 placed CMNT N/A SAT UNSAT THEN close the following sump isolation valve handswitch (Step 2HS-2060-1 to closed.(Critical) 20.1.6) valves:

Observed 2CV-2060-1 closed by 2CV-2060-1 (2HS-2060-1) the green light ON and red light EXAMINER CUE: If OFF. (Not Critical) candidate report to the CRS Tech entry is required due Maintained Aux Building sump 2CV-2061-2 not closing level <100%. (Critical) acknowledge and report the CRS has entered the appropriate Tech Spec.

END STOP TIME:

ANO-2-JPM-NRC-CMNT2 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

Containment Sump level is ~76%

Steps 20.1.1 and 20.1.2 of 2104.014 LRW/BMS operations are complete INITIATING CUE:

The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting with step 20.1.3".

ANO-2-JPM-NRC-CMNT2 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

Containment Sump level is ~76%

Steps 20.1.1 and 20.1.2 of 2104.014 LRW/BMS operations are complete INITIATING CUE:

The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting with step 20.1.3".

ANO-2-JPM-NRC-RCP02 PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 006 DATE:

SYSTEM/DUTY AREA: Abnormal/Emergency Operations TASK: Restore component cooling water to reactor coolant pumps (Alternate Success Path)

JTA#: ANO2-RO-RCP-OFFNORM-9 KA VALUE RO: 3.2 SRO: 2.9 KA

REFERENCE:

003 A4.08 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 CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): EOP 2202.010 Attachment 21 EXAMINEE'S NAME: BADGE# :

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 Stop Total Time Time 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-RCP02 PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: 2A1 is re-energized from SU#2 following a degraded power situation. 2202.010 ATT. 29 steps up to 1.M.7 have been completed. A CCW pump has been restored to service. SW has been aligned to CCW. 2Y1 and 2Y2 are cross-tied.

TASK STANDARD: Controlled bleed off isolated to VCT and CBO relief valve isolated.

TASK PERFORMANCE AIDS: Copy of EOP 2202.010 Attachment 21 SIMULATOR SETUP: Set up CCW valves per EOP 2202.010 Attachment 29 "STARTUP XFM# 2 USAGE" perform actions through step 1.M.6. Close RCP CCW RETURN valve, 2CV-5255-1, 2CV-5254-2 and 2CV-5236-1. NO SIAS actuation and RCP seal temperatures >180.

Set T4 = ccwrcp (this will trigger T4 when 2CV 5255 red light is energized).

When 2CV 5255-1 is taken to open position, it will trip the breaker T4=DO_HS_5255_R off (override)

T4=DO_HS_5255_G off (override)

T4=CV52551 = 0.0% (component malfunction)

ANO-2-JPM-NRC-RCP02 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify RCP bleed-off to VCT On panel 2C17, verified N/A SAT UNSAT valves open. 2CV-4846-1 red light ON; control (Step switch in OPEN.

2 A)

On panel 2C16 verified 2CV-4847-2 red light ON; control switch in OPEN.

2. Verify RCP Bleed-off Relief On panel 2C09, verified N/A SAT UNSAT Isolation to Quench Tank open. 2CV-4856 red light ON; key-(Step switch in LOCKED OPEN.

2 B)

(C) 3. Determine RCP Seal On panel 2C14 or on PMS N/A SAT UNSAT temperature. computer determined that RCP (Step seal temperatures is > 180ºF

3) EXAMINERS NOTE: RCP and Step 3 is NA.

seal temperature should be >

180ºF and step 3 will be NA.

4. Verify RCP CCW Return valve On panel 2C17, verified N/A SAT UNSAT (2CV-5255-1) CLOSED. 2CV-5255-1 CLOSED.

(Step 4 A) Observed green light ON; red light OFF above handswitch.

(C) 5. Open RCP CCW Supply valve On panel 2C17, placed N/A SAT UNSAT (2CV-5236-1). handswitch for 2CV-5236-1 in (Step OPEN.

4 B)

Observed green light OFF; red light ON.

ANO-2-JPM-NRC-RCP02 PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 6. Open RCP CCW Return valve On panel 2C16, Verified N/A SAT UNSAT (2CV-5254-2). handswitch for 2CV-5254-2 (Step "OPEN".

4 C)

EXAMINER NOTE: If 2A4 is Observed green light OFF; red light ON.

Deenergized, provide the following CUE:

(NOTE: 2A4 may be 2CV-5254-2 is open. deenergized in this set then perform the following:)

Contact WCO for status of 2CV5254-2.

EXAMINERS NOTE:

When 2CV-5255-1 is taken to OPEN, the breaker will trip and cannot be reset. The valve will be bound closed.

(C) 7. Modulate RCP CCW Return On panel 2C17, took handswitch N/A SAT UNSAT valve (2CV-5255-1) OPEN. for 2CV-5255-1 to "OPEN" for (Step one (1) second then released.

4 D) EXAMINER CUE:

If WCO sent to the valve; Observed red and green lights 2CV-5255-1 cannot be OFF.

opened.

EXAMINEE may ask to dispatch If AO sent to the breaker, a NLO to the valve and or 2B53-G4; the breaker for breaker.

2CV-5255-1 cannot be reset.

EXAMINERS NOTE:

The examinee may elect to monitor RCP seal cooldown before making the decision that CCW cannot be restored. This monitoring of RCP seal cooldown may take 10 minutes to validate that 2CV-5255-1 did not open.

The examinee should go to step 5 of Attachment 21.

8. Verify ALL RCPs secured. On panel 2C04, observed N/A SAT UNSAT 2P32A, B, C, and D RCP (Step handswitches in STOP or PTL.

5)

Observed handswitch is green flagged; green light ON and red light OFF.

ANO-2-JPM-NRC-RCP02 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

9. Close 2CV-5254-2. On panel 2C16, placed N/A SAT UNSAT handswitch for 2CV-5254-2 to (Step CLOSE 5 A)

EXAMINER NOTE: If 2A4 is Observed green light ON; red Deenergized, provide the light OFF.

following CUE:

If 2A4 is deenergized then Waste Control Operator perform the following:

reports that 2CV-5254-2 is closed. Direct WCO to manually close 2CV 5254-2.

10. Close 2CV-5236-1. On panel 2C17, placed N/A SAT UNSAT handswitch for 2CV-5236-1 to (Step CLOSE 5 A)

Observed green light ON; red light OFF.

(C) 11. Close RCP bleedoff to VCT On panel 2C17, placed N/A SAT UNSAT valves. handswitch for 2CV-4846-1 to (Step CLOSE.

5 B 1)

On panel 2C16, placed handswitch for 2CV-4847-2 to CLOSE.

For each valve, observed green light ON; red light OFF.

(C) 12. Close RCP bleedoff relief On panel 2C09, placed N/A SAT UNSAT isolation to quench tank valve handswitch for 2CV-4856 to (Step (2CV-4856). CLOSE 5 B 2)

Observed green light ON; red light OFF.

END STOP TIME:

ANO-2-JPM-NRC-RCP02 PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

2A1 is re-energized from SU#2 following a degraded power situation.

2202.010 ATT. 29 steps up to 1.M.7 have been completed.

CCW pumps have been restored.

SW has been aligned to CCW 2Y1 and 2Y2 are cross connected.

INITIATING CUE:

The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."

ANO-2-JPM-NRC-RCP02 PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

2A1 is re-energized from SU#2 following a degraded power situation.

2202.010 ATT. 29 steps up to 1.M.7 have been completed.

CCW pumps have been restored.

SW has been aligned to CCW 2Y1 and 2Y2 are cross connected.

INITIATING CUE:

The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."

ANO-2-JPM-NRC-CCW02 PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 012 DATE:

SYSTEM/DUTY AREA: Component Cooling Water System TASK: Shift Running CCW pumps JTA#: ANO2-RO-CCW-NORM-10 KA VALUE RO: 3.3 SRO: 3.1 KA

REFERENCE:

008 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

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

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 8 Minutes REFERENCE(S): OP-2104.028 Component Cooling Water System Operations EXAMINEE'S NAME: Badge #:

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-CCW02 PAGE 2 OF 5 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

2P-33B running in a normal configuration. Component Cooling water loops are cross tied.

Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.

TASK STANDARD:

2P33A running supplying CCW and 2P33B & 2P-33C in PULL-TO-LOCK.

TASK PERFORMANCE AIDS:

OP 2104.028 Section 18.2.5 SIMULATOR SETUP:

Any power level or mode.

2P-33B CCW pump in service with CCW loops cross tied.

ANO-2-JPM-NRC-CCW02 PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Contact AO to vent 2P-33A. Using telephone or radio, N/A SAT UNSAT contacted AO and directed him (Step EXAMINER CUE: to vent 2P-33A Casing, using 18.2.5 A 2CCW-1001.

& B) AO reports casing vented and 2CCW-1001 closed.

(C) 2. Verify 2P-33C handswitch On panel 2C14, placed 2P-33C N/A SAT UNSAT (2HS-5234) in PTL. handswitch (2HS-5234) in Pull-(Step To-Lock.

18.2.5 C)

(C) 3. Start 2P-33A. On panel 2C14, took 2P-33A N/A SAT UNSAT handswitch (2HS-5225) to (Step 18.2.5 D) START and released EXAMINER CUE: handswitch.

If requested 2P-33A is running satisfactory.

Observed red light ON above handswitch.

(C) 4. Place 2P-33B handswitch On panel 2C14, placed 2P-33B N/A SAT UNSAT (2HS-5228) to PTL. handswitch (2HS-5228) in Pull-(Step 18.2.5 E) To-Lock.

Observed 2K-12 PUMP 2P-33A/B/C LOCKED alarm. (Not Critical)

5. Observe normal flow and On panel 2C14, observed CCW N/A SAT UNSAT discharge pressure. flow between 1000 to 3000 gpm.

(Step 18.2.5 F)

Directed operator to observe EXAMINER CUE: discharge pressure between 100 to 120 psig locally.

Local operator reports discharge pressure 110 psig locally.

END STOP TIME:

ANO-2-JPM-NRC-CCW02 PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

2P-33B is running in a normal configuration.

Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.

INITIATING CUE:

The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

ANO-2-JPM-NRC-CCW02 PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

2P-33B is running in a normal configuration.

Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.

INITIATING CUE:

The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 09 PAGE 1 of 7 SYSTEM/DUTY AREA: Diesel Generator System (Alternate Success Path)

TASK: Start up the AAC diesel generator manually locally during a Loss of Offsite Power JTA # : ANO2-AO-AACDG-OFFNORM-18 KA VALUE RO: 4.0 SRO: 4.3 KA

REFERENCE:

064 A4.01 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: CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 minutes REFERENCE(S) OP 2104.037, Exhibit 1 EXAMINEES NAME: Badge #:

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# ANO-2-JPM-NRC-AACLS REV 09 PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

The following conditions exist:

The reactor has tripped due to a loss of off-site power.

Both emergency diesel generators are tied to their respective buses.

An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.

TASK STANDARD:

This is an alternate success path JPM.

The AAC Diesel has been started and is at 4160 V and 900 rpm with the output breaker (2A-1001) closed.

The 480V bus 2B16 has been powered from the AAC diesel generator.

TASK PERFORMANCE AIDS:

OP 2104.037 Exhibit 1

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 09 PAGE 3 of 7 INITIATING CUE:

The CRS provides the following direction:

Start the AAC Diesel Generator using OP 2104.037 Exhibit 1 and bring the unit up to rated speed and voltage carrying house loads.

START TIME:

EXAMINERS NOTE:

Provide examinee with copy of 2104.037, Exhibit 1 If asked about the conditions of the alarms, tell the examinee that the only alarm in is H-3, GENERATOR CIRCUIT BREAKER OPEN.

If asked if 125 VDC is available, tell them that the indications for bus availability are as seen (assumes no actual maintenance in progress)

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Place Local/Remote switch in On panel 2C-440, placed the N/A SAT UNSAT LOCAL. Local/Remote switch (2HS-(Step 7118) in LOCAL.

1.1)

POSITIVE CUE:

Local/Remote switch indicates LOCAL.

2. Start the AAC Diesel using the On panel 2C-440 turned the N/A SAT UNSAT local start switch. local control switch CW to start (Step (2HS-7117).

1.2)

EXAMINERS NOTE:

Provide the following cue after ~ 35 seconds when the local start switch is taken to START.

EXAMINERS CUE:

There has been NO change in AAC diesel generator frequency or noise level.

Examiners NOTE:

Step 2 requires a transition to the AAC diesel engine room.

3. Open the pre-lube pump On the south side of the engine N/A SAT UNSAT solenoid (2SV-7224) for >10 at the generator end, rotated the (Step seconds. manual operator of 2SV-7224 2.1)

CW to open for >10 seconds.

EXAMINERS CUE:

Air noise is heard.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 09 PAGE 4 of 7 (C) 4. Open EITHER of the air start On the south side of the engine N/A SAT UNSAT solenoid valves: at the generator end, rotated the (Step manual operator of one of the air 2.2) - 2SV-7222 OR start solenoid valves CW to

- 2SV-7223 open.

EXAMINERS CUE: Looked for an increase in engine noise and/or discharge of oil and Engine speed and noise air from the air start motors.

levels are rising.

5. Close the air start solenoid On the south side of the engine N/A SAT UNSAT valve that was opened. at the generator end, rotated the (Step manual operator for the air start 2.3) solenoid valve CCW to close.

6. Close the pre-lube solenoid On the south side of the engine N/A SAT UNSAT (2SV-7224). at the generator end, rotated the (Step manual operator of 2SV-7224 2.3)

CCW to close.

7. Verify the AAC Diesel On panel 2C-440, observed N/A SAT UNSAT Generator is at rated speed generator frequency at 60 Hz (Step and voltage. and voltage at 4160V.

3)

EXAMINERS CUE:

Frequency indicates 60 Hz and voltage indicates 4160V.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 09 PAGE 5 of 7 EXAMINERS NOTE:

When the examinee inspects the condition of 2A-1001, provide the NEGATIVE CUE first to indicate that the breaker has NOT automatically closed. Once the action has been taken to close the breaker, provide the POSITIVE CUE.

(C) 8. Verify the AAC Generator Observed breaker position N/A SAT UNSAT Output Breaker (2A-1001) is indication on the door of 2A-(Step CLOSED 1001.

4.1)

EXAMINERS CUE: Rotated breaker local control switch for 2A-1001 to the The green breaker OPEN CLOSE position.

light is lit.

AND The white breaker spring charging light is lit.

EXAMINERS CUE:

The Red breaker CLOSED light is lit.

TRANSITION NOTE:

Go to the upstairs area of the switchgear room.

9. Verify the London Feed to Observed the mechanical N/A SAT UNSAT MCC 2B161 breaker 2B16-A1 position indicator breaker for (Step is OPEN. 2B16-A1 to show green open 4.2) and the green breaker position indication light is lit.

EXAMINERS CUE:

Green OPEN light is lit on 2B16-A1 and mechanical position indicator showing green open

10. Verify Load Center 2B16 Observed the mechanical N/A SAT UNSAT Supply from the AAC diesel position indicator breaker for (Step (2B16-B1) is CLOSED. 2B16-B1 to show red closed and 4.3) the red breaker position indication light is lit.

EXAMINERS CUE:

Red CLOSED light is lit on 2B16-B1 and mechanical position indicator showing red closed.

END STOP TIME:

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 09 PAGE 6 of 7 Examiners Copy JPM INITIAL TASK CONDITIONS The following conditions exist:

The reactor has tripped due to a loss of off-site power.

Both emergency diesel generators are tied to their respective buses.

An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.

INITIATING CUE:

The CRS provides the following direction:

Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.

Bring the unit up to rated speed and voltage carrying house loads.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 09 PAGE 7 of 7 Examinees Copy JPM INITIAL TASK CONDITIONS The following conditions exist:

The reactor has tripped due to a loss of off-site power.

Both emergency diesel generators are tied to their respective buses.

An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.

INITIATING CUE:

The CRS provides the following direction:

Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.

Bring the unit up to rated speed and voltage carrying house loads.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV REV. 04 PAGE 1 of 6 SYSTEM/DUTY AREA: Steam Dump & Bypass Control TASK: Operate the SDBCS valves locally. (Upstream Atmospheric Dump Valve A)

JTA #: ANO2-AO-SDBCS-OFFNORM-10 KA VALUE RO: 3.0 SRO: 3.1 KA

REFERENCE:

041 A4.08 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: CLASSROOM: _________

POSITION EVALUATED: RO: SRO: _________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM: _______

TESTING METHOD: SIMULATE: PERFORM: _________

APPROXIMATE COMPLETION TIME IN MINUTES: 15 minutes REFERENCE(S): OP 2105.008 EXAMINEES NAME: BADGE#:

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 ANO-2-JPM-NRC-AUADV REV. 04 PAGE 2 of 6 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

The plant is in Mode 3 due to a station blackout.

The MSIVs are closed.

Instrument Air is not available from Unit 1.

2CV-1002 (Isolation MOV for A Upstream Atmospheric Dump Valve) is OPEN 2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.

TASK STANDARD: A Upstream Atmospheric Dump Valve (2CV-1001) has been throttled open to control A SG pressure.

TASK PERFORMANCE AIDS: OP 2105.008 Exhibit 2; flashlight

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV REV. 04 PAGE 3 of 6 INITIATING CUE:

The SM/CRS directs, Take local manual control of the A Upstream Atmospheric Dump Valve 2CV-1001 using OP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERS NOTES:

1. Two flashlights are required for lighting. One for the instructor and one for the student

2. Dump valves are reverse seating. Air is on the bottom of valve and valve is air to close. Therefore when valve strokes downward valve is opening.

3. The positioner is reverse acting. Therefore if the student operates the bleed valve on the outlet of the I/P the dump valve will not open.

(C) 1. Place the handle position selector to At 2CV-1001 actuator, rotated handle N/A SAT UNSAT MAN. position selector switch to MAN.

(Step 4.1) EXAMINERS CUE:

Handle position selector switch in MAN (C) 2. Rotate handwheel clockwise until Locally, rotated 2CV-1001 N/A SAT UNSAT resistance felt. handwheel CW until resistance felt (Step 4.2) EXAMINERS CUE:

Handwheel rotated CW and resistance felt

3. Verify ADV fully closed. Locally verified valve position using N/A SAT UNSAT stem indication.

(Step EXAMINERS CUE:

4.3)

Valve position is as indicated.

(C) 4. Place handle position selector to Locally, rotated handle position N/A SAT UNSAT LOCK selector to LOCK (Step 4.4) EXAMINERS CUE: (Left to center if facing straight on)

Handle position selector in LOCK (C) 5. Isolate instrument air to diaphragm Closed 2IA-287 by rotating hand N/A SAT UNSAT of 2CV-1001 (2IA-287) wheel CW until resistance felt.

(Step 4.5) EXAMINERS CUE:

Resistance felt with CW rotation.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV REV. 04 PAGE 4 of 6 PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERS NOTE:

1. The following step requires that the correct bleed valve is opened and the plug removed. If the plug is not removed the task is not successful.

2. There are three bleed valves. If the I/P output to the positioner bleed valve is operated instead of one of the two listed the task is not successful.

(C) 6. Open applicable local air bleed off At 2CV-1001, opened one of the N/A SAT UNSAT valve for 2CV-1001. following local air bleedoff valves (Step by rotating valve CCW and 4.6 & EXAMINERS CUE: removing the plug from the bleed 4.7) port.

Air bleed observed by feel and /

or sound coming from bleed-off 1. Air supply to the positioner.

port.

2. Positioner output to the operating diaphragm.

EXAMINERS NOTES:

1. Dump valves are reverse seating. Air is on bottom of valve and valve is air to close. Therefore when valve strokes downward valve is opening.

2. The dump valve will fail open rapidly if handle position selector held in the OPER position. The candidate should transition from OPER back to LOCK back to OPER while monitoring Steam Generator Pressure.

3. Step 4.8 - Opening the ADV MOV Isolation, 2CV-1002, was completed as stated in the initial conditions.

(C) 7. Place handle position selector to Placed handle position selector to N/A SAT UNSAT OPER. OPER (Step 4.9) EXAMINERS CUE:

Handle position selector in OPER, the valve is opening and pressure is slowly lowering.

(C) 8. When desired valve position is Placed the handle position selector N/A SAT UNSAT obtained, place handle position to LOCK when the desired valve (Step selector to LOCK. position was obtained.

4.10)

EXAMINERS CUE:

2CV-1001 valve stops movement. S/G pressure is ~

975 psia and stable.

END STOP TIME:

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV REV. 04 PAGE 5 of 6 EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is in Mode 3 due to a station blackout.

The MSIVs are closed.

Instrument Air is not available from Unit 1.

2CV-1002 (Isolation MOV for A Upstream Atmospheric Dump Valve) is OPEN 2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.

INITIATING CUE:

The SM/CRS directs, Take local manual control of the A Upstream Atmospheric Dump Valve 2CV-1001 using OP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV REV. 04 PAGE 6 of 6 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is in Mode 3 due to a station blackout.

The MSIVs are closed.

Instrument Air is not available from Unit 1.

2CV-1002 (Isolation MOV for A Upstream Atmospheric Dump Valve) is OPEN 2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.

INITIATING CUE:

The SM/CRS directs, Take local manual control of the A Upstream Atmospheric Dump Valve 2CV-1001 using OP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW REV 15 PAGE 1 of 7 SYSTEM/DUTY AREA: Spent Fuel Pool Cooling System TASK: Line up to fill the spent fuel pool from the RWT JTA # : ANO2-WCO-SFP-NORM-2 KA VALUE RO: 3.1 SRO: 3.5 KA

REFERENCE:

033 A2.03 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: CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: X PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 minutes REFERENCE(S) OP 2104.006, Section 11.0 EXAMINEES NAME: BADGE#:

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 ANO-2-JPM-NRC-SFPAW REV 15 PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

The following conditions exist:

1. The Plant is shutdown and in Mode 6 with the core off loaded.

2. 2K11-J5, FUEL POOL LEVEL LOW is in alarm.

3. SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated

4. SFP purification is aligned to the RWT

5. An operator is stationed at the SFP to monitor level increase.

6. Cask loading operations are NOT in progress.

TASK STANDARD:

Spent fuel pool level has been raised to 401.5 feet by adding water from the RWT.

TASK PERFORMANCE AIDS:

1. OP 2104.006, Section 11.0

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW REV 15 PAGE 3 of 7 INITIATING CUE: The CRS provides the following direction:

Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 to raise level to 401.5 feet START TIME:

EXAMINERS NOTE:

Provide examinee with OP 2104.006, Section 11.0.

PERFORMANCE CHECKLIST STANDARDS (Circle One)

TRANSITION NOTE:

Go to RAB elevation 335', Spent Fuel Pool Pump area (left of elevator upon exiting).

(C) 1. Secure Spent Fuel Pool Locally rotated 2P66 handswitch N/A SAT UNSAT (Step Purification Pump (2P66). (2HS-5411) to STOP and 11.2) released.

POSITIVE CUE:

Observed green light ON, red Green light ON, red light light OFF.

OFF.

EXAMINER'S NOTE:

IF student misinterprets cue and performs step 11.3 vice 11.4, THEN task will still be accomplished (student will realign purification from SFP to RWT)

(C) 2. Close Purification Loop to Rotated handwheel on 2FP-29 N/A SAT UNSAT (Step RWT (2FP-29). with chain operator CW to 11.4) CLOSE.

POSITIVE CUE:

2FP-29 pointer indicates closed.

.

TRANSITION NOTE:

Go to RAB elevation 354', Spent Fuel Pool Valve Gallery (left of elevator upon exiting).

(C) 3. Open Purification Loop to Fuel Rotated handwheel on 2FP-17 N/A SAT UNSAT (Step Pool Isolation (2FP-17). CCW to OPEN.

11.4)

POSITIVE CUE:

2FP-17 stem out, resistance felt.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW REV 15 PAGE 4 of 7 PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. Verify open Purification Loop Rotated handwheel on 2FP-18 N/A SAT UNSAT (Step to Fuel Pool (2FP-18). CW one turn then CCW to 11.4) fully OPEN.

POSITIVE CUE:

OR 2FP-18 stem out, resistance felt.

At 2FP-18, examined valve position indicators to determine valve OPEN position.

TRANSITION:

Go to RAB elevation 335', Spent Fuel Pool Pump area (left of elevator upon exiting)..

EXAMINERS NOTE:

If radiological conditions do not allow access to the Purification Pump Room, have examinee describe the actions that would be taken.

(C) 5. Close Purification Pump Rotated handwheel on 2FP-10 N/A SAT UNSAT (Step Discharge valve (2FP-10). CW to CLOSE.

11.5)

POSITIVE CUE:

2FP-10 stem in, resistance felt.

6. Verify 2P-66 Interlock Select Visually verified that 2HS-5413 N/A SAT UNSAT (Step Switch (2HS-5413) in is in the left NORMAL position.

11.6) NORMAL POSITIVE CUE:

2HS-5413 is in the NORMAL position.

7. Establish communications with Using plant telephones, radios, N/A SAT UNSAT (Step operator at SFP. or the Gaitronics; contacted 11.7) operator stationed at SFP.

POSITIVE CUE:

Operator acknowledges ready to monitor SFP level.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW REV 15 PAGE 5 of 7 (C) 8. Start Spent Fuel Pool Locally rotated 2P66 handswitch N/A SAT UNSAT (Step Purification Pump (2P66). (2HS-5411) to START and 11.8) released.

POSITIVE CUE:

Observed red light ON, green Red light ON, green light light OFF.

OFF.

EXAMINERS NOTE:

If radiological conditions do not allow access to the Purification Pump Room, have examinee describe the actions that would be taken.

(C) 9. Throttle open discharge valve Locally rotated 2FP-10 CCW as N/A SAT UNSAT (Step 2FP-10. follows:

11.9)

Until noise was heard.

POSITIVE CUES: Observed pump suction and discharge pressure steady Flow noise is heard.

while making small Suction and Discharge adjustments.

pump pressures are Observed P across 2F-4 steady throughout.

(2PDI-5406) and 2T5 (2PDI-2F4 and 2T5 Ps indicate 5407) as indication of flow.

flow. P is within log limits (2PI-Pump P is 75 psid. 5409 minus 2PI-5410).

Suction and Discharge Observed suction pressure pump pressures are and discharge pressure not steady. oscillating.

EXAMINERS NOTE:

Provide the following cue:

Operator at the SFP reports SFP at 401.5 feet.

(C) 10. Stop Spent Fuel Pool Locally placed 2P66 handswitch N/A SAT UNSAT (Step Purification Pump (2P66). (2HS-5411) to STOP and 11.10) released.

POSITIVE CUE:

Observed green light ON, red Green light ON, red light light OFF.

OFF.

END STOP TIME:

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW REV 15 PAGE 6 of 7 Examiners Copy JPM INITIAL TASK CONDITIONS The following conditions exist:

The Plant is shutdown and in Mode 6 with the core off loaded.

2K11-J5, FUEL POOL LEVEL LOW is in alarm.

SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated SFP purification is aligned to the RWT An operator is stationed at the SFP to monitor level increase.

Cask loading operations are NOT in progress.

INITIATING CUE: The CRS provides the following direction:

Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 to raise level to 401.5 feet.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW REV 15 PAGE 7 of 7 Examinees Copy JPM INITIAL TASK CONDITIONS The following conditions exist:

The Plant is shutdown and in Mode 6 with the core off loaded.

2K11-J5, FUEL POOL LEVEL LOW is in alarm.

SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated SFP purification is aligned to the RWT An operator is stationed at the SFP to monitor level increase.

Cask loading operations are NOT in progress.

INITIATING CUE: The CRS provides the following direction:

Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 to raise level to 401.5 feet.

Appendix D Scenario 1 Form ES-D-1 Facility: ANO-2 Scenario No.: 1 (New) Op-Test No.: 2011-1 Examiners: Operators:

Initial Conditions:

100% MOL, All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed. RED Train Maintenance Week.

Turnover:

100% Power 250 EFPD. EOOS indicates Minimal Risk. Gland Seal Steam Pressure Control Valve 2PCV-0231 is jacked closed; manually control seal steam pressure. RED Train Maintenance Week.

Evolution scheduled: Fill the Quench Tank to ~78% IAW 2103.007 Quench Tank and Reactor Drain Tank Operations. Step 7.2.1 of 2103.007 for filling the quench tank is complete.

Event Malf. No. Event Event No. Type* Description 1 N (BOP) Fill the Quench Tank.

N (SRO) 2 CV0242 R (ATC) #1 Main Turbine Generator Control Valve fails Closed.

C (SRO) Tech Spec for SRO.

3 RCSLOCATCA C (ATC) Shutdown required due to 15 gpm Reactor Coolant C (SRO) system leak on A cold leg. Tech Spec for SRO.

4 2C-11 I (BOP) Main Turbine Generator lube oil controller setpoint fails AI_TIC_1602 I (SRO) high.

MTGVIBINC Main Turbine Generator Vibrations increase causing a reactor trip.

5 500LOSE500 M (ALL) Loss of Offsite Power causing natural circulation of the 500LOSE161 RCS.

6 FW2PW5BAFT M(ALL) B Main Feed water line breaks inside containment.

7 416 A308 C (BOP) #1 EDG output breaker fails to automatically close.

C (SRO) 8 CVC2P36LOLVL I (ATC) Backup Charging pumps fail to start on SIAS or Low CVC2P36BSIAS I (SRO) PZR level. (Not credited for Malfunction after EOP entry due to possibly being discovered prior to EOP entry)

CVC2P36CSIAS 9 BS2P35BFAL C (BOP) 2P-35B Spray pump failed to automatically start and BS2P35AFAULT C (SRO) 2P-35A trips upon start.

K06-B01

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total malfunctions. = 8, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 2, EOPs with substantive actions =1, EOP Contingencies = 1, Critical tasks = 3.

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

1) Evaluate individual ability to operate reactor coolant auxiliary equipment.

2) Evaluate individual response to a failure of a Main Turbine Control valve.

3) Evaluate individual response to a small Reactor Coolant system leak.

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

5) Evaluate individual ability to respond to a failed controller.

6) Evaluate individual ability to respond to Degraded Electrical power.

7) Evaluate individual response to a failure of Emergency Diesel Generator output breaker to automatically close.

8) Evaluate individual ability to mitigate an Excess Steam Demand inside containment.

9) Evaluate individual response to a failure of automatic control of Pressurizer level control.

10) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.

SCENARIO #1 NARRATIVE Simulator session begins with the plant at 100% power steady state. Gland Seal Steam Pressure Control Valve, 2PCV-0231 is jacked closed.

When the crew has completed their control room walk down and brief, The BOP will fill the Quench Tank using the reactor makeup water system.

After the BOP has completed filling the Quench Tank to the appropriate level and cued by lead examiner; the #1 MTG control valve will fail closed. The SRO will enter AOP, 2203.024 Loss of Turbine Load. The SRO will direct the ATC to commence normal boration from a Boric Acid Makeup tank to lower reactor power until Tave and Tref are within 2 degrees. The SRO should call work management to investigate failure and may decide to fail #1 CV closed or have the BOP hold the test pushbutton for #1 CV which will maintain the valve closed.

After a five minute delay, a 15 gpm RCS leak will start. The SRO will enter the excess RCS leakage AOP, OP 2203.016. ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2. The SRO will direct the ATC to maintain pressurizer level within 5%

of set point by starting additional charging pumps as needed. The SRO will also direct the ATC to isolate letdown to determine the leak location. After the crew has determined the leak is not in letdown, they will restore letdown and the crew will change the boration method to commence a plant shutdown.

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

After letdown has been restore to service and cued by the lead examiner, the Main Turbine Generator (MTG) lube oil temperature controller setpoint will fail high causing lube oil temperatures to raise. The SRO should refer to the high bearing temperature annunciator corrective action 2K02- B7 (alarm setpoint is 225ºF) and attempt to manually control lube oil temperature. If temperature goes above 230 degrees Fahrenheit, the crew should manually trip the reactor. If temperature does not go about 230 degrees Fahrenheit, then Turbine vibrations will begin to rise requiring a turbine and reactor trip.

The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the Reactor trips a Loss of Offsite Power will occur and a Feedwater line break will start on the feedwater line to B S/G due to a water hammer on the Feedwater line Check valve. The Crew will manually actuate Main Steam Isolation Signal (MSIS) or verify that a Main Steam Isolation signal automatically actuates. The Crew will secure and/or verify that Emergency Feedwater (EFW) is not feeding B Steam generator. The output breaker for #1 EDG will not automatically close and the BOP should close the output breaker. The ATC will notice that the backup charging pumps did not start. The ATC will secure two Reactor Coolant Pumps when RCS pressure goes below 1400 psia.

The Containment Spray pump 2P-35B will fail to automatically start and Containment Spray pump 2P-35A will trip. The BOP will manual start 2P-35B to ensure containment design pressure is not exceeded.

The SRO will diagnose Functional Recovery due to two events in progress (Excess RCS leakage and Excess Steam demand) and enter OP 2202.009, Functional Recovery.

The crew will manually control Reactor Coolant Temperature once the B SG boils dry using the upstream Atmospheric Dump Valve on A SG. The ATC will control RCS pressure using auxiliary spray.

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Appendix D Scenario 1 Form ES-D-2 Simulator Instructions for Scenario 1 Reset simulator to MOL 100% power IC steady state.

Ensure that AACG is secured and annunciators clear.

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

A CCP lead charging pump. C CCP aligned to green train.

2PCV-0231, Gland sealing steam pressure control valve failed closed.

Quench tank level ~72%, 2K10 E4 is in alarm.

T1, T2, T3, T4, & T5 set to false.

T4 = Reactor trip T5 = CSAS-2 Event Malf. No. Value/ Event No. Ramp Description Time 1 Fill the Quench Tank.

2 SV0242 0 #1 Main Turbine Generator Control Valve fails Closed.

Trigger = T1 Tech Spec for SRO.

3 RCSLOCATCA 15 / Shutdown required due to 15 gpm Reactor Coolant system Trigger = T1 Delay 5 leak on A cold leg. Tech Spec for SRO.

min.

4 2C-11 200 Main Turbine Generator lube oil controller setpoint fails AI_TIC_1602 high.

Trigger = T2 MTGVIBINC 25 / Main Turbine Generator Vibrations increase causing a Trigger = T3 reactor trip.

5 min.

5 500LOSE500 True Loss of Offsite Power causing natural circulation of the 500LOSE161 True RCS.

Trigger = T4 6 FW2PW5BAFT 2000/ B Main Feed water line breaks inside containment.

Trigger = T4 10 min.

7 416 A308 NO_AUT #1 EDG output breaker fails to automatically close.

O_CL 8 CVC2P36LOLVL True Backup Charging pumps fail to start on SIAS or Low PZR CVC2P36BSIAS level.

CVC2P36CSIAS 9 BS2P35BFAL True 2P-35B Spray pump failed to automatically start and 2P-BS2P35AFAULT True / del 35A trips upon start.

K06-B01 30 sec.

ON / del.

Trigger = T5 31 sec.

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Appendix D Scenario 1 Form ES-D-2 Simulator Operator CUEs At T=0 Fill the Quench Tank.

Cued by Trigger T1 #1 Main Turbine Generator Control Valve fails Closed. Tech Spec for lead SRO.

examiner Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist in failing #1 Main Turbine Generator Control valve closed.

Cue: When called as Chemistry, report that you will sample the RCS for Iodine at the time requested.

Cued by Trigger T1 Shutdown required due to 15 gpm Reactor Coolant system leak on A lead cold leg. Tech Spec for SRO.

examiner Cue: If requested, then report that seal water pump is running for requested charging pump.

Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.

Cued by Trigger T2 Main Turbine Generator lube oil controller setpoint fails high.

lead examiner Cue: If contacted as the NLO for 2CV-1602 status, then report valve position based on the actual valve position and report flow noise is heard through the valve if it is open.

Cue: When contacted as the NLO, then report that Lube oil flows to bearing are normal but temperature are elevated (report temperatures based on actually simulator temperatures).

Cued by Trigger T3 Main Turbine Generator Vibrations increase.

lead examiner Cued by Trigger T4 Loss of Offsite Power causing natural circulation of the RCS.

lead B Main Feed water line break inside containment.

examiner or reactor trip Backup Charging pumps fail to start on SIAS or Low PZR level.

Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.

Cued by Trigger T5 2P-35B Spray pump failed to automatically start and 2P-35A trips CSAS upon start.

Cue: if requested as WCO, then report that 2P-35B Containment Spray pump post start checks are satisfactory.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 1 Event

Description:

Fill the Quench Tank using 2103.007 Quench Tank and Reactor Drain Tank Ops.

Time Position Applicant's Actions or Behavior BOP 7.2 Raising Quench Tank level ANY 7.2.2 Close Rx Drain Tank Makeup Water Isol (2CV-4693).

BOP 7.2.3 Open Containment Makeup Water Supply (2CV-4690-2).

BOP 7.2.4 Throttle open Quench Tank Supply (2CV-4685).

BOP 7.2.5 WHEN desired level is reached (maximum log level is 87%),

THEN close the following valves:

2CV-4685 2CV-4690-2 BOP 7.2.6 Open Rx Drain Tank Makeup Water Isol (2CV-4693).

Termination criteria: When 2CV-4693 is open or at lead examiners discretion.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3 Event

Description:

1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.

Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.

Tech Spec for SRO.

Time Position Applicant's Actions or Behavior Cued by ANY Report #1 MTG CV is failed Closed.

lead examiner SRO Enter and direct actions of AOP 2203.024, Loss of Turbine Load.

1. Open Placekeeping page.

SRO 2. Notify Control Board Operators to monitor floating steps.

ATC *3. Reduce Reactor power to match TAVE within 2°F of TREF using 2104.003 Exhibit 3, normal boration.

ANY *4. Check RCS pressure 2025 to 2275 psia.

Cue: If asked, report that the MTG #1 CV indicates closed by local verification and If ask, report that the wires for the connector to the servo for # 1 CV are broken off and hanging to the side.

ANY *5. Verify SDBCS maintaining SG pressure at setpoint.

ANY *8. Check RCS TC 542 to 554.7°F using CPC PID 5, 6, 160, or 161.

(not met perform contingencies)

SRO *8. Refer to TS 3.2.6, Reactor Coolant Cold Leg Temperature.

Examiner note: The SRO must enter TS 3.2.6 or if boration has lowered temperature below the limit the SRO must log the TS 3.2.6 as been entered and exited.

Examiner note: The following steps may or may not be completed based on the timing of the Excess RCS leak and implementation of the Excess RCS leakage procedure.

ANY *9. Check ASI within limits as specified in Core Operating Limits Report (COLR).

ANY *10. Check CEA positions as follows:

A. ALL Regulating Group 6 CEAs above 112.5 inches.

B. ALL Regulating Group 1 through 5 CEAs fully withdrawn.

C. ALL Group P CEAs above 135 inches.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3 Event

Description:

1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.

Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.

Tech Spec for SRO.

ANY *11. Check Reactor NOT tripped.

ANY *12. Verify Feedwater Control System restoring SG levels to setpoint.

ANY *13. Check PZR level within 5% of setpoint:

ANY 15. Check Condenser pressure less than 5.3 inches Hg Abs.

ANY 16. Verify ALL required actions have been completed based on power level; refer to 2102.004, Power Operation.

ANY 18. Notify Chemistry to sample RCS for Iodine 2 to 6 Hrs following Reactor power change greater than 15% in 1 Hr, refer to TS 4.4.8, RCS Activity.

Cue: When called as Chemistry, report that you will sample the RCS for Iodine at the time requested.

SRO 19. IF Main Turbine has NOT tripped, THEN perform the following:

Re-establish Turbine control on Load Limit Pot.

Refer to TRM 3.3.4.1, Turbine Overspeed Protection.

IF desired to fail a Turbine Control Valve closed, THEN refer to 2106.009, Turbine Generator Operations.

Examiner note: The SRO may decide to pull up this step to fail a Turbine Control valve closed but it is not required to be performed.

Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist in failing #1 Main Turbine Generator Control valve closed.

If requested, after 5 minutes have the communicator enter the simulator control room and perform as requested by the crew.

Examiner Note: The following Steps are for Event 3 Excess RCS leakage and not all of the above steps from Loss of Turbine load AOP are required to be completed due to the scenario progression.

ANY Report any the following indications:

Containment dew point rising Pressurizer Level lowing.

Letdown flow lowering.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3 Event

Description:

1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.

Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.

Tech Spec for SRO.

SRO Perform the following actions:

Assess Critical parameters.

Determine RCS leak is present and enter Excess RCS Leakage AOP.

SRO Enter and direct the actions of AOP OP-2203.016, Excess RCS Leakage:

1. Open Placekeeping page.

SRO 2. Notify Control Board Operators to monitor floating steps.

ANY *3. Determine RCS leakrate by ANY of the following:

Computer LKRT programs.

Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.

Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.

CNTMT Sump level rate of rise.

Examiner note: The SRO may secure boration to assist in performing an RCS leak rate.

ATC *4. Maintain PZR level within 5% of setpoint by performing the following as necessary:

A. Cycle Charging pumps.

B. Isolate Letdown as follows:

1) Verify at least ONE Letdown Isolation valve closed:

2CV-4820-2

2CV-4821-1

2CV-4823-2 (least preferred)

2) Record Charging Header Data in 2202.010 Attachment 44, Charging Header Data.

Examiner note: The ATC may discover that at least one back up charging pump is not going to start based on PZR level during the excess RCS leak. Typically the SRO will give a more restrictive PZR level band of within 3% of setpoint and the ATC may not determine that the backup charging pumps will not start based on PZR level. See event #8 Revision 0 Page 6 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3 Event

Description:

1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.

Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.

Tech Spec for SRO.

Cue: If requested, then report that seal water pump is running for requested charging pump.

Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.

ATC *5. Check PZR level maintained within 10% of setpoint.

ATC *7. Maintain VCT level 60% to 75%; refer to 2104.003, Chemical Addition.

SRO *10. Refer to 1903.010, Emergency Action Level Classification.

Examiner note: The SRO will direct the SM to refer to EALs.

11. IF location of leak known, THEN perform the applicable following steps (12.A through 12.J):

CNTMT step 12.A SRO If this step entered from step 11, then only perform substep for identified leak path.

12. IF location of leak unknown, THEN locate and isolate leak as follows:

A. Perform the following:

1) IF leakage is within allowable limits of TS 3.4.6.2, THEN, Attempt to locate leak in CNTMT by monitoring CAMS suction points and CNTMT Area Radiation monitors.

Examiner note: 15 gpm is not within the allowable limits of TS 3.4.6.2.

ATC 2) Verify leak NOT in Letdown line inside CNTMT by performing the following:

a) Isolate Letdown by verifying at least ONE Letdown Isolation valve closed:

2CV-4820-2

2CV-4821-1

2CV-4823-2 (least preferred) b) IF RCS leakage NOT stopped, THEN letdown may be restored at discretion of SM using 2104.002, Chemical and Volume Control.

Examiners Note: Isolating Letdown will not isolate the leak and Letdown should be restored to service.

Revision 0 Page 7 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3 Event

Description:

1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.

Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.

Tech Spec for SRO.

SRO *13. Check leakage within allowable limits; refer to TS 3.4.6.2, Reactor Coolant System Leakage.

Examiners Note: SRO must enter Tech Spec 3.4.6.2 action b.

ALL *13. Perform the following:

A. Continue efforts to locate and isolate leak.

B. IF plant shutdown required, THEN perform EITHER of the following using 2102.004, Power Operations:

1) IF leakage greater than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Attachment R, RCS Boration from the RWT or BAMT.

2) IF RCS leakage less than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at Power.

Examiners Note: The ATC should start a shutdown using 2104.003, Chemical Addition, Attachment R. The ATC may already be borating using Exhibit 3 but must change the boration method due to the leakrate value. This does not have to be accomplished prior to moving to the next event.

Termination criteria: When letdown has been isolated and verified the RCS leak is still on going, or Letdown is restored, or at lead examiners discretion.

Revision 0 Page 8 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 4 Event

Description:

Main Turbine Generator lube oil controller setpoint fails high. Main Turbine Generator Vibrations increase.

Time Position Applicant's Actions or Behavior Cued by ANY Determine that Turbine Lube oil temperature is rising.

examiner ANY IF 2K02-B7 TURB BRNG TEMP HI comes in alarm then announce the alarm.

SRO IF 2K02-B7 TURB BRNG TEMP HI comes in alarm then implements actions of the Turbine bearing temp high alarm.

ANY 2.1 Monitor bearing temperatures on 2TRS-0211 and Plant computer.

BOP 2.2 Verify Lube Oil 2E-15A/B Temperature controller (2TIC-1602) set to control temperature at 115°F.

Examiner note: The SRO should direct manual control of 2TIC-1602 Lube Oil temperature controller.

Cue: If contacted as the NLO for 2CV-1602 status, then report valve position based on the actual valve position and report flow noise is heard through the valve if it is open.

SRO 2.4 IF bearing metal temperature reaches 230°F OR Bearing Oil Pressure Low in alarm (2K02-A7),

THEN perform the following:

2.4.1 IF Reactor power greater than SDBCS capacity, THEN trip Reactor.

Examiner Note: Depending on how soon that manual control is taken for turbine lube oil cooling, the crew may have to trip the reactor based on bearing metal temperatures. If they do not have to trip the reactor, then the malfunction for turbine vibrations should be triggered.

ANY Direct NLOs to perform the following:

2.6 Check lube oil flow and temperature at affected bearings.

Cue: If contacted as the NLO, then report that Lube oil flows to bearings are normal but temperatures are elevated (report temperatures based on actual simulator temperatures).

ANY Contact work management to repair 2TIC-1602.

ANY Report Turbine Vibrations trending higher.

SRO The SRO may take conservative action to trip the turbine and reactor if vibrations are noted to be trending higher.

ANY Report Turbine Bearing Vibration Hi alarm BOP Report Turbine Tripped.

SRO Direct Reactor trip due to the turbine trip.

Termination Criteria: 2TIC-1602 in manual and controlling lube oil temperatures, or crew tripped the reactor due to elevated bearing temperatures, or at lead examiner's discretion.

Revision 0 Page 9 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior Cued by ANY Report Reactor Tripped.

examiner SRO Enter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

2. Open Safety Function Tracking page.

ANY Close MSIVs due to LOOP and an unisolated flow path from Main steam to the condenser.

Examiner Note: The SRO will probably pull up the step to close MSIVs from RCS heat removal due to the known flow path.

Reactivity ATC 3. Check Reactivity Control established as follows:

control safety A. Reactor power lowering.

function B. ALL CEAs fully inserted. (The CEAs will be fully inserted and can be verified by CEAC indications)

BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Main Turbine tripped.

B. Generator Output breakers open.

C. Exciter Field breaker open.

D. At least ONE 6900v AC bus energized. (Not met)

E. At least ONE 4160v Non-vital AC bus energized.

Vital Auxiliaries F. BOTH 4160v Vital AC buses energized. (2A-4 Vital bus will safety function be energized but 2A-3 will not be energized until #1 EDG output breaker is closed.)

G. BOTH DGs secured. (Both DGs will be running, Service water will be aligned to #2 EDG and after #1 EDG output breaker is closed service water will be aligned.)

H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 Revision 0 Page 10 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ATC 5. Check RCS Inventory Control established as follows:

A. PZR level:

10 to 80%.

Trending to setpoint. (May not be met due to ESD Event

5 perform contingency if not met)

RCS B. RCS MTS 30°F or greater.

Inventory Control Examiners Note: This may or may not be performed depending on the Safety SRO PZR level trend at the time this safety function is function assessed.

Direct the following as necessary:

A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.

2) Verify PZR Level Control system restoring level to setpoint.

ATC 6. Check RCS Pressure Control:

___

1800 to 2250 psia.

___

Trending to setpoint. (May not be met due to ESD Event #6.

Perform contingency if not met)

SRO Examiners Note: This may or may not be performed depending on the Pressurizer level trend at the time this safety function is assessed.

Direct the following actions as necessary:

RCS 6. Perform as necessary:

Pressure Control C. IF valid CNTMT Spray in progress, Safety THEN verify ALL RCPs tripped. (Should be performed if function spray is actuated.)

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed. (Should be performed if RCPs are secured.)

E. IF RCS pressure lowers to 1650 psia or less, THEN perform the following:

1) Verify SIAS actuated on PPS inserts.

2) GO TO Step 7.

Revision 0 Page 11 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running. (RCPs will be secured due LOOP and CRS should perform the contingency)

Core Heat Removal safety function. SRO If required, direct the contingency for step 7. E ATC A. IF ALL RCPs stopped, THEN perform the following:

1) Verify BOTH PZR Spray valves in MANUAL and closed.

2) GO TO Step 8.

8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

At least ONE SG level 10 to 90%.

FW maintaining SG level. (Should not be met due to MSIS, perform contingency if necessary)

B. Check MFW in RTO. (Should not be met due to MSIS, perform contingency if necessary)

RCS Heat C. Check Feedwater line intact by the following: (Not met but Removal ANY these conditions can not be assessed due to plant Safety Function configuration)

SG level stable or rising.

NO unexplained step changes or erratic FW flow.

NO unexplained step changes or erratic Condensate flow.

D. Check Condensate Pump discharge header pressure < 753 psig.

E. Check SG pressure 950 to 1050 psia. (Not Met, perform Contingency)

F. Check RCS TC 540 to 555°F.

ANY Perform step 8 contingency actions that are applicable:

A. Perform the following:

1) IF SG level lowering, THEN verify EFAS actuated. (To the A S/G only)

Revision 0 Page 12 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ANY B. Verify EITHER of the following:

BOTH MFW pumps tripped.

SG levels controlling at setpoint E. Perform as necessary:

1) IF SG pressure 751 psia or less, THEN perform the following:

a) Verify MSIS actuated on PPS inserts.

RCS Heat b) Maintain RCS post-cooldown conditions as follows:

Removal ANY Maintain RCS pressure within P-T limits with PZR Safety Function heaters and spray using Attachment 27, PZR Spray Operation.

Maintain RCS temperature by steaming intact SG using Upstream ADV or Upstream ADV Isolation MOV.

c) GO TO Step 9.

Revision 0 Page 13 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ANY 9. Check CNTMT parameters:

A. Temperature and Pressure: (Not met due to ESD Event #6.

Perform contingency)

Temperature less than 140°F.

Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured. (Not met, perform contingency)

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:

"CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.

2) RCS leakage alarms:

Containment * "AREA RADIATION HI/LO" annunciator (2K11-B10)

Safety clear.

Function

"PROC LIQUID RADIATION HI/LO" annunciator (2K11-C10) clear.

3) Check the following radiation monitors trend stable:

CNTMT Area

CAMS

Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

2) Secondary Systems Radiation monitors trend stable:

Main Steam lines

SG Sample

Condenser Off Gas Revision 0 Page 14 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ANY Contingency for Containment parameters not being met.

A. Perform the following:

2) IF CNTMT pressure 18.3 psia or greater, THEN verify the following:

CIAS, CCAS, and SIAS actuated on PPS inserts.

At least ONE Emergency Penetration Room Vent Fan running.

CNTMT Cooling fans running in Emergency Mode.

ANY 3) IF CNTMT pressure 23.3 psia or greater, THEN verify the following:

CSAS actuated on PPS inserts.

Spray flow greater than 1875 gpm per header.

ALL RCPs stopped AND BOTH PZR Spray valves in MANUAL and closed.

Examiner note: See Event #9 SRO 10. Notify STA to report to control room.

11. Verify NLOs informed of Reactor trip.

12. Verify Reactor trip announced on Plant page.

13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose Functional Recovery EOP 2202.009.

SRO Enter and implement Functional Recovery EOP 2202.009.

Revision 0 Page 15 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior SRO 2. Record present time:

Time .

SRO

3. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

ANY

4. Check RCS pressure greater than 1400 psia.

ANY If not performed in SPTAs, then perform contingency to secure 2 RCPs

4. Perform the following:

A. IF RCS pressure less than 1400 psia, THEN perform the following:

1) Verify maximum of ONE RCP running in EACH loop.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

Examiner Note:

The SRO should have directed the ATC and BOP actions for maintaining post-cooldown conditions from SPTAs and therefore may not implement the following floating step.

SRO The SRO should pull up the floating step for maintaining post-cooldown conditions if not directed from SPTAs. HR-2 Step 33.

BOP 33. Maintain RCS post-cooldown conditions as follows:

Maintain A. Maintain RCS temperature by steaming intact SG using post- EITHER of the following:

cooldown

Upstream ADV.

conditions

Upstream ADV Isolation MOV.

CRITICAL TASK RCS temperature must be maintained within 40ºF of B Steam Generator Tc when generator boiled dry.

Maintain ATC B. Maintain RCS pressure within P-T limits using PZR heaters and post- 2202.010 Attachment 27, PZR Spray Operation.

cooldown conditions Post steam generator blow down, use attachment 27 to maintain RCS CRITICAL pressure within the Pressure-Temperature limits of 200°F and 30°F TASK Margin to Saturation.

ANY

5. IF SIAS or MSIS actuated, THEN perform the following:

A. Verify at least ONE SW pump running on EACH loop.

ANY B. Check EITHER DG running.

ANY C. Verify running DG SW Outlet valve open:

Revision 0 Page 16 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior

2CV-1503-1

2CV-1504-2 ANY D. Verify SW pump suction aligned to Lake.

ANY E. Check 4160v Non-vital bus 2A1 OR 2A2 energized from offsite power.

ANY F. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.

ANY G. Start SW pumps as needed to maintain SW header pressure.

ANY H. Check SW to CCW restored. (CCW is not restored, perform contingency)

ANY I. Check ACW restored. (ACW is not restored, perform contingency)

BOP I. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

ANY J. Maintain SW header pressure greater than 85 psig.

ANY 6. Notify Chemistry to sample BOTH SGs for activity.

ANY 7. Verify SG Sample valves open.

ANY 8. Check ALL available Hydrogen Analyzers in service; refer to 2104.044, Containment Hydrogen Control Operations - Exhibit 1, Hydrogen Analyzer Auto Start. (perform contingency)

ANY 8. Verify all available Hydrogen Analyzers in service within 70 minutes from start of event.

Record time from Entry Section step 2:

Time ______________

Examiner note: This step may not be performed due to 70 minute allowance for start.

ANY 9. Open Functional Recovery Success Path Tracking page.

SRO 10. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010 Exhibit 9, ESFAS Actuation.

ANY 11. Determine safety function status as follows:

A. Check Reactivity Control satisfied by EITHER of the following:

Revision 0 Page 17 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior

Maximum of ONE CEA NOT fully inserted and Reactor power lowering.

Reactor power less than 10-1% and stable or lowering.

Examiners note: Reactivity will be satisfied.

ANY B. Check Vital DC Auxiliaries satisfied:

1) At least ONE 125v Vital DC bus energized:

2D01-SPDS point E2D01

2D02-SPDS point E2D02

2) At least ONE 120v Vital AC bus energized:

2RS1 - SPDS point E2RS1 or E2RS1RS3

2RS2 - SPDS point E2RS2 or E2RS2RS4

2RS3 - SPDS point E2RS3 or E2RS1RS3

2RS4 - SPDS point E2RS4 or E2RS2RS4 Examiners note: Vital DC will be satisfied.

ANY C. Check Vital AC Auxiliaries satisfied:

1) At least ONE 4160v Vital AC bus (2A3/2A4) energized.

Examiners note: Vital AC will be satisfied.

ANY D. Check RCS Inventory Control satisfied:

1) CVCS maintaining PZR level 10 to 80% [40 to 70%] and level stable or trending to setpoint.

2) RCS MTS 30°F or greater.

3) RVLMS LVL 03 or higher elevation indicates WET.

Examiners note: Inventory Control may not be satisfied due to ESD.

ANY E. Check RCS Pressure Control satisfied:

1) RCS pressure maintained within P-T limits, refer to Attachment 1, P-T Limits.

Examiners note: P-T limits will be satisfied.

Revision 0 Page 18 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ANY F. Check RCS and Core Heat Removal satisfied:

1) At least ONE intact SG available for Heat Removal by EITHER of the following:

Level 10 to 90% [20 to 90%] with FW available.

Level being restored with total FW flow of 485 gpm or greater.

2) IF ANY RCP operating, THEN RCS T less than 10°F and NOT rising.

3) IF ALL RCPs secured, THEN RCS T less than 50°F and NOT rising.

4) RCS TC less than 555°F and NOT rising.

5) RCS MTS 30°F or greater.

6) RVLMS LVL 01 indicates WET.

ANY G. Check CNTMT Isolation satisfied:

1) CNTMT parameters normal:

a) "CNTMT RADIATION HI" annunciator (2K10-A6) clear.

b) NO unexplained rise in CNTMT radiation.

c) CNTMT pressure less than 18.3 psia.

2) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

3) NO unexplained rise in Secondary Systems Radiation monitor trends:

Main Steam lines

SG Sample

Condenser Off Gas Examiners note: CNTMT Isolation will not be satisfied due to ESD.

Revision 0 Page 19 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7 Event

Description:

Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.

Time Position Applicant's Actions or Behavior ANY H. Check CNTMT Temperature and Pressure Control satisfied:

1) CNTMT pressure less than 16 psia.

2) CNTMT temperature less than 140°F.

Examiners note: CNTMT Temperature and Pressure Control will not be satisfied due to ESD.

ANY 12. Locally remove danger tags and close the following breakers.

2B51-E4 LTOP RELIEF ISOL 2CV-4730-1 2B51-K2 LTOP RELIEF ISOL 2CV-4741-1 ANY *13. Check ALL Safety Function acceptance criteria satisfied.

SRO *13. Perform the following:

A. Determine appropriate success paths using Success Path Decision Trees.

B. Initiate success paths for ALL Safety Functions in the following order:

1) Jeopardized.

2) Challenged.

3) Satisfied.

C. IF higher priority Safety Function jeopardized AND lower priority safety function success path in progress, THEN GO TO appropriate success path for highest priority safety function in jeopardy.

D. WHEN success path implemented for EACH Safety Function, THEN RETURN TO Step 14 of Entry procedure.

Examiner Note: The SRO should complete the safety functions in order of hierarchy that are challenged first, and then the satisfied safety functions.

Examiner Note: The SRO may discuss Tech Spec 3.4.1.2 RCS loops and 3.4.9.1 RCS cooldown limits to due the excess steam demand event.

Termination criteria: When post-cooldown conditions have been stabilized and safety functions prioritized or at examiners discretion.

Revision 0 Page 20 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 8 Event

Description:

Backup Charging pump fail to start on SIAS or Low PZR level.

Time Position Applicant's Actions or Behavior ANY Recognize the Backup Charging pumps failed to automatically start.

SRO Direct the ATC to manually start the Backup charging pumps during the ESD event using OP-2202.010 Standard Attachment, Exhibit 9.

ATC Perform the following to start backup charging pumps:

3.0 IF SIAS, THEN verify the following:

Available Charging Pumps in service with proper discharge pressure and flow.

Examiner note: Charging pumps may be secured after the ESD event to maintain PZR level in the desired control band.

Examiner note: The ATC may discover the failure of the backup charging pumps during the Loss of Turbine load AOP, excess RCS leakage AOP, or post reactor trip. The actions should be to start the back up charging pumps IAW with the procedure in use. See Loss of Turbine load and Excess RCS leakage charging steps below.

Examiner note: Loss of Turbine Load AOP steps for charging control ANY *13. Check PZR level within 5% of setpoint:

ATC 13. Perform the following as needed:

Check auto operation of Charging and Letdown.

Take manual control of Charging and Letdown to restore PZR level to within 5% of setpoint.

IF PZR level >67%,

THEN refer to TS 3.4.4 Examiner note: Excess RCS leakage AOP steps for charging control ATC *4. Maintain PZR level within 5% of setpoint by performing the following as necessary:

A. Cycle Charging pumps.

Termination criteria: Charging pumps controlled as needed to maintain pressurizer level within given bands or at examiners discretion.

Revision 0 Page 21 of 22

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 9 Event

Description:

2P-35B Spray pump failed to automatically start and 2P-35A trips upon start.

Time Position Applicant's Actions or Behavior ANY Recognize the 2P-35B has failed to auto start.

ANY Recognize the 2P-35A has tripped after start.

SRO Direct BOP to verify Red Train Containment Spray pump running and CSAS actuated IAW 2202.010 Exhibit 9.

CRITICAL BOP 4.0 IF CSAS, THEN verify the following:

TASK CSS Pump 2P35B in service with proper discharge pressure and flow.

CSS Header Isolation (2CV-5613-1) open.

Examiner Note: 2P-35B should be started prior to containment exceeding the design pressure of 59 psig or 73.7 psia.

Cue: if requested as WCO, then report that 2P-35B Containment Spray pump post start checks are satisfactory.

Termination criteria: 2P-35B Containment Spray Pump running or at examiners discretion.

Revision 0 Page 22 of 22

Appendix D Scenario 2 Form ES-D-1 Facility: ANO-2 Scenario No.: 2 (New) Op-Test No.: 2011-1 Examiners: Operators:

Initial Conditions:

100% MOL; All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed. RED Train Maintenance Week Turnover:

100%. 250 EFPD. EOOS indicates Minimal Risk. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed; manually control seal steam pressure. RED Train Maintenance Week.

Event Malf. No. Event Event No. Type* Description 1 XSI2LT-5637 I (BOP) RWT level transmitter fails low. Tech Spec for SRO.

I (SRO) 2 SW2P4AWND C (BOP) 2P-4A Service water pump high winding temperature C (SRO) causing pump swap.

3 SGATUBE R (ATC) Shutdown required due to 4 gpm steam generator tube N (BOP) leak on A steam generator. Tech Spec for SRO.

N (SRO) 4 CVC2P39B C(ATC) 2P-39B Boric Acid Makeup pump will trip when it is C(SRO) started.

5 SGATUBE M (ALL) A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

6 CEA35STUCK C (ATC) Control Element Assembly #35 remains fully CV48731 C (SRO) withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not CVC4916SIAS automatically open.

7 ESFK401AAF C (BOP) 2CV-5017-1, 2CV-5015-1 Low pressure safety 416A406 C (SRO) injection (LPSI) and High pressure safety injection valves (HPSI) fail to open and the B HPSI pump trips K05-C03 due to motor overload.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total malfunctions. = 7, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 1, EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 3.

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

1) Evaluate individual response to a failure of a Refueling water tank level transmitter.

2) Evaluate individual response to a failure of a Service Water pump motor.

3) Evaluate individual ability to operate safety related equipment.(swap service water pump)

4) Evaluate individual response to a primary to secondary leak.

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

6) Evaluate individual response to a failure of a Boric Acid Makeup pump.

7) Evaluate individual response to a stuck out CEA after a Reactor Trip.

8) Evaluate individual response to failed ESF relays causing multiple high pressure and low pressure injection valve to not automatically reposition.

9) Evaluate individual ability to mitigate a Steam Generator Tube rupture.

10) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.

SCENARIO #2 NARRATIVE Simulator session begins with the plant at 100% power steady state Gland Seal Regulator; 2PCV-0231 is jacked closed.

When the crew has completed their control room walk down and brief, the RWT level transmitter 2LT-5637-2 will fail low. The SRO should enter Tech Specs 3.3.2.1 ESF Actuation system instrumentation and 3.3.3.6 Post accident instrumentation. The BOP will be required to bypass the Plant Protection System channel 2 for RWT level point 18.

When the appropriate Tech specs have been entered and the BOP goes to the back panel to bypass point 18 and cued by lead examiner; the A Service Water Pump (2P-4A) winding temperature will come into alarm. The SRO will use the Annunciator Corrective action and direct swapping service water pumps. The BOP will swap service water pumps by placing 2P-4B Service Water Pump in service supplying loop 1 Service Water.

After the Crew has swapped service water pumps and cued by lead examiner, a primary to secondary leak will start. The SRO will enter the primary to secondary leakage AOP, OP 2203.038.

ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2.

The SRO will direct the NLOs to control secondary contamination using standard attachment 19 and direct the chemists to sample the SGs for activity. The crew will isolate Main steam from A Steam Generator to 2P-7A EFW pump and commence a plant shutdown using boration from Boric Acid Make up tank.

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Appendix D Scenario 2 Form ES-D-1 SCENARIO #2 NARRATIVE (continued)

When the boration is started 2P-39B Boric Acid Makeup pump will trip and the ATC will need to swap boric acid make up pumps. If the ATC attempts to use the gravity feed boration method, it will not work due to the Volume Control tank outlet valve not closing. The SRO may refer to the TRM for boration flow paths.

After the ATC has performed the required power reduction and cued by the lead examiner, the primary to secondary leak value will ramp up to 200 GPM. The Crew will recognize that the leak rate is greater than reactor trip criteria of 44 GPM. The SRO will direct tripping the reactor and actuating Safety Injection Actuation Signal and Containment Cooling Actuation Signal.

The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactor trips one CEA will remain withdrawn which requires emergency boration. The VCT outlet will remain open and emergency borate valve will fail to auto open from SIAS. The ATC will commence emergency boration by opening 2CV-4916-2 emergency borate valve. Two LPSI and HPSI injection valve fail to automatically open. The BOP will open HPSI valves and the crew may determine to open the LPSI even though they are not currently required for plant conditions. The ATC will secure two Reactor coolant Pumps when RCS pressure goes below 1400 psia. The Crew will lower Steam Dump master controller setpoint during SPTAs to aid in maintaining margin to saturation. The BOP will also override Service Water to Component Cooling water to allow RCP operation.

The SRO will diagnose a Steam Generator Tube Rupture event and enter OP 2202.004, Steam Generator Tube Rupture. The ATC will cool down the RCS to less than 535°F using the bypass valves to the condenser. The BOP will override Service Water to Auxiliary Cooling Water. The BOP will isolate the A SG using standard attachment 10 when RCS Thot is less than 535°F.

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Appendix D Scenario 2 Form ES-D-2 Simulator Instructions for Scenario 2 Reset simulator to MOL 100% power IC steady state.

Ensure that AACG is secured and annunciators clear.

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

A CCP lead charging pump. C CCP aligned to green train.

2PCV-0231, Gland Sealing Steam Pressure Control Valve failed closed.

T1, T2, T3, T4, T5 set to false.

T4 = SIAS2 T5 = hf3b4928 ( 2HS-4928 mode select switch in borate)

Event Malf. No. Value/ Event No. Ramp Description Time 1 XSI2LT-5637 0 RWT level transmitter fails low.

Trigger = T1 2 SW2P4AWND True 2P-4A Service water pump high winding temperature Trigger = T2 causing pump swap.

3 SGATUBE 4/ Shutdown required due to 4 gpm steam generator tube Trigger = T3 2 min. leak on A steam generator. Tech Spec for SRO.

4 CVC2P39B True 2P-39B Boric Acid Makeup pump will trip when it is Trigger = T5 started.

5 SGATUBE 200/ A Steam Generator tube leakage ramps up to 200 gpm 5 min. over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

6 CEA35STUCK 0% Control Element Assembly #35 remains fully withdrawn CV48731 1 when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

CVC4916SIAS True 7 ESFK401AAF True 2CV-5017-1, 2CV-5015-1 Low pressure safety injection 416A406 Lck_Op (LPSI) and High pressure safety injection valves (HPSI)

/ Delay fail to open and the B HPSI pump trips due to motor 15 sec overload.

On /

K05-C03 Delay Trigger 4 for B 15 sec HPSI breaker and alarm Revision 0 Page 4 of 31

Appendix D Scenario 2 Form ES-D-2 Simulator Operator CUEs At T=0 Trigger T1 RWT level transmitter fails low.

Cue: When contacted as the WWM, then report that I&C will start planning a work package to repair the failed instrument.

Cued by Trigger T2 2P-4A Service water pump high winding temperature causing pump lead swap.

examiner Cue: If asked, report that the motor for A Service Water Pump is very hot to touch.

Cue: When contacted as NLO, report that intake Door louvers open, Space heaters secured, Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down), Sheet metal plates above SW pump motors removed.

Cue: NLO reports that oil level is between Min and Max mark for 2P-4B service water pump.

Cue: NLO report that SW pump packing leakoff is acceptable, Air/Vacuum Release valve vented pump and is closed, solid stream of pressurized water issuing from the constant vent line.

Cue: If contacted as Chemistry, then respond by telling the control room that you will realign chemical injection to the appropriate pumps.

Cue: When contacted as the WWM, then report that electrical maintenance will investigate the high winding temperature.

Cued by Trigger T3 Shutdown required due to 4 gpm steam generator tube leak on A lead steam generator.

examiner Cue: If contacted as NLO to investigate N-16 monitors locally, report that you do not see any problems with the N-16 monitor but their readings are elevated(give them the CR N-16 readings).

Cue: If contacted as Chemistry, then report you will sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.

Cue: If contacted as the AO, then report you are commencing Standard Attachment 19 control of secondary contamination.

Trigger T5 2P-39B Boric Acid Makeup pump will trip when it is started.

Cue: If contacted as NLO, report the 2P-39B breaker 2B62-B6 breaker is trip free and 2P-39B motor has an acrid odor.

Cued by A Steam Generator tube leakage ramps up to 200 gpm over 5 lead minutes. Manual reactor trip criteria when greater than 44 gpm.

examiner Cue: When contacted as Chemistry, then report you will sample both S/G for activity and Monitor RDACS for off site dose releases.

Cue: If contacted as the AO, then report after 5 min that the local portions of Attachment 10 for A S/G are complete.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

SIAS2 Trigger T4 2CV-5017-1, 2CV-5015-1 Low pressure safety injection (LPSI) and High pressure safety injection valves (HPSI) fail to open and the B HPSI pump trips due to motor overload.

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Appendix D Scenario 2 Form ES-D-2 Cue: If asked, report that the motor for B High Pressure Injection pump is hot to touch, but no fire or smoke is evident.

Cue: If asked, report that the over current drop flags for B High Pressure Injection pump are dropped.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 1 Event

Description:

RWT level transmitter fails low. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciators:

lead 2K04-A4 CH B RPS/ESF/PRETRIP/TRIP examiner 2K04-B3 PPS Channel TRIP 2K06-A9 RWT level Lo Lo RAS pretrip.

ANY Report RAS pretrip/trip on PPS insert.

Also, report channel 2 RWT level reading 0.

BOP Compare all four channels and report 2LT-5637-2 indicates zero.

Cue: If contacted as the WCO, report that 2LT-5637-2 is not leaking and there are no local indications of a problem.

SRO Implement Annunciator Corrective Action 2203.012D.

2K04-A5 CH B RPS/ESF/PRETRIP/TRIP applicable actions:

2.1 Refer to PPS insert on 2C03 to determine cause.

2.2 Compare all Channels to validate alarm.

2.6 IF channel failed, THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6, and TRM 3.3.1.1.

2K04-B3 PPS Channel TRIP applicable actions:

2.1 Determine which RPS or ESFAS trips have occurred on PPS inserts.

2.3 IF channel failed, THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM 3.3.1.1.

SRO Enter Tech 3.3.2.1, and 3.3.3.6.

Direct BOP to bypass bistable points for the associated functional units:

RWT level low (Bistable 18).

Examiner Note: SRO must enter Tech Spec 3.3.2.1 action 10 and 3.3.3.6 action 1 for Post Accident Instrumentation.

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Appendix D Scenario 2 Form ES-D-2 Bypass point 18 on PPS Channel B:

11.1 Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 and TRM 3.3.1.1.

11.2 Circle channel and functional units (points) to be bypassed below:

Channel to be bypassed: A B C D Points to be bypassed:

1 2 3 4 5 6 7 8 9 10 11 12 13 16 17 18 19 20 11.3 Enter appropriate Tech Spec/TRM actions.

11.4 Verify points to be bypassed NOT bypassed in ANY other channel.

11.5 Place desired points in BYPASS for selected channel on 2C23.

Examiners Note: Key 12 required.

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

SRO Contact work management.

Cue: When contacted as the WWM, then report that I&C will start planning a work package to repair the failed instrument.

Termination criteria: Affected channel points placed in bypass or at lead examiner's discretion.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 2 Event

Description:

2P-4A Service water pump high winding temperature causing pump swap.

Time Position Applicant's Actions or Behavior Cued by ANY Report alarm 2K10-K2 SW PUMPS BRG/WDG TEMP HI lead examiner Examiner Note: Should be cued as soon as point 18 is bypassed due to time for temperature to trend up to the alarm setpoint.

BOP 2.1 Check 2TR-1428 to determine affected pump.

BOP 2.2 Press ACK ALM1 2TRS-1428 to acknowledge alarm and allow reflash.

ANY 2.3 Verify the following as necessary to ensure adequate Intake Structure Ventilation:

Both Intake Structure Exhaust Fans running:

- 2VEF-25A

- 2VEF-25B (should be started)

Door louvers open.

Space heaters secured.

Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down).

Sheet metal plates above SW pump motors removed.

Cue: If asked, report that the motor for A Service Water Pump is very hot to touch.

Cue: When contacted as NLO, wait ~ 2 minutes and report that intake Door louvers open, Space heaters secured, Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down), and Sheet metal plates above SW pump motors removed previously but have been checked.

BOP 2.4 IF unable to reduce temperature, THEN shift to standby Service Water pump.

Examiners note: The Crew may elect to not use the normal procedure due to the rate of temperature rise.

BOP Except from OP-2104.029 Service water system operation.

19.0 STARTING AND STOPPING SERVICE WATER PUMPS 19.1 IF desired to START Service Water Pump (2P-4A, 2P-4B or 2P-4C),

THEN perform the following:

BOP 19.1.2 IF NOT starting SW pump to pump down bay, Revision 0 Page 9 of 31

Appendix D Scenario 2 Form ES-D-2 THEN verify suction source aligned to ECP or Lake per Shifting Service Water Suction Sources section of this procedure.

BOP Calls NLO to verify the following:

19.1.3 Verify motor oil levels between Min and Max mark.

Cue: NLO reports that oil level is between Min and Max mark for 2P-4B service water pump.

BOP 19.1.4 Start selected SW Pump (2P-4A/B/C).

BOP 19.1.5 Check appropriate pressures rise:

Loop 1 SW: 2PIS-1417-1 or P1417-1 Loop 2 SW: 2PIS-1423-2 or P1423-2 ACW: 2PI-1603 or P1603 BOP Calls NLO to verify the following:

19.1.6 Check the following for proper response:

SW pump packing leakoff acceptable (enough to cool the packing, not so excessive that a safety hazard is created).

Air/Vacuum Release valve vents pump for maximum of two minutes, then closes (verified by audible response).

Solid stream of pressurized water issuing from the Constant Vent line.

Cue: NLO report that SW pump packing leakoff is acceptable, Air/Vacuum Release valve vented pump and is closed, solid stream of pressurized water issuing from the constant vent line.

BOP 19.2 IF desired to STOP Service Water Pump (2P-4A),

THEN perform the following:

19.2.1 Verify ANY of the following:

2P-4B aligned to Loop 1 SW per Attachment I and running. (This condition is satisfied)

Requirements of 1015.008, Unit 2 SDC Control met.

Appropriate Tech Specs entered for inoperable SW loop. Refer to 2203.022, Loss of Service Water.

BOP 19.2.2 Secure Service Water pump (2P-4A).

Examiner Note: The crew may determine to place 2P-4A service water pump in PTL due to the high winding temperature.

BOP 19.2.3 IF 2P-4B in operation on Loop 1 SW, THEN check header pressures reading as follows:

Loop 1 SW (2PIS-1417-1 or P1417-1) (55 to 118 psig)

ACW (2PI-1603 or P1603) (35 to 118 psig)

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Appendix D Scenario 2 Form ES-D-2 BOP Calls NLO to verify the following:

19.2.4 Check 2P-4A Discharge Check Valve (2SW-2A) closes.

19.2.5 Verify 2P-4A shaft rotation stops.

Cue: NLO report that 2P-4A SW pump discharge check valve is closed as indicated by a slam and the 2P-4A shaft rotation has stopped.

BOP 19.2.6 IF SW pump manipulations complete, THEN inform Chemistry of present SW pump configuration.

Cue: If contacted as Chemistry, then respond by telling the control room that you will realign chemical injection to the appropriate pumps.

SRO Contact Work Week Manager to investigate/ repair 2P-4A service water pump.

Cue: When contacted as the WWM, then report that electrical maintenance will investigate the high winding temperature.

Termination criteria: When 2P-4B is running and 2P-4A is secured or at lead examiners discretion.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4 Event

Description:

Shutdown required due to 4 gpm steam generator tube leak on A steam generator.

Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.

Time Position Applicant's Actions or Behavior Cued by ANY Announce alarm SEC SYS RADIATION HI.

lead examiner Cue: If contacted as NLO to investigate N-16 monitors locally, report that you do not see any problems with the N-16 monitor but their readings are elevated(give them the CR N-16 readings).

SRO Enter and Implement AOP 2203.038, Primary to Secondary leakage.

SRO 2. Notify Control Board Operators to monitor floating steps.

ATC *3. Cycle Charging pumps to maintain PZR level within 5% of setpoint.

ANY *4. Check PZR level maintained within 10% of setpoint.

ANY 6. Notify Chemistry to sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.

Cue: If contacted as Chemistry, then report you will sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.

ATC 7. Initiate secondary contamination control using 2202.010 Attachment 19, Control of Secondary Contamination.

Cue: If contacted as the AO, then report you are commencing Standard Attachment 19 control of secondary contamination.

ATC *8. Maintain VCT level 60 to 75%; refer to 2104.003, Chemical Addition.

ANY 9. Determine Primary to Secondary leakrate by ANY of the following:

Computer RCS LKRT programs.

Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.

Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.

Chemistry leakrate calculation using 1604.013, Measurement of Primary to Secondary Leakage.

SG Tube Leak N-16 monitors.

Manual leakrate calculation.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4 Event

Description:

Shutdown required due to 4 gpm steam generator tube leak on A steam generator.

Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.

Time Position Applicant's Actions or Behavior ANY *10. Refer to TS 3.4.6.2, Reactor Coolant System Leakage.

Examiner Note: SRO must enter Tech Spec 3.4.6.2 action a due to primary to secondary leakage ATC 12. Determine leaking SG by ANY of the following:

A. Secondary Systems Radiation Trend recorder:

2RR-1057 B. SG Sample Radiation monitors:

2RITS-5854 2RITS-5864 C. Main Steam Line Radiation monitors:

2RI-1007 2RI-1057 D. SG water sample results.

E. SG Tube Leak N-16 monitors.

SRO When the Leakrate is determined to be greater than 44 gpm the SRO will direct the Reactor trip.

13. IF RCS leakage greater than 44 gpm AND in Mode 1 OR 2, THEN perform the following:

A. Trip Reactor.

B. Actuate SIAS.

C. Actuate CCAS D. GO TO 2202.001, Standard Post Trip Actions.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4 Event

Description:

Shutdown required due to 4 gpm steam generator tube leak on A steam generator.

Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.

Time Position Applicant's Actions or Behavior BOP 15. Isolate EFW pump 2P7A Steam supply as follows:

A. Close Main Steam Supply valve to 2P7A from leaking SG:

2CV-1000-1 2CV-1050-2 SRO B. Refer to TS 3.7.1.2, Emergency Feedwater System.

Examiner Note: The SRO must enter TS 3.7.1.2 when the Main steam supply valve to 2P-7A is closed.

ANY 16. Check SG Blowdown aligned to SU/BD DI.

Cue: If requested as NLO for S/G blowdown alignment then, report S/G blowdown is aligned to SU/BD DI SRO *21. IF confirmed primary to secondary leakage on ANY SG quantified to meet ANY of the following:

> 75 gpd (.052 gpm) AND rate of leak rise is

> 30 gpd/hr (.021 gpm)

Leak spike of >150 gpd (>0.1 gpm)

Leakage in any one SG that exceeds 100 gpd (0.07 gpm) during allowed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period of operation after ACTION LEVEL TWO entry.

THEN perform ACTION LEVEL THREE section of Attachment A.

SRO Attachment A:

ACTION LEVEL THREE A. IF leakage > 75 gpd (> 0.052 gpm) AND rising by > 30 gpd/hr, THEN perform the following as necessary:

1) IF at power, THEN commence power reduction as necessary to be < 50% power within one hour.

2) Be in Mode 3 within the next two hours.

B. For all other cases concerning ACTION LEVEL THREE required entry, commence power reduction as necessary to be in Mode 3 within six hours.

C. Ensure any out of service leak monitoring equipment returned to service as soon as practical.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4 Event

Description:

Shutdown required due to 4 gpm steam generator tube leak on A steam generator.

Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.

Time Position Applicant's Actions or Behavior ALL 22. IF required by Attachment A, THEN commence power reduction using 2102.004, Power Operations as follows:

B. IF RCS leakage less than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at Power.

Examiners Note: The ATC should start a shutdown using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at power.

SRO Examiner Note: Excerpt from Power Operations for power reduction.

12.2 Commence Power reduction by performing the following as necessary:

Boration using Normal Borate Mode to Charging pump suction (unless directed otherwise by Abnormal Operating Procedure)

Refer to Chemical Addition (2104.003), Exhibit 3, Normal RCS Boration at Power.

2102.004 CEA insertion using CEDMCS Control System Operation Power (2105.009), Exhibit 3 CEDMCS Operations (normally for operations ASI control).

12.3 Lower Turbine load as necessary to hold Tave within +/- 2°F of program Tref using Exhibit 1, TAVE VS TREF.

12.5 IF Shutdown directed by TECH SPECS, THEN initiate ATTACHMENT L to determine mode specific time limits and continue with shutdown.

Examiner Note: The SRO should give attachment L to the Shift Manager to perform.

ATC 1.0 Verify Boric Acid Makeup Flow controller (2FIC-4926) set as follows:

In MANUAL OR AUTO.

Setpoint set to desired flowrate.

2.0. Verify desired BAM pump (2P-39A OR 2P-39B) selected for automatic operation using BAM pump Select switch (2HS-4911-2).

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4 Event

Description:

Shutdown required due to 4 gpm steam generator tube leak on A steam generator.

Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.

Time Position Applicant's Actions or Behavior ATC 3.0 Operate Mode Select Switch (2HS-4928) as follows:

3.1 Place to BORATE.

3.2 Verify the following:

Charging Pump Suction From Boric Acid (2CV-4930) opens.

Selected BAM pump (2P-39A OR 2P-39B) running.

Examiner Note: When the Mode Select Switch is placed in the Borate position 2P-39B will start and then trip.

ATC Recognize and report 2P-39B tripped after start.

Cue: If contacted as NLO, report the 2P-39B breaker 2B62-B6 breaker is trip free and 2P-39B motor has an acrid odor.

SRO Direct another boration method i.e. 2P-39A preferred, gravity feed.

Examiner Note: gravity feed boration will not be available due to the VCT outlet valve not closing.

ATC 2.0. Verify desired BAM pump (2P -39A OR 2P -39B) selected for automatic operation using BAM pump Select switch (2HS-4911-2).

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4 Event

Description:

Shutdown required due to 4 gpm steam generator tube leak on A steam generator.

Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.

Time Position Applicant's Actions or Behavior ATC 3.0 Operate Mode Select Switch (2HS-4928) as follows:

3.1 Place to BORATE.

3.2 Verify the following:

Charging Pump Suction From Boric Acid (2CV-4930) opens.

Selected BAM pump (2P-39A OR 2P-39B) running.

Examiner Note: Step 3 may not need to be performed again but the SRO may direct securing normal lineup prior to swapping BAM pumps

4.0 IF additional boric acid flow required, THEN manually start additional BAM pump (2P-39A OR 2P-39B).

5.0 Verify BAM Tank Recirc Valve (2CV-4903-2 OR 2CV-4915-2) open for running pumps.

6.0 Operate Boric Acid Makeup Flow Batch controller (2FQIS-4926) as follows:

6.1 Depress Red pushbutton.

6.2 Verify 2FQIS-4926 set for desired quantity.

6.3 Verify 2FIC-4926 indicates desired flow rate.

7.0 Monitor the following parameters:

RCS Tave Axial Shape Index Reactor power Examiner Note: The SRO may enter the TRM 3.1.2.2 for boration flow path or TRM 3.1.2.6 for 2P-39B if it is discovered that the VCT outlet valve 2CV-4873-1 will not close or if 2T-6A Boric acid tank level lowers below the limit.

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

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior Cued by ANY Crew determines the leak rate has risen to >44gpm.

lead examiner ALL 13. IF RCS leakage greater than 44 gpm AND in Mode 1 OR 2, THEN perform the following:

A. Trip Reactor.

B. Actuate SIAS.

C. Actuate CCAS D. GO TO 2202.001, Standard Post Trip Actions.

SRO Enter and implement EOP 2202.001, Standard Post Trip Actions.

1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

SRO

2. Open Safety Function Tracking page.

Reactivity ATC 3. Check Reactivity Control established as follows:

control safety A. Reactor power lowering.

function

_____B. ALL CEAs fully inserted by observing Rod bottom lights illuminated. (Not met due to Event #6, perform contingency)

Reactivity SRO Direct ATC to perform emergency boration in progress using Exhibit 1, control Emergency Boration.

safety function _____B. Perform the following as necessary:

_____1) Check CEACs 1 AND 2 indicates ALL CEAs fully inserted. (Not met due to Event #6, perform contingency)

_____2) Verify emergency boration in progress using Exhibit 1, Emergency Boration.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior ATC 1. Select ONE of the following Emergency Boration flowpaths:

FLOWPATH ACTIONS REQUIRED A. Gravity Feed A. Verify at least ONE BAM Tank Gravity Feed valve open:

2CV-4920-1

2CV-4921-1 B. BAM pumps B. 1) Start at least ONE BAM pump.

2) Open Emergency Borate valve (2CV-4916-2).

Emergency 3) Verify Boric Acid Makeup Boration Flow Control valve (2CV-4926) closed.

Critical C. RWT to Charging pumps C. Open Charging Pump Suction Task:

Emergency Source From RWT valve Boration (2CV-4950-2).

must be Examiner Note: 2P-39A Boric Acid Makeup pump will be required to started be used and should already be running.

prior to completion ATC 2. Close VCT Outlet valve (2CV-4873-1).

of SPTAs Examiner Note: The VCT outlet valve will not close and ATC should perform step 3.

ATC 3. IF VCT Outlet valve does NOT close, THEN verify BAM Pumps Emergency Boration flowpath selected.

Examiner Note: The emergency borate valve 2CV-4916-2 will not automatically open and must be manually opened by ATC.

ATC 4. Verify Reactor Makeup Water Flow Control valve (2CV-4927) closed.

5. Verify at least ONE Charging pump running and charging header flow greater than 40 gpm.

BOP Complete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Check Main Turbine tripped by BOTH of the following:

ALL Main Stop Valves closed.

Generator megawatts indicate zero.

B. Generator Output breakers open.

C. Exciter Field breaker open.

D. At least ONE 6900v AC bus energized Vital Auxiliaries E. At least ONE 4160v Non-vital AC bus energized.

safety function F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured. Both DGs will be running with service water aligned)

H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC 5. Check RCS Inventory Control established as follows:

A. PZR level:

RCS Inventory 10 to 80%.

Control Trending to setpoint. (Will not be met due to SGTR Event Safety #5 perform contingency) function B. RCS MTS 30°F or greater.

SRO Direct the following as necessary:

RCS A. Perform as necessary:

Inventory Control Safety 1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.

function

2) Verify PZR Level Control system restoring level to setpoint.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior RCS BOP 6. Check RCS Pressure Control:

___

Pressure

1800 to 2250 psia.

___

Trending to setpoint. (Not met due to SGTR Event #5, Control Safety perform contingency) function SRO Direct the following actions as necessary:

6. Perform as necessary:

A. IF RCS pressure lowers to less than 1400 psia, THEN trip ONE RCP in EACH loop.

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and RCS closed.

Pressure Control E. IF RCS pressure lowers to 1650 psia or less, Safety THEN perform the following:

function 1) Verify SIAS actuated on PPS inserts.

2) GO TO Step 7.

F. Verify PZR Pressure Control system restoring pressure to setpoint.

ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running.

B. CCW flow aligned to RCPs.

C. Loop delta T less than 10°F.

Core Heat Removal D. RCS MTS 30°F or greater.

safety function.

E. Check SW aligned to CCW. (SW will not be aligned due to SIAS and should perform contingency)

F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.

SRO Direct the contingency for step 7. E Revision 0 Page 21 of 31

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior BOP E. IF CCW available, THEN restore SW to CCW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

Examiner Note: The SRO may decide to pull up the step to align SW to ACW to maintain condenser vacuum pump working properly.

BOP/ATC 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

At least ONE SG level 10 to 90%.

FW maintaining SG level B. Check MFW in RTO (MFW may not be in RTO due to steam generator levels being at setpoint, and the contingencies are satisfied if steam generator levels are controlling near the setpoint)

C. Check Feedwater line intact by the following:

RCS Heat Removal

SG level stable or rising.

Safety Function

NO unexplained step changes or erratic FW flow.

NO unexplained step changes or erratic Condensate flow.

D. Check SG pressure 950 to 1050 psia.

E. IF desired, THEN perform the following for SDBCS Master Controller using 2105.008 Exhibit 3:

1) Place controller in Auto/Local.

2) Set setpoint at 960 psia.

F. Check RCS TC 540 to 555°F.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior ANY 9. Check CNTMT parameters:

A. Temperature and Pressure:

Temperature less than 140°F.

Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured.

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:

"CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.

2) RCS leakage alarms:

"AREA RADIATION HI/LO" annunciator (2K11-B10)

Containment clear.

Safety * "PROC LIQUID RADIATION HI/LO" annunciator Function (2K11-C10) clear.

3) Check the following radiation monitors trend stable:

CNTMT Area

CAMS

Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity: (Not met due to SGTR Event #5)

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

2) Secondary Systems Radiation monitors trend stable:

Main Steam lines

SG Sample

Condenser Off Gas Revision 0 Page 23 of 31

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior SRO 10. Notify STA to report to control room.

11. Verify NLOs informed of Reactor trip.

12. Verify Reactor trip announced on Plant page.

13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose Steam Generator Tube Rupture EOP 2202.004 SRO Enter and implement Steam Generator Tube Rupture EOP 2202.004 SRO

1. Confirm diagnosis of SGTR:

A. Check SFSC acceptance criteria satisfied every 15 minutes.

B. Refer to 2202.010 Attachment 20, Break Identification Chart.

C. Verify SG Sample valves open.

D. Notify Chemistry to perform BOTH of the following:

Sample BOTH SGs for activity.

Monitor RDACS for off site dose releases.

Cue: When contacted as Chemistry, then report you will sample both S/G for activity and Monitor RDACS for off site dose releases.

SRO

2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

SRO 3. Open Placekeeping Page.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior SRO 4. Record present time:

Time ANY 5. Verify SIAS and CCAS actuated on PPS inserts.

SRO 6. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010, Exhibit 9, ESFAS Actuation.

ANY *7. Check CCW aligned to RCPs.

SRO May elect to pull up the floating step for commencing a cooldown. Step 12.

It is possible that the SRO will implement step 11 at the same time he implements step 8.

ATC 12. Commence RCS cooldown to less than 535°F TH as follows:

A. Reset Low SG Pressure setpoints during cooldown and depressurization.

B. Commence RCS depressurization to maintain RCS MTS 30 to 45°F.

C. Monitor cooldown rate as follows:

Record RCS TC and PZR temperature using Attachment 8, RCS Cooldown Table.

Plot RCS pressure versus RCS TC using 2202.010 Attachment 1, P-T Limits every 15 minutes.

D. IF ANY RCPs running, THEN initiate RCS cooldown using EITHER of the following:

1) SDBCS Bypass valves (condenser available) - most preferred.

2) SDBCS ADV from intact SG to atmosphere - least preferred IF necessary, THEN supplement with SDBCS ADV from ruptured SG to atmosphere as needed.

Examiner Note: The SDBCS Bypass valves should be used to minimize off site release.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior ANY F. IF SDBCS Bypass valves available for RCS cooldown, THEN place ALL ADV Permissive switches in OFF.

BOP G. Control S/G levels with EFW or AFW using 2106.006, Emergency Feedwater System Operations.

ANY H. Secure running MFW pump.

BOP I. Close ALL MFW Block valves.

ANY 8. Restore ESF/Non-ESF systems post-SIAS as follows:

A. Verify at least ONE SW pump running on EACH loop.

ANY B. Verify DG SW Outlet valves open.

ANY C. Verify SW pump suction aligned to Lake.

ANY D. Check 4160v Non-vital bus 2A1 or 2A2 energized from offsite power.

ANY E. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.

BOP F. Start SW pumps as needed to maintain SW header pressure.

ANY G. Check SW to CCW restored.

ANY H. Check ACW restored. (Not met, perform contingency)

BOP H. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

BOP I. Maintain SW header pressure greater than 85 psig.

ANY *9. Verify Safety Injection flow to RCS as follows:

A. Check total HPSI flow acceptable using 2202.010 Exhibit 2, HPSI Flow Curve.

B. Check total LPSI flow acceptable using 2202.010 Exhibit 3, LPSI Flow Curve.

Examiner Note: will not be met see event #7 actions ANY 10. Check RCS pressure greater than 1400 psia. (May not be met, if not met perform contingency)

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior ANY 10. Perform the following: (Contingency)

A. IF RCS pressure less than 1400 psia, THEN perform the following:

1) Verify maximum of ONE RCP running in EACH loop.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

B. IF NPSH requirements violated OR RCS MTS less than 30°F, THEN perform the following:

1) Stop ALL RCPs.

2) Verify BOTH PZR Spray valves in MANUAL and closed.

ANY 11. Check IA pressure greater than 65 psig.

ANY *13. Minimize primary to secondary break flow as follows:

A. Check ANY RCP running.

B. Maintain RCS pressure within the following criteria:

Within 100 psia above minimum RCP NPSH requirement, refer to 2202.010 Attachment 1, P-T Limits.

Less than 1000 psia as conditions allow.

Within 50 psi of ruptured SG pressure as RCP NPSH requirements allow.

Examiners Note: The criteria to minimize break flow can not be established until HPSI is overridden. Then the crew should establish these limits.

ANY C. Use EITHER of the following to depressurize RCS:

1) 2202.010 Attachment 27, PZR Spray Operation.

2) IF HPSI termination criteria met, THEN cycle Charging pumps or throttle HPSI flow to lower PZR pressure.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior ANY D. IF RCS pressure less than ruptured SG pressure, THEN sample RCS Boron concentration every 30 minutes.

ANY 14. Determine ruptured SG by comparing ANY of the following:

A. Secondary Systems Radiation Trend recorder (2RR-1057).

B. Main Steam Line Radiation Monitors:

2RI-1007

2RI-1057 C. SG Sample Radiation Monitors:

2RITS-5854

2RITS-5864 D. SG Tube Leak N-16 Monitor history trends.

E. SG levels.

1) Level rising faster in ONE SG with similar FW flow rates and steaming rates in BOTH SGs.

2) Rising SG level with ALL FW isolated.

F. Steam flow and FW flow prior to Reactor trip.

G. SG water sample results.

ANY Direct the NLOs to perform the following:

15. Minimize secondary contamination by performing BOTH of the following:

A. Commence isolation of ruptured SG by performing local actions ONLY of 2202.010 Attachment 10, SG Isolation.

B. 2202.010 Attachment 19, Control of Secondary Contamination.

Examiner Note: Standard Att. 19 should already be started and may not be communicated again to NLOs.

Cue: If contacted as the AO, then report after 5 min that the local portions of Attachment 10 for A S/G are complete.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior ANY 16. Isolate ruptured SG Steam Supply to EFW pump 2P7A as follows:

ANY A. Verify EFW pump 2P7B running.

B. IF 2P7B NOT running, THEN verify AFW pump 2P75 running.

ANY C. Stop EFW pump 2P7A:

1) Override and close Steam Supply to 2P7A valve (2CV-0340-2).

2) Close Main Steam Supply valve from ruptured SG to EFW pump 2P7A:

"SG A TO EMER FW PMP TURB" 2CV-1000-1

"SG B TO EMER FW PMP TURB" 2CV-1050-2 ALL 19. Isolate ruptured SG as follows:

A. Monitor RCS TH during cooldown with ANY of the following:

PMS point T4614

PMS point T4714

SPDS display B. WHEN RCS TH less than 535°F, THEN isolate ruptured SG using 2202.010 Attachment 10, SG Isolation.

C. Maintain ruptured SG less than 1050 psia with ONE of the following:

MSIV Bypass valve

Upstream ADV Revision 0 Page 29 of 31

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.

Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.

Time Position Applicant's Actions or Behavior BOP 2. Verify each component in the following table in the indicated position:

COMPONENT DESCRIPTION 1.0 2.0 3.0 NUMBER LOCATION POSITION ADV UPSTRM ISOL 2CV-1002* 2C02 CLOSED (1) 2CV-1001 PERMISSIVE 2CV-1001 2C02 OFF (1)

MSIV HEADER #1 2SV-1010-1A 2C17 CLOSED MSIV HEADER #1 2SV-1010-2A 2C16 CLOSED MSIV HEADER #1 BYP 2CV-1040-1 2C17 CLOSED (1)

MAIN STEAM TO EFWP TURB 2K03 2CV-1000-1 2C17 CLOSED CRITICAL FEEDWATER BLOCK VALVE TO SG-A 2CV-1024-1 2C17 CLOSED TASK Control FEEDWATER BLOCK VALVE TO SG-A 2CV-1023-2 2C16 CLOSED Room actions for SG BLOWDOWN ISOLATION 2CV-1016-1 2C17 CLOSED (1) 2202.010 2P7B DISCHARGE TO SG-A 2CV-1038-2* 2C17 CLOSED (1)

Standard Attachment FLOW CONTROL VALVE TO SG-A 2CV-1025-1* 2C17 CLOSED (1) 10 SAMPLE ISOLATION VALVE SG-A 2CV-5850 2C17 CLOSED (1) 2P7A DISCHARGE TO SG-A 2CV-1026-2* 2C16 CLOSED (1) 2P7A DISCHARGE TO SG-A 2CV-1037-1* 2C16 CLOSED (1)

SAMPLE ISOLATION VALVE STEAM GEN A 2CV-5852-2* 2C16 CLOSED (1)

Denotes override capability.

NOTE #1: Valves may be open at SM/CRS discretion.

Examiner Note: 2202.010 Attachment 10 local and control room actions must be complete within 30 minutes of entering the Steam Generator Tube Rupture EOP.

Termination criteria: RCS Cool down to less than 535°F Th and A SG isolated or at the discretion of the lead examiner.

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Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 7 Event

Description:

2CV-5017-1, 2CV-5015-1 Low pressure safety injection (LPSI) and High pressure safety injection valves (HPSI) fail to open and the B HPSI pump trips due to motor overload.

Time Position Applicant's Actions or Behavior ANY Report that 2P-89B High pressure safety injection pump has tripped.

ANY Dispatch NLO to investigate 2P-89B breaker for overcurrent drop flags and to investigate 2P-89B locally Cue: If asked, report that the over current relays for 2P-89B High Pressure Safety Injection pump are dropped.

Cue: If asked, report that 2P-89B High Pressure Safety Injection pump looks normal locally.

ANY Report that 2CV-5017-1, and 2CV-5015-1 did not open during SIAS SRO Direct BOP to place 2CV-5017-1 and 2CV-5015-1 in their actuated positions Examiner Note: The SRO may direct the BOP to use Standard Attachments Exhibit 2 or Standard Attachments Exhibit 9 to verify actuated components. Both exhibits are directed from 2202.004 Steam Generator Tube rupture.

CRITICAL BOP Open 2CV-5017-1 and 2CV-5015-1 to establish minimum design safety TASK injection flow.

Examiner Note: 2CV-5015-1 HPSI valve must be opened prior to reaching 10ºF Margin to Saturation.

Examiner Note: The SRO may discuss Tech Spec 3.5.2 or 3.5.3 due to failure of 2P-89B, 2CV-5015-1, and 2CV-5017-1.

Termination criteria: When 2CV-5015-1 HPSI valve has been fully opened or at examiners discretion.

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Appendix D Scenario 3 Form ES-D-1 Facility: ANO-2 Scenario No.: 3 (New) Op-Test No.: 2011-1 Examiners: Operators:

Initial Conditions:

60% MOL, All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed. RED Train Maintenance Week.

Turnover: 60% power for repair of 2P-1B Feedwater pump. 250 EFPD. EOOS indicates Minimal Risk.

Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed, manually control seal steam pressure. RED Train Maintenance Week. B Main Feedwater pump PMT is complete and is idling for oxygen control. Evolution scheduled: Place B Main Feedwater pump in service and raise power to 100%. Step 10.1 of 2106.007, Main Feedwater pump and FWCS operation, for placing the B Main Feedwater pump in service is complete. Commence power escalation using applicable 2104.002 steps 9.1 through 9.11 are complete and steps 9.13 to 9.18 and 9.20 to 9.29 are not applicable or complete with the exception of placing B Main feedwater pump in service (step 9.25). (provide markup copy of Power OPS procedure 2104.002 Section 9)

Event Malf. No. Event Event No. Type* Description 1 N (BOP) Place B MFWP in service.

N (SRO) 2 R (ATC) Power Ascension.

N (SRO) 3 XRC2TE46111 I (BOP) Tc temperature transmitter fails high. Tech Spec for I (SRO) SRO.

4 CVC4817DEM I (ATC) Letdown Hand Indicating Controller (HIC) demand I (SRO) fails high causing low pressurizer level.

5 XRCCHBPLVL I (ATC) Channel B Pressurizer level channel fails low. Tech I (SRO) Spec for SRO.

6 EHSYSLEAK M (ALL) Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps.

7 XMSHDRPRS I (BOP) SDBCS input fails low after the Reactor trip.

I(SRO) 8 CV0332 C (BOP) 2P-7A Emergency Feedwater pump overspeed trips on EFW2P7BFLT C (SRO) start and 2P-7B motor trips due to a winding failure.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total malfunctions. = 6, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 1, EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 2.

Revision 1 Page 1 of 3

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

1) Evaluate individual ability to place a Main Feedwater pump in service.

2) Evaluate individual ability to perform a power escalation.

3) Evaluate individual response to a RCS temperature instrument failure.

4) Evaluate individual response to a failure of a Hand indicating controller failure.

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

6) Evaluate individual response to an Electro Hydraulic system leak.

7) Evaluate individual response to a failure of the Steam Dump Bypass control system to function in automatic.

8) Evaluate individual ability to mitigate a Loss of Feedwater event.

9) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.

SCENARIO #3 NARRATIVE Simulator session begins with the plant at 60% power steady state Gland Seal Regulator, 2PCV-0231 is jacked closed.

When the crew has completed their control room walk down and brief, The BOP will place the 2P-1B feedwater pump in service. Also, while the BOP is placing 2P-1B feedwater pump in service the ATC will raise reactor power using RCS dilution.

After the BOP has placed the B feedwater pump in service and the ATC has completed the required reactivity manipulation and cued by lead examiner, 2TE-4611-1(2TI-4605-1) RCS temperature transmitter will fail high. The ATC/BOP will announce Trip and Pretrip alarms on A PPS channel. The SRO will refer to the ACA for RPS Pretrip-Trip alarms and Technical Specifications. Then the SRO will direct that points on A channel PPS for LPD, and DNBR must be bypassed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months as required by Tech Specs.

After the A channel PPS points have been bypassed and cued by lead examiner, the demand on the Letdown Hand Indicating controller (HIC) will ramp to 100%. This will result in letdown going to maximum flow. The elevated letdown flow will cause pressurizer level to lower and the volume control tank level to trend up until the automatic setpoint is reached to divert the excess letdown flow to the online holdup tank. Eventually, a backup charging pump will start based on low pressurizer level causing the low oil pressure alarm to come in and then clear. The ATC and SRO should diagnose that the letdown controller demand does not match the demand from the pressurizer level controller. The ATC will take the letdown flow controller to manual and control PZR level.

After letdown has been placed in manual and pressurizer level is being restored to set point by manual control and cued by the lead examiner, the B channel pressurizer level instrument will fail low. This will cause the backup charging pumps to automatically start and will de-energize all pressurizer heaters. AOP 2203.028, PZR Systems Malfunctions, will be entered and actions directed by the SRO. The ATC will verify that the other level control channel is reading correctly and select that channel for control and place the PZR low level cutoff switch to the unaffected channel. The ATC will also restore the pressurizer proportional heaters to service. The SRO will enter Tech Spec 3.3.3.5 Remote Shutdown instrumentation and 3.3.3.6 Post Accident Instrumentation.

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Appendix D Scenario 3 Form ES-D-1 SCENARIO #3 NARRATIVE (continued)

After the ATC has placed A Channel pressurizer level control in service and restored pressurizer proportional heaters, an EH leak will start down stream of isolation valve 2EH-1A (on EH Pump Skid) on the common header. EH pressure will degrade to ~1300 psig over the next 3 minutes.

Annunciator 2K02-A9, LOW EH Pressure, will alarm and the standby EH pump will automatically start. EH pressure will rise and then lower again as the leak degrades. Annunciator 2K02-C10, EH Tank Low Level will alarm about 5 minutes after the start of the malfunction. The Main Turbine Generator will automatically trip at 1100 psig EH pressure. The Main Feed Pumps will automatically trip at 400 psig EH pressure. The crew will secure the EH pumps and the CRS will enter SPTAs.

The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactor trips, the input to the Steam Dump Bypass Control System (SDBCS) will fail low. This will cause the SDBCS valves to have no demand and remain closed. The crew should take manual control of the SDBCS valves to control S/G pressure. 2P-7B Emergency Feedwater pump will trip when it starts due to a motor fault. During SPTAs, 2P-7A will overspeed trip due to an oil leak. The ATC will secure two Reactor Coolant Pumps (RCP) during SPTAs based on no available feedwater and the BOP will close the Steam Generator blowdown valves. If the SRO directs all RCPs secured during SPTAs, the ATC will align for Auxiliary spray to control RCS pressure.

The SRO will diagnose Loss of Feedwater due no feedwater feeding the Steam Generators and enter OP 2202.006, Loss of Feedwater.

The crew will secure all RCPs if not secured during SPTAs. The ATC will align for Auxiliary spray to control RCS pressure if not aligned during SPTAs.

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Appendix D Scenario 3 Form ES-D-2 Simulator Instructions for Scenario 3 Reset simulator to MOL 60% power IC steady state.

Ensure that AACG is secured and annunciators clear.

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

Swing ESF equipment aligned to the RED train.

A CCP lead charging pump. C CCP aligned to green train.

2PCV-0231, Gland Sealing Steam Pressure Control Valve failed closed.

B Channel Pressurizer level and pressure in service.

B MFWP recirc valve is throttled open maintaining 1 gpm/1 rpm T1, T2, T3, T4, T5, & T6 set to false.

T5 = Reactor trip.

T6 = EFAS-1 Event Malf. No. Value/ Event No. Ramp Description Time 1 Place B MFWP in service.

2 Power Ascension.

3 XRC2TE46111 616 Tc temperature transmitter fails high. Tech Spec for Trigger = T1 SRO.

4 CVC4817DEM 100 Letdown Hand Indicating Controller (HIC) demand fails Trigger = T2 3 min. high causing low pressurizer level.

5 XRCCHBPLVL 0 Channel B Pressurizer level channel fails low. Tech Trigger = T3 Spec for SRO.

6 EHSYSLEAK True Leak in the Electro Hydraulic system causing a turbine Trigger = T4 trip, reactor trip and a loss of main feedwater pumps.

7 XMSHDRPRS 650 SDBCS input fails low after the Reactor trip.

Trigger = T5 8 CV0332 0 / Delay 2P-7A Emergency Feedwater pump overspeed trips on

= 3 min. start and 2P-7B motor trips due to a winding failure.

EFW2P7BFLT True /

Delay =

Trigger = T6 1 min.

Revision 1 Page 1 of 22

Appendix D Scenario 3 Form ES-D-2 Simulator Operator CUEs At T=0 Place B MFWP in service.

Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump pre-start checks are satisfactory.

Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump is running sat.

Cued by Trigger T1 Tc temperature transmitter fails high. Tech Spec for SRO.

lead examiner Cue: When contacted as the WWM, then report that I&C is developing a work package to troubleshoot the failed temperature transmitter.

Cued by Trigger T2 Letdown Hand Indicating Controller (HIC) demand fails high causing lead low pressurizer level.

examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed controller.

Cued by Trigger T3 Control Channel B Pressurizer Level fails Low.

lead examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.

Cued by Trigger T4 Leak in the Electro Hydraulic system causing a turbine trip, reactor trip lead and a loss of main feedwater pumps.

examiner Cue: When contacted by CRS, report that EH fluid is spraying into EH pit area from a break on the common EH discharge header down stream of isolation valve 2EH-1A and is a large leak.

Reactor Trip Trigger T5 SDBCS input fails low after the Reactor trip.

EFAS-1 Trigger T6 2P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.

Cue: If contacted as the WCO, then report after 2 min. that 2P-7A can not be reset due to a bent linkage and a loss of all governor control oil.

Cue: If contacted as the AO, then report that 2P-7B breaker has over current flags dropped on the breaker relays.

Cue: If contacted as the WCO, then report that 2P-7B motor has black residue coming from all the motor vents but there is no fire or significant smoke present.

Cue: If contacted as NLO, report pre-start checks are sat for 2P-75 AFW pump and after the 2P-75 is started report post start checks are sat.

Cue: When contacted as the AO, wait approximately 4 min, then contact the Control Room and report that the breakers for the LTOP relief isolation valves are closed. (Simulator booth operator should close the breakers prior to calling the Control Room by using remote functions under RCS.)

Revision 1 Page 2 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 1 Event

Description:

Place B MFWP in service.

Time Position Applicant's Actions or Behavior T=0 SRO Direct the BOP to place B Main Feedwater pump in service.

Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump pre-start checks are satisfactory.

BOP *10.2 Verify Condensate header pressure 650 to 750 psig.

BOP 10.3 Verify S/G levels and flows stable enough to place second MFWP on line.

BOP *10.4 Verify selected MFWP flow maintained ~ 1 gal/1 rpm at all times.

Examiner Note: The BOP may elect to initially throttle open the Main feedwater pump recirc to >3000 gpm because the feedwater pump should start feeding the steam generators at about 3000 RPM.

BOP 10.5 Slowly raise oncoming pump speed until pump speed controller demand matches Speed tracking Demand for respective FWCS.

WHEN automatic operation desired, THEN place speed controller for this pump in Automatic.

BOP 10.6 WHEN flow and S/G levels stabilized, THEN bump selected MFWP Recirc closed while performing the following:

10.6.1 Between bumps allow flows and S/G levels to stabilize.

10.6.2 Continue bumping selected MFWP Recirc until closed.

BOP 10.7 Adjust MFWP/CNDP Recirc Auto Close setpoint for both MFWP recirc valve controllers (pg 3 of controller) to ~ 850 psig:

2FIC-0742 2FIC-0735 BOP 10.8 Place HIC for affected MFWP Recircs in AUTO as desired.

Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump is running sat.

Termination criteria: When 2P-1B speed controller placed in automatic or at lead examiners discretion.

Revision 1 Page 3 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power Ascension.

Time Position Applicant's Actions or Behavior SRO Direct BOP to perform the following:

9.25 WHEN at ~ 40% power, THEN place second MFWP in service using Main Feedwater Pump and FWCS Operations (2106.007).

SRO Direct ATC to commence raising power IAW the reactivity plan and 2102.004 Power operations.

ATC 9.12 IF NOT specified otherwise by Reactor Engineering, THEN commence raising power using Attachment A of this procedure for ASI Control and power escalation limits:

Commence RCS dilution. [Refer to Chemical Addition (2104.003)]

Raise turbine load as necessary to maintain Tref within +/-

2°F of program Tave using Exhibit 1, TAVE VS TREF.

Revision 1 Page 4 of 22

Appendix D Scenario 3 Form ES-D-2 ATC OP-2104.003, Chemical Addition Exhibit 2 for dilution.

1.0 Verify EITHER Reactor Makeup pump (2P-109A OR 2P-109B) running.

2.0 Verify Mode Select switch (2HS-4928) in DILUTE.

3.0 Verify Reactor Makeup Water Flow controller (2FIC-4927) set up as follows:

In MANUAL OR AUTO.

Demand set to less than Charging flow.

4.0 Verify VCT Makeup Isol valve (2CV-4941-2) open.

5.0 Operate Reactor Makeup Water Flow Batch controller (2FQIS-4927) as follows:

5.1 Depress Red pushbutton.

5.2 Verify 2FQIS-4927 set for desired quantity.

5.3 Verify 2FIC-4927 indicates desired flow rate.

6.0 Monitor the following parameters:

RCS Tave Axial Shape Index Reactor power 7.0 IF desired to terminate dilution, THEN reset 2FQIS-4927 to zero.

8.0 WHEN 2FQIS-4927 at zero, THEN verify the following:

RMW Flow Control valve (2CV-4927) closes.

No flow indicated on 2FIC-4927.

9.0 Repeat steps 5.0 through 8.0 as required.

10.0 Close 2CV-4941-2.

11.0 Verify 2FQIS-4927 Batch Volume placard updated to current batch volume.

ANY Direct a NLO to perform the following:

9.19 Perform the following:

Monitor secondary chemistry during power escalation Adjust chemical feed as necessary using Secondary System Chemical Addition (2106.028).

Termination criteria: When the required reactivity manipulation is complete or at lead examiners discretion.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Tc temperature transmitter fails high. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciators:

Lead Examiner 2K04-A4 CH A RPS/ESF/PRETRIP/TRIP 2K04-B3 PPS Channel TRIP 2K04-G4 Channel Sensor Failure ANY Report A LPD and DNBR trip on PPS insert.

ANY Compare all four channels and report Core delta T power indicates low and determines that 2TE-4611-1(2TI-4605-1) is failed low.

ALL Implement Annunciator Corrective Action 2203.012D.

2K04-H4 PPS Channel TRIP applicable actions:

2.1 Determine affected channel by checking CPC TROUBLE lights on CPC Operator Modules.

2.3 Examine PIDs 415, 416, 417, and 418 as necessary to determine affected CPC Channel and Sensor Classification.

2.4 Select CPC Maintenance Page menu and check Option 1, Failed Sensor Status Report and Option 4, CPC Sensor Status Words to determine affected sensor and present status.

SRO Implement Annunciator Corrective Action 2203.012D.

2K04-A4 CH A RPS/ESF/PRETRIP/TRIP applicable actions:

2.1 Refer to PPS insert on 2C03 to determine cause.

2.2 Compare all Channels to validate alarm.

2.6 IF channel failed, THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6, and TRM 3.3.1.1.

2.8 IF a Linear Power, Log Power or CPC Channel is inoperable, THEN refer to 2105.001, CPC/CEAC Operations.

Revision 1 Page 6 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Tc temperature transmitter fails high. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior SRO 2K04-B3 PPS Channel TRIP applicable actions:

2.1 Determine which RPS or ESFAS trips have occurred on PPS inserts.

2.3 IF channel failed, THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM 3.3.1.1.

SRO Enter Tech Spec 3.3.1.1 action 2 Direct BOP to bypass bistable points for the associated functional units:

LPD (Bistable 3)

DNBR (Bistable 4)

BOP Bypass the point 3, and 4 on Channel A IAW OP-2105.001 CPC/CEAC operations 11.1 Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 and TRM 3.3.1.1.

11.2 Circle channel and functional units (points) to be bypassed below:

Channel to be bypassed: A B C D Points to be bypassed:

1 2 3 4 5 6 7 8 9 10 11 12 13 16 17 18 19 20 11.3 Enter appropriate Tech Spec/TRM actions.

11.4 Verify points to be bypassed NOT bypassed in ANY other channel.

11.5 Place desired points in BYPASS for selected channel on 2C23.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Tc temperature transmitter fails high. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior ANY Verify annunciator 2K04-C3 PPS CHANNEL BYPASSED Verify correct channels in bypass.

SRO Contact work management.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed temperature instrument.

Termination Criteria: Affected channel points placed in bypass or at lead examiner's discretion.

Revision 1 Page 8 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 4 Event

Description:

Letdown Hand Indicating Controller (HIC) demand fails high causing low pressurizer level.

Time Position Applicant's Actions or Behavior Cued by ATC Determine that the letdown flow is elevated causing pressurizer level to lead lower.

examiner SRO Direct manual control of letdown.

Examiner Note: The guidance to take manual control of letdown flow is contained in the ACA for 2K-12 B1 Regen Hx to 2E-29 Temperature HI, 2K-12 C1 Letdown Heat exchanger temperature HI, and 2K-12 F1 Letdown to Purification Filters Flow HI but the letdown alarms may not come in this case prior to the crew recognizing the failure.

The SRO may elect to use the guidance contained in EN-OP-115 Conduct of Operations which states the following.

If an automatic control malfunctions, immediately place that control in manual.

2K-12 B1 ANY 2.1 Check temperature on 2TI-4820 and Computer Point (T4820).

ATC 2.2 IF Letdown Flow Controller (2HIC-4817) NOT controlling in AUTOMATIC, THEN perform the following per Chemical and Volume Control (2104.002):

2.2.1 Place 2HIC-4817 in MANUAL.

2.2.2 Stabilize flow.

2K-12 C1 ANY 2.1 Check temperature on 2TI-4815 and Computer Point (T4805).

ATC 2.2 Verify letdown flow (2FIS-4801) within 10 gpm of charging flow (2FIS-4863). Refer to Chemical and Volume Control (2104.002).

Examiner Note: The ATC will be required to control letdown in manual until completion of the drill.

2K-12 F1 ANY 2.1 Check flow on 2FIS-4801 and Computer Point (F4801).

ATC 2.2 IF Letdown Flow Controller (2HIC-4817) NOT controlling in AUTOMATIC, THEN perform the following per Chemical and Volume Control (2104.002):

2.2.1 Place 2HIC-4817 in MANUAL.

2.2.2 Reduce flow to < 128 gpm.

SRO Contact Work Week Manager to repair 2HIC-4817.

Revision 1 Page 9 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 4 Event

Description:

Letdown Hand Indicating Controller (HIC) demand fails high causing low pressurizer level.

Time Position Applicant's Actions or Behavior 2K-12 J1 ANY Radmonitor Flow Low applicable actions:

2.3 Verify letdown flow (2FIS-4801) > 28 gpm. Refer to Chemical and Volume Control (2104.002).

2.4 Verify L/D to Rad Monitor (2CV-4804) open.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed controller.

Termination Criteria: Letdown being controlled in manual or at lead examiner's discretion.

Revision 1 Page 10 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 5 Event

Description:

B Pressurizer level channel fails Low. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior Cued by ANY Announce alarm 2K10-J6 CNTRL CH 2 LEVEL LO.

lead Report 2LI-4627-1 and 2LR-4625 indicate normal.

examiner All charging pumps are running.

SRO Enter and implement AOP 2203.028, PZR Systems Malfunctions SRO 6. Check the following PZR level annunciators clear:

"CNTRL CH 1/2 LEVEL LO" 2K10-G6/G7 (Annunciators not clear, implement contingency)

"CNTRL CH 1/2 LEVEL HI" 2K10-J6/J7 ANY 6. Perform the following:

A. Compare PZR level instruments to determine the affected channel.

ATC C. IF selected control channel failed, THEN perform the following:

1) Place Letdown Flow controller (2HIC-4817) in MANUAL.

Examiner Note: Letdown will already be in manual due to previous failure but this does not significantly impact the PZR level failure because if letdown was in auto it would only lower 12 gpm.

ATC 2) Place PZR Level Channel Select switch (2HS-4628) to unaffected channel. (Channel 1)

ATC 3) Place PZR Low Level Cutoff select switch (2HS-4642) to unaffected channel. (Channel A)

ANY 4) Verify PZR heaters and Normal Spray operating to restore RCS pressure 2025 to 2275 psia.

Examiners Note: The ATC should restore the PZR proportional heater to operation.

ATC 5) WHEN Letdown Flow controller (2HIC-4817) automatic AND manual signals match, THEN place Letdown Flow controller in AUTO.

Examiner Note: Letdown can not be restored to auto based on the earlier demand failure.

SRO E. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and 3.3.3.6, Post-Accident Instrumentation.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 5 Event

Description:

B Pressurizer level channel fails Low. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior Examiner Note: SRO must enter Tech Spec 3.3.3.5 Remote Shutdown Instrumentation and 3.3.3.6 action 1 for Post Accident Instrumentation.

SRO Contact work management.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.

Termination Criteria: PZR level control selected to channel 1 or at lead examiner's discretion.

Revision 1 Page 12 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior Cued by ANY Report Annunciators 2K02-A9, EH Header Press LO and 2K02-B9, EH lead Pump 2P14A/B Auto Start are in alarm and report that Standby EH Pump examiner 2P14B automatically started.

SRO Refer to ACA for 2K02-A9 and direct appropriate actions.

BOP 2.1 Check EH pressure on 2PI-9650 and Computer point P9650.

BOP 2.2 Verify standby EH pump (2P-14A or 2P-14B) started.

ANY Direct NLO to investigate locally and perform the following step if it can be accomplished.

2.3 Adjust header pressure to between 1580 and 1620 psig using 2106.012, Electrohydraulic Oil System Operation.

Cue: When contacted by CRS, report that EH fluid is spraying into EH pit area from a break on the common EH discharge header down stream of isolation valve 2EH-1A and is a large leak.

ANY Report Annunciator 2K02-C10, EH Tank 2T38 Level Hi/LO is in alarm.

SRO Refer to ACA for 2K02-C10 and direct appropriate actions.

ANY Direct NLOs to perform the following as needed.

2.3 IF Low level, THEN perform the following:

2.3.1 IF EH pumps are running, THEN immediately add EH to 2T-38 using 2106.012, Electrohydraulic Oil System Operation.

2.3.2 Check system for leaks. Refer to Limits and Precautions section of 2106.012, Electrohydraulic Oil System Operation for hazard associated with EH fluid.

2.3.3 Station Operator locally to monitor for EH pump cavitation.

2.3.4 IF EH pump cavitating, THEN pump should be secured.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior BOP Monitor EH pressure and report that pressure is approaching Main Turbine Generator (MTG) trip set point and recommend manually tripping the plant.

Examiner Note: The crew should take conservative action and trip the reactor prior to the Turbine trip. If the Turbine trips the reactor should trip shortly afterward if not automatically tripped.

ANY If the Turbine automatically trips, then trip the reactor.

BOP Place both EH pump in PTL to stop the EH leak.

Cue: If the crew does not place both EH pumps in PTL then 3 minutes after the reactor trip call as the NLO and report that the running EH pumps are cavitating.

ANY Report Reactor Tripped SRO Enter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

2. Open Safety Function Tracking page.

ATC 3. Check Reactivity Control established as follows:

Reactivity control A. Reactor power lowering.

safety function B. ALL CEAs fully inserted.

BOP Complete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Main Turbine tripped.

B. Generator Output breakers open.

C. Exciter Field breaker open.

D. At least ONE 6900v AC bus energized Vital Auxiliaries E. At least ONE 4160v Non-vital AC bus energized.

safety function F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured.

H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC 5. Check RCS Inventory Control established as follows:

A. PZR level:

RCS Inventory 10 to 80%.

Control Trending to setpoint.

Safety function B. RCS MTS 30°F or greater.

Examiner Note: Letdown will still be in manual and will need to be controlled by the ATC RCS ATC 6. Check RCS Pressure Control:

___

Pressure

1800 to 2250 psia.

___

Trending to setpoint.

Control Safety function Revision 1 Page 15 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running.

B. CCW flow aligned to RCPs.

Core Heat C. Loop delta T less than 10°F.

Removal safety D. RCS MTS 30°F or greater.

function.

E. Check SW aligned to CCW.

F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.

BOP 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

At least ONE SG level 10 to 90%.

FW maintaining SG level. (Should not be met due to loss of EFW and main feed water, perform contingency)

B. Check MFW in RTO. (Should not be met due to loss of main feed water, perform contingency as necessary)

RCS Heat Removal C. Check Feedwater line intact by the following:

Safety Function

SG level stable or rising.

NO unexplained step changes or erratic FW flow.

NO unexplained step changes or erratic Condensate flow.

D. Check SG pressure 950 to 1050 psia. (Contingency should be performed due to SDBCS failure)

F. Check RCS TC 540 to 555°F.

Revision 1 Page 16 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior Cue: If contacted as the WCO, then report after 2 min. that 2P-7A can not be reset due to a bent linkage and a loss of all governor control oil.

Cue: If contacted as the AO, then report that 2P-7B breaker has over current flags dropped on the breaker relays.

Cue: If contacted as the WCO, then report that 2P-7B motor has black residue coming from all the motor vents but there is no fire or significant smoke present.

SRO Direct the following actions as necessary:

8. Check RCS Heat Removal:

A. Perform the following:

1) IF SG level lowering, THEN verify EFAS actuated. (should be automatically actuated previously)

2) IF SG level less than 10%,

THEN verify total flow greater than 485 gpm. (Can not be verified due to Loss of Feedwater)

5) IF FW NOT available, THEN perform the following:

RCS Heat Removal a) Verify maximum of ONE RCP running in each Safety loop. (SRO may elect to secure all RCPs to Function minimize heat input) b) Close SG Blowdown Isolation valves:

2CV-1016-1

2CV-1066-1 c) GO TO Step 8.C.

D. Perform as necessary:

2) Verify SDBCS restoring SG pressure 950 to 1050 psia.

Examiner Note: Step 5 may not be implemented when the crew assesses RCS heat removal to due to timing of the EFW pumps tripping after the actuation but the SRO should return and complete step 5.

Revision 1 Page 17 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior ANY 9. Check CNTMT parameters:

A. Temperature and Pressure:

Temperature less than 140°F.

Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured.

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:

"CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.

2) RCS leakage alarms:

"AREA RADIATION HI/LO" annunciator (2K11-B10)

Containment clear.

Safety * "PROC LIQUID RADIATION HI/LO" annunciator Function (2K11-C10) clear.

3) Check the following radiation monitors trend stable:

CNTMT Area

CAMS

Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

2) Secondary Systems Radiation monitors trend stable:

Main Steam lines

SG Sample

Condenser Off Gas SRO 10. Notify STA to report to control room.

11. Verify NLOs informed of Reactor trip.

12. Verify Reactor trip announced on Plant page.

13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

Revision 1 Page 18 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7 Event

Description:

Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.

Time Position Applicant's Actions or Behavior SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose Loss of Feedwater EOP 2202.006.

Termination Criteria: Feedwater has been restored per event #8or at lead examiner's discretion.

Revision 1 Page 19 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 8 Event

Description:

2P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.

Time Position Applicant's Actions or Behavior Cued by SRO Direct Actions of 2202.006 Loss of Feedwater.

lead examiner SRO Direct STA to perform the following:

1. Confirm diagnosis of Loss Of Feedwater by checking SFSC acceptance criteria satisfied every 15 minutes.

SRO

2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

3. Open Placekeeping page.

4. Notify Control Board Operators to monitor floating steps.

ATC 5. Reduce RCS heat input as follows:

A. Stop ALL RCPs.

B. Verify BOTH PZR Spray valves in MANUAL and closed.

BOP 6. Conserve SG inventory as follows:

A. Verify SG Blowdown Isolation valves closed:

2CV-1016-1

2CV-1066-1 B. Verify SG Sample valves closed.

ANY 7. Check ALL AC and Vital DC buses energized.

Critical ATC

8. Maintain RCS pressure 1800 to 2250 psia with the following:

Task

PZR heaters.

Aux spray using 2202.010 Attachment 27, PZR Spray Operation.

Use attachment 27 to maintain RCS pressure within the Pressure-Temperature limits of 200°F and 30°F Margin to Saturation.

SRO Direct a NLO to perform the following:

9. Locally remove danger tags and close the following breakers:

2B51-E4 LTOP RELIEF ISOL 2CV-4730-1 2B51-K2 LTOP RELIEF ISOL 2CV-4741-1 Revision 1 Page 20 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 8 Event

Description:

2P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.

Time Position Applicant's Actions or Behavior Cue: When contacted as the AO, wait approximately 4 min, then contact the Control Room and report that the breakers for the LTOP relief isolation valves are closed. (Simulator booth operator should close the breakers prior to calling the Control Room by using remote functions under RCS.)

SRO 11. Establish EFW flow to SGs from EFW pump 2P7B as follows:

A. Check 2P7B available. (Not met perform contingency)

SRO A. IF 2P7B NOT available, THEN GO TO Step 12.

SRO 12. Establish EFW flow to SGs from EFW pump 2P7A as follows:

Examiner Note: 2P-7A is not available and the SRO will continue on to step 13.

SRO 13. Establish AFW flow to SGs from AFW pump 2P75 as follows:

ANY A. Check 4160v non-vital bus 2A1 energized.

ANY C. Check MSIS AND CSAS reset.

BOP D. Start AFW Lube Oil pump 2P225 AND check 2P225 amber light OFF.

Cue: If contacted as NLO, report pre-start checks are sat for 2P-75 AFW pump and after the 2P-75 is started report post start checks are sat.

BOP E. IF SG level less than 49%,

THEN verify following valves closed:

2P75 to EFW Train A Flow Control Valve (2CV-0761) 2P75 to EFW Train B Flow Control Valve ( 2CV-0760)

Critical BOP F. Start 2P75.

Task G. Place AFW Lube Oil Pump 2P225 handswitch 2HS-0766 in BOP OFF, then in AUTO.

Restore BOP H. IF a SG level was less than 49%,

Feedwater THEN perform the following:

using 2P-75 AFW 1) Throttle open associated 2P75 to EFW Train Flow Control pump prior Valve to establish flow of less than 150 gpm:

to both A EFW - 2CV-0761 S/Gs reaching B EFW - 2CV-0760 70 inches wide range BOP 2) Maintain feed flow to SG less than 150 gpm until level rise level. noted or feed flow has been maintained for greater than 5 minutes.

Revision 1 Page 21 of 22

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 8 Event

Description:

2P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.

Time Position Applicant's Actions or Behavior BOP I. Restore SG level to 60% using 2202.010 Attachment 46, Establishing EFW Flow.

Termination criteria: Feedwater restored to both S/Gs with level restoring to setpoint or at examiners discretion.

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-{{#Wiki_filter:Revision 0ES-301Administrative Topics OutlineForm ES-301-1Facility:   Arkansas Nuclear One Unit 2Date of Examination:  01/28/2011Examination Level:   RO X        SROOperating Test Number:    2011-1Administrative Topic (see Note)Type Code*Describe activity to be performedA1. Conduct of Operations2.1.32 RO (3.8)
+{{#Wiki_filter:ES-301                              Administrative Topics Outline                            Form ES-301-1 Facility: Arkansas Nuclear One Unit 2                              Date of Examination: 01/28/2011 Examination Level: RO X           SRO                              Operating Test Number:      2011-1 Administrative Topic            Type                    Describe activity to be performed (see Note)                Code*
-P/RApply limit and precautions to transferring UnitAuxiliaries to Start Up Transformer #2.ANO-2-JPM-NRC-ADMIN-SU2LOADA2. Conduct of Operations2.1.37 RO (4.3)D/RPerform a dilution calculation (Manual method)ANO-2-JPM-NRC-ADMIN-CVCS6A3. Equipment Control2.2.37 RO (3.6)N/RDetermine applicable Tech Specs for EFWANO-2-JPM-NRC-ADMIN-EFWTSA4. Radiation Control2.3.15 RO (2.9)N/RDetermine Condenser Off gas Radiation monitorsetting.ANO-2-JPM-NRC-ADMIN-CRADMONEmergency Procedures/PlanNOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)
+Apply limit and precautions to transferring Unit Auxiliaries to Start Up Transformer #2.
-ANO-2-JPM-NRC-ADMIN-SU2LOADPAGE  1  OF 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV#: 0DATE:SYSTEM/DUTY AREA:Conduct of OperationsTASK:Perform Transferring Unit Auxiliaries from SU3 or Unit Aux to SU2JTA#: ANO-RO-ELECD-NORM-026KA VALUE RO:3.8SRO:4.0KA
+A1. Conduct of Operations              P/R ANO-2-JPM-NRC-ADMIN-SU2LOAD 2.1.32 RO (3.8)
+Perform a dilution calculation (Manual method)
+A2. Conduct of Operations              D/R       ANO-2-JPM-NRC-ADMIN-CVCS6 2.1.37 RO (4.3)
+Determine applicable Tech Specs for EFW A3. Equipment Control                  N/R       ANO-2-JPM-NRC-ADMIN-EFWTS 2.2.37 RO (3.6)
+Determine Condenser Off gas Radiation monitor setting.
+A4. Radiation Control                  N/R ANO-2-JPM-NRC-ADMIN-CRADMON 2.3.15 RO (2.9)
+Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
+* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
+(N)ew or (M)odified from bank ( 1)
+(P)revious 2 exams ( 1; randomly selected)
+Revision 0
+ANO-2-JPM-NRC-ADMIN-SU2LOAD                                                                    PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT:       2                         REV #:        0                   DATE:
+SYSTEM/DUTY AREA:          Conduct of Operations TASK:      Perform Transferring Unit Auxiliaries from SU3 or Unit Aux to SU2 JTA#:      ANO-RO-ELECD-NORM-026 KA VALUE         RO:        3.8        SRO:            4.0        KA
 ==REFERENCE:==
-.1.32APPROVED FOR ADMINISTRATION TO:
+.1.32 APPROVED FOR ADMINISTRATION TO:                 RO:         X     SRO:
-RO: XSRO:TASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM:PerformPOSITION EVALUATED:
+TASK LOCATION:             INSIDE CR:                   OUTSIDE CR:             BOTH:         X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANTSITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:
+PLANT SITE:                           SIMULATOR:          Perform       CLASSROOM:    Perform POSITION EVALUATED:           RO:                         SRO:
-MinutesREFERENCE(S):OP 2107.001 Attachment PEXAMINEE'S NAME:Badge #EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED: DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+ACTUAL TESTING ENVIRONMENT:               SIMULATOR:                    PLANT         CLASSROOM:
-ANO-2-JPM-NRC-ADMIN-SU2LOADPAGE  2  OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS:Mode 4; 250 EFPD. All ESF systems are in normal alignment.Startup Transformer #3 is supplying all AC electrical busses.Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.2H2 loading is 4MVA, 2H1 loading is 5 MVAData from Feeder breaker 2A112: Vab = 4082VAC; Vbc=4050VAC; Vca=4102VACData from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps;Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc=4050VAC; Vca=4102VACData from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps;TASK STANDARD:    Calculate Startup #2 loading to be 22.57 MVA (21.1 MVA to 23 MVA is acceptable) and determine thatStartup #2 limits for forced oil and forced air cooling will be exceeded.TASK PERFORMANCE AIDS:    OP 2107.001 limits and precautions, step 11.8, and Attachment 'P'.SIMULATOR SETUP:N/A.
+SITE:
-ANO-2-JPM-NRC-ADMIN-SU2LOADPAGE  3  OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:The CRS/SM directs, "Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001Step 11.8.5, "Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.Calculated average Voltage on2A1.Calculated average voltage on 2A1to be 4.078 KV (between 4.05 KVand 4.10 KV). N/A  SAT  UNSAT 2.Calculate current on 2A1.Calculated average current on 2A1to be 1716.67 amps (between 1712amps and 1720 amps). N/A  SAT  UNSAT 3.Calculated 2A1 loadingCalculated loading on 2A1 to be12.11 MVA (from 12 MVA to 13MVA is acceptable)  N/A  SAT  UNSAT 4.Calculated average Voltage on2A2.Calculated average voltage on 2A2to be 4.078 KV (between 4.05 KVand 4.10 KV). N/A  SAT  UNSAT 5.Calculate current on 2A2.Calculated current on 2A2 to be1482.67 amps (between 1478 ampsand 1486 amps. N/A  SAT  UNSAT 6.Calculated 2A2 loadingCalculated loading on 2A2 to be10.46 MVA (from 10 MVA to 11MVA is acceptable)  N/A  SAT  UNSAT(C)7.Total 4160 AC loading.Calculated total 4160 AC loading tobe 22.57 MVA (21.1 MVA to 23MVA is acceptable). N/A  SAT  UNSAT(C)8.Compare calculated loading tolimit and precaution step 5.1.7.Determine that limits for SU#2loading with Forced oil and aircooling will be exceeded. N/A  SAT  UNSATENDSTOP TIME:
+TESTING METHOD:          SIMULATE:                        PERFORM:
-ANO-2-JPM-NRC-ADMIN-SU2LOADPAGE  4  OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER's COPYINITIAL PLANT CONDITIONSMode 4; 250 EFPD. All ESF systems are in normal alignment.Startup Transformer #3 is supplying all AC electrical busses.Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.2H2 loading is 4MVA, 2H1 loading is 5 MVAData from Feeder breaker 2A112: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VACData from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717ampsData from Feeder breaker 2A212: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VACData from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485ampsInitiating CUE:The CRS/SM directs, "Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001Step 11.8.5, "Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P."
+APPROXIMATE COMPLETION TIME IN MINUTES:                         15 Minutes REFERENCE(S):        OP 2107.001 Attachment P EXAMINEE'S NAME:                                                        Badge #
-ANO-2-JPM-NRC-ADMIN-SU2LOADPAGE  5  OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE's COPYINITIAL PLANT CONDITIONSMode 4; 250 EFPD. All ESF systems are in normal alignment.Startup Transformer #3 is supplying all AC electrical busses.Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.2H2 loading is 4MVA, 2H1 loading is 5 MVAData from Feeder breaker 2A112: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VACData from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717ampsData from Feeder breaker 2A212: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VACData from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485ampsInitiating CUE:The CRS/SM directs, "Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001Step 11.8.5, "Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P."
+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-ADMIN-SU2LOAD                                                                       PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
+Mode 4; 250 EFPD. All ESF systems are in normal alignment.
+Startup Transformer #3 is supplying all AC electrical busses.
+Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.
+H2 loading is 4MVA, 2H1 loading is 5 MVA Data from Feeder breaker 2A112: Vab = 4082VAC; Vbc=4050VAC; Vca=4102VAC Data from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps; Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc=4050VAC; Vca=4102VAC Data from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps; TASK STANDARD: Calculate Startup #2 loading to be 22.57 MVA (21.1 MVA to 23 MVA is acceptable) and determine that Startup #2 limits for forced oil and forced air cooling will be exceeded.
+TASK PERFORMANCE AIDS: OP 2107.001 limits and precautions, step 11.8, and Attachment P.
+SIMULATOR SETUP: N/A.
+ANO-2-JPM-NRC-ADMIN-SU2LOAD                                                                                  PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS/SM directs, Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001 Step 11.8.5, Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P.
+START TIME:
+PERFORMANCE CHECKLIST                                  STANDARDS                          (Circle One)
+: 1. Calculated average Voltage on      Calculated average voltage on 2A1          N/A SAT UNSAT 2A1.                               to be 4.078 KV (between 4.05 KV and 4.10 KV).
+: 2. Calculate current on 2A1.          Calculated average current on 2A1          N/A SAT UNSAT to be 1716.67 amps (between 1712 amps and 1720 amps).
+: 3. Calculated 2A1 loading             Calculated loading on 2A1 to be            N/A SAT UNSAT 12.11 MVA (from 12 MVA to 13 MVA is acceptable)
+: 4. Calculated average Voltage on      Calculated average voltage on 2A2          N/A SAT UNSAT 2A2.                               to be 4.078 KV (between 4.05 KV and 4.10 KV).
+: 5. Calculate current on 2A2.          Calculated current on 2A2 to be            N/A SAT UNSAT 1482.67 amps (between 1478 amps and 1486 amps.
+: 6. Calculated 2A2 loading             Calculated loading on 2A2 to be            N/A SAT UNSAT 10.46 MVA (from 10 MVA to 11 MVA is acceptable)
+(C)       7. Total 4160 AC loading.             Calculated total 4160 AC loading to        N/A SAT UNSAT be 22.57 MVA (21.1 MVA to 23 MVA is acceptable).
+(C)       8. Compare calculated loading to      Determine that limits for SU#2             N/A SAT UNSAT limit and precaution step 5.1.7. loading with Forced oil and air cooling will be exceeded.
+END STOP TIME:
-ANO-2-JPM-NRC-ADMIN-CVCS6PAGE  1  OF  5JOB PERFORMANCE MEASURE UNIT:          2 REV#:          02 DATE:SYSTEM/DUTY AREA:   Conduct of OperationsTASK:   Perform a dilution calculation (Manual Method)JTA#:   ANO2-RO-CHADD-NORM-3KA VALUE      RO:           4.3     SRO:          4.6      KA
+ANO-2-JPM-NRC-ADMIN-SU2LOAD                                                                                  PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS Mode 4; 250 EFPD. All ESF systems are in normal alignment.
+Startup Transformer #3 is supplying all AC electrical busses.
+Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.
+H2 loading is 4MVA, 2H1 loading is 5 MVA Data from Feeder breaker 2A112: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps Initiating CUE:
+The CRS/SM directs, Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001 Step 11.8.5, Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P.
+ANO-2-JPM-NRC-ADMIN-SU2LOAD                                                                                  PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS Mode 4; 250 EFPD. All ESF systems are in normal alignment.
+Startup Transformer #3 is supplying all AC electrical busses.
+Unit 1 is at 100% and all busses energized from their Unit Auxiliary Transformer.
+H2 loading is 4MVA, 2H1 loading is 5 MVA Data from Feeder breaker 2A112: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A113: Ic=1718amps, Ia=1715amps; Ib=1717amps Data from Feeder breaker 2A212: Vab = 4082VAC; Vbc = 4050VAC; Vca = 4102VAC Data from Feeder breaker 2A213: Ic=1483amps, Ia=1480amps, Ib=1485amps Initiating CUE:
+The CRS/SM directs, Maintenance on Startup transformer #3 is planned and must be removed from service. Perform OP 2107.001 Step 11.8.5, Determine if combined load on 2A1 and 2A2 are within limits of step 5.1.7 using Attachment P.
+ANO-2-JPM-NRC-ADMIN-CVCS6                                                            PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT:     2                   REV #:       02                      DATE:
+SYSTEM/DUTY AREA: Conduct of Operations TASK: Perform a dilution calculation (Manual Method)
+JTA#: ANO2-RO-CHADD-NORM-3 KA VALUE     RO:        4.3        SRO:      4.6      KA
 ==REFERENCE:==
-.1.37APPROVED FOR ADMINISTRATION TO:  RO:         X      SRO:TASK LOCATION:  INSIDE CR:    OUTSIDE CR:   BOTH:            XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):    PLANT SITE:    SIMULATOR: Perform  CLASSROOM:      PerformPOSITION EVALUATED:      RO:      SRO:ACTUAL TESTING ENVIRONMENT:  SIMULATOR: PLANT SITE: CLASSROOM:TESTING METHOD:  SIMULATE:      PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:     10 minutesREFERENCE(S): OP 2103.004 Attachment A.3 & C , OP 2102.016EXAMINEE'S NAME:  Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:        SATISFACTORY:        UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS: Start Time Stop TimeTotal TimeSIGNED__________________________________
+.1.37 APPROVED FOR ADMINISTRATION TO: RO:                 X       SRO:
-DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+TASK LOCATION: INSIDE CR:                    OUTSIDE CR:              BOTH:        X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-ANO-2-JPM-NRC-ADMIN-CVCS6PAGE  2  OF  5JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS:   OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted tothe ECB value. Mode 3  PZR level = 42%,     RCS pressure = 2200 psia,  Tave = 545&deg;F,  VCT level = 65%,present boron concentration = 750 ppm,  ECB is calculated to be 350 ppm.    (handout JPM task initial conditionsattachment to examinee)TASK STANDARD:    The amount of water needed to dilute from actual to ECB boron concentration has been calculated using OP 2103.004 Attachment 'A.3'.TASK PERFORMANCE AIDS: Copy of Plant conditions and OP 2103.004 Attachment 'A.3'and  Attachment C.SIMULATOR INITIAL CONDITIONS:    Plant is in hot standby condition.
+PLANT SITE:                      SIMULATOR: Perform            CLASSROOM:       Perform POSITION EVALUATED:         RO:                  SRO:
-ANO-2-JPM-NRC-ADMIN-CVCS6PAGE  3  OF  5JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution waterrequired to bring RCS boron concentration to the given ECB concentration."Start Time:PERFORMANCE CHECKLIST STANDARDS(Circle One)1. Recorded data from initialconditions attachment.POSITIVE CUE:Data from initial plant conditionsrecorded on Attachment A.3.Record the following:  - 545&deg;F  (Tave)  - 2200 psia (RCS Press)  - 42% (PZR Level)  - 65% (VCT Level)  - 750 PPM (initial)  - 350 PPM (final)  N/A  SAT  UNSAT (C)2. Determine RCS mass  for 42%PZR level in attachment C.Determine RCS mass from OP2103.004 Attachment C.
+ACTUAL TESTING ENVIRONMENT: SIMULATOR:                     PLANT SITE:          CLASSROOM:
-lb (+/- 1%)  N/A  SAT  UNSAT (C)3. Calculated Mass of DI water.Calculate DI water Feed Mass:Mf = 481980 ln (750/350)Mf = 367336.3 lb
+TESTING METHOD: SIMULATE:                          PERFORM:
-(+/- 1%)  N/A  SAT  UNSAT (C)4. Calculate DI water feed volumeCalculate DI water feed volume:F = 367336.3 (0.1204)F = 44227.3 gal.
+APPROXIMATE COMPLETION TIME IN MINUTES:               10 minutes REFERENCE(S): OP 2103.004 Attachment A.3 & C , OP 2102.016 EXAMINEE'S NAME:                                             Badge #:
-(+/- 1%)  N/A  SAT  UNSATEND ANO-2-JPM-NRC-ADMIN-CVCS6PAGE  4  OF  5JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM TASK INITIAL CONDITIONS OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value.Mode 3PZR level = 42%RCS pressure = 2200 psiaTave = 545&deg;FVCT level = 65%Present RCS boron Concentration = 750 ppmECB is calculated to be 350 ppmINITIATING CUE:The CRS directs, "Using OP 2103.004 Attachment A.3 and Attachment C, determine theamount of dilution water required to bring RCS boron concentration to the given ECBconcentration."
+EVALUATOR'S NAME:
-ANO-2-JPM-NRC-ADMIN-CVCS6PAGE  5  OF  5JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM TASK INITIAL CONDITIONS OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value.Mode 3PZR level = 42%RCS pressure = 2200 psiaTave = 545&deg;FVCT level = 65%Present RCS boron Concentration = 750 ppmECB is calculated to be 350 ppmINITIATING CUE:The CRS directs, "Using OP 2103.004 Attachment A.3 and Attachment C, determine theamount of dilution water required to bring RCS boron concentration to the given ECBconcentration."
+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.
-PROC./WORK PLAN NO.2103.004PROCEDURE/WORK PLAN TITLE:SOLUBLE POISON CONCENTRATION CONTROLPAGE:6 of 21CHANGE: 010 ATTACHMENT A.3 PAGE 1 OF 1 WORK SHEET FOR MAKEUP IN DILUTE MODE NOTE Changes made affecting the calculation should be coordinated with Computer Support prior to implementation. The BORON2 program located on the plant computer is the preferred method for performing the calculations in this procedure. Manual calculations include assumptions for simplicity that result in slightly different calculated volumes than those calculated using BORON2 (see Limit and Precaution 5.2)1.0 Record the following: RCS Temp. = _______________________&deg;F Pressurizer Level = _______________________% VCT Level = _______________________________% Initial RCS Boron Conc.(Cr i) = ____________________ppm Final Desired RCS Boron Conc.(Cr F) = ______________ppm2.0 Determine the RC Mass from Attachment C:
+ANO-2-JPM-NRC-ADMIN-CVCS6                                                                            PAGE 2 OF 5 JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS: OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value. Mode 3 PZR level = 42%,       RCS pressure = 2200 psia, Tave = 545&deg;F, VCT level = 65%,
-Mass of Reactor Coolant (Mr) = _________________lb.3.0 Calculate the DI Water Feed Mass (M f):            Cr i M f = M r ln   Cr F M f = (________________) ln (_______________)
+present boron concentration = 750 ppm, ECB is calculated to be 350 ppm.      (handout JPM task initial conditions attachment to examinee)
-(               )
+TASK STANDARD:          The amount of water needed to dilute from actual to ECB boron concentration has been calculated using OP 2103.004 Attachment A.3.
-M f = __________________lb.4.0 Calculate the DI Water Feed Volume (F) that must be fed to change the boron concentration from Cr i to Cr F: F = M F V F (7.48)V F = Specific Volume of Feed @80&deg;F(ft 3/lb.)= 0.0161 ft 3/lb.F = (___________________lb.)(0.0161 ft 3/lb.) (7.48 gal/ft 3)F = (___________________lb.)(0.1204)
+TASK PERFORMANCE AIDS: Copy of Plant conditions and OP 2103.004 Attachment A.3and Attachment C.
+SIMULATOR INITIAL CONDITIONS:               Plant is in hot standby condition.
+ANO-2-JPM-NRC-ADMIN-CVCS6                                                                     PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution water required to bring RCS boron concentration to the given ECB concentration.
+Start Time:
+PERFORMANCE CHECKLIST                                   STANDARDS                   (Circle One)
+: 1. Recorded data from initial           Record the following:           N/A SAT UNSAT conditions attachment.                - 545&deg;F (Tave)
+POSITIVE CUE:                         - 2200 psia (RCS Press)
+Data from initial plant conditions recorded on Attachment A.3.           - 42% (PZR Level)
+                                                         - 65% (VCT Level)
+                                                         - 750 PPM (initial)
+                                                         - 350 PPM (final)
+(C)       2. Determine RCS mass for 42%           Determine RCS mass from OP      N/A SAT UNSAT PZR level in attachment C.           2103.004 Attachment C.
+lb
+(+/- 1%)
+(C)       3. Calculated Mass of DI water.         Calculate DI water Feed Mass:   N/A SAT UNSAT Mf = 481980 ln (750/350)
+Mf = 367336.3 lb
+(+/- 1%)
+(C)       4. Calculate DI water feed volume       Calculate DI water feed volume: N/A SAT UNSAT F = 367336.3 (0.1204)
+F = 44227.3 gal.
+(+/- 1%)
+END
+ANO-2-JPM-NRC-ADMIN-CVCS6                                                      PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM TASK INITIAL CONDITIONS OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value.
+Mode 3 PZR level = 42%
+RCS pressure = 2200 psia Tave = 545&deg;F VCT level = 65%
+Present RCS boron Concentration = 750 ppm ECB is calculated to be 350 ppm INITIATING CUE:
+The CRS directs, Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution water required to bring RCS boron concentration to the given ECB concentration.
+ANO-2-JPM-NRC-ADMIN-CVCS6                                                      PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM TASK INITIAL CONDITIONS OP 2102.016 Step 7.17 requires that RCS boron concentration is adjusted to the ECB value.
+Mode 3 PZR level = 42%
+RCS pressure = 2200 psia Tave = 545&deg;F VCT level = 65%
+Present RCS boron Concentration = 750 ppm ECB is calculated to be 350 ppm INITIATING CUE:
+The CRS directs, Using OP 2103.004 Attachment A.3 and Attachment C, determine the amount of dilution water required to bring RCS boron concentration to the given ECB concentration.
+PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:                         PAGE:    6 of 21 2103.004             SOLUBLE POISON CONCENTRATION CONTROL         CHANGE:  010 ATTACHMENT A.3 PAGE 1 OF 1 WORK SHEET FOR MAKEUP IN DILUTE MODE NOTE Changes made affecting the calculation should be coordinated with Computer Support prior to implementation.
+The BORON2 program located on the plant computer is the preferred method for performing the calculations in this procedure. Manual calculations include assumptions for simplicity that result in slightly different calculated volumes than those calculated using BORON2 (see Limit and Precaution 5.2) 1.0     Record the following:
+RCS Temp. = _______________________&deg;F Pressurizer Level = _______________________%
+VCT Level = _______________________________%
+Initial RCS Boron Conc.(Cri) = ____________________ppm Final Desired RCS Boron Conc.(CrF) = ______________ppm 2.0     Determine the RC Mass from Attachment C:
+Mass of Reactor Coolant (Mr) = _________________lb.
+.0     Calculate the DI Water Feed Mass (Mf):
+Cri Mf = Mr ln   CrF Mf = (________________) ln (_______________)
+(                 )
+Mf = __________________lb.
+.0     Calculate the DI Water Feed Volume (F) that must be fed to change the boron concentration from Cri to CrF:
+F = MFVF (7.48)
+VF = Specific Volume of Feed @80&deg;F(ft3/lb.)= 0.0161 ft3/lb.
+F = (___________________lb.)(0.0161 ft3/lb.) (7.48 gal/ft3)
+F = (___________________lb.)(0.1204)
 F = ______________gal. DI water Performed By: ______________________________ Time: __________ Date: __________
 Supervisor Review: __________________________________________ Date: __________
-PROC./WORK PLAN NO.2103.004PROCEDURE/WORK PLAN TITLE:SOLUBLE POISON CONCENTRATION CONTROLPAGE:15 of 21CHANGE: 010 ATTACHMENT C PAGE 1 OF 2 REACTOR COOLANT MASS TABLE ANO - UNIT 2 MR (MASS OF REACTOR COOLANT AT GIVEN TEMP., LBS.)PZR PRESSURE 250 psia 250 psia 250 psia 250 psia 1000 psia 2200 psiaPZR LEVEL (%)
-F 140F 200F 240F 300F 545F 0632,303 626,598 614,668 604,785 556,500 462,894 2633,589 627,885 615,957 606,075 557,617 463,803 4634,874 629,172 617,246 607,365 558,733 464,711 6636,160 630,459 618,535 608,656 559,850 465,620 8637,446 631,746 619,824 609,946 560,966 466,529 10638,731 633,033 621,113 611,237 562,083 467,438 12640,017 634,320 622,402 612,527 563,199 468,347 14641,303 635,607 623,691 613,817 564,315 469,256 16642,588 636,894 624,980 615,108 565,432 470,165 18643,874 638,181 626,269 616,398 566,548 471,074 20645,160 639,468 627,558 617,689 567,665 471,982 22646,445 640,755 628,847 618,979 568,781 472,891 24647,731 642,042 630,137 620,270 569,898 473,800 26649,017 643,329 631,426 621,560 571,014 474,709 28650,302 644,616 632,715 622,850 572,131 475,618 30651,588 645,903 634,004 624,141 573,247 476,527 32652,874 647,190 635,293 625,431 574,364 477,436 34654,159 648,477 636,582 626,722 575,480 478,345 36655,445 649,764 637,871 628,012 576,596 479,253 38656,731 651,051 639,160 629,302 577,713 480,162 40658,016 652,338 640,449 630,593 578,829 481,071 42659,302 653,626 641,738 631,883 579,946 481,980 44660,588 654,913 643,027 633,174 581,062 482,889 46661,873 656,200 644,316 634,464 582,179 483,798 48663,159 657,487 645,605 635,754 583,295 484,707
-ANO-2-JPM-NRC-ADMIN-EFWTS     Page  1 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 0DATE:SYSTEM/DUTY AREA:   Equipment controlsTASK:    Determine EFW TS applicability.JTA#: ANO2-RO-EFW-SURV-51KA VALUE RO:3.6SRO:4.6KA
+PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:                               PAGE:       15 of 21 2103.004              SOLUBLE POISON CONCENTRATION CONTROL                CHANGE:     010 ATTACHMENT C PAGE 1 OF 2 REACTOR COOLANT MASS TABLE ANO - UNIT 2 MR (MASS OF REACTOR COOLANT AT GIVEN TEMP., LBS.)
+PZR PRESSURE       250 psia   250 psia 250 psia 250 psia 1000 psia   2200 psia PZR LEVEL (%)       100 F      140 F     200 F   240 F     300 F       545 F 0           632,303    626,598   614,668 604,785   556,500     462,894 2           633,589    627,885   615,957 606,075   557,617     463,803 4           634,874    629,172   617,246 607,365   558,733     464,711 6           636,160    630,459   618,535 608,656   559,850     465,620 8           637,446    631,746   619,824 609,946   560,966     466,529 10          638,731    633,033   621,113 611,237   562,083     467,438 12          640,017    634,320   622,402 612,527   563,199     468,347 14          641,303    635,607   623,691 613,817   564,315     469,256 16          642,588    636,894   624,980 615,108   565,432     470,165 18          643,874    638,181   626,269 616,398   566,548     471,074 20          645,160    639,468   627,558 617,689   567,665     471,982 22          646,445    640,755   628,847 618,979   568,781     472,891 24          647,731    642,042   630,137 620,270   569,898     473,800 26          649,017    643,329   631,426 621,560   571,014     474,709 28          650,302    644,616   632,715 622,850   572,131     475,618 30          651,588    645,903   634,004 624,141   573,247     476,527 32          652,874    647,190   635,293 625,431   574,364     477,436 34          654,159    648,477   636,582 626,722   575,480     478,345 36          655,445    649,764   637,871 628,012   576,596     479,253 38          656,731    651,051   639,160 629,302   577,713     480,162 40          658,016    652,338   640,449 630,593   578,829     481,071 42          659,302    653,626   641,738 631,883   579,946     481,980 44          660,588    654,913   643,027 633,174   581,062     482,889 46          661,873    656,200   644,316 634,464   582,179     483,798 48          663,159    657,487   645,605 635,754   583,295     484,707
+ANO-2-JPM-NRC-ADMIN-EFWTS                                                           Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT:      2                      REV #:      0                       DATE:
+SYSTEM/DUTY AREA:         Equipment controls TASK:       Determine EFW TS applicability.
+JTA#:     ANO2-RO-EFW-SURV-51 KA VALUE       RO:        3.6      SRO:          4.6         KA
 ==REFERENCE:==
-.2.37APPROVED FOR ADMINISTRATION TO:
+.2.37 APPROVED FOR ADMINISTRATION TO:             RO:       X      SRO:
-RO: XSRO:TASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): 2106.006, Emergency Feedwater system operation, 2104.036 Emergency DieselOperations, ANO Unit 2 Tech Specs.EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+TASK LOCATION:           INSIDE CR:               OUTSIDE CR:              BOTH:        X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-ANO-2-JPM-NRC-ADMIN-EFWTS     Page  2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS
+PLANT SITE:                       SIMULATOR:            Perform       CLASSROOM:     Perform POSITION EVALUATED:        RO:                     SRO:
-: Plant is in Mode 1. PPS Matrix testing is in progress and all administrative requirements are satisfiedincluding TS entry. When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing thefeeder breaker trips. The Inside AO reports an oil leak on #2 EDG governor and the oil level is belowindicating range.TASK STANDARD: Determine that TS 3.7.1.2 and TS 3.8.1.1 must be entered.TASK PERFORMANCE AIDS: OP 2106.006, Emergency Feedwater operations, OP-2104.036 Emergency Diesel operations, Unit 2 Tech Specs.
+ACTUAL TESTING ENVIRONMENT:         SIMULATOR:               PLANT SITE:         CLASSROOM:
-ANO-2-JPM-NRC-ADMIN-EFWTS     Page  3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Determine any additional TS for the given plant conditions.
+TESTING METHOD:        SIMULATE:                PERFORM:
-START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One)1. Review OP 2106.006attachment D, EmergencyFeedwater system operation and TS.Examinee reviewed theEmergency feedwater systemoperation and Tech Specs.N/A  SAT  UNSAT (C)2. Using 2104.036 L&P 5.22determines #2 EDGoperability.Examinee determined that #2EDG is inoperable.N/A  SAT  UNSAT (C)3. Using attachment D of2106.006 determines greentrain EFW operability.Examinee determined thatgreen train EFW is notoperable because 2CV-1037-1is closed in Mode 1.N/A  SAT  UNSAT (C)4. Determine applicable requiredactions IAW TS.Determined the following TSactions must be entered:TS 3.8.1.1 is applicable.TS 3.7.1.2 is applicable.N/A  SAT  UNSATExaminer note: The examinee may mention TS 3.4.4 for proportional heater and TS 3.6.3.1 forcontainment isolation but are not required.
+APPROXIMATE COMPLETION TIME IN MINUTES:                   15 Minutes REFERENCE(S):      2106.006, Emergency Feedwater system operation, 2104.036 Emergency Diesel Operations, ANO Unit 2 Tech Specs.
-ENDSTOP TIME:
+EXAMINEE'S NAME:                                                  Badge #:
-ANO-2-JPM-NRC-ADMIN-EFWTS     Page  4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS
+EVALUATOR'S NAME:
-: Plant is in Mode 1. PPS Matrix testing is in progress and all administrative requirements are satisfiedincluding PPS TS entry. When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing thefeeder breaker trips. The Inside AO reports an oil leak on #2 EDG governor and the oil level is belowindicating range.INITIATING CUE:Determine TS applicability for the given plant conditions using 2106.006 EmergencyFeedwater operations, 2104.036 Emergency Diesel operations, and Unit 2 Tech Specs.Do not include PPS Tech Specs.Applicable Tech Specs: ______TS 3.7.1.2 and TS 3.8.1.1_______________
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-ANO-2-JPM-NRC-ADMIN-EFWTS     Page  5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS
+SATISFACTORY:                     UNSATISFACTORY:
-: Plant is in Mode 1. PPS Matrix testing is in progress and all administrative requirements are satisfiedincluding PPS TS entry. When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing thefeeder breaker trips. The Inside AO reports an oil leak on #2 EDG governor and the oil level is belowindicating range.INITIATING CUE:Determine TS applicability for the given plant conditions using 2106.006 EmergencyFeedwater operations, 2104.036 Emergency Diesel operations, and Unit 2 Tech Specs.Do not include PPS Tech Specs.Applicable Tech Specs: __________________________________________________
+PERFORMANCE CHECKLIST COMMENTS:
-ANO-2-JPM-NRC-ADMIN-CRADMON     Page  1 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 0DATE:SYSTEM/DUTY AREA:   Radiation ControlTASK:    Determine Condenser off gas radiation monitor setting.JTA#: ANO2-RO-RMS-OFFNORM-13KA VALUE RO:2.9SRO:3.1KA
+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-ADMIN-EFWTS                                                     Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
+Plant is in Mode 1.
+PPS Matrix testing is in progress and all administrative requirements are satisfied including TS entry.
+When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing the feeder breaker trips.
+The Inside AO reports an oil leak on #2 EDG governor and the oil level is below indicating range.
+TASK STANDARD: Determine that TS 3.7.1.2 and TS 3.8.1.1 must be entered.
+TASK PERFORMANCE AIDS: OP 2106.006, Emergency Feedwater operations, OP-2104.036 Emergency Diesel operations, Unit 2 Tech Specs.
+ANO-2-JPM-NRC-ADMIN-EFWTS                                                      Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
+Determine any additional TS for the given plant conditions.
+START TIME:
+PERFORMANCE CHECKLIST                               STANDARD             (Circle One)
+N/A SAT UNSAT
+: 1. Review OP 2106.006                      Examinee reviewed the attachment D, Emergency                 Emergency feedwater system Feedwater system operation              operation and Tech Specs.
+and TS.
+N/A SAT UNSAT (C)   2. Using 2104.036 L&P 5.22                 Examinee determined that #2 determines #2 EDG                       EDG is inoperable.
+operability.
+N/A SAT UNSAT (C)   3. Using attachment D of                   Examinee determined that 2106.006 determines green               green train EFW is not train EFW operability.                  operable because 2CV-1037-1 is closed in Mode 1.
+N/A SAT UNSAT (C)   4. Determine applicable required Determined the following TS actions IAW TS.                         actions must be entered:
+TS 3.8.1.1 is applicable.
+TS 3.7.1.2 is applicable.
+Examiner note: The examinee may mention TS 3.4.4 for proportional heater and TS 3.6.3.1 for containment isolation but are not required.
+END STOP TIME:
+ANO-2-JPM-NRC-ADMIN-EFWTS                                                     Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+Plant is in Mode 1.
+PPS Matrix testing is in progress and all administrative requirements are satisfied including PPS TS entry.
+When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing the feeder breaker trips.
+The Inside AO reports an oil leak on #2 EDG governor and the oil level is below indicating range.
+INITIATING CUE:
+Determine TS applicability for the given plant conditions using 2106.006 Emergency Feedwater operations, 2104.036 Emergency Diesel operations, and Unit 2 Tech Specs.
+Do not include PPS Tech Specs.
+Applicable Tech Specs: ______TS 3.7.1.2 and TS 3.8.1.1 _______________
+ANO-2-JPM-NRC-ADMIN-EFWTS                                                     Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+Plant is in Mode 1.
+PPS Matrix testing is in progress and all administrative requirements are satisfied including PPS TS entry.
+When 2CV-1037-1 (2P-7A Feed to A S/G) is fully closed by PPS matrix testing the feeder breaker trips.
+The Inside AO reports an oil leak on #2 EDG governor and the oil level is below indicating range.
+INITIATING CUE:
+Determine TS applicability for the given plant conditions using 2106.006 Emergency Feedwater operations, 2104.036 Emergency Diesel operations, and Unit 2 Tech Specs.
+Do not include PPS Tech Specs.
+Applicable Tech Specs: __________________________________________________
+ANO-2-JPM-NRC-ADMIN-CRADMON                                                        Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT:      2                      REV #:     0                       DATE:
+SYSTEM/DUTY AREA:         Radiation Control TASK:       Determine Condenser off gas radiation monitor setting.
+JTA#:     ANO2-RO-RMS-OFFNORM-13 KA VALUE       RO:        2.9       SRO:        3.1         KA
 ==REFERENCE:==
-.3.15APPROVED FOR ADMINISTRATION TO:
+.3.15 APPROVED FOR ADMINISTRATION TO:           RO:        X      SRO:
-RO: XSRO:TASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): 2105.016, Radiation Monitoring and Evacuation system.EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+TASK LOCATION:           INSIDE CR:              OUTSIDE CR:              BOTH:        X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-ANO-2-JPM-NRC-ADMIN-CRADMON     Page  2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS
+PLANT SITE:                       SIMULATOR:           Perform       CLASSROOM:     Perform POSITION EVALUATED:        RO:                     SRO:
-: Unit 2 is in Mode 1. 2K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645Condenser off gas. Crew has entered Primary to Secondary leakage AOP due to a small primary tosecondary leak that does not require a shutdown. The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.TASK STANDARD: Determine the new potentiometer setting for the alarm setpoint of2RITS-0645 (potentiometer setting: 3.62) and the new voltage setting for 2RR-1057 (1.845)Secondary Radiation Recorder.TASK PERFORMANCE AIDS: 2105.016, Radiation Monitoring and Evacuation system,OPS-B2 Log ANO-2-JPM-NRC-ADMIN-CRADMON     Page  3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor andvoltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring andEvacuation System. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645potentiometer until after the voltage reading is obtained for 2RR-1057.
+ACTUAL TESTING ENVIRONMENT:          SIMULATOR:             PLANT SITE:         CLASSROOM:
-START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One) 1.Determine new high alarm setpointfor 2RITS-0645 from CBO Electricaland CAMS Log (OPS-B2).Verify setpoint within the followinglimits:- Minimum high alarm setpoint of 250 cpm- Smaller of 2 times background or300 cpm above backgroundExaminee reviewed the OPS-B2 and2105.016 log and determines thatthe new alarm set point should be700 cpm.N/A  SAT  UNSAT (C)2.Determine potentiometer dial settingwhich corresponds to desired highalarm setpoint from Table 1.Examinee determined the newsetting for 2RITS-0645 is 3.62 fromthe table.N/A  SAT  UNSAT (C)3.Determine voltage setting whichcorresponds to desired high alarmsetpoint from Table 2.Examinee determined the newsetting for 2RR-1057 is 1.845 fromthe table.N/A  SAT  UNSAT ENDSTOP TIME:
+TESTING METHOD:        SIMULATE:               PERFORM:
-ANO-2-JPM-NRC-ADMIN-CRADMON     Page  4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS
+APPROXIMATE COMPLETION TIME IN MINUTES:                  15 Minutes REFERENCE(S):      2105.016, Radiation Monitoring and Evacuation system.
-: Unit 2 is in Mode 1. 2K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645Condenser off gas. Crew has entered Primary to Secondary leakage AOP due to a small primary tosecondary leak that does not require a shutdown. The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.INITIATING CUE:The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gasradiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW2105.016 Radiation Monitoring andEvacuation system and OPS-B2 CBO log. The SM hasapproved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer untilafter the voltage reading is obtained for 2RR-1057.2RITS-0645 potentiometer setting: ______3.62_______________________2RR-1057 voltage setting: _______1.845_______________________
+EXAMINEE'S NAME:                                                 Badge #:
-ANO-2-JPM-NRC-ADMIN-CRADMON     Page  5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS
+EVALUATOR'S NAME:
-: Unit 2 is in Mode 1. 2K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645Condenser off gas. Crew has entered Primary to Secondary leakage AOP due to a small primary tosecondary leak that does not require a shutdown. The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.INITIATING CUE:The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gasradiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW2105.016 Radiation Monitoring andEvacuation system and OPS-B2 log. The SM hasapproved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer untilafter the voltage reading is obtained for 2RR-1057.2RITS-0645 potentiometer setting: ______________________________2RR-1057 voltage setting: ______________________________
+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-ADMIN-CRADMON                                                 Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
+Unit 2 is in Mode 1.
+K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645 Condenser off gas.
+Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.
+The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.
+TASK STANDARD: Determine the new potentiometer setting for the alarm setpoint of 2RITS-0645 (potentiometer setting: 3.62) and the new voltage setting for 2RR-1057 (1.845)
+Secondary Radiation Recorder.
+TASK PERFORMANCE AIDS: 2105.016, Radiation Monitoring and Evacuation system, OPS-B2 Log
-Revision 0ES-301Administrative Topics OutlineForm ES-301-1Facility:  Arkansas Nuclear One Unit 2Date of Examination: 01/28/2011Examination Level:   RO        SRO XOperating Test Number:   2011-1Administrative Topic (see Note)Type Code*Describe activity to be performedA5. Conduct of Operations2.1.23 SRO (4.4)D/RReview CEA#1 Upper Gripper Coil Temperature Dataand determine correct temperature.ANO-2-JPM-NRC-ADMIN-XTCEAA6. Conduct of Operations2.1.29 SRO (4.0)D/RReview CCW system line up to normal operation.ANO-2-JPM-NRC-ADMIN-CCWVLVLUA7. Equipment Control2.2.37 SRO (4.6)N/RDetermine applicable Tech Spec for Control RoomVentilation.ANO-2-JPM-NRC-ADMIN-CREVSTSA8. Radiation Control2.3.14 SRO (3.8)
+ANO-2-JPM-NRC-ADMIN-CRADMON                                                              Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
-P/RApprove administration of Potassium Iodide.ANO-2-JPM-NRC-ADMIN-KIA9. EmergencyProcedures/Plan2.4.41 SRO (4.6)D/RDetermine Emergency Action Level for given conditions.ANO-2-JPM-NRC-ADMIN-EAL11NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)
+The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring and Evacuation System. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer until after the voltage reading is obtained for 2RR-1057.
-ANO-2-JPM-NRC-ADMIN-XTCEA            PAGE 1of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREUNIT: 2 REV#: 01DATE:SYSTEM/DUTY AREA: Conduct of OperationsTASK:Verify and determine CEA#1 Upper Gripper Coil TemperatureJTA#: ANO2-RO-CEDM-NORM-10KA VALUERO:4.3SRO:4.4KA
+START TIME:
+PERFORMANCE CHECKLIST                                  STANDARD                   (Circle One)
+N/A SAT UNSAT
+: 1. Determine new high alarm setpoint         Examinee reviewed the OPS-B2 and for 2RITS-0645 from CBO Electrical       2105.016 log and determines that and CAMS Log (OPS-B2).                   the new alarm set point should be Verify setpoint within the following         700 cpm.
+limits:
+       - Minimum high alarm setpoint of 250 cpm
+       - Smaller of 2 times background or 300 cpm above background N/A SAT UNSAT (C)   2. Determine potentiometer dial setting      Examinee determined the new which corresponds to desired high        setting for 2RITS-0645 is 3.62 from alarm setpoint from Table 1.             the table.
+N/A SAT UNSAT (C)   3. Determine voltage setting which           Examinee determined the new corresponds to desired high alarm        setting for 2RR-1057 is 1.845 from setpoint from Table 2.                   the table.
+END STOP TIME:
+ANO-2-JPM-NRC-ADMIN-CRADMON                                                 Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+Unit 2 is in Mode 1.
+K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645 Condenser off gas.
+Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.
+The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.
+INITIATING CUE:
+The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring and Evacuation system and OPS-B2 CBO log. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer until after the voltage reading is obtained for 2RR-1057.
+RITS-0645 potentiometer setting: ______3.62_______________________
+RR-1057 voltage setting: _______1.845_______________________
+ANO-2-JPM-NRC-ADMIN-CRADMON                                                 Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+Unit 2 is in Mode 1.
+K11-A10 Secondary System radiation hi alarm is locked in due 2RITS-0645 Condenser off gas.
+Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.
+The 2RITS-0645 was logged reading 400 CPM on the OPS-B2 CBO log.
+INITIATING CUE:
+The CRS/SM directs to determine the new potentiometer setting of 2RITS-0645 Off Gas radiation monitor and voltage setting for 2RR-1057 Secondary Radiation recorder IAW 2105.016 Radiation Monitoring and Evacuation system and OPS-B2 log. The SM has approved a procedure deviation to skip the step to adjust 2RITS-0645 potentiometer until after the voltage reading is obtained for 2RR-1057.
+RITS-0645 potentiometer setting: ______________________________
+RR-1057 voltage setting: ______________________________
+ES-301                              Administrative Topics Outline                            Form ES-301-1 Facility: Arkansas Nuclear One Unit 2                              Date of Examination: 01/28/2011 Examination Level: RO              SRO X                           Operating Test Number: 2011-1 Administrative Topic            Type                    Describe activity to be performed (see Note)                Code*
+Review CEA#1 Upper Gripper Coil Temperature Data and determine correct temperature.
+A5. Conduct of Operations              D/R ANO-2-JPM-NRC-ADMIN-XTCEA 2.1.23 SRO (4.4)
+Review CCW system line up to normal operation.
+A6. Conduct of Operations              D/R       ANO-2-JPM-NRC-ADMIN-CCWVLVLU 2.1.29 SRO (4.0)
+Determine applicable Tech Spec for Control Room Ventilation.
+A7. Equipment Control                  N/R ANO-2-JPM-NRC-ADMIN-CREVSTS 2.2.37 SRO (4.6)
+Approve administration of Potassium Iodide.
+A8. Radiation Control                  P/R       ANO-2-JPM-NRC-ADMIN-KI 2.3.14 SRO (3.8)
+Determine Emergency Action Level for given conditions.
+A9. Emergency                          D/R       ANO-2-JPM-NRC-ADMIN-EAL11 Procedures/Plan 2.4.41 SRO (4.6)
+NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
+* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
+(N)ew or (M)odified from bank ( 1)
+(P)revious 2 exams ( 1; randomly selected)
+Revision 0
+ANO-2-JPM-NRC-ADMIN-XTCEA                                                     PAGE 1of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT:      2                     REV #:     01                     DATE:
+SYSTEM/DUTY AREA:        Conduct of Operations TASK:    Verify and determine CEA#1 Upper Gripper Coil Temperature JTA#:    ANO2-RO-CEDM-NORM-10 KA VALUE       RO:        4.3     SRO:         4.4        KA
 ==REFERENCE:==
-.1.23APPROVED FOR ADMINISTRATION TO:RO: SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR: PerformCLASSROOM:PerformPOSITION EVALUATED:RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S):OP 2105.009EXAMINEE'S NAME:BADGE # :EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+.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):
-ANO-2-JPM-NRC-ADMIN-XTCEA            PAGE 2of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS:1. Plant is at full power.2. Both Main Chillers have tripped and cannot be started.3. I&C is not available to obtain CEDM Coil temperatures.4. OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.5. Readings obtained from the CEDM coil using a calibrated DVM are: 1) Upper Gripper coil voltage, V ug = 44V;     2) Upper Gripper Shunt voltage Vshunt = 6.46 mVTASK STANDARD:Two of the three errors on the completed Exhibit 2 must be identified:1. 8.46mV was recorded instead of the 6.46mV in step 4.3.1 and 4.23 Amps instead of 3.23 Amps in step 5.2.2. 10.4 ohms was recorded instead of 9.88 ohms in step 6.3.3. Temperature of upper gripper coil was recorded as 353.373&deg;F instead of 320.038&deg;F.NOTE: It is acceptable to correctly calculate and identify the correct values throughout the exhibit instead ofidentifying errors in calculation execution in given exhibit. Refer to "Correct Exhibit 2".AndCorrect CEA 01 upper gripper coil temperature of 500.050&deg;F must be calculated.TASK PERFORMANCE AIDS:1. OP 2105.009 Exhibit 2 (completed)2. Calculator.
+PLANT SITE:                      SIMULATOR:      Perform        CLASSROOM:     Perform POSITION EVALUATED:        RO:                   SRO:
-ANO-2-JPM-NRC-ADMIN-XTCEA            PAGE 3of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:The SM directs, "As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA,the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Verify andidentify all errors in the calculation by circling each error and determine the correct temperature."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One)1. Review OP 2105.009 Exhibit 2.Review the completed OP2105.009 Exhibit 2. N/A  SAT  UNSAT (C)2. Specific Errors present onExhibit 2:1. 8.46mV was recordedinstead of the 6.46mV instep 4.3.1 and 4.23 Ampsinstead of 3.23 Amps instep 5.2.2. 10.4 ohms was recordedinstead of 9.88 ohms in step6.3. (0.525 should havebeen subtracted from 10.4.).3. Temperature of uppergripper coil was recorded as353.373&deg;F (value for 10.9ohms) instead of 320.038&deg;F(value for 10.4 ohms).It is acceptable to correctlycalculate and identify thecorrect values throughout theexhibit instead of identifyingerrors in calculation executionin given exhibit. Refer to"Correct Exhibit 2".Two of the three errors on thecompleted Exhibit 2 must beidentified. N/A  SAT  UNSAT (C)3. Calculate correct CEA 01upper gripper coil temperatureto be 506.665&deg;F.Calculated the correct CEA 01upper gripper coil temperatureas 506.665&deg;F (acceptancecriteria is  500.050&deg;F). N/A  SAT  UNSAT ENDSTOP TIME:
+ACTUAL TESTING ENVIRONMENT:          SIMULATOR:            PLANT SITE:       CLASSROOM:
-ANO-2-JPM-NRC-ADMIN-XTCEA            PAGE 4of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS: Plant is at full power. Both Main Chillers have tripped and cannot be started. I&C is not available to obtain CEDM Coil temperatures. OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is inalarm. Readings obtained from the CEDM coil using a calibrated DVM are:1) Upper Gripper coil voltage, V ug = 44V2) Upper Gripper Shunt voltage V shunt = 6.46 mVINITIATING CUE:The SM directs, "As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water FlowLow ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009,Exhibit 2. Identify all errors in the calculation by circling each error and determine the correcttemperature."
+TESTING METHOD:        SIMULATE:              PERFORM:
-ANO-2-JPM-NRC-ADMIN-XTCEA            PAGE 5of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS: Plant is at full power. Both Main Chillers have tripped and cannot be started. I&C is not available to obtain CEDM Coil temperatures. OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is inalarm. Readings obtained from the CEDM coil using a calibrated DVM are:1) Upper Gripper coil voltage, V ug = 44V2) Upper Gripper Shunt voltage V shunt = 6.46 mVINITIATING CUE:The SM directs, "As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water FlowLow ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009,Exhibit 2. Identify all errors in the calculation by circling each error and determine the correcttemperature."
+APPROXIMATE COMPLETION TIME IN MINUTES:              15 Minutes REFERENCE(S):      OP 2105.009 EXAMINEE'S NAME:                                             BADGE # :
+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-ADMIN-CCWVLVLU Page 1 of 7Administrative JOB PERFORMANCE MEASUREUnit 2REV #: 003DATE:SYSTEM/DUTY AREA:Conduct of OperationTASK:Review a system lineup to restore the Component Cooling Water system to normal operationfollowing completion of maintenance.JTA#:ANO-SRO-ADMIN-NORM-260KA VALUE RO:4.1SRO:4.0KA
+ANO-2-JPM-NRC-ADMIN-XTCEA                                                                   PAGE 2of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
+: 1. Plant is at full power.
+: 2. Both Main Chillers have tripped and cannot be started.
+: 3. I&C is not available to obtain CEDM Coil temperatures.
+: 4. OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.
+: 5. Readings obtained from the CEDM coil using a calibrated DVM are: 1) Upper Gripper coil voltage, Vug = 44V;
+: 2) Upper Gripper Shunt voltage Vshunt = 6.46 mV TASK STANDARD:
+Two of the three errors on the completed Exhibit 2 must be identified:
+: 1. 8.46mV was recorded instead of the 6.46mV in step 4.3.1 and 4.23 Amps instead of 3.23 Amps in step 5.2.
+: 2. 10.4 ohms was recorded instead of 9.88 ohms in step 6.3.
+: 3. Temperature of upper gripper coil was recorded as 353.373&deg;F instead of 320.038&deg;F.
+NOTE: It is acceptable to correctly calculate and identify the correct values throughout the exhibit instead of identifying errors in calculation execution in given exhibit. Refer to Correct Exhibit 2.
+And Correct CEA 01 upper gripper coil temperature of 500.050&deg;F must be calculated.
+TASK PERFORMANCE AIDS:
+: 1. OP 2105.009 Exhibit 2 (completed)
+: 2. Calculator.
+ANO-2-JPM-NRC-ADMIN-XTCEA                                                                    PAGE 3of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
+The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Verify and identify all errors in the calculation by circling each error and determine the correct temperature.
+START TIME:
+PERFORMANCE CHECKLIST                                     STANDARDS                     (Circle One)
+: 1.      Review OP 2105.009 Exhibit 2.         Review the completed OP             N/A SAT UNSAT 2105.009 Exhibit 2.
+(C)     2.      Specific Errors present on            Two of the three errors on the      N/A SAT UNSAT Exhibit 2:                            completed Exhibit 2 must be identified.
+: 1. 8.46mV was recorded instead of the 6.46mV in step 4.3.1 and 4.23 Amps instead of 3.23 Amps in step 5.2.
+: 2. 10.4 ohms was recorded instead of 9.88 ohms in step 6.3. (0.525 should have been subtracted from 10.4.).
+: 3. Temperature of upper gripper coil was recorded as 353.373&deg;F (value for 10.9 ohms) instead of 320.038&deg;F (value for 10.4 ohms).
+It is acceptable to correctly calculate and identify the correct values throughout the exhibit instead of identifying errors in calculation execution in given exhibit. Refer to Correct Exhibit 2.
+(C)     3.      Calculate correct CEA 01              Calculated the correct CEA 01       N/A SAT UNSAT upper gripper coil temperature        upper gripper coil temperature to be 506.665&deg;F.                      as 506.665&deg;F (acceptance criteria is 500.050&deg;F).
+END STOP TIME:
+ANO-2-JPM-NRC-ADMIN-XTCEA                                                       PAGE 4of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:
+Plant is at full power.
+Both Main Chillers have tripped and cannot be started.
+I&C is not available to obtain CEDM Coil temperatures.
+OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.
+Readings obtained from the CEDM coil using a calibrated DVM are:
+: 1) Upper Gripper coil voltage, Vug = 44V
+: 2) Upper Gripper Shunt voltage Vshunt = 6.46 mV INITIATING CUE:
+The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Identify all errors in the calculation by circling each error and determine the correct temperature.
+ANO-2-JPM-NRC-ADMIN-XTCEA                                                       PAGE 5of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:
+Plant is at full power.
+Both Main Chillers have tripped and cannot be started.
+I&C is not available to obtain CEDM Coil temperatures.
+OP 2203.012M, 2K13 ACA, for window C4, CEDM cooling coils water flow low ACA is in alarm.
+Readings obtained from the CEDM coil using a calibrated DVM are:
+: 1) Upper Gripper coil voltage, Vug = 44V
+: 2) Upper Gripper Shunt voltage Vshunt = 6.46 mV INITIATING CUE:
+The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, the Upper Gripper temperature for CEA 01 has been calculated using 2105.009, Exhibit 2. Identify all errors in the calculation by circling each error and determine the correct temperature.
+ANO-2-JPM-NRC-ADMIN-CCWVLVLU                                               Page 1 of 7 Administrative JOB PERFORMANCE MEASURE Unit        2                       REV #:    003                     DATE:
+SYSTEM/DUTY AREA:          Conduct of Operation TASK:      Review a system lineup to restore the Component Cooling Water system to normal operation following completion of maintenance.
+JTA#:      ANO-SRO-ADMIN-NORM-260 KA VALUE         RO:        4.1      SRO:         4.0       KA
 ==REFERENCE:==
-.1.29APPROVED FOR ADMINISTRATION TO:
+.1.29 APPROVED FOR ADMINISTRATION TO:             RO:             SRO:   X TASK LOCATION:             INSIDE CR:              OUTSIDE CR:              BOTH:   X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:CLASSROOM:PerformPOSITION EVALUATED:
+PLANT SITE:                         SIMULATOR:                      CLASSROOM:    Perform POSITION EVALUATED:          RO:                    SRO:
-RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE (S):OP-1015.001,PID for Component Cooling Water System M-2234 sheet 1 & 2EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+ACTUAL TESTING ENVIRONMENT:            SIMULATOR:            PLANT SITE:       CLASSROOM:
-ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 2 of 7Administrative JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS:    Component cooling water loop are cross connected.The CCW system danger tags have been removed following maintenance. The shiftmanager has directed a partial valve lineup to be performed on the affected parts of thesystem.TASK STANDARD:Examinee's should identify 5 of the 6 errors on the partial valve line upsheet:2CV-5217 Loop I CCW Surge Tank Vent: Should not be locked closed2CCW-1023 Surge Tank 2T-37B Drain: wrong position2CCW-89 Surge Tank 2T-37B Chem. Recirc wrong position2CV-5210 Condensate Transfer to 2T-37A: valve cycles automatically based on tank level andshould be specified as per 1015.001 Att. A.32CV-5218 Loop II CCW Surge Tank Vent: Should not be locked closed2CCW-1022 Surge Tank 2T-37A Drain: wrong position ANDDo not sign partial valve line up sheet and return to SM to redo lineup.TASK PERFORMANCE AIDS:  OP-1015.001, OP-2104.028, and  PID for ComponentCooling Water System M-2234 sheet 1 & 2 ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 3 of 7Administrative JOB PERFORMANCE MEASUREInitiating Cue: The component cooling water system is being restored to normal system lineup followingcompletion of maintenance on the system. The Shift Manager has instructed you to review the partial systemlineup and verify proper restoration.Start Time: ____________NOTE: Provide a marked up copy of the system lineup to the examineePERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.Perform final SRO review of thesystem lineup paperwork.Reviews thesystem lineuppaperworkprovided.(C)2. 2CV-5217 Loop I CCW Surge Tank Vent:should not be locked closed2CCW-1023 Surge Tank 2T-37B Drain:wrong position2CCW-89 Surge Tank 2T-37B Chem.Recirc wrong position2CV-5210 Condensate Transfer to2T-37A: Valve cycles automatically basedon tank level and should be specified asper 1015.001 Att. A.3.2CV-5218 Loop II CCW Surge Tank Vent:should not be locked closed.2CCW-1022 Surge Tank 2T-37A Drain:wrong positionExamineeIdentifies 5 of the 6errors and mustidentify the ventvalvesSAT   UNSATSAT   UNSATSAT   UNSATSAT   UNSATSAT   UNSATSAT   UNSAT (C)3.Perform the step required forunsatisfactory resultsInforms ShiftManager of errors.SAT   UNSATExaminer note: The candidates may put the position for the control valves but it is notrequired per 1015.001 Att. A.3TERMINATING CUE:This JPM is complete.Stop Time: __________
+TESTING METHOD:          SIMULATE:              PERFORM:
-ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 4 of 7Administrative JOB PERFORMANCE MEASUREEXAMINER'S COPYInitial Conditions:Component cooling water loop are cross connected. The CCW system danger tagshave been removed following maintenance. The shift manager has directed a partialvalve lineup to be performed on the affected parts of the system.Initiating Cue:The component cooling water system is being restored to normal system lineupfollowing completion of maintenance on the system. The Shift Manager has directedyou to review the partial system lineup and verify proper restoration.
+APPROXIMATE COMPLETION TIME IN MINUTES:                15 Minutes REFERENCE (S):       OP-1015.001, PID for Component Cooling Water System M-2234 sheet 1 & 2 EXAMINEE'S NAME:                                                Badge #:
-ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 5 of 7Administrative JOB PERFORMANCE MEASURE KEYARKANSAS NUCLEAR ONEE-DOC TITLE:PARTIAL SYSTEM LINEUP SHEETE-DOC NO.1015.001GCHANGE NO.055-00-0System: Component Cooling Water       Page   1    of    1Reason for partial lineup, e.g. post maintenance test, clearance no., etc. Describe lineup if needed, e.g., listmajor components, boundaries, or list components excluded, etc.:Restore system to normal line up following completion of piping repairs.Partial lineup approval:Bob Shifty02/02/2011SRO SignatureDate:ComponentDescription(optional)RequiredPositionCheckedInitial SROInitial*2CCW-52142LT/LG-5214 Root Valve OPEN JR2CV-5217Loop I CCW Surge Tank VentPer 1015.001,  Att. A.3 JR2CCW-1023Surge Tank 2T-37B Drain OPEN JR2CCW-89Surge Tank 2T-37B Chem. Recirc OPEN JR2CCW-5031Surge Tanks 2T-37A/BX-Connect Drain CLOSED JR2CCW-5030Surge Tanks 2T-37A/B Drain to LRW CLOSED JR2CT-6512FI-5210 Inlet Isol OPEN JR2CT-6502FI-5210 Outlet Isol OPEN JR2CT-6522FI-5210 Bypass CLOSED JR2CT-6532FI-5210 Drain CLOSED JR2CT-16Surge Tanks 2T-37A/B Makeup Isol OPEN JR2CV-5210Condensate Transfer to 2T-37APer 1015.001, Att. A.3 JR2CV-5218Loop II CCW Surge Tank VentPer 1015.001, Att. A.3 JR2CCW-5082Surge Tank 2T-37A Makeup Line Vent CLOSED JR2CCW-50832LT/LG-5210 Root Valve OPEN JR2CCW-52102LT/LG-5210 Root Valve OPEN JR2CCW-1022Surge Tank 2T-37A Drain OPEN JR2CCW-88Surge Tank 2T-37A Chem. Recirc OPEN JR2CV-5214Condensate Transfer Supply to 2T-37BPer 1015.001, Att. A.3 JR2CCW-5084Surge Tank 2T-37B Makeup Line Vent CLOSED JR2CCW-50852LT/LG-5214 Root Valve OPEN JR*SRO Initial signifies review.Lineup Performed By:Joe Reactor
+EVALUATOR'S NAME:
- /JR  /   02/02/2011SignatureInitialDate NA /NA /NASignatureInitialDateSRO Review: Date ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 6 of 7Administrative JOB PERFORMANCE MEASUREEXAMINEE'S COPYInitial Conditions:Component cooling water loop are cross connected. The CCW system danger tagshave been removed following maintenance. The shift manager has directed a partialvalve lineup to be performed on the affected parts of the system.Initiating Cue:The component cooling water system is being restored to normal system lineupfollowing completion of maintenance on the system. The Shift Manager has directedyou to review the partial system lineup and verify proper restoration.
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-ANO-2-JPM-NRC-ADMIN-CCWVLVLU Page 7 of 7Administrative JOB PERFORMANCE MEASUREARKANSAS NUCLEAR ONEE-DOC TITLE:PARTIAL SYSTEM LINEUP SHEETE-DOC NO.1015.001GCHANGE NO.055-00-0System: Component Cooling Water       Page   1    of    1Reason for partial lineup, e.g. post maintenance test, clearance no., etc. Describe lineup if needed, e.g., listmajor components, boundaries, or list components excluded, etc.:Restore system to normal line up following completion of piping repairs.Partial lineup approval:Bob Shifty       02/02/2011SRO SignatureDate:ComponentDescription(optional)RequiredPositionCheckedInitial SROInitial*2CCW-52142LT/LG-5214 Root Valve OPEN JR2CV-5217Loop I CCW Surge Tank VentPer 1015.001,  Att. A.3 LOCKED CLOSED JR2CCW-1023Surge Tank 2T-37B Drain CLOSED JR2CCW-89Surge Tank 2T-37B Chem. Recirc CLOSED JR2CCW-5031Surge Tanks 2T-37A/BX-Connect Drain CLOSED JR2CCW-5030Surge Tanks 2T-37A/B Drain to LRW CLOSED JR2CT-6512FI-5210 Inlet Isol OPEN JR2CT-6502FI-5210 Outlet Isol OPEN JR2CT-6522FI-5210 Bypass CLOSED JR2CT-6532FI-5210 Drain CLOSED JR2CT-16Surge Tanks 2T-37A/B Makeup Isol OPEN JR2CV-5210Condensate Transfer to 2T-37A OPEN JR2CV-5218Loop II CCW Surge Tank VentPer 1015.001, Att. A.3 LOCKED CLOSED JR2CCW-5082Surge Tank 2T-37A Makeup Line Vent CLOSED JR2CCW-50832LT/LG-5210 Root Valve OPEN JR2CCW-52102LT/LG-5210 Root Valve OPEN JR2CCW-1022Surge Tank 2T-37A Drain CLOSED JR2CCW-88Surge Tank 2T-37A Chem. Recirc OPEN JR2CV-5214Condensate Transfer Supply to 2T-37BPer 1015.001, Att. A.3 JR2CCW-5084Surge Tank 2T-37B Makeup Line Vent CLOSED JR2CCW-50852LT/LG-5214 Root Valve OPEN JR*SRO Initial signifies review.Lineup Performed By:Joe Reactor
+SATISFACTORY:                       UNSATISFACTORY:
- /JR  / 02/02/2011SignatureInitialDate NA /NA /NASignatureInitialDateSRO Review: Date ANO-2-JPM-NRC-ADMIN-CREVSTS     Page  1 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 0DATE:SYSTEM/DUTY AREA:   Equipment controlsTASK:    Determine CREVS TS applicability and any required actions.JTA#: ANO-SRO-ADMIN-NORM-103KA VALUE RO:3.6SRO:4.6KA
+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-ADMIN-CCWVLVLU                                           Page 2 of 7 Administrative JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS: Component cooling water loop are cross connected.
+The CCW system danger tags have been removed following maintenance. The shift manager has directed a partial valve lineup to be performed on the affected parts of the system.
+TASK STANDARD: Examinees should identify 5 of the 6 errors on the partial valve line up sheet:
+CV-5217 Loop I CCW Surge Tank Vent: Should not be locked closed 2CCW-1023 Surge Tank 2T-37B Drain: wrong position 2CCW-89 Surge Tank 2T-37B Chem. Recirc wrong position 2CV-5210 Condensate Transfer to 2T-37A: valve cycles automatically based on tank level and should be specified as per 1015.001 Att. A.3 2CV-5218 Loop II CCW Surge Tank Vent: Should not be locked closed 2CCW-1022 Surge Tank 2T-37A Drain: wrong position AND Do not sign partial valve line up sheet and return to SM to redo lineup.
+TASK PERFORMANCE AIDS: OP-1015.001, OP-2104.028, and PID for Component Cooling Water System M-2234 sheet 1 & 2
+ANO-2-JPM-NRC-ADMIN-CCWVLVLU                                                   Page 3 of 7 Administrative JOB PERFORMANCE MEASURE Initiating Cue: The component cooling water system is being restored to normal system lineup following completion of maintenance on the system. The Shift Manager has instructed you to review the partial system lineup and verify proper restoration.
+Start Time: ____________
+NOTE: Provide a marked up copy of the system lineup to the examinee PERFORMANCE CHECKLIST                             STANDARDS              (Circle One)
+: 1. Perform final SRO review of the          Reviews the system lineup paperwork.                 system lineup paperwork provided.
+(C)         2. 2CV-5217 Loop I CCW Surge Tank Vent:                            SAT UNSAT should not be locked closed 2CCW-1023 Surge Tank 2T-37B Drain:
+SAT UNSAT wrong position 2CCW-89 Surge Tank 2T-37B Chem.                                  SAT UNSAT Recirc wrong position Examinee Identifies 5 of the 6 2CV-5210 Condensate Transfer to                                  SAT UNSAT errors and must 2T-37A: Valve cycles automatically based    identify the vent on tank level and should be specified as         valves per 1015.001 Att. A.3.
+CV-5218 Loop II CCW Surge Tank Vent:
+SAT UNSAT should not be locked closed.
+CCW-1022 Surge Tank 2T-37A Drain:                               SAT UNSAT wrong position (C)         3. Perform the step required for            Informs Shift unsatisfactory results                   Manager of errors.      SAT UNSAT Examiner note: The candidates may put the position for the control valves but it is not required per 1015.001 Att. A.3 TERMINATING CUE:
+This JPM is complete.
+Stop Time: __________
+ANO-2-JPM-NRC-ADMIN-CCWVLVLU                                    Page 4 of 7 Administrative JOB PERFORMANCE MEASURE EXAMINERS COPY Initial Conditions:
+Component cooling water loop are cross connected. The CCW system danger tags have been removed following maintenance. The shift manager has directed a partial valve lineup to be performed on the affected parts of the system.
+Initiating Cue:
+The component cooling water system is being restored to normal system lineup following completion of maintenance on the system. The Shift Manager has directed you to review the partial system lineup and verify proper restoration.
+ANO-2-JPM-NRC-ADMIN-CCWVLVLU                                                                   Page 5 of 7 Administrative JOB PERFORMANCE MEASURE KEY ARKANSAS NUCLEAR ONE E-DOC TITLE:                                                           E-DOC NO.                    CHANGE NO.
+PARTIAL SYSTEM LINEUP SHEET                                  1015.001G                       055-00-0 System: Component Cooling Water                                                                       Page 1     of  1 Reason for partial lineup, e.g. post maintenance test, clearance no., etc. Describe lineup if needed, e.g., list major components, boundaries, or list components excluded, etc.:
+Restore system to normal line up following completion of piping repairs.
+Partial lineup approval:                          Bob Shifty                                             02/02/2011 SRO Signature                                                    Date:
+Component          Description                                      Required                  Checked       SRO (optional)                                       Position                  Initial       Initial*
+CCW-5214          2LT/LG-5214 Root Valve                           OPEN                      JR 2CV-5217           Loop I CCW Surge Tank Vent                       Per 1015.001, Att. A.3    JR 2CCW-1023          Surge Tank 2T-37B Drain                          OPEN                      JR 2CCW-89            Surge Tank 2T-37B Chem. Recirc                   OPEN                      JR 2CCW-5031          Surge Tanks 2T-37A/B                             CLOSED                    JR X-Connect Drain 2CCW-5030          Surge Tanks 2T-37A/B Drain to LRW                CLOSED                    JR 2CT-651            2FI-5210 Inlet Isol                              OPEN                      JR 2CT-650            2FI-5210 Outlet Isol                             OPEN                      JR 2CT-652            2FI-5210 Bypass                                  CLOSED                    JR 2CT-653            2FI-5210 Drain                                   CLOSED                    JR 2CT-16             Surge Tanks 2T-37A/B Makeup Isol                 OPEN                      JR 2CV-5210           Condensate Transfer to 2T-37A                    Per 1015.001, Att. A.3    JR 2CV-5218           Loop II CCW Surge Tank Vent                      Per 1015.001, Att. A.3    JR 2CCW-5082          Surge Tank 2T-37A Makeup Line Vent               CLOSED                    JR 2CCW-5083          2LT/LG-5210 Root Valve                           OPEN                      JR 2CCW-5210          2LT/LG-5210 Root Valve                           OPEN                      JR 2CCW-1022          Surge Tank 2T-37A Drain                          OPEN                      JR 2CCW-88            Surge Tank 2T-37A Chem. Recirc                   OPEN                      JR 2CV-5214           Condensate Transfer Supply to 2T-37B             Per 1015.001, Att. A.3    JR 2CCW-5084          Surge Tank 2T-37B Makeup Line Vent               CLOSED                    JR 2CCW-5085          2LT/LG-5214 Root Valve                           OPEN                      JR
+*SRO Initial signifies review.
+Lineup Performed By:
+Joe Reactor                             /     JR                       / 02/02/2011 Signature                                             Initial                        Date NA                            /     NA                      /      NA Signature                                             Initial                        Date SRO Review:                                                                Date
+ANO-2-JPM-NRC-ADMIN-CCWVLVLU                                    Page 6 of 7 Administrative JOB PERFORMANCE MEASURE EXAMINEES COPY Initial Conditions:
+Component cooling water loop are cross connected. The CCW system danger tags have been removed following maintenance. The shift manager has directed a partial valve lineup to be performed on the affected parts of the system.
+Initiating Cue:
+The component cooling water system is being restored to normal system lineup following completion of maintenance on the system. The Shift Manager has directed you to review the partial system lineup and verify proper restoration.
+ANO-2-JPM-NRC-ADMIN-CCWVLVLU                                                               Page 7 of 7 Administrative JOB PERFORMANCE MEASURE ARKANSAS NUCLEAR ONE E-DOC TITLE:                                                     E-DOC NO.                      CHANGE NO.
+PARTIAL SYSTEM LINEUP SHEET                            1015.001G                         055-00-0 System: Component Cooling Water                                                                   Page 1     of  1 Reason for partial lineup, e.g. post maintenance test, clearance no., etc. Describe lineup if needed, e.g., list major components, boundaries, or list components excluded, etc.:
+Restore system to normal line up following completion of piping repairs.
+Partial lineup approval:                Bob Shifty                                                02/02/2011 SRO Signature                                                Date:
+Component          Description                                Required                    Checked       SRO (optional)                                 Position                    Initial       Initial*
+CCW-5214          2LT/LG-5214 Root Valve                     OPEN                        JR 2CV-5217           Loop I CCW Surge Tank Vent                 Per 1015.001, Att. A.3      JR LOCKED CLOSED 2CCW-1023          Surge Tank 2T-37B Drain                    CLOSED                      JR 2CCW-89            Surge Tank 2T-37B Chem. Recirc             CLOSED                      JR 2CCW-5031          Surge Tanks 2T-37A/B                       CLOSED                      JR X-Connect Drain 2CCW-5030          Surge Tanks 2T-37A/B Drain to LRW          CLOSED                      JR 2CT-651            2FI-5210 Inlet Isol                        OPEN                        JR 2CT-650            2FI-5210 Outlet Isol                       OPEN                        JR 2CT-652            2FI-5210 Bypass                            CLOSED                      JR 2CT-653            2FI-5210 Drain                             CLOSED                      JR 2CT-16             Surge Tanks 2T-37A/B Makeup Isol           OPEN                        JR 2CV-5210           Condensate Transfer to 2T-37A              OPEN                        JR 2CV-5218           Loop II CCW Surge Tank Vent                Per 1015.001, Att. A.3      JR LOCKED CLOSED 2CCW-5082          Surge Tank 2T-37A Makeup Line Vent         CLOSED                      JR 2CCW-5083          2LT/LG-5210 Root Valve                     OPEN                        JR 2CCW-5210          2LT/LG-5210 Root Valve                     OPEN                        JR 2CCW-1022          Surge Tank 2T-37A Drain                    CLOSED                      JR 2CCW-88            Surge Tank 2T-37A Chem. Recirc             OPEN                        JR 2CV-5214           Condensate Transfer Supply to 2T-37B       Per 1015.001, Att. A.3      JR 2CCW-5084          Surge Tank 2T-37B Makeup Line Vent         CLOSED                      JR 2CCW-5085          2LT/LG-5214 Root Valve                     OPEN                        JR
+*SRO Initial signifies review.
+Lineup Performed By:
+Joe Reactor                           / JR                        / 02/02/2011 Signature                                       Initial                          Date NA                          / NA                      /        NA Signature                                       Initial                          Date SRO Review:                                                          Date
+ANO-2-JPM-NRC-ADMIN-CREVSTS                                                        Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT:      2                      REV #:     0                      DATE:
+SYSTEM/DUTY AREA:         Equipment controls TASK:       Determine CREVS TS applicability and any required actions.
+JTA#:     ANO-SRO-ADMIN-NORM-103 KA VALUE       RO:        3.6      SRO:         4.6        KA
 ==REFERENCE:==
-.2.37APPROVED FOR ADMINISTRATION TO:
+.2.37 APPROVED FOR ADMINISTRATION TO:           RO:              SRO:     X TASK LOCATION:           INSIDE CR:              OUTSIDE CR:              BOTH:        X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): 2104.007, Control Room Emergency Ventilation, Unit 2 Tech Specs.EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+PLANT SITE:                       SIMULATOR:          Perform       CLASSROOM:      Perform POSITION EVALUATED:        RO:                    SRO:
-ANO-2-JPM-NRC-ADMIN-CREVSTS     Page  2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS
+ACTUAL TESTING ENVIRONMENT:          SIMULATOR:            PLANT SITE:          CLASSROOM:
-: Unit 1 is in Mode 6 for a refueling outage and currently de-fueled. Unit 2 is in Mode 1. Unit 2 is loading a dry fuel cask. VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55bus outage. Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pumpfailure.TASK STANDARD: Determined that 3.0.3 is applicable. Determined that TS 3.7.6.1 actionj is also applicable requiring immediately suspending handling of irradiated fuel.TASK PERFORMANCE AIDS: OP 2104.007, Control Room Emergency Ventilation, Unit 2 Tech Specs.
+TESTING METHOD:        SIMULATE:               PERFORM:
-ANO-2-JPM-NRC-ADMIN-CREVSTS     Page  3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:The CBOT discovers that 2VSF-9 feeder breaker is trip free.Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Includeany applicable instrumentation TS/TRM and required actions for the given plant conditions.
+APPROXIMATE COMPLETION TIME IN MINUTES:                 15 Minutes REFERENCE(S):      2104.007, Control Room Emergency Ventilation, Unit 2 Tech Specs.
-START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One)1. Review OP 2104.007attachment B and C, ControlRoom Emergency Ventilationand TS 3.7.6.1.Examinee reviewed the controlroom ventilation procedureand Tech Specs.N/A  SAT  UNSAT2. Using attachment C of2104.007 determine that TRMentry is not required for theinoperable chlorine monitors.Examinee determined thatTRM entry is not required forchlorine monitors that areinoperable.N/A  SAT  UNSAT (C)3. Using TS and 2104.007determine applicable TSactions.Examinee determined that TS3.0.3 and TS 3.7.6.1 action jare applicable.N/A  SAT  UNSATExaminer Note: The candidate may indicate TS 3.7.6.1 action 'e' is applicable, but is notrequired. TS 3.7.6.1 action 'e' states to apply the action of TS 3.0.3 (C)4. Determine most restrictiverequired action IAW TS.Determined the followingactions:Immediately suspend handlingof irradiated fuel (action J)N/A  SAT  UNSAT ENDSTOP TIME:
+EXAMINEE'S NAME:                                                Badge #:
-ANO-2-JPM-NRC-ADMIN-CREVSTS     Page  4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS
+EVALUATOR'S NAME:
-: Unit 1 is in Mode 6 for a refueling outage and currently de-fueled. Unit 2 is in Mode 1. Unit 2 is loading a dry fuel cask. VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55bus outage. Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pumpfailure.INITIATING CUE: The CBOT discovers that 2VSF-9 feeder breaker is trip free. Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in responseto chlorine. Determine all additional applicable Unit 2 Tech Specs/TRM associated with Controlroom ventilation. Include any applicable instrumentation TS/TRM and required actionsfor the given plant conditions.Applicable Tech Specs: 3.7.6.1 action j, and 3.0.3 (directed by 3.7.6.1 action e).Most restrictive Required Action:Action j:With both CREVS inoperable or with one more CREVS inoperable due to an inoperableCRE boundary, immediately suspend all activities involving the handling or irradiated fuel.
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-ANO-2-JPM-NRC-ADMIN-CREVSTS     Page  5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS
+SATISFACTORY:                     UNSATISFACTORY:
-: Unit 1 is in Mode 6 for a refueling outage and currently de-fueled. Unit 2 is in Mode 1. Unit 2 is loading a dry fuel cask. VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55bus outage. Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pumpfailure.INITIATING CUE: The CBOT discovers that 2VSF-9 feeder breaker is trip free. Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in responseto chlorine. Determine all additional applicable Unit 2 Tech Specs/TRM associated with Controlroom ventilation. Include any applicable instrumentation TS/TRM and required actionsfor the given plant conditions.Applicable Tech Specs: __________________________________________________Most restrictive Required Action:________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________
+PERFORMANCE CHECKLIST COMMENTS:
-ANO-2-JPM-NRC-ADMIN-KI     Page  1 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 002DATE:SYSTEM/DUTY AREA:   Radiation ControlsTASK:    Approve administration of Potassium Iodide.JTA#: ANO-SRO-EPLAN-EMERG-292KA VALUE RO:3.4SRO:3.8KA
+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-ADMIN-CREVSTS                                                    Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
+Unit 1 is in Mode 6 for a refueling outage and currently de-fueled.
+Unit 2 is in Mode 1.
+Unit 2 is loading a dry fuel cask.
+VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55 bus outage.
+Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pump failure.
+TASK STANDARD: Determined that 3.0.3 is applicable. Determined that TS 3.7.6.1 action j is also applicable requiring immediately suspending handling of irradiated fuel.
+TASK PERFORMANCE AIDS: OP 2104.007, Control Room Emergency Ventilation, Unit 2 Tech Specs.
+ANO-2-JPM-NRC-ADMIN-CREVSTS                                                                  Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:
+The CBOT discovers that 2VSF-9 feeder breaker is trip free.
+Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.
+Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Include any applicable instrumentation TS/TRM and required actions for the given plant conditions.
+START TIME:
+PERFORMANCE CHECKLIST                               STANDARD                           (Circle One)
+N/A SAT UNSAT
+: 1. Review OP 2104.007                     Examinee reviewed the control attachment B and C, Control            room ventilation procedure Room Emergency Ventilation             and Tech Specs.
+and TS 3.7.6.1.
+N/A SAT UNSAT
+: 2. Using attachment C of                  Examinee determined that 2104.007 determine that TRM            TRM entry is not required for entry is not required for the          chlorine monitors that are inoperable chlorine monitors.          inoperable.
+N/A SAT UNSAT (C)    3. Using TS and 2104.007                  Examinee determined that TS determine applicable TS                3.0.3 and TS 3.7.6.1 action j actions.                               are applicable.
+Examiner Note: The candidate may indicate TS 3.7.6.1 action e is applicable, but is not required. TS 3.7.6.1 action e states to apply the action of TS 3.0.3 N/A SAT UNSAT (C) 4. Determine most restrictive                Determined the following required action IAW TS.                actions:
+Immediately suspend handling of irradiated fuel (action J)
+END STOP TIME:
+ANO-2-JPM-NRC-ADMIN-CREVSTS                                                    Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+Unit 1 is in Mode 6 for a refueling outage and currently de-fueled.
+Unit 2 is in Mode 1.
+Unit 2 is loading a dry fuel cask.
+VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55 bus outage.
+Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pump failure.
+INITIATING CUE:
+The CBOT discovers that 2VSF-9 feeder breaker is trip free.
+Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.
+Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Include any applicable instrumentation TS/TRM and required actions for the given plant conditions.
+Applicable Tech Specs: 3.7.6.1 action j, and 3.0.3 (directed by 3.7.6.1 action e).
+Most restrictive Required Action:
+Action j:
+With both CREVS inoperable or with one more CREVS inoperable due to an inoperable CRE boundary, immediately suspend all activities involving the handling or irradiated fuel.
+ANO-2-JPM-NRC-ADMIN-CREVSTS                                                  Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+Unit 1 is in Mode 6 for a refueling outage and currently de-fueled.
+Unit 2 is in Mode 1.
+Unit 2 is loading a dry fuel cask.
+VSF-9 Unit 1 Emergency Filter/Fan is tagged out to align power from Unit 2 for a B55 bus outage.
+Chlorine Detector 2CLS-8761-1 is inoperable and bypassed due to sample pump failure.
+INITIATING CUE:
+The CBOT discovers that 2VSF-9 feeder breaker is trip free.
+Also, I&C reports that 2CLS-8762-2 is inoperable because it will not actuate in response to chlorine.
+Determine all additional applicable Unit 2 Tech Specs/TRM associated with Control room ventilation. Include any applicable instrumentation TS/TRM and required actions for the given plant conditions.
+Applicable Tech Specs: __________________________________________________
+Most restrictive Required Action:
+________________________________________________________________________
+________________________________________________________________________
+________________________________________________________________________
+________________________________________________________________________
+________________________________________________________________________
+ANO-2-JPM-NRC-ADMIN-KI                                                             Page 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT:      2                      REV #:    002                      DATE:
+SYSTEM/DUTY AREA:         Radiation Controls TASK:       Approve administration of Potassium Iodide.
+JTA#:     ANO-SRO-EPLAN-EMERG-292 KA VALUE       RO:        3.4      SRO:          3.8        KA
 ==REFERENCE:==
-.3.14APPROVED FOR ADMINISTRATION TO:
+.3.14 APPROVED FOR ADMINISTRATION TO:            RO:              SRO:    X TASK LOCATION:           INSIDE CR:               OUTSIDE CR:             BOTH:        X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 MinutesREFERENCE(S): 1903.035, Administration of Potassium IodideEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+PLANT SITE:                       SIMULATOR:           Perform       CLASSROOM:     Perform POSITION EVALUATED:        RO:                     SRO:
-ANO-2-JPM-NRC-ADMIN-KI     Page  2 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS
+ACTUAL TESTING ENVIRONMENT:         SIMULATOR:              PLANT SITE:         CLASSROOM:
-: The plant is tripped from 100% power. 300 gpm LOCA in progress. Loss of Offsite power is in progress. LOCA EOP is being implemented. RDACS indicates an off site release in progress. Data indicates I-131 concentration of 8.0 E-05ci/cc in area of work in Upper SouthPiping Penetration room. Whole body dose rates in area of work are 1Rem/hr. Site Area Emergency has been declared. RP estimates that it will take approximately 15 minutes to complete emergency actionsand stop the release and all RP required controls/authorizations are complete. Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodideif required. Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will beused in place of a SCBA due to piping interference. EOF, OSC and TSC have NOT been staffed.TASK STANDARD: Determine that KI should be administered.TASK PERFORMANCE AIDS: OP 1903.0035, Potassium Iodide Administration,completed form 1903.035C, ANO Medical Questionnaire-Iodine Sensitivity and 1903.035A,Potassium Iodide Administration.
+TESTING METHOD:        SIMULATE:               PERFORM:
-ANO-2-JPM-NRC-ADMIN-KI     Page  3 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:  Determine if KI, Potassium Iodide should be issued and complete necessary paperwork,using OP 1903.035.
+APPROXIMATE COMPLETION TIME IN MINUTES:                  20 Minutes REFERENCE(S):      1903.035, Administration of Potassium Iodide EXAMINEE'S NAME:                                                 Badge #:
-START TIME:Examiner Note: Provide the examinee a blank KI Administration Form 1903.035A and aMedical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completed byJoe MechanicPERFORMANCE CHECKLIST STANDARD(Circle One)1. Review OP 1903.035,Administration of PotassiumIodide to determine criteria foradministering KI.Examinee determined thecriteria for administration of KIis 10 REM exposure to thyroidcommitted dose equivalent orif concentration is unknown,the possibility exists forreceiving large amounts ofradioactive airborne iodine.N/A  SAT  UNSAT (C)2. Using graph on 1903.035Attachment 1 and informationprovided in initial conditions,determine that Joe Mechanicwill exceed 10 REM duringthe maintenance evolution.Determined that expectedexposure will exceed 10 REMthreshold.N/A  SAT  UNSAT3. Complete form 1903.035A.Completed all areas of form1903.035A, Potassium IodideAdministration, from initial conditions: Estimated Thyroid dosecommitment. Date. Respiratory protection. Signature of Joe Mechanicthat he chooses to receive KI.N/A  SAT  UNSAT ANO-2-JPM-NRC-ADMIN-KI     Page  4 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREExaminer Note: Provide the examinee a blank KI Administration Form 1903.035A and aMedical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completed byJoe MechanicPERFORMANCE CHECKLIST STANDARD(Circle One)(C)4. Determine that Joe Mechanicis not sensitive to norexperienced an allergicreaction to Iodide.Reviewed 1903.035C formand determined that JoeMechanic was not sensitive tonor experienced an allergicreaction to Iodide.N/A  SAT  UNSAT (C)5. Determine that KI may beapproved for distribution toJoe Mechanic during theUpper South Pipingpenetration work.Examinee approveddistribution of KI to JoeMechanic by signing anddating form.N/A  SAT  UNSAT ENDSTOP TIME:
+EVALUATOR'S NAME:
-ANO-2-JPM-NRC-ADMIN-KI     Page  5 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-: The plant is tripped from 100% power. 300 gpm LOCA in progress. Loss of Offsite power is in progress. LOCA EOP is being implemented. RDACS indicates an off site release in progress. Data indicates I-131 concentration of 8.0 E-05ci/cc in area of work in Upper SouthPiping Penetration room. Whole body dose rates in area of work are 1Rem/hr. Site Area Emergency has been declared. RP estimates that it will take approximately 15 minutes to complete emergency actionsand stop the release and all RP required controls/authorizations are complete. Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodideif required. Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will beused in place of a SCBA due to piping interference. EOF, OSC and TSC have NOT been staffed.INITIATING CUE:Determine if KI, Potassium Iodide should be issued and complete necessary paperwork,using OP 1903.035.
+SATISFACTORY:                     UNSATISFACTORY:
-ANO-2-JPM-NRC-ADMIN-KI     Page  6 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS
+PERFORMANCE CHECKLIST COMMENTS:
-: The plant is tripped from 100% power. 300 gpm LOCA in progress. Loss of Offsite power is in progress. LOCA EOP is being implemented. RDACS indicates an off site release in progress. Data indicates I-131 concentration of 8.0 E-05ci/cc in area of work in Upper SouthPiping Penetration room. Whole body dose rates in area of work are 1Rem/hr. Site Area Emergency has been declared. RP estimates that it will take approximately 15 minutes to complete emergency actionsand stop the release and all RP required controls/authorizations are complete. Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodideif required. Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will beused in place of a SCBA due to piping interference. EOF, OSC and TSC have NOT been staffed.INITIATING CUE:Determine if KI, Potassium Iodide should be issued and complete necessary paperwork,using OP 1903.035.
+Start Time            Stop Time               Total Time SIGNED:                                              DATE:
-Page 14 of 16 Potassium Iodide (KI) Administration Form Name of Exposed Individual: , ,  Last First Middle Badge Number:
+SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
-Duration of Exposure:  I-131 Concentration:  Minutes Ci/cc in air Estimated Thyroid Dose Commitment:
-Rem  10 Rem  Unknown, large exposure possible General Emergency Declared Date of Exposure:
+ANO-2-JPM-NRC-ADMIN-KI                                                          Page 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM INITIAL TASK CONDITIONS:
-Respiratory Protection Worn During Exposure:
+The plant is tripped from 100% power.
-Yes No Respirator Protection Factor:
+gpm LOCA in progress.
-Known Iodide Allergy/Previous Allergic Reaction to iodide:
+Loss of Offsite power is in progress.
-Yes  No CAUTION If the above box is checked yes, then DO NOT administer Potassium Iodide.
+LOCA EOP is being implemented.
+RDACS indicates an off site release in progress.
+Data indicates I-131 concentration of 8.0 E-05 ci/cc in area of work in Upper South Piping Penetration room.
+Whole body dose rates in area of work are 1Rem/hr.
+Site Area Emergency has been declared.
+RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.
+Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodide if required.
+Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.
+EOF, OSC and TSC have NOT been staffed.
+TASK STANDARD: Determine that KI should be administered.
+TASK PERFORMANCE AIDS: OP 1903.0035, Potassium Iodide Administration, completed form 1903.035C, ANO Medical Questionnaire-Iodine Sensitivity and 1903.035A, Potassium Iodide Administration.
+ANO-2-JPM-NRC-ADMIN-KI                                                                Page 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE: Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.
+START TIME:
+Examiner Note: Provide the examinee a blank KI Administration Form 1903.035A and a Medical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completed by Joe Mechanic PERFORMANCE CHECKLIST                             STANDARD                      (Circle One)
+N/A SAT UNSAT
+: 1. Review OP 1903.035,                  Examinee determined the Administration of Potassium          criteria for administration of KI Iodide to determine criteria for     is 10 REM exposure to thyroid administering KI.                    committed dose equivalent or if concentration is unknown, the possibility exists for receiving large amounts of radioactive airborne iodine.
+N/A SAT UNSAT (C)   2. Using graph on 1903.035              Determined that expected Attachment 1 and information         exposure will exceed 10 REM provided in initial conditions,      threshold.
+determine that Joe Mechanic will exceed 10 REM during the maintenance evolution.
+N/A SAT UNSAT
+: 3. Complete form 1903.035A.             Completed all areas of form 1903.035A, Potassium Iodide Administration, from initial conditions:
+Estimated Thyroid dose commitment.
+Date.
+Respiratory protection.
+Signature of Joe Mechanic that he chooses to receive KI.
+ANO-2-JPM-NRC-ADMIN-KI                                                    Page 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE Examiner Note: Provide the examinee a blank KI Administration Form 1903.035A and a Medical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completed by Joe Mechanic PERFORMANCE CHECKLIST                          STANDARD              (Circle One)
+N/A SAT UNSAT (C)   4. Determine that Joe Mechanic       Reviewed 1903.035C form is not sensitive to nor           and determined that Joe experienced an allergic           Mechanic was not sensitive to reaction to Iodide.               nor experienced an allergic reaction to Iodide.
+N/A SAT UNSAT (C)      5. Determine that KI may be       Examinee approved approved for distribution to  distribution of KI to Joe Joe Mechanic during the       Mechanic by signing and Upper South Piping            dating form.
+penetration work.
+END STOP TIME:
+ANO-2-JPM-NRC-ADMIN-KI                                                          Page 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+The plant is tripped from 100% power.
+gpm LOCA in progress.
+Loss of Offsite power is in progress.
+LOCA EOP is being implemented.
+RDACS indicates an off site release in progress.
+Data indicates I-131 concentration of 8.0 E-05 ci/cc in area of work in Upper South Piping Penetration room.
+Whole body dose rates in area of work are 1Rem/hr.
+Site Area Emergency has been declared.
+RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.
+Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodide if required.
+Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.
+EOF, OSC and TSC have NOT been staffed.
+INITIATING CUE:
+Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.
+ANO-2-JPM-NRC-ADMIN-KI                                                          Page 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+The plant is tripped from 100% power.
+gpm LOCA in progress.
+Loss of Offsite power is in progress.
+LOCA EOP is being implemented.
+RDACS indicates an off site release in progress.
+Data indicates I-131 concentration of 8.0 E-05 ci/cc in area of work in Upper South Piping Penetration room.
+Whole body dose rates in area of work are 1Rem/hr.
+Site Area Emergency has been declared.
+RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.
+Joe Mechanic has read the precaution leaflet and has chosen to take Potassium Iodide if required.
+Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.
+EOF, OSC and TSC have NOT been staffed.
+INITIATING CUE:
+Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.
+Page 14 of 16 Potassium Iodide (KI) Administration Form Name of Exposed Individual:                         ,                  ,
+Last                 First           Middle Badge Number:
+Duration of Exposure:                            I-131 Concentration:
+Minutes                                   Ci/cc in air Estimated Thyroid Dose Commitment:                      10 Rem         10 Rem Unknown, large exposure possible General Emergency Declared Date of Exposure:
+Respiratory Protection Worn During Exposure:                         Yes      No Respirator Protection Factor:
+Known Iodide Allergy/Previous Allergic Reaction to iodide:           Yes     No CAUTION If the above box is checked yes, then DO NOT administer Potassium Iodide.
 I verify that I have read and understand the precaution leaflet and I understand that taking thyroid blocking agent (KI) is strictly voluntary.
-I choose  do not choose to take KI. Signature of Exposed Individual Date Approved:Shift Manager/EOF Director/TSC Director Date Check if approval is via telecom.
+I         choose         do not choose to take KI.
-KI Issued By: Signature Date Notes:FORM TITLE:POTASSIUM IODIDE ADMINISTRATION CHANGE:.1903.035AREV.011
+Signature of Exposed Individual                               Date Approved:
+Shift Manager/EOF Director/TSC Director                      Date Check if approval is via telecom.
+KI Issued By:
+Signature                                   Date Notes:
+FORM TITLE:                                                         CHANGE:.        REV.
+POTASSIUM IODIDE ADMINISTRATION                    1903.035A         011
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE    1   of   5 UNIT: 2 REV#: 001 DATE:SYSTEM/DUTY AREA: Emergency PlanTASK: Determine Emergency Action Level for given conditions. (Time Critical JPM)JTA#: ANO-SRO-EPLAN-EMERG-278KA VALUE RO:
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11            REV      01                                      PAGE 1 of 5 UNIT:      2                       REV #:     001                         DATE:
-.9SRO: 4.6KA
+SYSTEM/DUTY AREA:         Emergency Plan TASK:     Determine Emergency Action Level for given conditions. (Time Critical JPM)
+JTA#:     ANO-SRO-EPLAN-EMERG-278 KA VALUE       RO:         2.9      SRO:           4.6        KA
 ==REFERENCE:==
-.4.41APPROVED FOR ADMINISTRATION TO: RO:SRO: XTASK LOCATION:
+.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):
-INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR: PerformCLASSROOM:PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD: SIMULATE
+PLANT SITE:                       SIMULATOR:         Perform         CLASSROOM:          Perform POSITION EVALUATED:         RO:                      SRO:
-:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES: 5 Minutes - Read initial Conditions15 Minutes - EAL ClassificationREFERENCE(S): 1903.010EXAMINEE'S NAME:BADGE:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED: DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+ACTUAL TESTING ENVIRONMENT:            SIMULATOR:               PLANT SITE:          CLASSROOM:
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE    2   of   5THE 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 theexaminee.JPM INITIAL TASK CONDITIONS
+TESTING METHOD:         SIMULATE                 PERFORM:
-:Unit 2 has been operating at 100% for 230 consecutive days.A plant trip has occurred due to a loss of offsite power with a concurrent Loss of CoolantAccident estimated to be 1500 gpm.[[estimated NRC review hours::4 hours]] following the trip, High Range containment radiation monitors read 74450 R/hr and77730 R/hr respectively.RCS average Core Exit Thermocouples are reading 430&deg;FPZR pressure is 325 psiaContainment Pressure is 20 psia and slowly trending downRDACs indicates NO offsite release in progressAll safety systems are responding as designedTASK STANDARD: Determine the following ( Time Critical - 5 minutes to read initial conditions/ 15minutes to classify event):
+:
-.Determine containment radiation is at GE level 2.Determine EAL classification GE, 1.5,  Containment Radiation readings which indicate LOCAand >50% fuel overheatTASK PERFORMANCE AIDS: 1903.010, Emergency Action Levels JOB PERFORMANCE MEASUREANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE    3   of   5INITIATING CUE:Determine the highest EAL classification from the given initial conditions (list EAL classification event number).
+APPROXIMATE COMPLETION TIME IN MINUTES:                 5 Minutes - Read initial Conditions 15 Minutes - EAL Classification REFERENCE(S):      1903.010 EXAMINEE'S NAME:                                                     BADGE
-.START:PERFORMANCECHECKLISTSTANDARD(Circle One) 1.Determined containmentradiation readings are notmodified due to powerhistory.Using OP 1903.010 Attachment6, verified power history does notrequire modifying containmentradiation readings.N/A  SAT  UNSAT (C)2.Determined containmentradiation is GE levelUsing OP 1903.010 Attachment6, determined containmentradiation readings the GE criteria.(critical element verified byclassifying EAL as event 1.5)N/A  SAT  UNSAT (C)3.Determined GE EALclassification.Using OP 1903.010, determinedGE EAL classification 1.5,Containment Radiation readingswhich indicate LOCA and >50%fuel overheatN/A  SAT  UNSAT(C) 4. JPM complete in 15minutes.JPM complete in 15 minutes with5 minutes to read conditions.N/A  SAT  UNSAT ENDSTOP:
+:
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE    4   of   5Examiner's CopyJPM is TIME CRITICALJPM INITIAL TASK CONDITIONS
+EVALUATOR'S NAME:
-:Unit 2 has been operating at 100% for 230 consecutive days.A plant trip has occurred due to a loss of offsite power with a concurrent Loss of CoolantAccident estimated to be 1500 gpm.[[estimated NRC review hours::4 hours]] following the trip, High Range containment radiation monitors read 74,450 R/hr and77,730 R/hr respectively and trending up.RCS average Core Exit Thermocouples are reading 430&deg;FPZR pressure is 325 psiaContainment Pressure is 20 psia and slowly trending downRDACs indicates NO offsite release in progressAll safety systems are responding as designedINITIATING CUE:Determine the highest EAL classification from the given initial conditions (list EAL classification eventnumber).ANSWER:EAL classification and event number:GE, EAL1.5, Containment Radiation readingswhich indicate LOCA and >50% fuel overheat JOB PERFORMANCE MEASUREANO-2-JPM-NRC-ADMIN-EAL11 REV 01 PAGE    5   of   5Examinee's CopyJPM is TIME CRITICALJPM INITIAL TASK CONDITIONS
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-:Unit 2 has been operating at 100% for 230 consecutive days.A plant trip has occurred due to a loss of offsite power with a concurrent Loss of CoolantAccident estimated to be 1500 gpm.[[estimated NRC review hours::4 hours]] following the trip, High Range containment radiation monitors read 74,450 R/hr and77,730 R/hr respectively and trending up.RCS average Core Exit Thermocouples are reading 430&deg;FPZR pressure is 325 psiaContainment Pressure is 20 psia and slowly trending downRDACs indicates NO offsite release in progressAll safety systems are responding as designedINITIATING CUE:Determine the highest EAL classification from the given initial conditions (list EAL classification eventnumber).ANSWER:EAL classification and event number:
+SATISFACTORY:                      UNSATISFACTORY:
-Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility:  Arkansas Nuclear One Unit 2                                         Date of Examination:  01/28/2011Exam Level:  RO X      SRO-I      SRO-UOperating Test No.:   2011-1Control Room Systems
+PERFORMANCE CHECKLIST COMMENTS:
-@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-AOP3010 A2.02 RO-3.9/SRO-3.9Isolate failed PZR spray valveA/N/S 3Pressure Control S2.ANO-2-JPM-NRC-SIT08006 A1.13 RO-3.5/SRO-3.7Lower SIT levelD/EN/S 2Inventory Control S3.ANO-2-JPM-NRC-EDG06064 A4.06 RO-3.9/SRO-3.9Align 2A-2 to 2A-4D/S 6ElectricalS4.ANO-2-JPM-NRC-CEA02012 A4.06 RO-4.3/SRO-4.3Test a Reactor Trip Circuit BreakerD/S 7Instrumentation S5.ANO-2-JPM-NRC-CEA01001 A4.03 RO-4.0/SRO-3.7Perform a CEA exerciseD/S 1Reactivity control S6.ANO-2-JPM-NRC-CNMT2103 A3.01 RO-3.9/SRO-4.2Drain the containment sumpA/N/S 5ContainmentIntegrity S7.ANO-2-JPM-NRC-RCP02003 A4.08 RO-3.2/SRO-2.9Restore CCW to RCPsA/D/L/S 4Heat Removal S8.ANO-2-JPM-NRC-CCW02008 A4.01 RO-3.3/SRO-3.1Shift running CCW pumps P/S 8Plant servicesystemsIn-Plant Systems
+Start Time             Stop Time                Total Time SIGNED:                                                DATE:
-@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
+SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
-P1.ANO-2-JPM-NRC-AACLS064 A4.01 RO-4.0/SRO-4.3Start up AAC diesel generator manually locally during a LOOPA/P/E/L 6ElectricalP2.ANO-2-JPM-NRC-AUADV041 A4.08 RO-3.0/SRO-3.1Operate SDBCS valves locallyD/E/L 4Heat RemovalP3.ANO-2-JPM-NRC-SFPAW033 A2.03 RO-3.1/SRO-3.5Fill SFP from RWTD/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -   /   1 (control room system) 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility:  Arkansas Nuclear One Unit 2Date of Examination:  01/28/2011Exam Level:  RO      SRO-I X      SRO-UOperating Test No.:   2011-1Control Room Systems
-@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-AOP3010 A2.02 RO-3.9/SRO-3.9Isolate failed PZR spray valveA/N/S 3Pressure Control S2.ANO-2-JPM-NRC-SIT08006 A1.13 RO-3.5/SRO-3.7Lower SIT levelD/EN/S 2Inventory Control S3.ANO-2-JPM-NRC-EDG06064 A4.06 RO-3.9/SRO-3.9Align 2A-2 to 2A-4D/S 6ElectricalS4.ANO-2-JPM-NRC-CEA02012 A4.06 RO-4.3/SRO-4.3Test a Reactor Trip Circuit BreakerD/S 7Instrumentation S5.ANO-2-JPM-NRC-CEA01001 A4.03 RO-4.0/SRO-3.7Perform a CEA exerciseD/S 1Reactivity control S6.ANO-2-JPM-NRC-CNMT2103 A3.01 RO-3.9/SRO-4.2Drain the containment sumpA/N/S 5ContainmentIntegrity S7.ANO-2-JPM-NRC-RCP02003 A4.08 RO-3.2/SRO-2.9Restore CCW to RCPsA/D/L/S 4Heat Removal S8.In-Plant Systems
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11                 REV        01                                     PAGE 2 of 5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
-@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
+The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.
-P1.ANO-2-JPM-NRC-AACLS064 A4.01 RO-4.0/SRO-4.3Start up AAC diesel generator manually locally during a LOOPA/P/E/L 6ElectricalP2.ANO-2-JPM-NRC-AUADV041 A4.08 RO-3.0/SRO-3.1Operate SDBCS valves locallyD/E/L 4Heat RemovalP3.ANO-2-JPM-NRC-SFPAW033 A2.03 RO-3.1/SRO-3.5Fill SFP from RWTD/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -   /   1 (control room system) 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility:  Arkansas Nuclear One Unit 2Date of Examination:  01/28/2011Exam Level:  RO      SRO-I      SRO-U  XOperating Test No.:   2011-1Control Room Systems
+JPM INITIAL TASK CONDITIONS:
-@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-AOP3010 A2.02 RO-3.9/SRO-3.9Isolate failed PZR spray valveA/N/S 3Pressure Control S2.ANO-2-JPM-NRC-SIT08006 A1.13 RO-3.5/SRO-3.7Lower SIT levelD/EN/S 2Inventory ControlIn-Plant Systems
+Unit 2 has been operating at 100% for 230 consecutive days.
-@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
+A plant trip has occurred due to a loss of offsite power with a concurrent Loss of Coolant Accident estimated to be 1500 gpm.
-P1.ANO-2-JPM-NRC-AACLS064 A4.01 RO-4.0/SRO-4.3Start up AAC diesel generator manually locally during a LOOPA/P/E/L 6ElectricalP2.ANO-2-JPM-NRC-AUADV041 A4.08 RO-3.0/SRO-3.1Operate SDBCS valves locallyD/E/L 4Heat RemovalP3.ANO-2-JPM-NRC-SFPAW033 A2.03 RO-3.1/SRO-3.5Fill SFP from RWTD/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -   /   1 (control room system) 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 ANO-2-JPM-NRC-AOP3PAGE  1  OF  6JOB PERFORMANCE MEASUREUNIT: 2 REV#: 000DATE:SYSTEM/DUTY AREA:Pressurizer Spray operationTASK:Isolate failed open Pressurizer Spray valve.  (Alternate Success Path)JTA#: ANO2-RO-EOPAOP-OFFNORM-181KA VALUERO:3.9SRO:3.9KA
+[[estimated NRC review hours::4 hours]] following the trip, High Range containment radiation monitors read 74450 R/hr and 77730 R/hr respectively.
+RCS average Core Exit Thermocouples are reading 430&deg;F PZR pressure is 325 psia Containment Pressure is 20 psia and slowly trending down RDACs indicates NO offsite release in progress All safety systems are responding as designed TASK STANDARD: Determine the following ( Time Critical - 5 minutes to read initial conditions/ 15 minutes to classify event):
+: 1. Determine containment radiation is at GE level
+: 2. Determine EAL classification GE, 1.5, Containment Radiation readings which indicate LOCA and >50% fuel overheat TASK PERFORMANCE AIDS: 1903.010, Emergency Action Levels
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11                REV      01                                            PAGE 3 of 5 INITIATING CUE:
+Determine the highest EAL classification from the given initial conditions (list EAL classification event number).
+.
+START:
+PERFORMANCE                                 STANDARD                             (Circle One)
+CHECKLIST N/A SAT UNSAT
+: 1.       Determined containment            Using OP 1903.010 Attachment radiation readings are not        6, verified power history does not modified due to power             require modifying containment history.                          radiation readings.
+N/A SAT UNSAT (C)   2.       Determined containment            Using OP 1903.010 Attachment radiation is GE level             6, determined containment radiation readings the GE criteria.
+(critical element verified by classifying EAL as event 1.5)
+: 3.      Determined GE EAL                   Using OP 1903.010, determined                 N/A SAT UNSAT (C)           classification.                     GE EAL classification 1.5, Containment Radiation readings which indicate LOCA and >50%
+fuel overheat (C)     4. JPM complete in 15                 JPM complete in 15 minutes with               N/A SAT UNSAT minutes.                           5 minutes to read conditions.
+END STOP:
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11            REV      01                                    PAGE 4 of 5 Examiners Copy JPM is TIME CRITICAL JPM INITIAL TASK CONDITIONS:
+Unit 2 has been operating at 100% for 230 consecutive days.
+A plant trip has occurred due to a loss of offsite power with a concurrent Loss of Coolant Accident estimated to be 1500 gpm.
+[[estimated NRC review hours::4 hours]] following the trip, High Range containment radiation monitors read 74,450 R/hr and 77,730 R/hr respectively and trending up.
+RCS average Core Exit Thermocouples are reading 430&deg;F PZR pressure is 325 psia Containment Pressure is 20 psia and slowly trending down RDACs indicates NO offsite release in progress All safety systems are responding as designed INITIATING CUE:
+Determine the highest EAL classification from the given initial conditions (list EAL classification event number).
+ANSWER:
+EAL classification and event number:       GE, EAL 1.5, Containment Radiation readings which indicate LOCA and >50% fuel overheat
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-ADMIN-EAL11            REV      01                                    PAGE 5 of 5 Examinees Copy JPM is TIME CRITICAL JPM INITIAL TASK CONDITIONS:
+Unit 2 has been operating at 100% for 230 consecutive days.
+A plant trip has occurred due to a loss of offsite power with a concurrent Loss of Coolant Accident estimated to be 1500 gpm.
+[[estimated NRC review hours::4 hours]] following the trip, High Range containment radiation monitors read 74,450 R/hr and 77,730 R/hr respectively and trending up.
+RCS average Core Exit Thermocouples are reading 430&deg;F PZR pressure is 325 psia Containment Pressure is 20 psia and slowly trending down RDACs indicates NO offsite release in progress All safety systems are responding as designed INITIATING CUE:
+Determine the highest EAL classification from the given initial conditions (list EAL classification event number).
+ANSWER:
+EAL classification and event number:
+ES-301                                Control Room/In-Plant Systems Outline                         Form ES-301-2 Facility: Arkansas Nuclear One Unit 2                                    Date of Examination: 01/28/2011 Exam Level: RO X               SRO-I           SRO-U                     Operating Test No.: 2011-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
+System / JPM Title                                Type Code*             Safety Function S1. ANO-2-JPM-NRC-AOP3                                                                                      3 010 A2.02 RO-3.9/SRO-3.9                                                         A/N/S         Pressure Control Isolate failed PZR spray valve S2. ANO-2-JPM-NRC-SIT08                                                                                     2 006 A1.13 RO-3.5/SRO-3.7                                                        D/EN/S         Inventory Control Lower SIT level S3. ANO-2-JPM-NRC-EDG06                                                                                     6 064 A4.06 RO-3.9/SRO-3.9                                                          D/S               Electrical Align 2A-2 to 2A-4 S4. ANO-2-JPM-NRC-CEA02                                                                                     7 012 A4.06 RO-4.3/SRO-4.3                                                          D/S           Instrumentation Test a Reactor Trip Circuit Breaker S5. ANO-2-JPM-NRC-CEA01                                                                                     1 001 A4.03 RO-4.0/SRO-3.7                                                          D/S          Reactivity control Perform a CEA exercise S6. ANO-2-JPM-NRC-CNMT2                                                                                     5 103 A3.01 RO-3.9/SRO-4.2 Drain the containment sump A/N/S            Containment Integrity S7. ANO-2-JPM-NRC-RCP02                                                                                     4 003 A4.08 RO-3.2/SRO-2.9                                                        A/D/L/S          Heat Removal Restore CCW to RCPs S8. ANO-2-JPM-NRC-CCW02                                                                                     8 008 A4.01 RO-3.3/SRO-3.1                                                          P/S Plant service Shift running CCW pumps                                                                             systems In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
+P1. ANO-2-JPM-NRC-AACLS                                                                                     6 064 A4.01 RO-4.0/SRO-4.3                                                        A/P/E/L Electrical Start up AAC diesel generator manually locally during a LOOP P2. ANO-2-JPM-NRC-AUADV                                                                                     4 041 A4.08 RO-3.0/SRO-3.1                                                         D/E/L           Heat Removal Operate SDBCS valves locally P3. ANO-2-JPM-NRC-SFPAW                                                                                     8 033 A2.03 RO-3.1/SRO-3.5                                                          D/R             Plant service Fill SFP from RWT systems
+ @           All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
+* Type Codes                                  Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                                 9/ 8/ 4 (E)mergency or abnormal in-plant                                                   1/ 1/ 1 (EN)gineered safety feature                                                       - / - / 1 (control room system)
+(L)ow-Power / Shutdown                                                             1/ 1/ 1 (N)ew or (M)odified from bank including 1(A)                                       2/ 2/ 1 (P)revious 2 exams                                                                 3 / 3 / 2 (randomly selected)
+(R)CA                                                                              1/ 1/ 1 (S)imulator Revision 0
+ES-301                                Control Room/In-Plant Systems Outline                         Form ES-301-2 Facility: Arkansas Nuclear One Unit 2                                    Date of Examination: 01/28/2011 Exam Level: RO                   SRO-I X       SRO-U                     Operating Test No.: 2011-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
+System / JPM Title                                Type Code*             Safety Function S1. ANO-2-JPM-NRC-AOP3                                                                                      3 010 A2.02 RO-3.9/SRO-3.9                                                         A/N/S         Pressure Control Isolate failed PZR spray valve S2. ANO-2-JPM-NRC-SIT08                                                                                     2 006 A1.13 RO-3.5/SRO-3.7                                                        D/EN/S         Inventory Control Lower SIT level S3. ANO-2-JPM-NRC-EDG06                                                                                     6 064 A4.06 RO-3.9/SRO-3.9                                                          D/S               Electrical Align 2A-2 to 2A-4 S4. ANO-2-JPM-NRC-CEA02                                                                                     7 012 A4.06 RO-4.3/SRO-4.3                                                          D/S           Instrumentation Test a Reactor Trip Circuit Breaker S5. ANO-2-JPM-NRC-CEA01                                                                                     1 001 A4.03 RO-4.0/SRO-3.7                                                          D/S          Reactivity control Perform a CEA exercise S6. ANO-2-JPM-NRC-CNMT2                                                                                     5 103 A3.01 RO-3.9/SRO-4.2 Drain the containment sump A/N/S            Containment Integrity S7. ANO-2-JPM-NRC-RCP02                                                                                     4 003 A4.08 RO-3.2/SRO-2.9                                                        A/D/L/S          Heat Removal Restore CCW to RCPs S8.
+In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
+P1. ANO-2-JPM-NRC-AACLS                                                                                     6 064 A4.01 RO-4.0/SRO-4.3                                                        A/P/E/L Electrical Start up AAC diesel generator manually locally during a LOOP P2. ANO-2-JPM-NRC-AUADV                                                                                     4 041 A4.08 RO-3.0/SRO-3.1                                                         D/E/L           Heat Removal Operate SDBCS valves locally P3. ANO-2-JPM-NRC-SFPAW                                                                                     8 033 A2.03 RO-3.1/SRO-3.5                                                          D/R             Plant service Fill SFP from RWT systems
+ @           All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
+* Type Codes                                  Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                                 9/ 8/ 4 (E)mergency or abnormal in-plant                                                   1/ 1/ 1 (EN)gineered safety feature                                                       - / - / 1 (control room system)
+(L)ow-Power / Shutdown                                                             1/ 1/ 1 (N)ew or (M)odified from bank including 1(A)                                       2/ 2/ 1 (P)revious 2 exams                                                                 3 / 3 / 2 (randomly selected)
+(R)CA                                                                              1/ 1/ 1 (S)imulator Revision 0
+ES-301                                Control Room/In-Plant Systems Outline                         Form ES-301-2 Facility: Arkansas Nuclear One Unit 2                                    Date of Examination: 01/28/2011 Exam Level: RO                  SRO-I           SRO-U X                  Operating Test No.: 2011-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
+System / JPM Title                                 Type Code*            Safety Function S1. ANO-2-JPM-NRC-AOP3                                                                                     3 010 A2.02 RO-3.9/SRO-3.9                                                         A/N/S         Pressure Control Isolate failed PZR spray valve S2. ANO-2-JPM-NRC-SIT08                                                                                    2 006 A1.13 RO-3.5/SRO-3.7                                                        D/EN/S         Inventory Control Lower SIT level In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
+P1. ANO-2-JPM-NRC-AACLS                                                                                    6 064 A4.01 RO-4.0/SRO-4.3                                                        A/P/E/L Electrical Start up AAC diesel generator manually locally during a LOOP P2. ANO-2-JPM-NRC-AUADV                                                                                    4 041 A4.08 RO-3.0/SRO-3.1                                                         D/E/L           Heat Removal Operate SDBCS valves locally P3. ANO-2-JPM-NRC-SFPAW                                                                                    8 033 A2.03 RO-3.1/SRO-3.5                                                          D/R            Plant service Fill SFP from RWT systems
+ @           All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
+* Type Codes                                  Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                                 9/ 8/ 4 (E)mergency or abnormal in-plant                                                   1/ 1/ 1 (EN)gineered safety feature                                                       - / - / 1 (control room system)
+(L)ow-Power / Shutdown                                                             1/ 1/ 1 (N)ew or (M)odified from bank including 1(A)                                       2/ 2/ 1 (P)revious 2 exams                                                                 3 / 3 / 2 (randomly selected)
+(R)CA                                                                              1/ 1/ 1 (S)imulator Revision 0
+ANO-2-JPM-NRC-AOP3                                                         PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT:    2                      REV #:   000                    DATE:
+SYSTEM/DUTY AREA:       Pressurizer Spray operation TASK:   Isolate failed open Pressurizer Spray valve. (Alternate Success Path)
+JTA#:   ANO2-RO-EOPAOP-OFFNORM-181 KA VALUE     RO:         3.9     SRO:        3.9       KA
 ==REFERENCE:==
-A2.02APPROVED FOR ADMINISTRATION TO: RO:
+A2.02 APPROVED FOR ADMINISTRATION TO:        RO:        X    SRO:       X TASK LOCATION:          INSIDE CR:     X      OUTSIDE CR:              BOTH:
-XSRO: XTASK LOCATION:INSIDE CR:
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD: SIMULATE:
+PLANT SITE:                     SIMULATOR:     Perform          CLASSROOM:
-PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:6 MinutesREFERENCE(S): OP-2203.028 PZR System MalfunctionsEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+POSITION EVALUATED:       RO:                  SRO:
-ANO-2-JPM-NRC-AOP3PAGE  2  OF  6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D ofNUREG 1021 Appendix E.JPM INITIAL TASK CONDITIONS:2CV-4651 PZR spray valve failed open. Mode 1TASK STANDARD:Reactor tripped and 2P-32A secured.TASK PERFORMANCE AIDS:OP 2203.028 Step 2 SIMULATOR SETUP:All RCPs running. Mode 1CV4651 value = 1.Trigger1:  CV4656 value = .9, DO_HS_4656_G = off, & DO_HS_4656_R = offConditional trigger 1 set gh4g4656.Have all backup htrs on.
+ACTUAL TESTING ENVIRONMENT:        SIMULATOR:             PLANT SITE:      CLASSROOM:
-ANO-2-JPM-NRC-AOP3PAGE  3  OF  6JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions step 2"START TIME:EXAMINER NOTE:  Maintain the simulator in Freeze until the candidate is ready to start.PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C) 1.(Step 2 A)IF ANY PZR Spray valve failed open,THEN perform the following:A. Place affected PZR Sprayvalve in MANUAL and close:2CV-46512CV-4652On panel 2C04 placed PZRspray valve 2HS-4651B inmanualPlaced 2CV-4651 handswitch inclosed.Observed red and green lightsflash above handswitch and thered light remains on. N/A  SAT  UNSAT 2.(Step 2.B.1)IF affected PZR Spray valvedid NOT close, THEN performthe following:Place associated PZR Sprayvalve handswitch to OPEN for1 second:2CV-46512CV-4652.On panel 2C04, placedhandswitch for 2CV-4651 inopen for 1 sec.Observed red light ON abovehandswitch  N/A  SAT  UNSAT(C) 3.(Step 2.B.2)WHEN 5 seconds haveelapsed, THEN placehandswitch in CLOSE untilgreen indicating light flashes.On panel 2C04 and 5 sec haveelapsed, placed handswitch for2CV-4651 in close until lightsflash.Observed red and green lightsflash above handswitch and thered light remains on. N/A  SAT  UNSAT(C) 4.(Step 2.B.3)IF affected PZR Spray valvewill NOT close, THEN closeassociated energized Blockvalves:2CV-46552CV-4656On panel 2C04, placed 2CV-4655/2CV-4656 handswitch toclose.Observed 2CV-4656 lights outand PZR pressure lowering. N/A  SAT  UNSAT ANO-2-JPM-NRC-AOP3PAGE  4  OF  6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)EXAMINER'S NOTE:The following is the alternate path portion of this JPM 5.(Step2.B.4.a)IF associated energized PZRSpray Block valves will NOTclose,THEN perform the following:a) Verify ALL PZR heatersON.On panel 2C04, observed allPZR heater on as indicated byred lights above thehandswitches. N/A  SAT  UNSAT(C) 6.(Step 2.B.4.b.1)IF RCS pressure lowers to2000 psia,THEN perform the following:IF plant in mode 1 or 2, THENtrip Reactor.EXAMINER CUE:If desired to speed up JPMthen inform examinee thatRCS pressure is 2000 psia.When, RCS pressure isobserved at 2000 psia orinformed by evaluator RCS is2000 psia, tripped the reactor. N/A  SAT  UNSAT(C) 7.(Step 2.B.4.b.2)Stop RCP in loop with failedPZR Spray valve.Secured 2P-32A ReactorCoolant pump. N/A  SAT  UNSAT ENDSTOP TIME:
+TESTING METHOD:       SIMULATE:            PERFORM:
-ANO-2-JPM-NRC-AOP3PAGE  5  OF  6JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS:Mode 12CV-4651 PZR spray valve has failed open during boron equalization.INITIATING CUE:The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR systemmalfunctions starting with step 2".
+APPROXIMATE COMPLETION TIME IN MINUTES:            6 Minutes REFERENCE(S):    OP-2203.028 PZR System Malfunctions EXAMINEE'S NAME:                                            Badge #:
-ANO-2-JPM-NRC-AOP3PAGE  6  OF  6JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS:Mode 12CV-4651 PZR spray valve has failed open during boron equalization.INITIATING CUE:The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR systemmalfunctions starting with step 2".
+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                Stop                 Total Time Time                 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.
-INSTRUCTIONS CONTINGENCY ACTIONSPROC NO TITLE REVISION PAGE2203.028PZR SYSTEMS MALFUNCTION0103 of 102. IF ANY PZR Spray valve failed open,THEN perform the following:A. Place affected PZR Spray valve inMANUAL and close:* 2CV-4651* 2CV-4652(Step 2 continued on next page)
+ANO-2-JPM-NRC-AOP3                                                                   PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
-INSTRUCTIONS CONTINGENCY ACTIONSPROC NO TITLE REVISION PAGE2203.028PZR SYSTEMS MALFUNCTION0104 of 102. (continued)B. IF affected PZR Spray valve did NOTclose, THEN perform the following:1) Place associated PZR Spray valvehandswitch to OPEN for 1 second:* 2CV-4651* 2CV-46522) WHEN 5 seconds have elapsed,THEN place handswitch in CLOSEuntil green indicating light flashes.3) IF affected PZR Spray valve will NOTclose, THEN close associatedenergized Block valves:* 2CV-4655* 2CV-4656* 2CV-4653* 2CV-46544) IF associated energized PZR SprayBlock valves will NOT close,THEN perform the following:a) Verify ALL PZR heaters ON.b) IF RCS pressure lowers to2000 psia,THEN perform the following:1. IF plant in mode 1 or 2,THEN trip Reactor.2. Stop RCP in loop with failedPZR Spray valve.3.GOTO 2202.001, StandardPost Trip Actions.
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
-ANO-2-JPM-NRC-SIT008PAGE  1  OF 6JOB PERFORMANCE MEASUREUNIT: 2 REV#: 009DATE:SYSTEM/DUTY AREA:Safety Injection SystemTASK:Lower Safety Injection Tank level (2T2A)JTA#:ANO2-RO-ECCS-NORM-5KA VALUERO:3.5SRO:3.7KA
+JPM INITIAL TASK CONDITIONS:
+CV-4651 PZR spray valve failed open. Mode 1 TASK STANDARD:
+Reactor tripped and 2P-32A secured.
+TASK PERFORMANCE AIDS:
+OP 2203.028 Step 2 SIMULATOR SETUP:
+All RCPs running. Mode 1 CV4651 value = 1.
+Trigger1: CV4656 value = .9, DO_HS_4656_G = off, & DO_HS_4656_R = off Conditional trigger 1 set gh4g4656.
+Have all backup htrs on.
+ANO-2-JPM-NRC-AOP3                                                                     PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions step 2" START TIME:
+EXAMINER NOTE: Maintain the simulator in Freeze until the candidate is ready to start.
+PERFORMANCE CHECKLIST                              STANDARDS                  (Circle One)
+(C)   1.        IF ANY PZR Spray valve failed   On panel 2C04 placed PZR         N/A SAT UNSAT open,                           spray valve 2HS-4651B in (Step THEN perform the following:     manual 2 A)
+Placed 2CV-4651 handswitch in A. Place affected PZR Spray     closed.
+valve in MANUAL and close:
+* 2CV-4651               Observed red and green lights
+* 2CV-4652               flash above handswitch and the red light remains on.
+: 2.        IF affected PZR Spray valve     On panel 2C04, placed            N/A SAT UNSAT did NOT close, THEN perform     handswitch for 2CV-4651 in (Step the following:                  open for 1 sec.
+.B.1)
+Observed red light ON above Place associated PZR Spray      handswitch valve handswitch to OPEN for 1 second:
+* 2CV-4651
+* 2CV-4652
+                  .
+(C)   3.        WHEN 5 seconds have             On panel 2C04 and 5 sec have     N/A SAT UNSAT elapsed, THEN place             elapsed, placed handswitch for (Step handswitch in CLOSE until       2CV-4651 in close until lights 2.B.2)                                    flash.
+green indicating light flashes.
+Observed red and green lights flash above handswitch and the red light remains on.
+(C)   4.        IF affected PZR Spray valve     On panel 2C04, placed 2CV-       N/A SAT UNSAT will NOT close, THEN close      4655/2CV-4656 handswitch to (Step 2.B.3)    associated energized Block      close.
+valves:
+* 2CV-4655               Observed 2CV-4656 lights out and PZR pressure lowering.
+* 2CV-4656
+ANO-2-JPM-NRC-AOP3                                                                    PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                               STANDARDS                 (Circle One)
+EXAMINERS NOTE:
+The following is the alternate path portion of this JPM
+: 5.         IF associated energized PZR      On panel 2C04, observed all     N/A SAT UNSAT Spray Block valves will NOT      PZR heater on as indicated by (Step 2.B.4.a)   close,                           red lights above the THEN perform the following:      handswitches.
+a) Verify ALL PZR heaters ON.
+(C)   6.         IF RCS pressure lowers to        When, RCS pressure is           N/A SAT UNSAT 2000 psia,                       observed at 2000 psia or (Step 2.B.4.b.1) THEN perform the following:      informed by evaluator RCS is 2000 psia, tripped the reactor.
+IF plant in mode 1 or 2, THEN trip Reactor.
+EXAMINER CUE:
+If desired to speed up JPM then inform examinee that RCS pressure is 2000 psia.
+(C)   7.         Stop RCP in loop with failed     Secured 2P-32A Reactor          N/A SAT UNSAT PZR Spray valve.                 Coolant pump.
+(Step 2.B.4.b.2)
+END STOP TIME:
+ANO-2-JPM-NRC-AOP3                                                      PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:
+Mode 1 2CV-4651 PZR spray valve has failed open during boron equalization.
+INITIATING CUE:
+The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions starting with step 2".
+ANO-2-JPM-NRC-AOP3                                                      PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:
+Mode 1 2CV-4651 PZR spray valve has failed open during boron equalization.
+INITIATING CUE:
+The CRS directs, "Isolate PZR spray valve 2CV-4651 using 2203.028 PZR system malfunctions starting with step 2".
+INSTRUCTIONS                    CONTINGENCY ACTIONS
+: 2. IF ANY PZR Spray valve failed open, THEN perform the following:
+A. Place affected PZR Spray valve in MANUAL and close:
+* 2CV-4651
+* 2CV-4652 (Step 2 continued on next page)
+PROC NO                           TITLE               REVISION    PAGE 2203.028              PZR SYSTEMS MALFUNCTION         010       3 of 10
+INSTRUCTIONS                        CONTINGENCY ACTIONS
+: 2. (continued)
+B. IF affected PZR Spray valve did NOT close, THEN perform the following:
+: 1) Place associated PZR Spray valve handswitch to OPEN for 1 second:
+* 2CV-4651
+* 2CV-4652
+: 2) WHEN 5 seconds have elapsed, THEN place handswitch in CLOSE until green indicating light flashes.
+: 3) IF affected PZR Spray valve will NOT close, THEN close associated energized Block valves:
+* 2CV-4655
+* 2CV-4656
+* 2CV-4653
+* 2CV-4654
+: 4) IF associated energized PZR Spray Block valves will NOT close, THEN perform the following:
+a) Verify ALL PZR heaters ON.
+b) IF RCS pressure lowers to 2000 psia, THEN perform the following:
+: 1. IF plant in mode 1 or 2, THEN trip Reactor.
+: 2. Stop RCP in loop with failed PZR Spray valve.
+: 3. GO TO 2202.001, Standard Post Trip Actions.
+PROC NO                                 TITLE              REVISION    PAGE 2203.028                 PZR SYSTEMS MALFUNCTION           010       4 of 10
+ANO-2-JPM-NRC-SIT008                                                             PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT:      2                       REV #:    009                     DATE:
+SYSTEM/DUTY AREA:        Safety Injection System TASK:    Lower Safety Injection Tank level (2T2A)
+JTA#:    ANO2-RO-ECCS-NORM-5 KA VALUE     RO:          3.5       SRO:         3.7        KA
 ==REFERENCE:==
-A1.13APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:
+A1.13 APPROVED FOR ADMINISTRATION TO:            RO:        X     SRO:     X TASK LOCATION:           INSIDE CR:        X      OUTSIDE CR:              BOTH:
-XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSRROOM:POSITION EVALUATED:RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:8 MinutesREFERENCE(S):OP 2104.001EXAMINEE'S NAME:Badge#:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-ANO-2-JPM-NRC-SIT008PAGE  2  OF 6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG1021 Appendix E.JPM INITIAL TASK CONDITIONS:    'A' SIT needs to be lowered 0.1%.TASK STANDARD:    SIT (2T2A) level has been lowered at least 0.1%.TASK PERFORMANCE AIDS:    OP 2104.001 Section 7.1SIMULATOR SETUP:2T2A level is ~85.2% and pressure is 616 psig.Use the following as necessary to adjust SIT level/pressure on the monitor screen simn2(1) ~775 andSIM301(1) ~ 97700 ANO-2-JPM-NRC-SIT008PAGE  3  OF 6JOB PERFORMANCE MEASUREINITIATING CUE:The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning withStep 7.1.2. OPS B-37 does not need to be completed."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)1.(Step7.1.4)Open SIT Drain to RDT.(2CV-5081)On panel 2C33, placedhandswitch for SIT Drain to RDT(2CV-5081) to OPEN.Observed red light ON greenlight OFF above handswitch. N/A  SAT  UNSATEXAMINER'S NOTE: The examinee will close 2CV-5081; then open and close 2SV-5000-1; then open2CV-5081 2.(Step7.1.5)Close SIT Drain to RDT.2CV-5081)On panel 2C33, placedhandswitch for SIT Drain to RDT(2CV-5081) to CLOSED.Observed green light ON redlight OFF above handswitch. N/A  SAT  UNSAT  3.(Step7.1.6)Check for RCS back leakagethrough Check Valve2SI-15A.Examiner note:  2PIS-5000will be less than 650 psigand the rest of step 7.1.6will be N/AOn panel 2C17 checked2PIS-5000 < 650 psig. N/A  SAT  UNSAT (C)4.Step7.1.7)Open SIT (2T2A) Drain Valve.(2SV-5001-1)On panel 2C17, placedhandswitch for SIT A DrainValve (2SV-5001-1) to OPEN.Observed red light ON greenlight OFF above handswitch. N/A  SAT  UNSAT ANO-2-JPM-NRC-SIT008PAGE  4  OF 6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)5.Step7.1.8)Verify SIT (2T2A) desiredlevel is achieved.Verified SIT (2T2A) levelbetween 84.8% and 85.1%.Observed SIT (2T2A) controlboard level instrument(s):  - 2LIS-5008 (2C17)  - 2LI-5010  (2C17)  - 2LIS-5009 (2C16)
+PLANT SITE:                        SIMULATOR:           Perform      CLASSRROOM:
-ORObserved SIT (2T2A) level onPMS, or SPDS computerpoint/trend display. N/A  SAT  UNSAT (C)6.Step7.1.8)Close SIT (2T2A) DrainValve.(2SV-5001-1)On panel 2C17, placedhandswitch for SIT A DrainValve (2SV-5001-1) to CLOSE.Observed green light ON abovehandswitch. N/A  SAT  UNSAT ENDSTOP TIME:
+POSITION EVALUATED:        RO:                     SRO:
-ANO-2-JPM-NRC-SIT008PAGE  5  OF 6JOB PERFORMANCE MEASUREExaminer's CopyJPM INITIAL TASK CONDITIONS:SIT (2T2A) level needs to be lowered.INITIATING CUE:The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001;Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."
+ACTUAL TESTING ENVIRONMENT:            SIMULATOR:             PLANT SITE:      CLASSROOM:
-ANO-2-JPM-NRC-SIT008PAGE  6  OF 6JOB PERFORMANCE MEASUREExaminee's CopyJPM INITIAL TASK CONDITIONS:SIT (2T2A) level needs to be lowered.INITIATING CUE:The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001;Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."
+TESTING METHOD:        SIMULATE:               PERFORM:
+APPROXIMATE COMPLETION TIME IN MINUTES:                 8 Minutes REFERENCE(S):    OP 2104.001 EXAMINEE'S NAME:                                             Badge#:
+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-EDG06PAGE  1  OF  6JOB PERFORMANCE MEASURE UNIT:          2 REV#:          1 DATE:SYSTEM/DUTY AREA:   Emergency Diesel Generator SystemTASK:   Align 2A2 to 2A4JTA#:   ANO2-RO-EDG-NORM-22KA VALUE      RO:         3.9     SRO:          3.9      KA
+ANO-2-JPM-NRC-SIT008                                                                   PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:         A SIT needs to be lowered 0.1%.
+TASK STANDARD:       SIT (2T2A) level has been lowered at least 0.1%.
+TASK PERFORMANCE AIDS:           OP 2104.001 Section 7.1 SIMULATOR SETUP: 2T2A level is ~85.2% and pressure is 616 psig.
+Use the following as necessary to adjust SIT level/pressure on the monitor screen simn2(1) ~775 and SIM301(1) ~ 97700
+ANO-2-JPM-NRC-SIT008                                                                 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
+The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."
+START TIME:
+PERFORMANCE CHECKLIST                            STANDARDS                    (Circle One)
+(C)       1. Open SIT Drain to RDT.          On panel 2C33, placed             N/A SAT UNSAT (2CV-5081)                      handswitch for SIT Drain to RDT (Step                                  (2CV-5081) to OPEN.
+.1.4)
+Observed red light ON green light OFF above handswitch.
+EXAMINERS NOTE: The examinee will close 2CV-5081; then open and close 2SV-5000-1; then open 2CV-5081
+: 2. Close SIT Drain to RDT.         On panel 2C33, placed             N/A SAT UNSAT 2CV-5081)                       handswitch for SIT Drain to RDT (Step                                   (2CV-5081) to CLOSED.
+.1.5)
+Observed green light ON red light OFF above handswitch.
+: 3. Check for RCS back leakage      On panel 2C17 checked             N/A SAT UNSAT through Check Valve             2PIS-5000 < 650 psig.
+(Step  2SI-15A.
+.1.6)
+Examiner note: 2PIS-5000 will be less than 650 psig and the rest of step 7.1.6 will be N/A (C)       4. Open SIT (2T2A) Drain Valve. On panel 2C17, placed             N/A SAT UNSAT (2SV-5001-1)                    handswitch for SIT A Drain Step                                  Valve (2SV-5001-1) to OPEN.
+.1.7)
+Observed red light ON green light OFF above handswitch.
+ANO-2-JPM-NRC-SIT008                                                   PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                      STANDARDS              (Circle One)
+(C)    5. Verify SIT (2T2A) desired Verified SIT (2T2A) level     N/A SAT UNSAT level is achieved.        between 84.8% and 85.1%.
+Step 7.1.8)                           Observed SIT (2T2A) control board level instrument(s):
+                                         - 2LIS-5008 (2C17)
+                                         - 2LI-5010 (2C17)
+                                         - 2LIS-5009 (2C16)
+OR Observed SIT (2T2A) level on PMS, or SPDS computer point/trend display.
+(C)    6. Close SIT (2T2A) Drain    On panel 2C17, placed         N/A SAT UNSAT Valve.                    handswitch for SIT A Drain Step  (2SV-5001-1)              Valve (2SV-5001-1) to CLOSE.
+.1.8)
+Observed green light ON above handswitch.
+END STOP TIME:
+ANO-2-JPM-NRC-SIT008                                                 PAGE 5 OF 6 JOB PERFORMANCE MEASURE Examiners Copy JPM INITIAL TASK CONDITIONS:
+SIT (2T2A) level needs to be lowered.
+INITIATING CUE:
+The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."
+ANO-2-JPM-NRC-SIT008                                                 PAGE 6 OF 6 JOB PERFORMANCE MEASURE Examinees Copy JPM INITIAL TASK CONDITIONS:
+SIT (2T2A) level needs to be lowered.
+INITIATING CUE:
+The SM/CRS directs, "Lower SIT (2T2A) level, to RDT, 0.1% using OP 2104.001; Section 7.1 beginning with Step 7.1.2. OPS B-37 does not need to be completed."
+ANO-2-JPM-NRC-EDG06                                                             PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT:     2                  REV #:    1                        DATE:
+SYSTEM/DUTY AREA: Emergency Diesel Generator System TASK: Align 2A2 to 2A4 JTA#: ANO2-RO-EDG-NORM-22 KA VALUE     RO:      3.9       SRO:     3.9       KA
 ==REFERENCE:==
-A4.06APPROVED FOR ADMINISTRATION TO:  RO:         X      SRO:          XTASK LOCATION:  INSIDE CR:          X    OUTSIDE CR:
+A4.06 APPROVED FOR ADMINISTRATION TO: RO:             X        SRO:     X TASK LOCATION: INSIDE CR:          X       OUTSIDE CR:               BOTH:
-BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):    PLANT SITE:    SIMULATOR:     Perform CLASSROOM:POSITION EVALUATED:      RO:      SRO:ACTUAL TESTING ENVIRONMENT:  SIMULATOR:  PLANT SITE: CLASSROOM:TESTING METHOD:  SIMULATE:      PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:     10 MinutesREFERENCE(S):    OP 2104.036EXAMINEE'S NAME:  BADGE#:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:        SATISFACTORY:        UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS: Start Time Stop Time Total TimeSIGNED__________________________________
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+PLANT SITE:                  SIMULATOR:     Perform           CLASSROOM:
-ANO-2-JPM-NRC-EDG06PAGE  2  OF  6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021Appendix E.JPM INITIAL TASK CONDITIONS:    2DG2 has been supplying 2A4 for [[estimated NRC review hours::4 hours]] to allow maintenance on 2A409. Maintenance and PMT are complete on 2A409.TASK STANDARD:    2A409 closed.TASK PERFORMANCE AIDS:    OP 2104.036 Section 14.0. Sync switch.SIMULATOR SETUP: 2DG2 supplying 2A4. 2A4 isolated from 2A2 with 2A409 open.
+POSITION EVALUATED:       RO:                SRO:
-ANO-2-JPM-NRC-EDG06PAGE  3  OF  6JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."START TIME:PERFORMANCE CHECKLIST STANDARDS(Circle One) 1.(Step14.1)Verify SIAS signal cleared.On panel 2C03, operator insertpanels, observed that SIAS matrixtrip lamps are lit and/or SIASannunciators are clear on 2K04 and2K05 and/or on 2C23 verify thatSIAS trip lamps are clear and thematrix trip lights are lit. N/A  SAT  UNSAT (C)2.(Step14.2.1)Verify 2A2 available to supply 2A4.On panel 2C10, verified that 2A2 isenergized by observing either:The handswitch from Unit Aux to2A2 has red light ON and Green lightOFF.Observed voltage on 2A2. N/A  SAT  UNSAT 3.(Step14.2.2)Verify Neutral Overvolt alarm2K131-3 clear.EXAMINER CUE:If asked NLO reports NeutralOvervolt alarm on 2K131-3 clear.On 2C33, observed annunciator2K09 Window J1 alarm,Engine/Gen trouble is clear byobserving that the annunciatorwindow is not lit.
+ACTUAL TESTING ENVIRONMENT: SIMULATOR:                       PLANT SITE:         CLASSROOM:
-orContact AO and check locally. N/A  SAT  UNSAT (C)4.(Step14.2.3)Place 2A409 synchronize switch to"ON".On panel 2C33, insertedsynchronize switch handle into2A409, 2A4 supply breakersynchronize switch.Rotated handle clockwise to "ON". N/A  SAT  UNSAT 5.(Step14.2.4)Adjust Generator voltage(Incoming) using VoltageRegulator switch (CS 3) as perBOTH of the following:Generator voltage (Incoming) ~100 volts higher than Systemvoltage (Running) by 2C-33indication.Generator voltage (Incoming)higher than System voltage(Running) by SPDS indication (NAif SPDS indication not available).On 2C33, compare incoming andRunning voltages. Verifiedincoming is ~100 volts higher thanrunning on 2C-33.Verified incoming voltage is higherthan running voltage by SPDSindication.Adjust EDG voltage using Voltageregulator switch to match voltages.(If required.)N/A  SAT  UNSAT ANO-2-JPM-NRC-EDG06PAGE  4  OF  6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLIST STANDARDS(Circle One)(C)6.(Step14.2.5)Adjust frequency to causesynchroscope to rotate slowly inFAST direction using GovernorControl switch (CS 4).On panel 2C33, adjusted frequencyto cause synchroscope to rotateslowly in the FAST direction usingGovernor Control Handswitch (CS4)to raise or lower 2DG2 speed.  (Ifrequired.)  N/A  SAT  UNSAT (C)7.(Step14.2.6)Perform the following to close 2A-409:A. WHEN synchroscopeapproaches the 12 o'clock position,THEN close 2A-409 (152-409/CS).B. Immediately raise 2DG2 load to~1400 KW to prevent a reversepower trip using Governor Controlswitch (CS 4).On panel 2C33, placed hand on2A409, 2A4 supply breaker (152-409).Observed 2DG2 synchroscoperotation.Rotated 152-409 handswitch to"CLOSE" when synchroscopepassed through 12 o'clock position.Verified red light for 2A409, 2A4supply breaker ON.Raised load by placing GovernorControl switch to raise until load is~1400 KW. N/A  SAT  UNSAT 8.(Step14.2.7)Adjust Generator KVARs between600 KVARs IN and1800 KVARs OUT using VoltageRegulator switch (CS 3).(Preferred range is 0 to 100 OUT)On panel 2C33, observed 2DG2Kilovar meter.Adjusted Voltage RegulatorHandswitch as required to maintain2DG2 Kilovars between 0 and 100Kilovars OUT. N/A  SAT  UNSAT 9.(Step14.2.8)Place 2A409, 2A4 supply breakerSynchroscope switch to "OFF".On panel 2C33, rotated 2A409, 2A4supply breaker Synchroscope Switch to "OFF". N/A  SAT  UNSATEXAMINER NOTE:This JPM may be stopped once 2A-409 synchroscope switch in OFF.ENDSTART TIME:
+TESTING METHOD: SIMULATE:                      PERFORM:
-ANO-2-JPM-NRC-EDG06PAGE  5  OF  6JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS: 2DG2 has been supplying 2A4 for [[estimated NRC review hours::4 hours]] to allow maintenance on 2A409. Maintenance and PMT are complete on 2A409.INITIATING CUE:The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."
+APPROXIMATE COMPLETION TIME IN MINUTES:            10 Minutes REFERENCE(S):    OP 2104.036 EXAMINEE'S NAME:                                          BADGE#:
-ANO-2-JPM-NRC-EDG06PAGE  6  OF  6JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS: 2DG2 has been supplying 2A4 for [[estimated NRC review hours::4 hours]] to allow maintenance on 2A409. Maintenance and PMT are complete on 2A409.INITIATING CUE:The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."
+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.
-PROC./WORK PLAN NO.2104.036PROCEDURE/WORK PLAN TITLE:EMERGENCY DIESEL GENERATOR OPERATIONSPAGE: 38 of 266CHANGE: 07514.0 MANUAL SHUTDOWN OF 2DG2NOTEIf 2DG2 is run unloaded for greater than ten minutes OR multiple startsperformed, the engine should be operated at full load for one hour prior tosecuring.14.1 IF SIAS is actuated,THEN reset SIAS per Attachment 13 of 2202.010, Standard Attachments.14.2 IF 2A4 Supply breaker (2A-409) open,AND necessary to supply 2A4 from offsite power,THEN perform the following:14.2.1 Verify 2A2 available to supply 2A4.NOTENeutral Overvolt (2K131-3) alarm clears when Engine/Gen Trouble (2K09-J1)is cleared.14.2.2 Verify Neutral Overvolt (2K131-3) alarm clear.14.2.3 Place 2A-409 Synchronize switch to ON.14.2.4 Adjust Generator voltage (Incoming) usingVoltage Regulator switch (CS 3) as per BOTH of thefollowing:Generator voltage (Incoming) ~ 100 volts higher thanSystem voltage (Running) by 2C-33 indication.Generator voltage (Incoming) higher thanSystem voltage (Running) by SPDS indication(NA if SPDS indication not available).14.2.5 Adjust frequency to cause synchroscope to rotate slowly inFAST direction using Governor Control switch (CS 4).CAUTION2DG2 load will lower when 2A-409 is closed because the governor controlcircuit shifts to DROOP.14.2.6 Perform the following to close 2A-409:A. WHEN synchroscope approaches the 12 o'clock position,THEN close 2A-409 (152-409/CS).B. Immediately raise 2DG2 load to ~1400 KW to prevent areverse power trip using Governor Control switch(CS 4).14.2.7 Adjust Generator KVARs between 600 KVARs IN and 1800 KVARsOUT using Voltage Regulator switch. (Preferred range is 0to 100 OUT)14.2.8 Place 2A-409 Synchronize switch in OFF.
+ANO-2-JPM-NRC-EDG06                                                                                 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
-ANO-2-JPM-NRC-CEA02PAGE  1  OF   9JOB PERFORMANCE MEASUREUNIT: 2 REV#: 9DATE: ______________SYSTEM/DUTY AREA:  Control Element Drive Mechanism Control SystemTASK:   Test a Reactor Trip Circuit Breaker.JTA#:   ANO2-RO-CEDM-SURV-15KA VALUE      RO:           4.3     SRO:          4.3      KA
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:              2DG2 has been supplying 2A4 for [[estimated NRC review hours::4 hours]] to allow maintenance on 2A409. Maintenance and PMT are complete on 2A409.
+TASK STANDARD:          2A409 closed.
+TASK PERFORMANCE AIDS:              OP 2104.036 Section 14.0. Sync switch.
+SIMULATOR SETUP: 2DG2 supplying 2A4. 2A4 isolated from 2A2 with 2A409 open.
+ANO-2-JPM-NRC-EDG06                                                                           PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."
+START TIME:
+PERFORMANCE CHECKLIST                                     STANDARDS                   (Circle One)
+: 1. Verify SIAS signal cleared.          On panel 2C03, operator insert       N/A SAT UNSAT (Step panels, observed that SIAS matrix 14.1)                                         trip lamps are lit and/or SIAS annunciators are clear on 2K04 and 2K05 and/or on 2C23 verify that SIAS trip lamps are clear and the matrix trip lights are lit.
+(C)      2. Verify 2A2 available to supply       On panel 2C10, verified that 2A2 is  N/A SAT UNSAT (Step 2A4.                                 energized by observing either:
+.2.1)
+The handswitch from Unit Aux to 2A2 has red light ON and Green light OFF.
+Observed voltage on 2A2.
+: 3. Verify Neutral Overvolt alarm        On 2C33, observed annunciator        N/A SAT UNSAT 2K131-3 clear.                       2K09 Window J1 alarm, (Step                                         Engine/Gen trouble is clear by 14.2.2) observing that the annunciator window is not lit.
+EXAMINER CUE:
+or If asked NLO reports Neutral         Contact AO and check locally.
+Overvolt alarm on 2K131-3 clear.
+(C)      4. Place 2A409 synchronize switch to    On panel 2C33, inserted              N/A SAT UNSAT (Step "ON".                                synchronize switch handle into 14.2.3)                                        2A409, 2A4 supply breaker synchronize switch.
+Rotated handle clockwise to "ON".
+: 5. Adjust Generator voltage             On 2C33, compare incoming and       N/A SAT UNSAT (Step (Incoming) using Voltage             Running voltages. Verified 14.2.4)   Regulator switch (CS 3) as per       incoming is ~100 volts higher than BOTH of the following:               running on 2C-33.
+Verified incoming voltage is higher Generator voltage (Incoming) ~       than running voltage by SPDS 100 volts higher than System         indication.
+voltage (Running) by 2C-33 indication.
+Generator voltage (Incoming)         Adjust EDG voltage using Voltage higher than System voltage           regulator switch to match voltages.
+(Running) by SPDS indication (NA     (If required.)
+if SPDS indication not available).
+ANO-2-JPM-NRC-EDG06                                                                          PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                                    STANDARDS                   (Circle One)
+(C)     6. Adjust frequency to cause            On panel 2C33, adjusted frequency     N/A SAT UNSAT (Step synchroscope to rotate slowly in     to cause synchroscope to rotate 14.2.5) FAST direction using Governor        slowly in the FAST direction using Control switch (CS 4).               Governor Control Handswitch (CS4) to raise or lower 2DG2 speed. (If required.)
+(C)     7. Perform the following to close 2A-   On panel 2C33, placed hand on         N/A SAT UNSAT (Step 409:                                 2A409, 2A4 supply breaker 14.2.6)                                      (152-409).
+A. WHEN synchroscope approaches the 12 o'clock position,  Observed 2DG2 synchroscope THEN close 2A-409 (152-409/CS).      rotation.
+B. Immediately raise 2DG2 load to    Rotated 152-409 handswitch to
+                ~1400 KW to prevent a reverse        "CLOSE" when synchroscope power trip using Governor Control    passed through 12 o'clock position.
+switch (CS 4).
+Verified red light for 2A409, 2A4 supply breaker ON.
+Raised load by placing Governor Control switch to raise until load is
+                                                     ~1400 KW.
+: 8. Adjust Generator KVARs between       On panel 2C33, observed 2DG2          N/A SAT UNSAT (Step 600 KVARs IN and                     Kilovar meter.
+.2.7) 1800 KVARs OUT using Voltage Regulator switch (CS 3).
+(Preferred range is 0 to 100 OUT)    Adjusted Voltage Regulator Handswitch as required to maintain 2DG2 Kilovars between 0 and 100 Kilovars OUT.
+: 9. Place 2A409, 2A4 supply breaker      On panel 2C33, rotated 2A409, 2A4     N/A SAT UNSAT (Step Synchroscope switch to "OFF".        supply breaker Synchroscope Switch 14.2.8)                                      to "OFF".
+EXAMINER NOTE:
+This JPM may be stopped once 2A-409 synchroscope switch in OFF.
+END START TIME:
+ANO-2-JPM-NRC-EDG06                                                       PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:
+DG2 has been supplying 2A4 for [[estimated NRC review hours::4 hours]] to allow maintenance on 2A409.
+Maintenance and PMT are complete on 2A409.
+INITIATING CUE:
+The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."
+ANO-2-JPM-NRC-EDG06                                                       PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:
+DG2 has been supplying 2A4 for [[estimated NRC review hours::4 hours]] to allow maintenance on 2A409.
+Maintenance and PMT are complete on 2A409.
+INITIATING CUE:
+The CRS directs, "Supply 2A4 from offsite power using OP 2104.036 section 14.0."
+PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:                           PAGE:   38 of 266 2104.036             EMERGENCY DIESEL GENERATOR OPERATIONS           CHANGE: 075 14.0   MANUAL SHUTDOWN OF 2DG2 NOTE If 2DG2 is run unloaded for greater than ten minutes OR multiple starts performed, the engine should be operated at full load for one hour prior to securing.
+.1      IF SIAS is actuated, THEN reset SIAS per Attachment 13 of 2202.010, Standard Attachments.
+.2      IF 2A4 Supply breaker (2A-409) open, AND necessary to supply 2A4 from offsite power, THEN perform the following:
+.2.1     Verify 2A2 available to supply 2A4.
+NOTE Neutral Overvolt (2K131-3) alarm clears when Engine/Gen Trouble (2K09-J1) is cleared.
+.2.2     Verify Neutral Overvolt (2K131-3) alarm clear.
+.2.3     Place 2A-409 Synchronize switch to ON.
+.2.4     Adjust Generator voltage (Incoming) using Voltage Regulator switch (CS 3) as per BOTH of the following:
+Generator voltage (Incoming) ~ 100 volts higher than System voltage (Running) by 2C-33 indication.
+Generator voltage (Incoming) higher than System voltage (Running) by SPDS indication (NA if SPDS indication not available).
+.2.5     Adjust frequency to cause synchroscope to rotate slowly in FAST direction using Governor Control switch (CS 4).
+CAUTION 2DG2 load will lower when 2A-409 is closed because the governor control circuit shifts to DROOP.
+.2.6     Perform the following to close 2A-409:
+A. WHEN synchroscope approaches the 12 o'clock position, THEN close 2A-409 (152-409/CS).
+B. Immediately raise 2DG2 load to ~1400 KW to prevent a reverse power trip using Governor Control switch (CS 4).
+.2.7     Adjust Generator KVARs between 600 KVARs IN and 1800 KVARs OUT using Voltage Regulator switch. (Preferred range is 0 to 100 OUT) 14.2.8     Place 2A-409 Synchronize switch in OFF.
+ANO-2-JPM-NRC-CEA02                                                            PAGE 1 OF 9 JOB PERFORMANCE MEASURE UNIT:     2                         REV #:        9                  DATE: ______________
+SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Test a Reactor Trip Circuit Breaker.
+JTA#: ANO2-RO-CEDM-SURV-15 KA VALUE    RO:        4.3       SRO:      4.3         KA
 ==REFERENCE:==
-A4.06APPROVED FOR ADMINISTRATION TO:  RO:         X      SRO:         XTASK LOCATION:  INSIDE CR:          X    OUTSIDE CR:   BOTH: _______SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):    PLANT SITE:    Simulate    SIMULATOR:    Perform    CLASSROOM: _______POSITION EVALUATED:      RO:      SRO:   _________ACTUAL TESTING ENVIRONMENT:  SIMULATOR:  PLANT SITE:CLASSROOM: ______TESTING METHOD:  SIMULATE:      PERFORM:   __________APPROXIMATE COMPLETION TIME IN MINUTES:   15 minutesREFERENCE(S):   OP 2105.009 SUPP. 1EXAMINEE'S NAME:  BADGE:  _____________________EVALUATOR'S NAME:   __________________________________________THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:        UNSATISFACTORY:  ______________PERFORMANCE CHECKLIST COMMENTS: Start Time Stop Time Total TimeSIGNED __________________________________DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+A4.06 APPROVED FOR ADMINISTRATION TO: RO:             X         SRO:    X TASK LOCATION: INSIDE CR:          X       OUTSIDE CR:               BOTH: _______
-ANO-2-JPM-NRC-CEA02PAGE  2  OF   9JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG1021 Appendix E.JPM INITIAL TASK CONDITIONS:   TCB-02 has been repaired following a component malfunction. Theplant isin Mode 1. Supplement 1 Section 1.0 of 2105.009 is completed. An operator is standing by in the CEDMroom.TASK STANDARD:   Reactor trip circuit breaker TCB-2 and TCB-6 operated in accordance with OP2105.009Supplement 1.TASK PERFORMANCE AIDS:   OP 2105.009 Supplement 1.0 section 2.1 and 2.2. TCB Close Key.SIMULATOR SETUP:TCB 9 closed. TCB 2  is open. Mode 1 ANO-2-JPM-NRC-CEA02PAGE  3  OF   9JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009Supplement 1.0 section 2.1 and 2.2. Leave TCB-2 closed. "Start Time:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.(Step 2.1.1)Verify undervoltage (UV) tripdevice position for Reactor TripCircuit Breakers TCB-2.EXAMINER CUE:CEDM Room operatorreports UV Trip Devicearmatures for TCB-2 is incontact with air gapadjusting screw.Contacted operator in CEDMroom.Requested verification of positionof UV trip device armatures for TCB-2. N/A  SAT  UNSAT 2.(Step 2.1.2)Obtain CPC Test/TCB closekey (#15) from SM key locker.CPC Test/TCB close key (#15)obtained from SM key locker. N/A  SAT  UNSAT 3.(Step 2.1.3)On 2C23, place applicableReset Actuation Trip Pathkeylock in UNLK.On 2C23, placed applicableReset Actuation Trip Path keylockin UNLK. N/A  SAT  UNSAT (C)4.(Step 2.1.4)Close TCB-2 using pushbutton on 2C23.Depress TCB-2 reset push button.On panel 2C23 or panel 2C14,verified red light ON for TCB-2.Placed key in LOCK position andremoved key. N/A  SAT  UNSAT (C)5.(Step 2.1.5)On 2C23, place applicableReset Actuation Trip Pathkeylock in LK.Placed key in LOCK position andremoved key. N/A  SAT  UNSAT ANO-2-JPM-NRC-CEA02PAGE  4  OF   9JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)Perform the following to test Shunt Trip:
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-.(Step 2.2)Verify TCB-2 closed per step2.1Verified TCB-2 closed per step2.1  N/A  SAT  UNSAT 7.(Step 2.2)Hold 2HS/TEST switch in UVBypass position (for TCB-2).EXAMINER CUE:CEDM Room operatorreports 2HS/TEST switch isin the UV Bypass Position.Contacted operator in CEDMroom.Requested 2HX/TEST switch beheld in the UV Bypass position. N/A  SAT  UNSAT (C)8.(Step 2.2)Depress Manual Reactor Trippush button (2HS-9071-2).On panel 2C03, depressed pushbutton 2HS-9071-2. N/A  SAT  UNSAT 9.(Step 2.2)Verify TCB-2 open.On panel 2C14, verified TCB-2opens. N/A  SAT  UNSAT 10.(Step 2.2)Check 2K12-A10 alarm comesin or reflashes.On annunciator panel 2K12,acknowledged that 2K12-A10actuated. N/A  SAT  UNSAT 11.(Step 2.2)Contact CEDM Room operatorto release 2HS/TEST switch.EXAMINER CUE:CEDM Room operatorreports that 2HS/TESTswitch is releasedContact CEDM Room operator torelease 2HS/TEST switch. N/A  SAT  UNSATEVALUATORS NOTE: The simulator does not model 2K426. When the examinee attempts to open thedoor to 2C14, give them the cue on the next step.
+PLANT SITE:    Simulate          SIMULATOR:     Perform            CLASSROOM: _______
-ANO-2-JPM-NRC-CEA02PAGE  5  OF   9JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 12.(Step 2.2)Verify reflash Unit 2K426 in 2C14 reset.EXAMINER CUE
+POSITION EVALUATED:        RO:                 SRO: _________
-: 2K426reflash unit is reset.Preceded to the back of 2C-14 toreset 2K426 reflash unit. N/A  SAT  UNSAT 13.(Step 2.1.1)Verify undervoltage (UV) tripdevice position for Reactor TripCircuit Breakers TCB-2.EXAMINER CUE
+ACTUAL TESTING ENVIRONMENT: SIMULATOR:                   PLANT SITE:      CLASSROOM: ______
-:CEDM Room operatorreports UV Trip Devicearmatures for TCB-2 is incontact with air gapadjusting screw.Contacted operator in CEDMroom.Requested verification of positionof UV trip device armatures for TCB-2. N/A  SAT  UNSAT (C)14.(Step 2.1)Close TCB-2.On panel 2C23, inserted key inESF reset push button keylock.Placed key in UNLOCK position.Depress TCB-2 reset push button.On panel 2C23 or panel 2C14,verified red light ON for TCB-2.Placed key in LOCK position andremoved key. N/A  SAT  UNSATPerform the following to test UV Trip:
+TESTING METHOD: SIMULATE:                       PERFORM: __________
-.(Step 2.2)Verify TCB-2 closed per step2.1Verified TCB-2 closed per step2.1  N/A  SAT  UNSAT ANO-2-JPM-NRC-CEA02PAGE  6  OF   9JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 16.(Step 2.2)Hold 2HS/TEST switch inShunt Bypass position (for TCB-2).EXAMINER CUE:CEDM Room operatorreports 2HS/TEST switch isin the Shunt BypassPosition.Contacted operator in CEDMroom.Requested 2HX/TEST switch beheld in the Shunt Bypass position. N/A  SAT  UNSAT (C)17.(Step 2.2)Depress Manual Reactor Trippush button (2HS-9071-2).On panel 2C03, depressed pushbutton 2HS-9071-2. N/A  SAT  UNSAT 18.(Step 2.2)Verify TCB-2 opens.On panel 2C14, verified TCB-2opens.Verified by green lights ON for TCB-2. N/A  SAT  UNSAT 19.(Step 2.2)Check 2K12-A10 alarm comesin or reflashes.On annunciator panel 2K12,acknowledged that 2K12-A10actuated. N/A  SAT  UNSAT 20.(Step 2.2)Contact CEDM Room operatorto release 2HS/TEST switch.EXAMINER CUE:CEDM Room operatorreports that 2HS/TESTswitch is releasedContact CEDM Room operator torelease 2HS/TEST switch. N/A  SAT  UNSATEVALUATORS NOTE: The simulator does not model 2K426. When the examinee attempts to open thedoor to 2C14, give them the cue below.
+APPROXIMATE COMPLETION TIME IN MINUTES: 15 minutes REFERENCE(S): OP 2105.009 SUPP. 1 EXAMINEE'S NAME:                                             BADGE: _____________________
-.(Step 2.2)Reset Reflash unit 2K426 in 2C14.EXAMINER CUE
+EVALUATOR'S NAME: __________________________________________
-: 2K426reflash unit is reset.Preceded to the back of 2C-14 toreset 2K426 reflash unit. N/A  SAT  UNSAT ANO-2-JPM-NRC-CEA02PAGE  7  OF   9JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 22.(Step 2.2)Verify undervoltage (UV) tripdevice position for Reactor TripCircuit Breakers TCB-2 and TCB-6.Examiner Cue
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-:CEDM Room operatorreports UV Trip Devicearmatures for TCB-2 andTCB-6 are in contact with airgap adjusting screws.Contacted operator in CEDMroom.Requested verification of positionof UV trip device armatures forTCB-2 and TCB-6. N/A  SAT  UNSAT (C)23.(Step 2.2.1)Close TCB-2 and TCB-6.On panel 2C23, inserted key inESF reset push button keylock.Placed key in UNLOCK position.Depress TCB-2 and TCB-6 resetpush button.On panel 2C23 or panel 2C14,verified red light ON for TCB-2and TCB-6.Placed key in LOCK position andremoved key. N/A  SAT  UNSAT ENDStop Time:
+SATISFACTORY:                        UNSATISFACTORY: ______________
-ANO-2-JPM-NRC-CEA02PAGE  8  OF   9JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM TASK INITIAL CONDITIONS TCB-02 has been repaired following a component malfunction. The plant is in Mode 1. Supplement 1 Section 1.0 of 2105.009 CEDM control system operations is completed. An operator is standing by in the CEDM room.INITIATING CUE:The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009Supplement 1 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed. "
+PERFORMANCE CHECKLIST COMMENTS:
-ANO-2-JPM-NRC-CEA02PAGE  9  OF   9JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM TASK INITIAL CONDITIONS TCB-02 has been repaired following a component malfunction. The plant is in Mode 1. Supplement 1 Section 1.0 of 2105.009 CEDM control system operations is completed. An operator is standing by in the CEDM room.INITIATING CUE:The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009Supplement 1 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed. "
+Start Time                           Stop Time                        Total Time SIGNED __________________________________ DATE: _____________________
-ANO-2-JPM-NRC-CEA01PAGE  1  OF  6JOB PERFORMANCE MEASURE UNIT:          2 REV#:           11 DATE:SYSTEM/DUTY AREA:   Control Element Drive Mechanism Control SystemTASK:    Perform control element assembly exercise.JTA#:   ANO2-RO-CEDM-SURV-13KA VALUE      RO:          4.0     SRO:          3.7      KA
+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-CEA02                                                                       PAGE 2 OF 9 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS: TCB-02 has been repaired following a component malfunction. The plant is in Mode 1. Supplement 1 Section 1.0 of 2105.009 is completed. An operator is standing by in the CEDM room.
+TASK STANDARD: Reactor trip circuit breaker TCB-2 and TCB-6 operated in accordance with OP 2105.009 Supplement 1.
+TASK PERFORMANCE AIDS: OP 2105.009 Supplement 1.0 section 2.1 and 2.2. TCB Close Key.
+SIMULATOR SETUP: TCB 9 closed. TCB 2 is open. Mode 1
+ANO-2-JPM-NRC-CEA02                                                                       PAGE 3 OF 9 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1.0 section 2.1 and 2.2. Leave TCB-2 closed. "
+Start Time:
+PERFORMANCE CHECKLIST                                STANDARDS                     (Circle One)
+: 1. Verify undervoltage (UV) trip      Contacted operator in CEDM           N/A SAT UNSAT device position for Reactor Trip   room.
+Circuit Breakers TCB-2.
+(Step 2.1.1)                                    Requested verification of position EXAMINER CUE:                      of UV trip device armatures for TCB-2.
+CEDM Room operator reports UV Trip Device armatures for TCB-2 is in contact with air gap adjusting screw.
+: 2. Obtain CPC Test/TCB close          CPC Test/TCB close key (#15)         N/A SAT UNSAT key (#15) from SM key locker.      obtained from SM key locker.
+(Step 2.1.2)
+: 3. On 2C23, place applicable          On 2C23, placed applicable           N/A SAT UNSAT Reset Actuation Trip Path          Reset Actuation Trip Path keylock keylock in UNLK.                   in UNLK.
+(Step 2.1.3)
+(C)     4. Close TCB-2 using pushbutton       Depress TCB-2 reset push button. N/A SAT UNSAT on 2C23.
+(Step                                     On panel 2C23 or panel 2C14, 2.1.4)                                    verified red light ON for TCB-2.
+Placed key in LOCK position and removed key.
+(C)     5. On 2C23, place applicable          Placed key in LOCK position and      N/A SAT UNSAT Reset Actuation Trip Path          removed key.
+(Step  keylock in LK.
+.1.5)
+ANO-2-JPM-NRC-CEA02                                                              PAGE 4 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                              STANDARDS               (Circle One)
+Perform the following to test Shunt Trip:
+: 6.       Verify TCB-2 closed per step   Verified TCB-2 closed per step  N/A SAT UNSAT 2.1                            2.1 (Step 2.2)
+: 7.       Hold 2HS/TEST switch in UV     Contacted operator in CEDM      N/A SAT UNSAT Bypass position (for TCB-2). room.
+(Step 2.2)     EXAMINER CUE:                  Requested 2HX/TEST switch be CEDM Room operator             held in the UV Bypass position.
+reports 2HS/TEST switch is in the UV Bypass Position.
+(C)    8.       Depress Manual Reactor Trip    On panel 2C03, depressed push   N/A SAT UNSAT push button (2HS-9071-2).      button 2HS-9071-2.
+(Step 2.2)
+: 9.       Verify TCB-2 open.             On panel 2C14, verified TCB-2   N/A SAT UNSAT opens.
+(Step 2.2)
+: 10.      Check 2K12-A10 alarm comes     On annunciator panel 2K12,      N/A SAT UNSAT in or reflashes.               acknowledged that 2K12-A10 (Step                                   actuated.
+.2)
+: 11.      Contact CEDM Room operator     Contact CEDM Room operator to   N/A SAT UNSAT to release 2HS/TEST switch. release 2HS/TEST switch.
+(Step 2.2)     EXAMINER CUE:
+CEDM Room operator reports that 2HS/TEST switch is released EVALUATORS NOTE: The simulator does not model 2K426. When the examinee attempts to open the door to 2C14, give them the cue on the next step.
+ANO-2-JPM-NRC-CEA02                                                                   PAGE 5 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                                STANDARDS                  (Circle One)
+: 12.      Verify reflash Unit 2K426 in     Preceded to the back of 2C-14 to   N/A SAT UNSAT 2C14 reset.                      reset 2K426 reflash unit.
+(Step 2.2)
+EXAMINER CUE: 2K426 reflash unit is reset.
+: 13.      Verify undervoltage (UV) trip    Contacted operator in CEDM         N/A SAT UNSAT device position for Reactor Trip room.
+Circuit Breakers TCB-2.
+(Step 2.1.1)                                    Requested verification of position EXAMINER CUE:                    of UV trip device armatures for CEDM Room operator               TCB-2.
+reports UV Trip Device armatures for TCB-2 is in contact with air gap adjusting screw.
+(C)    14.      Close TCB-2.                     On panel 2C23, inserted key in     N/A SAT UNSAT ESF reset push button keylock.
+(Step 2.1)                                      Placed key in UNLOCK position.
+Depress TCB-2 reset push button.
+On panel 2C23 or panel 2C14, verified red light ON for TCB-2.
+Placed key in LOCK position and removed key.
+Perform the following to test UV Trip:
+: 15.      Verify TCB-2 closed per step     Verified TCB-2 closed per step     N/A SAT UNSAT 2.1                              2.1 (Step 2.2)
+ANO-2-JPM-NRC-CEA02                                                               PAGE 6 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                            STANDARDS                  (Circle One)
+: 16. Hold 2HS/TEST switch in       Contacted operator in CEDM         N/A SAT UNSAT Shunt Bypass position (for    room.
+(Step   TCB-2).
+.2)
+EXAMINER CUE:
+Requested 2HX/TEST switch be CEDM Room operator            held in the Shunt Bypass position.
+reports 2HS/TEST switch is in the Shunt Bypass Position.
+(C)    17. Depress Manual Reactor Trip   On panel 2C03, depressed push      N/A SAT UNSAT push button (2HS-9071-2). button 2HS-9071-2.
+(Step 2.2)
+: 18. Verify TCB-2 opens.           On panel 2C14, verified TCB-2      N/A SAT UNSAT opens.
+(Step 2.2)                                  Verified by green lights ON for TCB-2.
+: 19. Check 2K12-A10 alarm comes    On annunciator panel 2K12,         N/A SAT UNSAT in or reflashes.              acknowledged that 2K12-A10 (Step                                 actuated.
+.2)
+: 20. Contact CEDM Room operator    Contact CEDM Room operator to      N/A SAT UNSAT to release 2HS/TEST switch. release 2HS/TEST switch.
+(Step 2.2)    EXAMINER CUE:
+CEDM Room operator reports that 2HS/TEST switch is released EVALUATORS NOTE: The simulator does not model 2K426. When the examinee attempts to open the door to 2C14, give them the cue below.
+: 21. Reset Reflash unit 2K426 in   Preceded to the back of 2C-14 to   N/A SAT UNSAT 2C14.                         reset 2K426 reflash unit.
+(Step 2.2)
+EXAMINER CUE: 2K426 reflash unit is reset.
+ANO-2-JPM-NRC-CEA02                                                                 PAGE 7 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                              STANDARDS                  (Circle One)
+: 22. Verify undervoltage (UV) trip    Contacted operator in CEDM         N/A SAT UNSAT device position for Reactor Trip room.
+Circuit Breakers TCB-2 and (Step  TCB-6.
+.2)                                    Requested verification of position of UV trip device armatures for Examiner Cue:                    TCB-2 and TCB-6.
+CEDM Room operator reports UV Trip Device armatures for TCB-2 and TCB-6 are in contact with air gap adjusting screws.
+(C)    23. Close TCB-2 and TCB-6.           On panel 2C23, inserted key in     N/A SAT UNSAT ESF reset push button keylock.
+(Step 2.2.1)                                  Placed key in UNLOCK position.
+Depress TCB-2 and TCB-6 reset push button.
+On panel 2C23 or panel 2C14, verified red light ON for TCB-2 and TCB-6.
+Placed key in LOCK position and removed key.
+END Stop Time:
+ANO-2-JPM-NRC-CEA02                                                                       PAGE 8 OF 9 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM TASK INITIAL CONDITIONS TCB-02 has been repaired following a component malfunction.
+The plant is in Mode 1.
+Supplement 1 Section 1.0 of 2105.009 CEDM control system operations is completed.
+An operator is standing by in the CEDM room.
+INITIATING CUE:
+The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed. "
+ANO-2-JPM-NRC-CEA02                                                                       PAGE 9 OF 9 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM TASK INITIAL CONDITIONS TCB-02 has been repaired following a component malfunction.
+The plant is in Mode 1.
+Supplement 1 Section 1.0 of 2105.009 CEDM control system operations is completed.
+An operator is standing by in the CEDM room.
+INITIATING CUE:
+The CRS directs, "Perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed. "
+ANO-2-JPM-NRC-CEA01                                                                    PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT:     2                  REV #:        11                       DATE:
+SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK:  Perform control element assembly exercise.
+JTA#: ANO2-RO-CEDM-SURV-13 KA VALUE     RO:       4.0        SRO:       3.7        KA
 ==REFERENCE:==
-A4.03APPROVED FOR ADMINISTRATION TO:  RO:         X      SRO:         XTASK LOCATION:  INSIDE CR:          X    OUTSIDE CR:
+A4.03 APPROVED FOR ADMINISTRATION TO: RO:                  X        SRO:    X TASK LOCATION: INSIDE CR:           X          OUTSIDE CR:                BOTH:
-BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):    PLANT SITE:    SIMULATOR:             Perform CLASSROOM:POSITION EVALUATED:      RO:      SRO:ACTUAL TESTING ENVIRONMENT:  SIMULATOR: PLANT SITE: CLASSROOM:TESTING METHOD:  SIMULATE:      PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:    12 minutesREFERENCE(S):   OP 2105.009EXAMINEE'S NAME:  BADGE #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:        SATISFACTORY:        UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS: Start Time Stop Time Total TimeSIGNED__________________________________
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+PLANT SITE:                   SIMULATOR:             Perform       CLASSROOM:
-ANO-2-JPM-NRC-CEA01PAGE  2  OF  6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021Appendix E.JPM INITIAL TASK CONDITIONS:   250 EFPD. OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEA's  except CEA #46. No T-alt installed on either RSPT.TASK STANDARD:   CEA #46 has been inserted seven (7) steps (5.25 inches) and withdrawn to the  programmed insertion limit.TASK PERFORMANCE AIDS:   OP 2105.009 Supplement 2. Complete Table 2 except for CEA 6-46.SIMULATOR SETUP:  CEA's withdrawn to Programmed insertion limit ANO-2-JPM-NRC-CEA01PAGE  3  OF  6JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Complete the CEA Exercise Test for CEA #46 using OP 2105.009 Supplement 2, beginning Step2.5."Start Time:PERFORMANCE CHECKLIST STANDARDS(Circle One) 1.(Step2.5.3)Select position indication for CEA
+POSITION EVALUATED:        RO:                    SRO:
-# 46.On panel 2C03, CEA #46 displayedon all available CEAC moduledisplays by one of the followingmethods:  - Standard OM,  - CEA group plot    (Group 6 selected)  - CEA values Page 2  - CEA subgroup plot    (Group 6 selected)  N/A  SAT  UNSAT (C)2.(Step2.5.4)Verify Group Select switchselected to group containingindividual CEAOn panel 2C03, verified group 6selected. N/A  SAT  UNSAT (C)1.(Step2.5.5)Place the individual CEAselection switches to CEA #46.On panel 2C03, selected CEA #46.Observed the TENS in "4" and theUNITS in "6". ORObserved CEA #46 individual light ON. N/A  SAT  UNSAT (C)4.(Step2.5.6)Place the mode select switch toMANUAL INDIVIDUAL.On panel 2C03, placed mode selectswitch to MI.Observed MI (MANUALINDIVIDUAL) light ON. N/A  SAT  UNSAT (C)5.(Step2.5.7)Verify CEA #46 at upperelectrical limit (UEL).On insert 2JC-9058, moved CEA 46to UEL by going to WITHDRAW onCEA insert until  #46 upperelectrical limit (UEL) red light on.Observed UEL red light ON. N/A  SAT  UNSAT ANO-2-JPM-NRC-CEA01PAGE  4  OF  6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLIST STANDARDS(Circle One)(C)2.(Step2.5.2)Verify CEA #46 position within 7inches of CEA's 1, 47, 48 and 49throughout exercise.Examiner Note:This step is a continuous actionthat must be completed whilemoving CEAs)Observed all Group 6 CEA's withinseven (7) inches using CEAC #1,CEAC #2, or PMS indications. N/A  SAT  UNSAT (C)6.(Step2.5.8)Insert CEA #46 seven steps (>
+ACTUAL TESTING ENVIRONMENT: SIMULATOR:                       PLANT SITE:         CLASSROOM:
-").Inserted CEA seven steps (>
+TESTING METHOD: SIMULATE:                           PERFORM:
-").Observed insertion of 5.0 inches orgreater on CEAC's #1 and #2displays. N/A  SAT  UNSAT (C)7(Step2.5.9)Return CEA to UEL.CEA #46 withdrawn to UEL. N/A  SAT  UNSAT (C)8.(Step2.5.10)Insert CEA #46 to Programmedinsertion limitCEA #46 inserted to programmedinsertion limit (UEL - 2 steps).Observed CEA #46 at 148.5" onPulse counter (149" on CEAC's)  N/A  SAT  UNSAT 9.(Step2.5.11)Record results.Using OP 2105.009 Supplement ATable 1, recorded the results of CEA#46 exercise. N/A  SAT  UNSATEXAMINER'S NOTE:The CEDMCS control may be left in any mode of operation.
+APPROXIMATE COMPLETION TIME IN MINUTES:                12 minutes REFERENCE(S): OP 2105.009 EXAMINEE'S NAME:                                               BADGE #:
-.(Step2.5.12)WHEN all required CEAmovements complete,THEN verify Mode Select switchin OFF.On insert 2JC-9058, selected offmode of operation. N/A  SAT  UNSATENDStopTime:
+EVALUATOR'S NAME:
-ANO-2-JPM-NRC-CEA01PAGE  5  OF  6JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS: 260 EFPD.OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step2.5.12 for all CEA's except CEA #46.No T-alt installed on either RSPT.Voltage Traces are not required.INITIATING CUE:The CRS directs, "Complete the CEA Exercise Test for CEA # 46 using OP 2105.009 Supplement 2,beginning with Step 2.5."
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-ANO-2-JPM-NRC-CEA01PAGE  6  OF  6JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS: 260 EFPD.OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step2.5.12 for all CEA's except CEA #46.No T-alt installed on either RSPT.Voltage Traces are not required.INITIATING CUE:The CRS directs, "Complete the CEA Exercise Test for CEA # 46 using OP 2105.009 Supplement 2,beginning with Step 2.5."
+SATISFACTORY:                         UNSATISFACTORY:
-ANO-2-JPM-NRC-CMNT2PAGE  1  OF  6JOB PERFORMANCE MEASUREUNIT: 2 REV#: 000DATE:SYSTEM/DUTY AREA:ContainmentTASK:Drain the Containment Sump.  (Alternate Success Path)JTA#: ANO2-WCO-LRWBMS-NORM-7KA VALUERO:3.9SRO:4.2KA
+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-CEA01                                                                                 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS: 250 EFPD. OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEAs except CEA #46. No T-alt installed on either RSPT.
+TASK STANDARD: CEA #46 has been inserted seven (7) steps (5.25 inches) and withdrawn to the programmed insertion limit.
+TASK PERFORMANCE AIDS: OP 2105.009 Supplement 2. Complete Table 2 except for CEA 6-46.
+SIMULATOR SETUP: CEAs withdrawn to Programmed insertion limit
+ANO-2-JPM-NRC-CEA01                                                                           PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, "Complete the CEA Exercise Test for CEA #46 using OP 2105.009 Supplement 2, beginning Step 2.5."
+Start Time:
+PERFORMANCE CHECKLIST                                    STANDARDS                    (Circle One)
+: 1. Select position indication for CEA On panel 2C03, CEA #46 displayed     N/A SAT UNSAT (Step
+                  # 46.                              on all available CEAC module 2.5.3)                                      displays by one of the following methods:
+                                                      - Standard OM,
+                                                      - CEA group plot (Group 6 selected)
+                                                      - CEA values Page 2
+                                                      - CEA subgroup plot (Group 6 selected)
+(C)     2. Verify Group Select switch         On panel 2C03, verified group 6      N/A SAT UNSAT selected to group containing       selected.
+(Step 2.5.4)   individual CEA (C)     1. Place the individual CEA           On panel 2C03, selected CEA #46. N/A SAT UNSAT (Step selection switches to CEA #46.
+.5.5)                                      Observed the TENS in "4" and the UNITS in "6".
+OR Observed CEA #46 individual light ON.
+(C)     4. Place the mode select switch to    On panel 2C03, placed mode select    N/A SAT UNSAT (Step MANUAL INDIVIDUAL.                 switch to MI.
+.5.6)
+Observed MI (MANUAL INDIVIDUAL) light ON.
+(C)     5. Verify CEA #46 at upper            On insert 2JC-9058, moved CEA 46     N/A SAT UNSAT (Step electrical limit (UEL).            to UEL by going to WITHDRAW on 2.5.7)                                      CEA insert until #46 upper electrical limit (UEL) red light on.
+Observed UEL red light ON.
+ANO-2-JPM-NRC-CEA01                                                                         PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                                   STANDARDS                    (Circle One)
+(C)     2. Verify CEA #46 position within 7    Observed all Group 6 CEA's within    N/A SAT UNSAT (Step  inches of CEAs 1, 47, 48 and 49    seven (7) inches using CEAC #1, 2.5.2) throughout exercise.                CEAC #2, or PMS indications.
+Examiner Note:
+This step is a continuous action that must be completed while moving CEAs)
+(C)     6. Insert CEA #46 seven steps (>5). Inserted CEA seven steps (>5).      N/A SAT UNSAT (Step 2.5.8)                                      Observed insertion of 5.0 inches or greater on CEAC's #1 and #2 displays.
+(C)      7    Return CEA to UEL.                  CEA #46 withdrawn to UEL.            N/A SAT UNSAT (Step 2.5.9)
+(C)     8. Insert CEA #46 to Programmed        CEA #46 inserted to programmed       N/A SAT UNSAT (Step insertion limit                     insertion limit (UEL - 2 steps).
+.5.10)
+Observed CEA #46 at 148.5 on Pulse counter (149 on CEACs)
+: 9. Record results.                     Using OP 2105.009 Supplement A       N/A SAT UNSAT (Step Table 1, recorded the results of CEA 2.5.11)                                     #46 exercise.
+EXAMINER'S NOTE:
+The CEDMCS control may be left in any mode of operation.
+: 10. WHEN all required CEA               On insert 2JC-9058, selected off     N/A SAT UNSAT (Step movements complete,                 mode of operation.
+.5.12) THEN verify Mode Select switch in OFF.
+END StopTime:
+ANO-2-JPM-NRC-CEA01                                                               PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+EFPD.
+OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEAs except CEA #46.
+No T-alt installed on either RSPT.
+Voltage Traces are not required.
+INITIATING CUE:
+The CRS directs, "Complete the CEA Exercise Test for CEA # 46 using OP 2105.009 Supplement 2, beginning with Step 2.5."
+ANO-2-JPM-NRC-CEA01                                                               PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+EFPD.
+OP 2105.009 Supplement 2, "CEA Exercise Test" is completed successfully through step 2.5.12 for all CEAs except CEA #46.
+No T-alt installed on either RSPT.
+Voltage Traces are not required.
+INITIATING CUE:
+The CRS directs, "Complete the CEA Exercise Test for CEA # 46 using OP 2105.009 Supplement 2, beginning with Step 2.5."
+ANO-2-JPM-NRC-CMNT2                                                       PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT:      2                   REV #:   000                    DATE:
+SYSTEM/DUTY AREA:      Containment TASK:    Drain the Containment Sump. (Alternate Success Path)
+JTA#:    ANO2-WCO-LRWBMS-NORM-7 KA VALUE     RO:        3.9     SRO:        4.2       KA
 ==REFERENCE:==
-A3.01APPROVED FOR ADMINISTRATION TO: RO:
+A3.01 APPROVED FOR ADMINISTRATION TO:       RO:        X    SRO:      X TASK LOCATION:         INSIDE CR:     X      OUTSIDE CR:              BOTH:
-XSRO: XTASK LOCATION:INSIDE CR:
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD: SIMULATE:
+PLANT SITE:                    SIMULATOR:     Perform        CLASSROOM:
-PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:10 MinutesREFERENCE(S): OP-2104.014 LRW/BMS operationsEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+POSITION EVALUATED:      RO:                  SRO:
-ANO-2-JPM-NRC-CMNT2PAGE  2  OF  6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D ofNUREG 1021 Appendix E.JPM INITIAL TASK CONDITIONS:Containment Sump level ~76%TASK STANDARD:2CV-2060-1 closed and Aux building sump level did not trend <100%.TASK PERFORMANCE AIDS:OP 2104.014 Section 20 SIMULATOR SETUP:Any mode, Containment Sump level ~76%CV20612 value = 1, ramp = 8 sec, set on a Conditional trigger set for rw_2061o.Using the monitor function the containment sump level can be adjusted using the ctmwtr name andsetting the value to 25,000.
+ACTUAL TESTING ENVIRONMENT:       SIMULATOR:            PLANT SITE:     CLASSROOM:
-ANO-2-JPM-NRC-CMNT2PAGE  3  OF  6JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting withstep 20.1.3"START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C) 1.(Step 20.1.3)Open the following valves todrain CNTMT sump:Containment Sump Isolation2CV-2060-1 (2HS-2060-1)Containment Sump Isolation2CV-2061-2 (2HS-2061-2)On panel 2C17 placed CMNTsump isolation valve handswitch2HS-2060-1 to OPEN.On panel 2C16 placed CMNTsump isolation valve handswitch2HS-2061-2 to OPEN.Observed red lights ON abovehandswitchs  N/A  SAT  UNSAT 2.(Step 20.1.4)Using level indication orcorresponding computerpoints, monitor the following toprevent overflow:Aux Building sump (2LIS-2000or 2LIS-2000B)In service Waste tank:
+TESTING METHOD:      SIMULATE:            PERFORM:
--2T-20A (2LIS-2010)
+APPROXIMATE COMPLETION TIME IN MINUTES:           10 Minutes REFERENCE(S):    OP-2104.014 LRW/BMS operations EXAMINEE'S NAME:                                           Badge #:
--2T-20B (2LIS-2012)On panel 2C14, monitored AuxBuilding sump level (2LIS-2000or 2LIS-2000B), and 2T-20A(2LIS-2010) waste tank.
+EVALUATOR'S NAME:
-ORMonitor Aux Building Sumplevel and 2T-20A waste tanklevel using PMS computer  N/A  SAT  UNSATEXAMINER'S NOTE:The following is the alternate path portion of this JPM(C) 3.(Step 20.1.5)Cycle 2CV-2061-2(2HS-2061-2) as necessary toprevent overflowing AuxBuilding sump.EXAMINER CUE:  Ifcandidate report to the CRS2CV-2061-2 has failed open,then instruct candidate totake appropriate action.On panel 2C16 placed CMNTsump isolation valve handswitch2HS-2061-2 to CLOSE. Andobserved that the valve did notclose.Critical to maintain Aux Buildingsump level <100%. N/A  SAT  UNSAT ANO-2-JPM-NRC-CMNT2PAGE  4  OF  6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C) 4.(Step 20.1.6)WHEN draining complete,THEN close the followingvalves:2CV-2060-1 (2HS-2060-1)EXAMINER CUE:  Ifcandidate report to the CRSTech entry is required due2CV-2061-2 not closingacknowledge and report theCRS has entered theappropriate Tech Spec.On panel 2C17 placed CMNTsump isolation valve handswitch2HS-2060-1 to closed.(Critical)Observed 2CV-2060-1 closed bythe green light ON and red light OFF.(Not Critical)Maintained Aux Building sumplevel <100%.(Critical)  N/A  SAT  UNSAT ENDSTOP TIME:
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-ANO-2-JPM-NRC-CMNT2PAGE  5  OF  6JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS: Containment Sump level is ~76% Steps 20.1.1 and 20.1.2 of 2104.014 LRW/BMS operations are completeINITIATING CUE:The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMSoperations starting with step 20.1.3".
+SATISFACTORY:                  UNSATISFACTORY:
-ANO-2-JPM-NRC-CMNT2PAGE  6  OF  6JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS: Containment Sump level is ~76% Steps 20.1.1 and 20.1.2 of 2104.014 LRW/BMS operations are completeINITIATING CUE:The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMSoperations starting with step 20.1.3".
+PERFORMANCE CHECKLIST COMMENTS:
-ANO-2-JPM-NRC-RCP02PAGE  1  OF   7JOB PERFORMANCE MEASUREUNIT: 2REV #: 006DATE:SYSTEM/DUTY AREA:Abnormal/Emergency OperationsTASK:Restore component cooling water to reactor coolant pumps  (Alternate SuccessPath)JTA#:ANO2-RO-RCP-OFFNORM-9KA VALUERO:3.2SRO:2.9KA
+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-CMNT2                                                                PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:
+Containment Sump level ~76%
+TASK STANDARD:
+CV-2060-1 closed and Aux building sump level did not trend <100%.
+TASK PERFORMANCE AIDS:
+OP 2104.014 Section 20 SIMULATOR SETUP:
+Any mode, Containment Sump level ~76%
+CV20612 value = 1, ramp = 8 sec, set on a Conditional trigger set for rw_2061o.
+Using the monitor function the containment sump level can be adjusted using the ctmwtr name and setting the value to 25,000.
+ANO-2-JPM-NRC-CMNT2                                                                      PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting with step 20.1.3" START TIME:
+PERFORMANCE CHECKLIST                                STANDARDS                  (Circle One)
+(C)   1.       Open the following valves to       On panel 2C17 placed CMNT         N/A SAT UNSAT drain CNTMT sump:                  sump isolation valve handswitch (Step                                       2HS-2060-1 to OPEN.
+.1.3)  Containment Sump Isolation 2CV-2060-1 (2HS-2060-1)
+On panel 2C16 placed CMNT Containment Sump Isolation         sump isolation valve handswitch 2CV-2061-2 (2HS-2061-2)            2HS-2061-2 to OPEN.
+Observed red lights ON above handswitchs
+: 2.       Using level indication or          On panel 2C14, monitored Aux      N/A SAT UNSAT corresponding computer             Building sump level (2LIS-2000 (Step points, monitor the following to   or 2LIS-2000B), and 2T-20A 20.1.4)                                     (2LIS-2010) waste tank.
+prevent overflow:
+Aux Building sump (2LIS-2000       OR or 2LIS-2000B)
+In service Waste tank:             Monitor Aux Building Sump level and 2T-20A waste tank
+                 -        2T-20A (2LIS-2010)        level using PMS computer
+                 -        2T-20B (2LIS-2012)
+EXAMINERS NOTE:
+The following is the alternate path portion of this JPM (C)   3.       Cycle 2CV-2061-2                   On panel 2C16 placed CMNT         N/A SAT UNSAT (2HS-2061-2) as necessary to       sump isolation valve handswitch (Step 20.1.5)  prevent overflowing Aux            2HS-2061-2 to CLOSE. And Building sump.                     observed that the valve did not close.
+EXAMINER CUE: If                   Critical to maintain Aux Building candidate report to the CRS        sump level <100%.
+CV-2061-2 has failed open, then instruct candidate to take appropriate action.
+ANO-2-JPM-NRC-CMNT2                                                            PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                      STANDARDS                   (Circle One)
+(C)   4.      WHEN draining complete,     On panel 2C17 placed CMNT        N/A SAT UNSAT THEN close the following    sump isolation valve handswitch (Step                               2HS-2060-1 to closed.(Critical) 20.1.6) valves:
+Observed 2CV-2060-1 closed by 2CV-2060-1 (2HS-2060-1)     the green light ON and red light EXAMINER CUE: If            OFF. (Not Critical) candidate report to the CRS Tech entry is required due  Maintained Aux Building sump 2CV-2061-2 not closing      level <100%. (Critical) acknowledge and report the CRS has entered the appropriate Tech Spec.
+END STOP TIME:
+ANO-2-JPM-NRC-CMNT2                                                     PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:
+Containment Sump level is ~76%
+Steps 20.1.1 and 20.1.2 of 2104.014 LRW/BMS operations are complete INITIATING CUE:
+The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting with step 20.1.3".
+ANO-2-JPM-NRC-CMNT2                                                     PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:
+Containment Sump level is ~76%
+Steps 20.1.1 and 20.1.2 of 2104.014 LRW/BMS operations are complete INITIATING CUE:
+The CRS directs, "Drain the containment sump to 40% using 2104.014 LRW/BMS operations starting with step 20.1.3".
+ANO-2-JPM-NRC-RCP02                                                       PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT:    2                     REV #:   006                     DATE:
+SYSTEM/DUTY AREA:     Abnormal/Emergency Operations TASK:   Restore component cooling water to reactor coolant pumps (Alternate Success Path)
+JTA#:   ANO2-RO-RCP-OFFNORM-9 KA VALUE     RO:       3.2      SRO:        2.9        KA
 ==REFERENCE:==
-A4.08APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:
+A4.08 APPROVED FOR ADMINISTRATION TO:       RO:        X     SRO:     X TASK LOCATION:        INSIDE CR:      X      OUTSIDE CR:              BOTH:
-XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM:POSITION EVALUATED:RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S):EOP 2202.010 Attachment 21EXAMINEE'S NAME:BADGE# :EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-ANO-2-JPM-NRC-RCP02PAGE  2  OF   7JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG1021 Appendix E.JPM INITIAL TASK CONDITIONS
+PLANT SITE:                   SIMULATOR:          Perform     CLASSROOM:
-:    2A1 is re-energized from SU#2 following a degraded powersituation. 2202.010 ATT. 29 steps up to 1.M.7 have been completed. A CCW pump has beenrestored to service. SW has been aligned to CCW. 2Y1 and 2Y2 are cross-tied.TASK STANDARD:Controlled bleed off isolated to VCT and CBO relief valve isolated.TASK PERFORMANCE AIDS:Copy of EOP 2202.010 Attachment 21SIMULATOR SETUP:Set up CCW valves per EOP 2202.010 Attachment 29 "STARTUP XFM# 2USAGE" perform actions through step 1.M.6. Close RCP CCW RETURN valve, 2CV-5255-1, 2CV-5254-2 and2CV-5236-1. NO SIAS actuation and RCP seal temperatures >180.Set T4 = ccwrcp (this will trigger T4 when 2CV 5255 red light is energized).When 2CV 5255-1 is taken to open position, it will trip the breakerT4=DO_HS_5255_R off (override)T4=DO_HS_5255_G off (override)T4=CV52551 = 0.0% (component malfunction)
+POSITION EVALUATED:     RO:                  SRO:
-ANO-2-JPM-NRC-RCP02PAGE  3  OF   7JOB PERFORMANCE MEASUREINITIATING CUE:The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.(Step 2 A)Verify RCP bleed-off to VCTvalves open.On panel 2C17, verified2CV-4846-1 red light ON; controlswitch in OPEN.On panel 2C16 verified2CV-4847-2 red light ON; controlswitch in OPEN. N/A  SAT  UNSAT 2.(Step 2 B)Verify RCP Bleed-off ReliefIsolation to Quench Tank open.On panel 2C09, verified2CV-4856 red light ON; key-switch in LOCKED OPEN. N/A  SAT  UNSAT (C)3.(Step 3)Determine RCP Sealtemperature.EXAMINER'S NOTE: RCPseal temperature should be >180&#xba;F and step 3 will be NA.On panel 2C14 or on PMScomputer determined that RCPseal temperatures is > 180&#xba;Fand Step 3 is NA. N/A  SAT  UNSAT 4.(Step 4 A)Verify RCP CCW Return valve(2CV-5255-1) CLOSED.On panel 2C17, verified2CV-5255-1 CLOSED.Observed green light ON; redlight OFF above handswitch. N/A  SAT  UNSAT (C)5.(Step 4 B)Open RCP CCW Supply valve(2CV-5236-1).On panel 2C17, placedhandswitch for 2CV-5236-1 in "OPEN".Observed green light OFF; redlight ON. N/A  SAT  UNSAT ANO-2-JPM-NRC-RCP02PAGE  4  OF   7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)6.(Step 4 C)Open RCP CCW Return valve(2CV-5254-2).EXAMINER NOTE:If 2A4 isDeenergized, provide thefollowing CUE:2CV-5254-2 is open.On panel 2C16, Verifiedhandswitch for 2CV-5254-2"OPEN".Observed green light OFF; redlight ON.(NOTE: 2A4 may bedeenergized in this set thenperform the following:)Contact WCO for status of2CV5254-2. N/A  SAT  UNSATEXAMINER'S NOTE:When 2CV-5255-1 is taken to OPEN, the breaker will trip and cannot be reset. The valve will be boundclosed.(C)7.(Step 4 D)Modulate RCP CCW Returnvalve (2CV-5255-1) OPEN.EXAMINER CUE:If WCO sent to the valve;2CV-5255-1 cannot beopened.If AO sent to the breaker,2B53-G4; the breaker for2CV-5255-1 cannot be reset.On panel 2C17, took handswitchfor 2CV-5255-1 to "OPEN" forone (1) second then released.Observed red and green lights OFF.EXAMINEE may ask to dispatcha NLO to the valve and orbreaker. N/A  SAT  UNSATEXAMINER'S NOTE:The examinee may elect to monitor RCP seal cooldown before making the decision that CCW cannotbe restored. This monitoring of RCP seal cooldown may take 10 minutes to validate that 2CV-5255-1did not open.The examinee should go to step 5 of Attachment 21.
+ACTUAL TESTING ENVIRONMENT:       SIMULATOR:            PLANT SITE:      CLASSROOM:
-.(Step 5)Verify ALL RCP's secured.On panel 2C04, observed2P32A, B, C, and D RCPhandswitches in STOP or PTL.Observed handswitch is greenflagged; green light ON and redlight OFF. N/A  SAT  UNSAT ANO-2-JPM-NRC-RCP02PAGE  5  OF   7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 9.(Step 5 A)Close 2CV-5254-2.EXAMINER NOTE:  If 2A4 isDeenergized, provide thefollowing CUE:Waste Control Operatorreports that 2CV-5254-2 isclosed.On panel 2C16, placedhandswitch for 2CV-5254-2 to"CLOSE"Observed green light ON; redlight OFF.If 2A4 is deenergized thenperform the following:Direct WCO to manually close2CV 5254-2. N/A  SAT  UNSAT 10.(Step 5 A)Close 2CV-5236-1.On panel 2C17, placedhandswitch for 2CV-5236-1 to"CLOSE"Observed green light ON; redlight OFF. N/A  SAT  UNSAT (C)11.(Step 5 B 1)Close RCP bleedoff to VCTvalves.On panel 2C17, placedhandswitch for 2CV-4846-1 to"CLOSE."On panel 2C16, placedhandswitch for 2CV-4847-2 to"CLOSE."For each valve, observed greenlight ON; red light OFF. N/A  SAT  UNSAT (C)12.(Step 5 B 2)Close RCP bleedoff reliefisolation to quench tank valve(2CV-4856).On panel 2C09, placedhandswitch for 2CV-4856 to"CLOSE"Observed green light ON; redlight OFF. N/A  SAT  UNSAT ENDSTOP TIME:
+TESTING METHOD:     SIMULATE:             PERFORM:
-ANO-2-JPM-NRC-RCP02PAGE  6  OF   7JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS: 2A1 is re-energized from SU#2 following a degraded power situation. 2202.010 ATT. 29 steps up to 1.M.7 have been completed. CCW pumps have been restored.SW has been aligned to CCW 2Y1 and 2Y2 are cross connected.INITIATING CUE:The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."
+APPROXIMATE COMPLETION TIME IN MINUTES:            15 Minutes REFERENCE(S):    EOP 2202.010 Attachment 21 EXAMINEE'S NAME:                                         BADGE# :
-ANO-2-JPM-NRC-RCP02PAGE  7  OF   7JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS: 2A1 is re-energized from SU#2 following a degraded power situation. 2202.010 ATT. 29 steps up to 1.M.7 have been completed. CCW pumps have been restored.SW has been aligned to CCW 2Y1 and 2Y2 are cross connected.INITIATING CUE:The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."
+EVALUATOR'S NAME:
-ANO-2-JPM-NRC-CCW02PAGE  1  OF  5JOB PERFORMANCE MEASUREUNIT: 2 REV#: 012DATE:SYSTEM/DUTY AREA:Component Cooling Water SystemTASK:Shift Running CCW pumpsJTA#: ANO2-RO-CCW-NORM-10KA VALUERO:3.3SRO:3.1KA
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
+SATISFACTORY:                  UNSATISFACTORY:
+PERFORMANCE CHECKLIST COMMENTS:
+Start              Stop                  Total Time Time               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-RCP02                                                                   PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:            2A1 is re-energized from SU#2 following a degraded power situation. 2202.010 ATT. 29 steps up to 1.M.7 have been completed. A CCW pump has been restored to service. SW has been aligned to CCW. 2Y1 and 2Y2 are cross-tied.
+TASK STANDARD:         Controlled bleed off isolated to VCT and CBO relief valve isolated.
+TASK PERFORMANCE AIDS:              Copy of EOP 2202.010 Attachment 21 SIMULATOR SETUP: Set up CCW valves per EOP 2202.010 Attachment 29 "STARTUP XFM# 2 USAGE" perform actions through step 1.M.6. Close RCP CCW RETURN valve, 2CV-5255-1, 2CV-5254-2 and 2CV-5236-1. NO SIAS actuation and RCP seal temperatures >180.
+Set T4 = ccwrcp (this will trigger T4 when 2CV 5255 red light is energized).
+When 2CV 5255-1 is taken to open position, it will trip the breaker T4=DO_HS_5255_R off (override)
+T4=DO_HS_5255_G off (override)
+T4=CV52551 = 0.0% (component malfunction)
+ANO-2-JPM-NRC-RCP02                                                           PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:
+The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."
+START TIME:
+PERFORMANCE CHECKLIST                          STANDARDS                 (Circle One)
+: 1. Verify RCP bleed-off to VCT    On panel 2C17, verified          N/A SAT UNSAT valves open.                   2CV-4846-1 red light ON; control (Step                                switch in OPEN.
+A)
+On panel 2C16 verified 2CV-4847-2 red light ON; control switch in OPEN.
+: 2. Verify RCP Bleed-off Relief    On panel 2C09, verified          N/A SAT UNSAT Isolation to Quench Tank open. 2CV-4856 red light ON; key-(Step                                switch in LOCKED OPEN.
+B)
+(C)     3. Determine RCP Seal             On panel 2C14 or on PMS          N/A SAT UNSAT temperature.                   computer determined that RCP (Step                                seal temperatures is > 180&#xba;F
+: 3)  EXAMINERS NOTE: RCP           and Step 3 is NA.
+seal temperature should be >
+&#xba;F and step 3 will be NA.
+: 4. Verify RCP CCW Return valve    On panel 2C17, verified          N/A SAT UNSAT (2CV-5255-1) CLOSED.           2CV-5255-1 CLOSED.
+(Step 4 A)                                Observed green light ON; red light OFF above handswitch.
+(C)     5. Open RCP CCW Supply valve      On panel 2C17, placed            N/A SAT UNSAT (2CV-5236-1).                  handswitch for 2CV-5236-1 in (Step                                OPEN.
+B)
+Observed green light OFF; red light ON.
+ANO-2-JPM-NRC-RCP02                                                              PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                           STANDARDS                   (Circle One)
+(C)      6. Open RCP CCW Return valve      On panel 2C16, Verified           N/A SAT UNSAT (2CV-5254-2).                  handswitch for 2CV-5254-2 (Step                                 "OPEN".
+C)
+EXAMINER NOTE: If 2A4 is       Observed green light OFF; red light ON.
+Deenergized, provide the following CUE:
+(NOTE: 2A4 may be 2CV-5254-2 is open.            deenergized in this set then perform the following:)
+Contact WCO for status of 2CV5254-2.
+EXAMINERS NOTE:
+When 2CV-5255-1 is taken to OPEN, the breaker will trip and cannot be reset. The valve will be bound closed.
+(C)      7. Modulate RCP CCW Return        On panel 2C17, took handswitch    N/A SAT UNSAT valve (2CV-5255-1) OPEN.       for 2CV-5255-1 to "OPEN" for (Step                                 one (1) second then released.
+D)  EXAMINER CUE:
+If WCO sent to the valve;      Observed red and green lights 2CV-5255-1 cannot be           OFF.
+opened.
+EXAMINEE may ask to dispatch If AO sent to the breaker,     a NLO to the valve and or 2B53-G4; the breaker for       breaker.
+CV-5255-1 cannot be reset.
+EXAMINERS NOTE:
+The examinee may elect to monitor RCP seal cooldown before making the decision that CCW cannot be restored. This monitoring of RCP seal cooldown may take 10 minutes to validate that 2CV-5255-1 did not open.
+The examinee should go to step 5 of Attachment 21.
+: 8. Verify ALL RCPs secured. On panel 2C04, observed           N/A SAT UNSAT 2P32A, B, C, and D RCP (Step                                handswitches in STOP or PTL.
+)
+Observed handswitch is green flagged; green light ON and red light OFF.
+ANO-2-JPM-NRC-RCP02                                                          PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST                            STANDARDS               (Circle One)
+: 9. Close 2CV-5254-2.              On panel 2C16, placed          N/A SAT UNSAT handswitch for 2CV-5254-2 to (Step                                 CLOSE 5 A)
+EXAMINER NOTE: If 2A4 is       Observed green light ON; red Deenergized, provide the       light OFF.
+following CUE:
+If 2A4 is deenergized then Waste Control Operator         perform the following:
+reports that 2CV-5254-2 is closed.                        Direct WCO to manually close 2CV 5254-2.
+: 10. Close 2CV-5236-1.              On panel 2C17, placed          N/A SAT UNSAT handswitch for 2CV-5236-1 to (Step                                 CLOSE 5 A)
+Observed green light ON; red light OFF.
+(C)    11. Close RCP bleedoff to VCT      On panel 2C17, placed          N/A SAT UNSAT valves.                        handswitch for 2CV-4846-1 to (Step                                 CLOSE.
+B 1)
+On panel 2C16, placed handswitch for 2CV-4847-2 to CLOSE.
+For each valve, observed green light ON; red light OFF.
+(C)    12. Close RCP bleedoff relief      On panel 2C09, placed          N/A SAT UNSAT isolation to quench tank valve handswitch for 2CV-4856 to (Step  (2CV-4856).                    CLOSE 5 B 2)
+Observed green light ON; red light OFF.
+END STOP TIME:
+ANO-2-JPM-NRC-RCP02                                                    PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+A1 is re-energized from SU#2 following a degraded power situation.
+.010 ATT. 29 steps up to 1.M.7 have been completed.
+CCW pumps have been restored.
+SW has been aligned to CCW 2Y1 and 2Y2 are cross connected.
+INITIATING CUE:
+The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."
+ANO-2-JPM-NRC-RCP02                                                    PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+A1 is re-energized from SU#2 following a degraded power situation.
+.010 ATT. 29 steps up to 1.M.7 have been completed.
+CCW pumps have been restored.
+SW has been aligned to CCW 2Y1 and 2Y2 are cross connected.
+INITIATING CUE:
+The SM/CRS directs, "Restore CCW to the RCP's using EOP 2202.010 Attachment 21."
+ANO-2-JPM-NRC-CCW02                                                         PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT:      2                    REV #:  012                    DATE:
+SYSTEM/DUTY AREA:       Component Cooling Water System TASK:    Shift Running CCW pumps JTA#:    ANO2-RO-CCW-NORM-10 KA VALUE      RO:        3.3     SRO:       3.1       KA
 ==REFERENCE:==
-A4.01APPROVED FOR ADMINISTRATION TO: RO:
+A4.01 APPROVED FOR ADMINISTRATION TO:        RO:   X        SRO:
-XSRO:TASK LOCATION:INSIDE CR:
+TASK LOCATION:          INSIDE CR:  X        OUTSIDE CR:                BOTH:
-XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD: SIMULATE:
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:8 MinutesREFERENCE(S): OP-2104.028 Component Cooling Water System OperationsEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.
+PLANT SITE:                     SIMULATOR:    Perform        CLASSROOM:
-ANO-2-JPM-NRC-CCW02PAGE  2  OF  5JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021Appendix E.JPM INITIAL TASK CONDITIONS:2P-33B running in a normal configuration. Component Cooling water loops are cross tied.Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pumprebuild.TASK STANDARD:2P33A running supplying CCW and 2P33B & 2P-33C in PULL-TO-LOCK.TASK PERFORMANCE AIDS:OP 2104.028 Section 18.2.5 SIMULATOR SETUP:Any power level or mode.2P-33B CCW pump in service with CCW loops cross tied.
+POSITION EVALUATED:       RO:                 SRO:
-ANO-2-JPM-NRC-CCW02PAGE  3  OF  5JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028Step 18.2.5."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.(Step 18.2.5 A& B)Contact AO to vent 2P-33A.EXAMINER CUE:AO reports casing ventedand 2CCW-1001 closed.Using telephone or radio,contacted AO and directed himto vent 2P-33A Casing, using2CCW-1001. N/A  SAT  UNSAT(C) 2.(Step 18.2.5 C)Verify 2P-33C handswitch(2HS-5234) in PTL.On panel 2C14, placed 2P-33Chandswitch (2HS-5234) in Pull-To-Lock. N/A  SAT  UNSAT(C) 3.(Step 18.2.5 D)Start 2P-33A.EXAMINER CUE:If requested 2P-33A isrunning satisfactory.On panel 2C14, took 2P-33Ahandswitch (2HS-5225) toSTART and releasedhandswitch.Observed red light ON abovehandswitch. N/A  SAT  UNSAT(C) 4.(Step 18.2.5 E)Place 2P-33B handswitch(2HS-5228) to PTL.On panel 2C14, placed 2P-33Bhandswitch (2HS-5228) in Pull-To-Lock.Observed 2K-12 PUMP 2P-33A/B/C LOCKED alarm. (NotCritical)  N/A  SAT  UNSAT 5.(Step 18.2.5 F)Observe normal flow anddischarge pressure.EXAMINER CUE:Local operator reportsdischarge pressure 110 psiglocally.On panel 2C14, observed CCWflow between 1000 to 3000 gpm.Directed operator to observedischarge pressure between 100to 120 psig locally. N/A  SAT  UNSAT ENDSTOP TIME:
+ACTUAL TESTING ENVIRONMENT:        SIMULATOR:           PLANT SITE:       CLASSROOM:
-ANO-2-JPM-NRC-CCW02PAGE  4  OF  5JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS:2P-33B is running in a normal configuration.Maintenance requests that 2P-33A be started and ran in single pump operation for PMTafter pump rebuild.INITIATING CUE:The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."
+TESTING METHOD:       SIMULATE:           PERFORM:
-ANO-2-JPM-NRC-CCW02PAGE  5  OF  5JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS:2P-33B is running in a normal configuration.Maintenance requests that 2P-33A be started and ran in single pump operation for PMTafter pump rebuild.INITIATING CUE:The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."
+APPROXIMATE COMPLETION TIME IN MINUTES:          8 Minutes REFERENCE(S):     OP-2104.028 Component Cooling Water System Operations EXAMINEE'S NAME:                                           Badge #:
-JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  1 of 7SYSTEM/DUTY AREA:Diesel Generator System (Alternate Success Path)TASK:Start up the AAC diesel generator manually locally during a Loss of Offsite PowerJTA # :ANO2-AO-AACDG-OFFNORM-18KA VALUERO:4.0SRO:4.3KA
+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-CCW02                                                                           PAGE 2 OF 5 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:
+P-33B running in a normal configuration. Component Cooling water loops are cross tied.
+Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.
+TASK STANDARD:
+P33A running supplying CCW and 2P33B & 2P-33C in PULL-TO-LOCK.
+TASK PERFORMANCE AIDS:
+OP 2104.028 Section 18.2.5 SIMULATOR SETUP:
+Any power level or mode.
+P-33B CCW pump in service with CCW loops cross tied.
+ANO-2-JPM-NRC-CCW02                                                                  PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:
+The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."
+START TIME:
+PERFORMANCE CHECKLIST                           STANDARDS                   (Circle One)
+: 1.        Contact AO to vent 2P-33A. Using telephone or radio,         N/A SAT UNSAT contacted AO and directed him (Step EXAMINER CUE:                 to vent 2P-33A Casing, using 18.2.5 A                                2CCW-1001.
+        & B)      AO reports casing vented and 2CCW-1001 closed.
+(C)   2.        Verify 2P-33C handswitch      On panel 2C14, placed 2P-33C      N/A SAT UNSAT (2HS-5234) in PTL.            handswitch (2HS-5234) in Pull-(Step                                   To-Lock.
+.2.5 C)
+(C)   3.        Start 2P-33A.                 On panel 2C14, took 2P-33A        N/A SAT UNSAT handswitch (2HS-5225) to (Step 18.2.5 D)                               START and released EXAMINER CUE:                 handswitch.
+If requested 2P-33A is running satisfactory.
+Observed red light ON above handswitch.
+(C)   4.        Place 2P-33B handswitch       On panel 2C14, placed 2P-33B      N/A SAT UNSAT (2HS-5228) to PTL.            handswitch (2HS-5228) in Pull-(Step 18.2.5 E)                               To-Lock.
+Observed 2K-12 PUMP 2P-33A/B/C LOCKED alarm. (Not Critical)
+: 5.        Observe normal flow and       On panel 2C14, observed CCW       N/A SAT UNSAT discharge pressure.           flow between 1000 to 3000 gpm.
+(Step 18.2.5 F)
+Directed operator to observe EXAMINER CUE:                 discharge pressure between 100 to 120 psig locally.
+Local operator reports discharge pressure 110 psig locally.
+END STOP TIME:
+ANO-2-JPM-NRC-CCW02                                                        PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:
+P-33B is running in a normal configuration.
+Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.
+INITIATING CUE:
+The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."
+ANO-2-JPM-NRC-CCW02                                                        PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:
+P-33B is running in a normal configuration.
+Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.
+INITIATING CUE:
+The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."
+JOB PERFORMANCE MEASURE JPM#      ANO-2-JPM-NRC-AACLS               REV     09                                    PAGE 1 of 7 SYSTEM/DUTY AREA:         Diesel Generator System (Alternate Success Path)
+TASK:     Start up the AAC diesel generator manually locally during a Loss of Offsite Power JTA # :   ANO2-AO-AACDG-OFFNORM-18 KA VALUE         RO:         4.0       SRO:         4.3        KA
 ==REFERENCE:==
-A4.01APPROVED FOR ADMINISTRATION TO: RO:
+A4.01 APPROVED FOR ADMINISTRATION TO:            RO:         X       SRO:       X TASK LOCATION:        INSIDE CR:               OUTSIDE CR:          X       BOTH:
-XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-XBOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD  (PERFORM OR SIMULATE):PLANT SITE:SimulateSIMULATOR:CLASSROOM:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD: SIMULATE:
+PLANT SITE:        Simulate      SIMULATOR:                      CLASSROOM:
-PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 minutesREFERENCE(S)OP 2104.037, Exhibit 1EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:DATE:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM 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:
+POSITION EVALUATED:         RO:           SRO:
-JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  2 of 7THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D ofNUREG 1021 Appendix E.JPM INITIAL TASK CONDITIONS:The following conditions exist:The reactor has tripped due to a loss of off-site power.Both emergency diesel generators are tied to their respective buses.An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 wasunsuccessful.TASK STANDARD:This is an alternate success path JPM.The AAC Diesel has been started and is at 4160 V and 900 rpm with the output breaker (2A-1001) closed.The 480V bus 2B16 has been powered from the AAC diesel generator.TASK PERFORMANCE AIDS:OP 2104.037 Exhibit 1 JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  3 of 7INITIATING CUE:The CRS provides the following direction:Start the AAC Diesel Generator using OP 2104.037 Exhibit 1 and bring the unit up to rated speed and voltagecarrying house loads.START TIME:EXAMINER'S NOTE:Provide examinee with copy of 2104.037, Exhibit 1If asked about the conditions of the alarms, tell the examinee that the only alarm in is H-3, GENERATORCIRCUIT BREAKER OPEN.If asked if 125 VDC is available, tell them that the indications for bus availability are as seen (assumes noactual maintenance in progress)PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)1.(Step1.1)Place "Local/Remote" switch inLOCAL.POSITIVE CUE:"Local/Remote" switchindicates LOCAL.On panel 2C-440, placed the"Local/Remote" switch (2HS-7118) in LOCAL. N/A  SAT  UNSAT 2.(Step1.2)Start the AAC Diesel using thelocal start switch.EXAMINER'S NOTE:Provide the following cueafter ~ 35 seconds when thelocal start switch is taken toSTART.EXAMINER'S CUE:There has been NO changein AAC diesel generatorfrequency or noise level.On panel 2C-440 turned thelocal control switch CW to start(2HS-7117). N/A  SAT  UNSATExaminer's NOTE:Step 2 requires a transition to the AAC diesel engine room.
+ACTUAL TESTING ENVIRONMENT:            SIMULATOR:            PLANT SITE:            CLASSROOM:
-.(Step2.1)Open the pre-lube pumpsolenoid (2SV-7224) for >10seconds.EXAMINER'S CUE:Air noise is heard.On the south side of the engineat the generator end, rotated themanual operator of 2SV-7224CW to open for >10 seconds. N/A  SAT  UNSAT JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  4 of 7 (C)4.(Step2.2)Open EITHER of the air startsolenoid valves: - 2SV-7222 OR - 2SV-7223EXAMINER'S CUE:Engine speed and noiselevels are rising.On the south side of the engineat the generator end, rotated themanual operator of one of the airstart solenoid valves CW to open.Looked for an increase in enginenoise and/or discharge of oil andair from the air start motors. N/A  SAT  UNSAT 5.(Step2.3)Close the air start solenoidvalve that was opened.On the south side of the engineat the generator end, rotated themanual operator for the air startsolenoid valve CCW to close. N/A  SAT  UNSAT 6.(Step2.3)Close the pre-lube solenoid(2SV-7224).On the south side of the engineat the generator end, rotated themanual operator of 2SV-7224CCW to close. N/A  SAT  UNSAT 7.(Step 3)Verify the AAC DieselGenerator is at rated speedand voltage.EXAMINER'S CUE:Frequency indicates 60 Hzand voltage indicates 4160V.On panel 2C-440, observedgenerator frequency at 60 Hzand voltage at 4160V. N/A  SAT  UNSAT JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  5 of 7EXAMINER'S NOTE:When the examinee inspects the condition of 2A-1001, provide the NEGATIVE CUE first to indicate thatthe breaker has NOT automatically closed. Once the action has been taken to close the breaker, providethe POSITIVE CUE.(C)8.(Step4.1)Verify the AAC GeneratorOutput Breaker (2A-1001) isCLOSEDEXAMINER'S CUE:The green breaker OPENlight is lit.ANDThe white breaker springcharging light is lit.EXAMINER'S CUE:The Red breaker CLOSEDlight is lit.Observed breaker positionindication on the door of 2A-1001.Rotated breaker local controlswitch for 2A-1001 to theCLOSE position. N/A  SAT  UNSATTRANSITION NOTE:Go to the upstairs area of the switchgear room.
+TESTING METHOD:         SIMULATE:            PERFORM:
-.(Step4.2)Verify the London Feed toMCC 2B161 breaker 2B16-A1is OPEN.EXAMINER'S CUE:Green OPEN light is lit on2B16-A1 and mechanicalposition indicator showinggreen openObserved the mechanicalposition indicator breaker for2B16-A1 to show green openand the green breaker positionindication light is lit. N/A  SAT  UNSAT 10.(Step4.3)Verify Load Center 2B16Supply from the AAC diesel(2B16-B1) is CLOSED.EXAMINER'S CUE:Red CLOSED light is lit on2B16-B1 and mechanicalposition indicator showingred closed.Observed the mechanicalposition indicator breaker for2B16-B1 to show red closed andthe red breaker positionindication light is lit. N/A  SAT  UNSAT ENDSTOP TIME:
+APPROXIMATE COMPLETION TIME IN MINUTES:                      20 minutes REFERENCE(S)       OP 2104.037, Exhibit 1 EXAMINEES NAME:                                              Badge #:
-JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  6 of 7Examiner's CopyJPM INITIAL TASK CONDITIONSThe following conditions exist:The reactor has tripped due to a loss of off-site power.Both emergency diesel generators are tied to their respective buses.An attempt to start the AACDG from the Control Room to energize4160v Non-vital bus 2A1 was unsuccessful.INITIATING CUE:The CRS provides the following direction:Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.Bring the unit up to rated speed and voltage carrying house loads.
+EVALUATORS NAME:                                              DATE:
-JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 09PAGE  7 of 7Examinee's CopyJPM INITIAL TASK CONDITIONSThe following conditions exist:The reactor has tripped due to a loss of off-site power.Both emergency diesel generators are tied to their respective buses.An attempt to start the AACDG from the Control Room to energize4160v Non-vital bus 2A1 was unsuccessful.INITIATING CUE:The CRS provides the following direction:Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.Bring the unit up to rated speed and voltage carrying house loads.
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-JOB PERFORMANCE MEASURE  ANO-2-JPM-NRC-AUADVREV. 04PAGE    1   of   6SYSTEM/DUTY AREA:    Steam Dump & Bypass Control TASK:    Operate the SDBCS valves locally.  (Upstream Atmospheric Dump Valve "A")
+SATISFACTORY:                                 UNSATISFACTORY:
-JTA #:    ANO2-AO-SDBCS-OFFNORM-10KA VALUE RO:
+PERFORMANCE CHECKLIST COMMENTS:
-.0SRO:      3.1 KA
+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#      ANO-2-JPM-NRC-AACLS               REV     09                                    PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:
+The following conditions exist:
+The reactor has tripped due to a loss of off-site power.
+Both emergency diesel generators are tied to their respective buses.
+An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.
+TASK STANDARD:
+This is an alternate success path JPM.
+The AAC Diesel has been started and is at 4160 V and 900 rpm with the output breaker (2A-1001) closed.
+The 480V bus 2B16 has been powered from the AAC diesel generator.
+TASK PERFORMANCE AIDS:
+OP 2104.037 Exhibit 1
+JOB PERFORMANCE MEASURE JPM#       ANO-2-JPM-NRC-AACLS                  REV       09                                          PAGE 3 of 7 INITIATING CUE:
+The CRS provides the following direction:
+Start the AAC Diesel Generator using OP 2104.037 Exhibit 1 and bring the unit up to rated speed and voltage carrying house loads.
+START TIME:
+EXAMINERS NOTE:
+Provide examinee with copy of 2104.037, Exhibit 1 If asked about the conditions of the alarms, tell the examinee that the only alarm in is H-3, GENERATOR CIRCUIT BREAKER OPEN.
+If asked if 125 VDC is available, tell them that the indications for bus availability are as seen (assumes no actual maintenance in progress)
+PERFORMANCE CHECKLIST                                 STANDARDS                       (Circle One)
+(C)      1. Place Local/Remote switch in      On panel 2C-440, placed the            N/A SAT UNSAT LOCAL.                              Local/Remote switch (2HS-(Step 7118) in LOCAL.
+.1)
+POSITIVE CUE:
+Local/Remote switch indicates LOCAL.
+: 2. Start the AAC Diesel using the      On panel 2C-440 turned the             N/A SAT UNSAT local start switch.                 local control switch CW to start (Step (2HS-7117).
+.2)
+EXAMINERS NOTE:
+Provide the following cue after ~ 35 seconds when the local start switch is taken to START.
+EXAMINERS CUE:
+There has been NO change in AAC diesel generator frequency or noise level.
+Examiners NOTE:
+Step 2 requires a transition to the AAC diesel engine room.
+: 3. Open the pre-lube pump              On the south side of the engine        N/A SAT UNSAT solenoid (2SV-7224) for >10         at the generator end, rotated the (Step seconds.                            manual operator of 2SV-7224 2.1)
+CW to open for >10 seconds.
+EXAMINERS CUE:
+Air noise is heard.
+JOB PERFORMANCE MEASURE JPM#   ANO-2-JPM-NRC-AACLS               REV     09                                   PAGE 4 of 7 (C)   4. Open EITHER of the air start     On the south side of the engine   N/A SAT UNSAT solenoid valves:                 at the generator end, rotated the (Step manual operator of one of the air 2.2)  - 2SV-7222 OR start solenoid valves CW to
+             - 2SV-7223                      open.
+EXAMINERS CUE:                  Looked for an increase in engine noise and/or discharge of oil and Engine speed and noise air from the air start motors.
+levels are rising.
+: 5. Close the air start solenoid     On the south side of the engine   N/A SAT UNSAT valve that was opened.           at the generator end, rotated the (Step manual operator for the air start 2.3) solenoid valve CCW to close.
+: 6. Close the pre-lube solenoid      On the south side of the engine   N/A SAT UNSAT (2SV-7224).                      at the generator end, rotated the (Step manual operator of 2SV-7224 2.3)
+CCW to close.
+: 7. Verify the AAC Diesel            On panel 2C-440, observed         N/A SAT UNSAT Generator is at rated speed      generator frequency at 60 Hz (Step and voltage.                     and voltage at 4160V.
+)
+EXAMINERS CUE:
+Frequency indicates 60 Hz and voltage indicates 4160V.
+JOB PERFORMANCE MEASURE JPM#      ANO-2-JPM-NRC-AACLS                REV      09                                    PAGE 5 of 7 EXAMINERS NOTE:
+When the examinee inspects the condition of 2A-1001, provide the NEGATIVE CUE first to indicate that the breaker has NOT automatically closed. Once the action has been taken to close the breaker, provide the POSITIVE CUE.
+(C)      8. Verify the AAC Generator           Observed breaker position        N/A SAT UNSAT Output Breaker (2A-1001) is        indication on the door of 2A-(Step CLOSED                             1001.
+.1)
+EXAMINERS CUE:                    Rotated breaker local control switch for 2A-1001 to the The green breaker OPEN CLOSE position.
+light is lit.
+AND The white breaker spring charging light is lit.
+EXAMINERS CUE:
+The Red breaker CLOSED light is lit.
+TRANSITION NOTE:
+Go to the upstairs area of the switchgear room.
+: 9. Verify the London Feed to          Observed the mechanical          N/A SAT UNSAT MCC 2B161 breaker 2B16-A1          position indicator breaker for (Step is OPEN.                           2B16-A1 to show green open 4.2) and the green breaker position indication light is lit.
+EXAMINERS CUE:
+Green OPEN light is lit on 2B16-A1 and mechanical position indicator showing green open
+: 10. Verify Load Center 2B16            Observed the mechanical          N/A SAT UNSAT Supply from the AAC diesel         position indicator breaker for (Step (2B16-B1) is CLOSED.               2B16-B1 to show red closed and 4.3) the red breaker position indication light is lit.
+EXAMINERS CUE:
+Red CLOSED light is lit on 2B16-B1 and mechanical position indicator showing red closed.
+END STOP TIME:
+JOB PERFORMANCE MEASURE JPM#   ANO-2-JPM-NRC-AACLS     REV  09                        PAGE 6 of 7 Examiners Copy JPM INITIAL TASK CONDITIONS The following conditions exist:
+The reactor has tripped due to a loss of off-site power.
+Both emergency diesel generators are tied to their respective buses.
+An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.
+INITIATING CUE:
+The CRS provides the following direction:
+Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.
+Bring the unit up to rated speed and voltage carrying house loads.
+JOB PERFORMANCE MEASURE JPM#   ANO-2-JPM-NRC-AACLS     REV  09                        PAGE 7 of 7 Examinees Copy JPM INITIAL TASK CONDITIONS The following conditions exist:
+The reactor has tripped due to a loss of off-site power.
+Both emergency diesel generators are tied to their respective buses.
+An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.
+INITIATING CUE:
+The CRS provides the following direction:
+Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.
+Bring the unit up to rated speed and voltage carrying house loads.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV                     REV. 04                                 PAGE 1 of 6 SYSTEM/DUTY AREA:           Steam Dump & Bypass Control TASK:    Operate the SDBCS valves locally. (Upstream Atmospheric Dump Valve A)
+JTA #:   ANO2-AO-SDBCS-OFFNORM-10 KA VALUE        RO:       3.0             SRO:     3.1            KA
 ==REFERENCE:==
+A4.08 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:                      CLASSROOM: _________
+POSITION EVALUATED:                       RO:                             SRO: _________
+ACTUAL TESTING ENVIRONMENT: SIMULATOR:                            PLANT SITE:            CLASSROOM: _______
+TESTING METHOD:                   SIMULATE:                               PERFORM: _________
+APPROXIMATE COMPLETION TIME IN MINUTES:                   15 minutes REFERENCE(S):        OP 2105.008 EXAMINEES NAME:                                                   BADGE#:
+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 ANO-2-JPM-NRC-AUADV                        REV. 04                                    PAGE 2 of 6 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
+JPM INITIAL TASK CONDITIONS:
+The plant is in Mode 3 due to a station blackout.
+The MSIVs are closed.
+Instrument Air is not available from Unit 1.
+CV-1002 (Isolation MOV for A Upstream Atmospheric Dump Valve) is OPEN 2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.
+TASK STANDARD: A Upstream Atmospheric Dump Valve (2CV-1001) has been throttled open to control A SG pressure.
+TASK PERFORMANCE AIDS:               OP 2105.008 Exhibit 2; flashlight
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV                          REV. 04                                        PAGE 3 of 6 INITIATING CUE:
+The SM/CRS directs, Take local manual control of the A Upstream Atmospheric Dump Valve 2CV-1001 using OP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig.
+START TIME:
+PERFORMANCE CHECKLIST                                       STANDARDS                          (Circle One)
+EXAMINERS NOTES:
+: 1. Two flashlights are required for lighting. One for the instructor and one for the student
+: 2. Dump valves are reverse seating. Air is on the bottom of valve and valve is air to close. Therefore when valve strokes downward valve is opening.
+: 3. The positioner is reverse acting. Therefore if the student operates the bleed valve on the outlet of the I/P the dump valve will not open.
+(C)       1. Place the handle position selector to At 2CV-1001 actuator, rotated handle     N/A SAT         UNSAT MAN.                                position selector switch to MAN.
+(Step 4.1)    EXAMINERS CUE:
+Handle position selector switch in MAN (C)       2. Rotate handwheel clockwise until      Locally, rotated 2CV-1001                N/A SAT         UNSAT resistance felt.                      handwheel CW until resistance felt (Step 4.2)    EXAMINERS CUE:
+Handwheel rotated CW and resistance felt
+: 3. Verify ADV fully closed.              Locally verified valve position using    N/A SAT         UNSAT stem indication.
+(Step    EXAMINERS CUE:
+.3)
+Valve position is as indicated.
+(C)       4. Place handle position selector to     Locally, rotated handle position         N/A SAT         UNSAT LOCK                                selector to LOCK (Step 4.4)    EXAMINERS CUE:                        (Left to center if facing straight on)
+Handle position selector in LOCK (C)       5. Isolate instrument air to diaphragm   Closed 2IA-287 by rotating hand          N/A SAT         UNSAT of 2CV-1001 (2IA-287)                 wheel CW until resistance felt.
+(Step 4.5)    EXAMINERS CUE:
+Resistance felt with CW rotation.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV                           REV. 04                                     PAGE 4 of 6 PERFORMANCE CHECKLIST                                      STANDARDS                          (Circle One)
+EXAMINERS NOTE:
+: 1. The following step requires that the correct bleed valve is opened and the plug removed. If the plug is not removed the task is not successful.
+: 2. There are three bleed valves. If the I/P output to the positioner bleed valve is operated instead of one of the two listed the task is not successful.
+(C)        6. Open applicable local air bleed off   At 2CV-1001, opened one of the           N/A SAT        UNSAT valve for 2CV-1001.                   following local air bleedoff valves (Step                                          by rotating valve CCW and 4.6 &     EXAMINERS CUE:                       removing the plug from the bleed 4.7)                                          port.
+Air bleed observed by feel and /
+or sound coming from bleed-off          1. Air supply to the positioner.
+port.
+: 2. Positioner output to the operating diaphragm.
+EXAMINERS NOTES:
+: 1. Dump valves are reverse seating. Air is on bottom of valve and valve is air to close. Therefore when valve strokes downward valve is opening.
+: 2. The dump valve will fail open rapidly if handle position selector held in the OPER position. The candidate should transition from OPER back to LOCK back to OPER while monitoring Steam Generator Pressure.
+: 3. Step 4.8 - Opening the ADV MOV Isolation, 2CV-1002, was completed as stated in the initial conditions.
+(C)        7. Place handle position selector to     Placed handle position selector to       N/A SAT        UNSAT OPER.                               OPER (Step 4.9)    EXAMINERS CUE:
+Handle position selector in OPER, the valve is opening and pressure is slowly lowering.
+(C)        8. When desired valve position is        Placed the handle position selector      N/A SAT        UNSAT obtained, place handle position       to LOCK when the desired valve (Step    selector to LOCK.                   position was obtained.
+.10)
+EXAMINERS CUE:
+CV-1001 valve stops movement. S/G pressure is ~
+psia and stable.
+END STOP TIME:
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV                         REV. 04                            PAGE 5 of 6 EXAMINERS COPY JPM INITIAL TASK CONDITIONS:
+The plant is in Mode 3 due to a station blackout.
+The MSIVs are closed.
+Instrument Air is not available from Unit 1.
+CV-1002 (Isolation MOV for A Upstream Atmospheric Dump Valve) is OPEN 2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.
+INITIATING CUE:
+The SM/CRS directs, Take local manual control of the A Upstream Atmospheric Dump Valve 2CV-1001 using OP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-AUADV                         REV. 04                            PAGE 6 of 6 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:
+The plant is in Mode 3 due to a station blackout.
+The MSIVs are closed.
+Instrument Air is not available from Unit 1.
+CV-1002 (Isolation MOV for A Upstream Atmospheric Dump Valve) is OPEN 2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.
+INITIATING CUE:
+The SM/CRS directs, Take local manual control of the A Upstream Atmospheric Dump Valve 2CV-1001 using OP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig.
-A4.08APPROVED FOR ADMINISTRATION TO:RO:         XSRO:          XTASK LOCATION: INSIDE CR:OUTSIDE CR:
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW                    REV     15                                  PAGE 1 of 7 SYSTEM/DUTY AREA:            Spent Fuel Pool Cooling System TASK:     Line up to fill the spent fuel pool from the RWT JTA # :   ANO2-WCO-SFP-NORM-2 KA VALUE         RO:            3.1        SRO:         3.5         KA
-XBOTH:_______SUGGESTED TESTING ENVIRONMENT AND METHOD(PERFORM OR SIMULATE):PLANT SITE: SimulateSIMULATOR: CLASSROOM:
-_________POSITION EVALUATED:RO:SRO:_________ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:
-_______TESTING METHOD:SIMULATE:PERFORM:_________APPROXIMATE COMPLETION TIME IN MINUTES:    15 minutesREFERENCE(S):    OP 2105.008EXAMINEE'S NAME:BADGE#:EVALUATOR'S NAME:
-DATE:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:__________Start Time__________ Stop Time__________ Total TimeSignature indicates this JPM has been compared to its applicable procedure by a qualified individual (not theexaminee) and is current with that revision.SIGNED: DATE:
-JOB PERFORMANCE MEASURE  ANO-2-JPM-NRC-AUADVREV. 04PAGE    2   of   6THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021Appendix E.JPM INITIAL TASK CONDITIONS:The plant is in Mode 3 due to a station blackout.The MSIV's are closed. Instrument Air is not available from Unit 1.2CV-1002 (Isolation MOV for "A" Upstream Atmospheric Dump Valve)is OPEN2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.TASK STANDARD: "A" Upstream Atmospheric Dump Valve (2CV-1001) has been throttled open to control 'A' SGpressure.TASK PERFORMANCE AIDS:    OP 2105.008 Exhibit 2; flashlight JOB PERFORMANCE MEASURE  ANO-2-JPM-NRC-AUADVREV. 04PAGE    3   of   6INITIATING CUE:The SM/CRS directs, "Take local manual control of the "A" Upstream Atmospheric Dump Valve 2CV-1001 usingOP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig."START TIME:PERFORMANCE CHECKLIST STANDARDS(Circle One)EXAMINER'S NOTES:
-.Two flashlights are required for lighting. One for the instructor and one for the student 2.Dump valves are reverse seating. Air is on the bottom of valve and valve is air to close. Therefore when valvestrokes downward valve is opening.
-.The positioner is reverse acting. Therefore if the student operates the bleed valve on the outlet of the I/P the dumpvalve will not open.(C)1.(Step 4.1)Place the handle position selector to "MAN".EXAMINER'S CUE:Handle position selector switchin "MAN"At 2CV-1001 actuator, rotated handleposition selector switch to "MAN". N/A    SAT     UNSAT (C)2.(Step 4.2)Rotate handwheel clockwise untilresistance felt.EXAMINER'S CUE:Handwheel rotated CW andresistance feltLocally, rotated 2CV-1001handwheel CW until resistance felt  N/A    SAT     UNSAT 3.(Step 4.3)Verify ADV fully closed.EXAMINER'S CUE:Valve position is as indicated.Locally verified valve position usingstem indication. N/A    SAT     UNSAT (C)4.(Step 4.4)Place handle position selector to"LOCK"EXAMINER'S CUE:Handle position selector in"LOCK"Locally, rotated handle positionselector to "LOCK" (Left to center if facing straight on)  N/A    SAT     UNSAT (C)5.(Step 4.5)Isolate instrument air to diaphragmof 2CV-1001 (2IA-287)EXAMINER'S CUE:Resistance felt with CWrotation.Closed 2IA-287 by rotating handwheel CW until resistance felt. N/A    SAT     UNSAT JOB PERFORMANCE MEASURE  ANO-2-JPM-NRC-AUADVREV. 04PAGE    4   of   6PERFORMANCE CHECKLIST STANDARDS(Circle One)EXAMINER'S NOTE:
-.The following step requires that the correct bleed valve is opened and the plug removed. If the plug is not removedthe task is not successful.
-.There are three bleed valves. If the I/P output to the positioner bleed valve is operated instead of one of the twolisted the task is not successful.(C)6.(Step4.6 &4.7)Open applicable local air bleed offvalve for 2CV-1001.EXAMINER'S CUE:Air bleed observed by feel and /or sound coming from bleed-offport.At 2CV-1001, opened one of thefollowing local air bleedoff valvesby rotating valve CCW andremoving the plug from the bleedport.1.Air supply to the positioner.
-.Positioner output to theoperating diaphragm. N/A    SAT     UNSATEXAMINER'S NOTES:
-.Dump valves are reverse seating. Air is on bottom of valve and valve is air to close. Therefore whenvalve strokes downward valve is opening.
-.The dump valve will fail open rapidly if handle position selector held in the OPER position. Thecandidate should transition from OPER back to LOCK back to OPER while monitoring SteamGenerator Pressure.
-.Step 4.8 - Opening the ADV MOV Isolation, 2CV-1002, was completed as stated in the initialconditions.(C)7.(Step 4.9)Place handle position selector to"OPER".EXAMINER'S CUE:Handle position selector in"OPER", the valve is openingand pressure is slowly lowering.Placed handle position selector toOPER  N/A    SAT     UNSAT (C)8.(Step 4.10)When desired valve position isobtained, place handle positionselector to "LOCK".EXAMINER'S CUE:2CV-1001 valve stopsmovement. S/G pressure is ~975 psia and stable.Placed the handle position selectorto LOCK when the desired valveposition was obtained. N/A    SAT     UNSAT ENDSTOP TIME:
-JOB PERFORMANCE MEASURE  ANO-2-JPM-NRC-AUADVREV. 04PAGE    5   of   6EXAMINER'S COPYJPM INITIAL TASK CONDITIONS:The plant is in Mode 3 due to a station blackout.The MSIV's are closed. Instrument Air is not available from Unit 1.2CV-1002 (Isolation MOV for "A" Upstream Atmospheric Dump Valve)is OPEN2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.INITIATING CUE:The SM/CRS directs, "Take local manual control of the "A" Upstream Atmospheric Dump Valve 2CV-1001 usingOP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig."
-JOB PERFORMANCE MEASURE  ANO-2-JPM-NRC-AUADVREV. 04PAGE    6   of   6EXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:The plant is in Mode 3 due to a station blackout.The MSIV's are closed. Instrument Air is not available from Unit 1.2CV-1002 (Isolation MOV for "A" Upstream Atmospheric Dump Valve)is OPEN2PI-1007 Main steam pressure gauge has been aligned IAW 2105.008 Exhibit 2.INITIATING CUE:The SM/CRS directs, "Take local manual control of the "A" Upstream Atmospheric Dump Valve 2CV-1001 usingOP 2105.008 Exhibit 2 and modulate to maintain S/G pressure 950 - 1000 psig."
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  1 of 7SYSTEM/DUTY AREA:Spent Fuel Pool Cooling SystemTASK:Line up to fill the spent fuel pool from the RWTJTA # :ANO2-WCO-SFP-NORM-2KA VALUERO:3.1SRO:3.5KA
 ==REFERENCE:==
-A2.03APPROVED FOR ADMINISTRATION TO: RO:
+A2.03 APPROVED FOR ADMINISTRATION TO:                  RO:       X        SRO:       X TASK LOCATION:          INSIDE CR:                   OUTSIDE CR:         X       BOTH:
-XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:
+SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):
-XBOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD  (PERFORM OR SIMULATE):PLANT SITE:SimulateSIMULATOR:CLASSROOM:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD: SIMULATE:
+PLANT SITE:        Simulate         SIMULATOR:                        CLASSROOM:
-X PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 minutesREFERENCE(S)OP 2104.006, Section 11.0EXAMINEE'S NAME:BADGE#:EVALUATOR'S NAME:DATE:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM 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:
+POSITION EVALUATED:            RO:              SRO:
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  2 of 7THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG1021 Appendix E.JPM INITIAL TASK CONDITIONS:The following conditions exist:1. The Plant is shutdown and in Mode 6 with the core off loaded.2. 2K11-J5, FUEL POOL LEVEL LOW is in alarm.3. SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated4. SFP purification is aligned to the RWT5. An operator is stationed at the SFP to monitor level increase.6. Cask loading operations are NOT in progress.TASK STANDARD:Spent fuel pool level has been raised to 401.5 feet by adding water from the RWT.TASK PERFORMANCE AIDS:1. OP 2104.006, Section 11.0 JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  3 of 7INITIATING CUE:The CRS provides the following direction:Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 toraise level to 401.5 feetSTART TIME:EXAMINER'S NOTE:Provide examinee with OP 2104.006, Section 11.0.PERFORMANCE CHECKLISTSTANDARDS(Circle One)TRANSITION NOTE:Go to RAB elevation 335', Spent Fuel Pool Pump area (left of elevator upon exiting).(C)1.(Step 11.2)Secure Spent Fuel PoolPurification Pump (2P66).POSITIVE CUE:Green light ON, red light OFF.Locally rotated 2P66 handswitch(2HS-5411) to STOP andreleased.Observed green light ON, redlight OFF. N/A  SAT  UNSATEXAMINER'S NOTE:
+ACTUAL TESTING ENVIRONMENT:                SIMULATOR:              PLANT SITE:         CLASSROOM:
-IF student misinterprets cue and performs step 11.3 vice 11.4, THEN task will still beaccomplished (student will realign purification from SFP to RWT)(C)2.(Step 11.4)Close Purification Loop toRWT (2FP-29).POSITIVE CUE:2FP-29 pointer indicatesclosed..Rotated handwheel on 2FP-29with chain operator CW toCLOSE. N/A  SAT  UNSATTRANSITION NOTE:Go to RAB elevation 354', Spent Fuel Pool Valve Gallery (left of elevator upon exiting).(C)3.(Step 11.4)Open Purification Loop to FuelPool Isolation (2FP-17).POSITIVE CUE:2FP-17 stem out, resistance felt.Rotated handwheel on 2FP-17CCW to OPEN. N/A  SAT  UNSAT JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  4 of 7PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)4.(Step 11.4)Verify open Purification Loopto Fuel Pool (2FP-18).POSITIVE CUE:2FP-18 stem out, resistancefelt.Rotated handwheel on 2FP-18 CW one turn then CCW tofully OPEN.
+TESTING METHOD:            SIMULATE:         X    PERFORM:
-ORAt 2FP-18, examined valveposition indicators to determinevalve OPEN position. N/A  SAT  UNSATTRANSITION:Go to RAB elevation 335', Spent Fuel Pool Pump area (left of elevator upon exiting)..EXAMINERS NOTE:If radiological conditions do not allow access to the Purification Pump Room, have examinee describe theactions that would be taken.(C)5.(Step 11.5)Close Purification PumpDischarge valve (2FP-10).POSITIVE CUE:2FP-10 stem in, resistance felt.Rotated handwheel on 2FP-10CW to CLOSE. N/A  SAT  UNSAT 6.(Step 11.6)Verify 2P-66 Interlock SelectSwitch (2HS-5413) in NORMALPOSITIVE CUE:2HS-5413 is in the NORMALposition.Visually verified that 2HS-5413is in the left NORMAL position. N/A  SAT  UNSAT 7.(Step 11.7)Establish communications withoperator at SFP.POSITIVE CUE:Operator acknowledgesready to monitor SFP level.Using plant telephones, radios,or the Gaitronics; contactedoperator stationed at SFP. N/A  SAT  UNSAT JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  5 of 7 (C)8.(Step 11.8)Start Spent Fuel PoolPurification Pump (2P66).POSITIVE CUE:Red light ON, green light OFF.Locally rotated 2P66 handswitch(2HS-5411) to START andreleased.Observed red light ON, greenlight OFF. N/A  SAT  UNSATEXAMINERS NOTE:If radiological conditions do not allow access to the Purification Pump Room, have examinee describe theactions that would be taken.(C)9.(Step 11.9)Throttle open discharge valve2FP-10.POSITIVE CUES:Flow noise is heard.Suction and Dischargepump pressures aresteady throughout.2F4 and 2T5 P's indicate flow.Pump P is 75 psid.Suction and Dischargepump pressures aresteady.Locally rotated 2FP-10 CCW asfollows: Until noise was heard. Observed pump suction anddischarge pressure steadywhile making smalladjustments. Observed  P across 2F-4(2PDI-5406) and 2T5 (2PDI-5407) as indication of flow.P is within log limits (2PI-5409 minus 2PI-5410). Observed suction pressureand discharge pressure notoscillating. N/A  SAT  UNSATEXAMINER'S NOTE:Provide the following cue:Operator at the SFP reports SFP at 401.5 feet.(C)10.(Step 11.10)Stop Spent Fuel PoolPurification Pump (2P66).POSITIVE CUE:Green light ON, red light OFF.Locally placed 2P66 handswitch(2HS-5411) to STOP andreleased.Observed green light ON, redlight OFF. N/A  SAT  UNSAT ENDSTOP TIME:
+APPROXIMATE COMPLETION TIME IN MINUTES:                           20 minutes REFERENCE(S)       OP 2104.006, Section 11.0 EXAMINEES NAME:                                                  BADGE#:
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  6 of 7Examiner's CopyJPM INITIAL TASK CONDITIONSThe following conditions exist: The Plant is shutdown and in Mode 6 with the core off loaded. 2K11-J5, FUEL POOL LEVEL LOW is in alarm. SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which hasbeen isolated SFP purification is aligned to the RWT An operator is stationed at the SFP to monitor level increase. Cask loading operations are NOT in progress.INITIATING CUE:The CRS provides the following direction:Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP2104.006, Section 11.0 to raise level to 401.5 feet.
+EVALUATORS NAME:                                                   DATE:
-JOB PERFORMANCE MEASUREANO-2-JPM-NRC-SFPAW REV 15PAGE  7 of 7Examinee's CopyJPM INITIAL TASK CONDITIONSThe following conditions exist: The Plant is shutdown and in Mode 6 with the core off loaded. 2K11-J5, FUEL POOL LEVEL LOW is in alarm. SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which hasbeen isolated SFP purification is aligned to the RWT An operator is stationed at the SFP to monitor level increase. Cask loading operations are NOT in progress.INITIATING CUE:The CRS provides the following direction:Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP2104.006, Section 11.0 to raise level to 401.5 feet.
+THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:
-Appendix D Scenario 1Form ES-D-1Revision 0Page 1 of 3Facility: ANO-2Scenario No.:  1 (New)Op-Test No.:  2011-1Examiners:Operators:Initial Conditions:100% MOL, All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure ControlValve 2PCV-0231 jacked closed. RED Train Maintenance Week.Turnover:100% Power 250 EFPD. EOOS indicates 'Minimal Risk'. Gland Seal Steam Pressure Control Valve2PCV-0231 is jacked closed; manually control seal steam pressure. RED Train Maintenance Week.Evolution scheduled:  Fill the Quench Tank to ~78% IAW 2103.007 Quench Tank and Reactor DrainTank Operations. Step 7.2.1 of 2103.007 for filling the quench tank is complete.EventNo.Malf. No.EventType*EventDescription 1 N (BOP)N (SRO)Fill the Quench Tank.
+SATISFACTORY:                                      UNSATISFACTORY:
-CV0242R (ATC)C (SRO)#1 Main Turbine Generator Control Valve fails Closed.Tech Spec for SRO.
+PERFORMANCE CHECKLIST COMMENTS:
-RCSLOCATCAC (ATC)C (SRO)Shutdown required due to 15 gpm Reactor Coolantsystem leak on 'A' cold leg. Tech Spec for SRO.
+Start Time:                    Stop Time:                   Total Time:
-2C-11AI_TIC_1602MTGVIBINC I (BOP)I (SRO)Main Turbine Generator lube oil controller setpoint failshigh.Main Turbine Generator Vibrations increase causing areactor trip.
+Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.
-500LOSE500 500LOSE161M (ALL)Loss of Offsite Power causing natural circulation of theRCS.6FW2PW5BAFTM(ALL)'B' Main Feed water line breaks inside containment.
+SIGNED:                                                                      DATE:
-A308C (BOP)C (SRO)#1 EDG output breaker fails to automatically close.
-CVC2P36LOLVLCVC2P36BSIASCVC2P36CSIASI (ATC)I (SRO)Backup Charging pumps fail to start on SIAS or LowPZR level.(Not credited for Malfunction after EOP entry due to possiblybeing discovered prior to EOP entry) 9BS2P35BFALBS2P35AFAULTK06-B01C (BOP)C (SRO)2P-35B Spray pump failed to automatically start and2P-35A trips upon start.*   (N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajorTotal malfunctions. = 8, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 2,EOPs with substantive actions =1, EOP Contingencies = 1, Critical tasks = 3.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW                 REV       15                                    PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:
-Appendix D Scenario 1Form ES-D-1Revision 0Page 2 of 3Scenario #1 Objectives 1)Evaluate individual ability to operate reactor coolant auxiliary equipment.
+The examiner shall verify the candidates have been briefed in accordance with Parts A, C, and D of NUREG 1021 Appendix E.
-)Evaluate individual response to a failure of a Main Turbine Control valve.
+JPM INITIAL TASK CONDITIONS:
-)Evaluate individual response to a small Reactor Coolant system leak.
+The following conditions exist:
-)Evaluate individual ability to perform a reduction in plant power.
+: 1. The Plant is shutdown and in Mode 6 with the core off loaded.
-)Evaluate individual ability to respond to a failed controller.
+: 2. 2K11-J5, FUEL POOL LEVEL LOW is in alarm.
-)Evaluate individual ability to respond to Degraded Electrical power.
+: 3. SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated
-)Evaluate individual response to a failure of Emergency Diesel Generator output breaker toautomatically close.
+: 4. SFP purification is aligned to the RWT
-)Evaluate individual ability to mitigate an Excess Steam Demand inside containment.
+: 5. An operator is stationed at the SFP to monitor level increase.
-)Evaluate individual response to a failure of automatic control of Pressurizer level control.
+: 6. Cask loading operations are NOT in progress.
-)Evaluate individual ability to monitor operation of Engineered Safety Features equipment.
+TASK STANDARD:
-SCENARIO #1 NARRATIVESimulator session begins with the plant at 100% power steady state.Gland Seal Steam PressureControl Valve, 2PCV-0231 is jacked closed.When the crew has completed their control room walk down and brief, The BOP will fill theQuench Tank using the reactor makeup water system.After the BOP has completed filling the Quench Tank to the appropriate level and cued by leadexaminer; the #1 MTG control valve will fail closed. The SRO will enter AOP, 2203.024 Loss ofTurbine Load. The SRO will direct the ATC to commence normal boration from a Boric AcidMakeup tank to lower reactor power until Tave and Tref are within 2 degrees. The SRO should callwork management to investigate failure and may decide to fail #1 CV closed or have the BOP holdthe test pushbutton for #1 CV which will maintain the valve closed.After a five minute delay, a 15 gpm RCS leak will start. The SRO will enter the excess RCSleakage AOP, OP 2203.016. ATC and BOP will perform RCS Leak rate determinations. The SROwill enter Tech Spec 3.4.6.2. The SRO will direct the ATC to maintain pressurizer level within 5%of set point by starting additional charging pumps as needed. The SRO will also direct the ATC toisolate letdown to determine the leak location. After the crew has determined the leak is not inletdown, they will restore letdown and the crew will change the boration method to commence aplant shutdown.
+Spent fuel pool level has been raised to 401.5 feet by adding water from the RWT.
-Appendix D Scenario 1Form ES-D-1Revision 0Page 3 of 3SCENARIO #1 NARRATIVE (continued)After letdown has been restore to service and cued by the lead examiner, the Main TurbineGenerator (MTG) lube oil temperature controller setpoint will fail high causing lube oiltemperatures to raise. The SRO should refer to the high bearing temperature annunciator correctiveaction 2K02- B7 (alarm setpoint is 225&#xba;F) and attempt to manually control lube oil temperature. Iftemperature goes above 230 degrees Fahrenheit, the crew should manually trip the reactor. Iftemperature does not go about 230 degrees Fahrenheit, then Turbine vibrations will begin to riserequiring a turbine and reactor trip.The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the Reactortrips a Loss of Offsite Power will occur and a Feedwater line break will start on the feedwater lineto 'B' S/G due to a water hammer on the Feedwater line Check valve. The Crew will manuallyactuate Main Steam Isolation Signal (MSIS) or verify that a Main Steam Isolation signalautomatically actuates. The Crew will secure and/or verify that Emergency Feedwater (EFW) is notfeeding 'B' Steam generator. The output breaker for #1 EDG will not automatically close and theBOP should close the output breaker. The ATC will notice that the backup charging pumps did notstart. The ATC will secure two Reactor Coolant Pumps when RCS pressure goes below 1400 psia.The Containment Spray pump 2P-35B will fail to automatically start and Containment Spray pump2P-35A will trip. The BOP will manual start 2P-35B to ensure containment design pressure is notexceeded.The SRO will diagnose Functional Recovery due to two events in progress (Excess RCS leakageand Excess Steam demand) and enter OP 2202.009, Functional Recovery.The crew will manually control Reactor Coolant Temperature once the 'B' SG boils dry using theupstream Atmospheric Dump Valve on 'A' SG. The ATC will control RCS pressure usingauxiliary spray.
+TASK PERFORMANCE AIDS:
-Appendix D Scenario 1Form ES-D-2Revision 0Page 1 of 22Simulator Instructions for Scenario 1Reset simulator to MOL 100% power IC steady state.Ensure that AACG is secured and annunciators clear.Place MINIMAL RISK, Green Train Protected and RED Train Maintenance Week signs on 2C11.'A' CCP lead charging pump. 'C' CCP aligned to green train.2PCV-0231, Gland sealing steam pressure control valve failed closed.Quench tank level ~72%, 2K10 E4 is in alarm.T1, T2, T3, T4, & T5 set to false.T4 = Reactor tripT5 = CSAS-2EventNo.Malf. No.Value/RampTimeEventDescription 1Fill the Quench Tank.
+: 1. OP 2104.006, Section 11.0
-SV0242Trigger = T1 0#1 Main Turbine Generator Control Valve fails Closed.Tech Spec for SRO.
-RCSLOCATCATrigger = T1 15 /Delay 5min.Shutdown required due to 15 gpm Reactor Coolant systemleak on 'A' cold leg. Tech Spec for SRO.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW                 REV      15                                     PAGE 3 of 7 INITIATING CUE: The CRS provides the following direction:
-2C-11AI_TIC_1602Trigger = T2MTGVIBINCTrigger = T3 200 25 /5 min.Main Turbine Generator lube oil controller setpoint failshigh.Main Turbine Generator Vibrations increase causing areactor trip.
+Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 to raise level to 401.5 feet START TIME:
-500LOSE500 500LOSE161Trigger = T4 True TrueLoss of Offsite Power causing natural circulation of theRCS.6FW2PW5BAFTTrigger = T4 2000/10 min.'B' Main Feed water line breaks inside containment.
+EXAMINERS NOTE:
-A308NO_AUTO_CL#1 EDG output breaker fails to automatically close.
+Provide examinee with OP 2104.006, Section 11.0.
-CVC2P36LOLVLCVC2P36BSIASCVC2P36CSIAS TrueBackup Charging pumps fail to start on SIAS or Low PZRlevel.9BS2P35BFALBS2P35AFAULTK06-B01Trigger = T5 TrueTrue / del30 sec.ON / del.31 sec.2P-35B Spray pump failed to automatically start and 2P-35A trips upon start.
+PERFORMANCE CHECKLIST                               STANDARDS                   (Circle One)
-Appendix D Scenario 1Form ES-D-2Revision 0Page 2 of 22Simulator Operator CUEsAt T=0Fill the Quench Tank.Cued byleadexaminerTrigger T1#1 Main Turbine Generator Control Valve fails Closed. Tech Spec forSRO.Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist infailing #1 Main Turbine Generator Control valve closed.Cue: When called as Chemistry, report that you will sample the RCS for Iodine at the timerequested.Cued byleadexaminerTrigger T1Shutdown required due to 15 gpm Reactor Coolant system leak on 'A'cold leg. Tech Spec for SRO.Cue: If requested, then report that seal water pump is running for requested charging pump.Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.Cued byleadexaminerTrigger T2Main Turbine Generator lube oil controller setpoint fails high.Cue: If contacted as the NLO for 2CV-1602 status, then report valve position based on the actualvalve position and report flow noise is heard through the valve if it is open.Cue: When contacted as the NLO, then report that Lube oil flows to bearing are normal buttemperature are elevated (report temperatures based on actually simulator temperatures).Cued byleadexaminerTrigger T3Main Turbine Generator Vibrations increase.Cued byleadexaminer orreactor tripTrigger T4Loss of Offsite Power causing natural circulation of the RCS.'B' Main Feed water line break inside containment.Backup Charging pumps fail to start on SIAS or Low PZR level.Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.Cued byCSASTrigger T52P-35B Spray pump failed to automatically start and 2P-35A tripsupon start.Cue: if requested as WCO, then report that 2P-35B Containment Spray pump post start checks aresatisfactory.
+TRANSITION NOTE:
-Appendix D Scenario 1Form ES-D-2Revision 0Page 3 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   1Event
+Go to RAB elevation 335', Spent Fuel Pool Pump area (left of elevator upon exiting).
+(C)      1. Secure Spent Fuel Pool           Locally rotated 2P66 handswitch   N/A SAT UNSAT (Step   Purification Pump (2P66).        (2HS-5411) to STOP and 11.2)                                    released.
+POSITIVE CUE:
+Observed green light ON, red Green light ON, red light light OFF.
+OFF.
+EXAMINER'S NOTE:
+IF student misinterprets cue and performs step 11.3 vice 11.4, THEN task will still be accomplished (student will realign purification from SFP to RWT)
+(C)      2. Close Purification Loop to       Rotated handwheel on 2FP-29       N/A SAT UNSAT (Step   RWT (2FP-29).                    with chain operator CW to 11.4)                                    CLOSE.
+POSITIVE CUE:
+FP-29 pointer indicates closed.
+                   .
+TRANSITION NOTE:
+Go to RAB elevation 354', Spent Fuel Pool Valve Gallery (left of elevator upon exiting).
+(C)      3. Open Purification Loop to Fuel   Rotated handwheel on 2FP-17       N/A SAT UNSAT (Step   Pool Isolation (2FP-17).         CCW to OPEN.
+.4)
+POSITIVE CUE:
+FP-17 stem out, resistance felt.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW                  REV     15                                   PAGE 4 of 7 PERFORMANCE CHECKLIST                                STANDARDS                (Circle One)
+(C)      4. Verify open Purification Loop     Rotated handwheel on 2FP-18      N/A SAT UNSAT (Step  to Fuel Pool (2FP-18).            CW one turn then CCW to 11.4)                                    fully OPEN.
+POSITIVE CUE:
+OR 2FP-18 stem out, resistance felt.
+At 2FP-18, examined valve position indicators to determine valve OPEN position.
+TRANSITION:
+Go to RAB elevation 335', Spent Fuel Pool Pump area (left of elevator upon exiting)..
+EXAMINERS NOTE:
+If radiological conditions do not allow access to the Purification Pump Room, have examinee describe the actions that would be taken.
+(C)      5. Close Purification Pump           Rotated handwheel on 2FP-10      N/A SAT UNSAT (Step  Discharge valve (2FP-10).         CW to CLOSE.
+.5)
+POSITIVE CUE:
+FP-10 stem in, resistance felt.
+: 6. Verify 2P-66 Interlock Select     Visually verified that 2HS-5413  N/A SAT UNSAT (Step  Switch (2HS-5413) in              is in the left NORMAL position.
+.6)  NORMAL POSITIVE CUE:
+HS-5413 is in the NORMAL position.
+: 7. Establish communications with     Using plant telephones, radios,  N/A SAT UNSAT (Step  operator at SFP.                  or the Gaitronics; contacted 11.7)                                    operator stationed at SFP.
+POSITIVE CUE:
+Operator acknowledges ready to monitor SFP level.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW                 REV      15                                   PAGE 5 of 7 (C)      8. Start Spent Fuel Pool             Locally rotated 2P66 handswitch   N/A SAT UNSAT (Step  Purification Pump (2P66).         (2HS-5411) to START and 11.8)                                    released.
+POSITIVE CUE:
+Observed red light ON, green Red light ON, green light light OFF.
+OFF.
+EXAMINERS NOTE:
+If radiological conditions do not allow access to the Purification Pump Room, have examinee describe the actions that would be taken.
+(C)      9. Throttle open discharge valve     Locally rotated 2FP-10 CCW as     N/A SAT UNSAT (Step  2FP-10.                           follows:
+.9)
+Until noise was heard.
+POSITIVE CUES:                       Observed pump suction and discharge pressure steady Flow noise is heard.
+while making small Suction and Discharge              adjustments.
+pump pressures are Observed P across 2F-4 steady throughout.
+(2PDI-5406) and 2T5 (2PDI-2F4 and 2T5 Ps indicate           5407) as indication of flow.
+flow.                                P is within log limits (2PI-Pump      P is 75 psid.            5409 minus 2PI-5410).
+Suction and Discharge              Observed suction pressure pump pressures are                 and discharge pressure not steady.                            oscillating.
+EXAMINERS NOTE:
+Provide the following cue:
+Operator at the SFP reports SFP at 401.5 feet.
+(C)      10. Stop Spent Fuel Pool              Locally placed 2P66 handswitch    N/A SAT UNSAT (Step  Purification Pump (2P66).         (2HS-5411) to STOP and 11.10)                                    released.
+POSITIVE CUE:
+Observed green light ON, red Green light ON, red light light OFF.
+OFF.
+END STOP TIME:
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW            REV    15                                PAGE 6 of 7 Examiners Copy JPM INITIAL TASK CONDITIONS The following conditions exist:
+The Plant is shutdown and in Mode 6 with the core off loaded.
+K11-J5, FUEL POOL LEVEL LOW is in alarm.
+SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated SFP purification is aligned to the RWT An operator is stationed at the SFP to monitor level increase.
+Cask loading operations are NOT in progress.
+INITIATING CUE: The CRS provides the following direction:
+Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 to raise level to 401.5 feet.
+JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-SFPAW            REV    15                                PAGE 7 of 7 Examinees Copy JPM INITIAL TASK CONDITIONS The following conditions exist:
+The Plant is shutdown and in Mode 6 with the core off loaded.
+K11-J5, FUEL POOL LEVEL LOW is in alarm.
+SFP level is 401.25 feet due to a leak on a SFP cooling pump packing gland which has been isolated SFP purification is aligned to the RWT An operator is stationed at the SFP to monitor level increase.
+Cask loading operations are NOT in progress.
+INITIATING CUE: The CRS provides the following direction:
+Add water to the spent fuel pool (SFP) from the refueling water tank (RWT) using OP 2104.006, Section 11.0 to raise level to 401.5 feet.
+Appendix D                                   Scenario 1                                                   Form ES-D-1 Facility: ANO-2                            Scenario No.: 1 (New)                           Op-Test No.: 2011-1 Examiners:                                                 Operators:
+Initial Conditions:
+% MOL, All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed. RED Train Maintenance Week.
+Turnover:
+% Power 250 EFPD. EOOS indicates Minimal Risk. Gland Seal Steam Pressure Control Valve 2PCV-0231 is jacked closed; manually control seal steam pressure. RED Train Maintenance Week.
+Evolution scheduled: Fill the Quench Tank to ~78% IAW 2103.007 Quench Tank and Reactor Drain Tank Operations. Step 7.2.1 of 2103.007 for filling the quench tank is complete.
+Event           Malf. No.           Event                                             Event No.                                Type*                                         Description 1                                N (BOP)         Fill the Quench Tank.
+N (SRO) 2      CV0242                    R (ATC)         #1 Main Turbine Generator Control Valve fails Closed.
+C (SRO)         Tech Spec for SRO.
+      RCSLOCATCA                C (ATC)         Shutdown required due to 15 gpm Reactor Coolant C (SRO)         system leak on A cold leg. Tech Spec for SRO.
+      2C-11                     I (BOP)         Main Turbine Generator lube oil controller setpoint fails AI_TIC_1602               I (SRO)         high.
+MTGVIBINC                                 Main Turbine Generator Vibrations increase causing a reactor trip.
+      500LOSE500                M (ALL)         Loss of Offsite Power causing natural circulation of the 500LOSE161                                RCS.
+      FW2PW5BAFT                M(ALL)          B Main Feed water line breaks inside containment.
+      416 A308                  C (BOP)         #1 EDG output breaker fails to automatically close.
+C (SRO) 8      CVC2P36LOLVL              I (ATC)         Backup Charging pumps fail to start on SIAS or Low CVC2P36BSIAS              I (SRO)         PZR level. (Not credited for Malfunction after EOP entry due to possibly being discovered prior to EOP entry)
+CVC2P36CSIAS 9      BS2P35BFAL                C (BOP)         2P-35B Spray pump failed to automatically start and BS2P35AFAULT              C (SRO)         2P-35A trips upon start.
+K06-B01
+ * (N)ormal,      (R)eactivity,   (I)nstrument,    (C)omponent,         (M)ajor Total malfunctions. = 8, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 2, EOPs with substantive actions =1, EOP Contingencies = 1, Critical tasks = 3.
+Revision 0                                                                                         Page 1 of 3
+Appendix D                              Scenario 1                                    Form ES-D-1 Scenario #1 Objectives
+: 1)  Evaluate individual ability to operate reactor coolant auxiliary equipment.
+: 2)  Evaluate individual response to a failure of a Main Turbine Control valve.
+: 3)  Evaluate individual response to a small Reactor Coolant system leak.
+: 4)  Evaluate individual ability to perform a reduction in plant power.
+: 5)  Evaluate individual ability to respond to a failed controller.
+: 6)  Evaluate individual ability to respond to Degraded Electrical power.
+: 7)  Evaluate individual response to a failure of Emergency Diesel Generator output breaker to automatically close.
+: 8) Evaluate individual ability to mitigate an Excess Steam Demand inside containment.
+: 9) Evaluate individual response to a failure of automatic control of Pressurizer level control.
+: 10) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.
+SCENARIO #1 NARRATIVE Simulator session begins with the plant at 100% power steady state. Gland Seal Steam Pressure Control Valve, 2PCV-0231 is jacked closed.
+When the crew has completed their control room walk down and brief, The BOP will fill the Quench Tank using the reactor makeup water system.
+After the BOP has completed filling the Quench Tank to the appropriate level and cued by lead examiner; the #1 MTG control valve will fail closed. The SRO will enter AOP, 2203.024 Loss of Turbine Load. The SRO will direct the ATC to commence normal boration from a Boric Acid Makeup tank to lower reactor power until Tave and Tref are within 2 degrees. The SRO should call work management to investigate failure and may decide to fail #1 CV closed or have the BOP hold the test pushbutton for #1 CV which will maintain the valve closed.
+After a five minute delay, a 15 gpm RCS leak will start. The SRO will enter the excess RCS leakage AOP, OP 2203.016. ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2. The SRO will direct the ATC to maintain pressurizer level within 5%
+of set point by starting additional charging pumps as needed. The SRO will also direct the ATC to isolate letdown to determine the leak location. After the crew has determined the leak is not in letdown, they will restore letdown and the crew will change the boration method to commence a plant shutdown.
+Revision 0                                                                      Page 2 of 3
+Appendix D                             Scenario 1                                     Form ES-D-1 SCENARIO #1 NARRATIVE (continued)
+After letdown has been restore to service and cued by the lead examiner, the Main Turbine Generator (MTG) lube oil temperature controller setpoint will fail high causing lube oil temperatures to raise. The SRO should refer to the high bearing temperature annunciator corrective action 2K02- B7 (alarm setpoint is 225&#xba;F) and attempt to manually control lube oil temperature. If temperature goes above 230 degrees Fahrenheit, the crew should manually trip the reactor. If temperature does not go about 230 degrees Fahrenheit, then Turbine vibrations will begin to rise requiring a turbine and reactor trip.
+The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the Reactor trips a Loss of Offsite Power will occur and a Feedwater line break will start on the feedwater line to B S/G due to a water hammer on the Feedwater line Check valve. The Crew will manually actuate Main Steam Isolation Signal (MSIS) or verify that a Main Steam Isolation signal automatically actuates. The Crew will secure and/or verify that Emergency Feedwater (EFW) is not feeding B Steam generator. The output breaker for #1 EDG will not automatically close and the BOP should close the output breaker. The ATC will notice that the backup charging pumps did not start. The ATC will secure two Reactor Coolant Pumps when RCS pressure goes below 1400 psia.
+The Containment Spray pump 2P-35B will fail to automatically start and Containment Spray pump 2P-35A will trip. The BOP will manual start 2P-35B to ensure containment design pressure is not exceeded.
+The SRO will diagnose Functional Recovery due to two events in progress (Excess RCS leakage and Excess Steam demand) and enter OP 2202.009, Functional Recovery.
+The crew will manually control Reactor Coolant Temperature once the B SG boils dry using the upstream Atmospheric Dump Valve on A SG. The ATC will control RCS pressure using auxiliary spray.
+Revision 0                                                                       Page 3 of 3
+Appendix D                                Scenario 1                                       Form ES-D-2 Simulator Instructions for Scenario 1 Reset simulator to MOL 100% power IC steady state.
+Ensure that AACG is secured and annunciators clear.
+Place MINIMAL RISK, Green Train Protected and RED Train Maintenance Week signs on 2C11.
+A CCP lead charging pump. C CCP aligned to green train.
+PCV-0231, Gland sealing steam pressure control valve failed closed.
+Quench tank level ~72%, 2K10 E4 is in alarm.
+T1, T2, T3, T4, & T5 set to false.
+T4 = Reactor trip T5 = CSAS-2 Event          Malf. No.         Value/                                Event No.                             Ramp                               Description Time 1                                          Fill the Quench Tank.
+       SV0242                     0       #1 Main Turbine Generator Control Valve fails Closed.
+Trigger = T1                       Tech Spec for SRO.
+       RCSLOCATCA                15 /     Shutdown required due to 15 gpm Reactor Coolant system Trigger = T1            Delay 5    leak on A cold leg. Tech Spec for SRO.
+min.
+       2C-11                     200      Main Turbine Generator lube oil controller setpoint fails AI_TIC_1602                        high.
+Trigger = T2 MTGVIBINC                 25 /     Main Turbine Generator Vibrations increase causing a Trigger = T3                       reactor trip.
+min.
+       500LOSE500                True     Loss of Offsite Power causing natural circulation of the 500LOSE161                True     RCS.
+Trigger = T4 6       FW2PW5BAFT               2000/     B Main Feed water line breaks inside containment.
+Trigger = T4            10 min.
+       416 A308               NO_AUT      #1 EDG output breaker fails to automatically close.
+O_CL 8       CVC2P36LOLVL              True     Backup Charging pumps fail to start on SIAS or Low PZR CVC2P36BSIAS                       level.
+CVC2P36CSIAS 9       BS2P35BFAL                True     2P-35B Spray pump failed to automatically start and 2P-BS2P35AFAULT           True / del  35A trips upon start.
+K06-B01                 30 sec.
+ON / del.
+Trigger = T5            31 sec.
+Revision 0                                                                          Page 1 of 22
+Appendix D                              Scenario 1                                         Form ES-D-2 Simulator Operator CUEs At T=0                           Fill the Quench Tank.
+Cued by        Trigger T1        #1 Main Turbine Generator Control Valve fails Closed. Tech Spec for lead                             SRO.
+examiner Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist in failing #1 Main Turbine Generator Control valve closed.
+Cue: When called as Chemistry, report that you will sample the RCS for Iodine at the time requested.
+Cued by        Trigger T1        Shutdown required due to 15 gpm Reactor Coolant system leak on A lead                             cold leg. Tech Spec for SRO.
+examiner Cue: If requested, then report that seal water pump is running for requested charging pump.
+Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.
+Cued by        Trigger T2        Main Turbine Generator lube oil controller setpoint fails high.
+lead examiner Cue: If contacted as the NLO for 2CV-1602 status, then report valve position based on the actual valve position and report flow noise is heard through the valve if it is open.
+Cue: When contacted as the NLO, then report that Lube oil flows to bearing are normal but temperature are elevated (report temperatures based on actually simulator temperatures).
+Cued by        Trigger T3        Main Turbine Generator Vibrations increase.
+lead examiner Cued by        Trigger T4        Loss of Offsite Power causing natural circulation of the RCS.
+lead                             B Main Feed water line break inside containment.
+examiner or reactor trip Backup Charging pumps fail to start on SIAS or Low PZR level.
+Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.
+Cued by        Trigger T5        2P-35B Spray pump failed to automatically start and 2P-35A trips CSAS                             upon start.
+Cue: if requested as WCO, then report that 2P-35B Containment Spray pump post start checks are satisfactory.
+Revision 0                                                                         Page 2 of 22
+Appendix D                              Scenario 1                                     Form ES-D-2 Op-Test No.: 2011-1                     Scenario No.: 1                      Event No.: 1 Event
 == Description:==
-Fill the Quench Tank using 2103.007 Quench Tank and Reactor Drain Tank Ops.TimePositionApplicant's Actions or Behavior BOP7.2 Raising Quench Tank levelANY7.2.2 Close Rx Drain Tank Makeup Water Isol (2CV-4693).
+Fill the Quench Tank using 2103.007 Quench Tank and Reactor Drain Tank Ops.
-BOP7.2.3 Open Containment Makeup Water Supply (2CV-4690-2).
+Time        Position                         Applicant's Actions or Behavior BOP        7.2  Raising Quench Tank level ANY              7.2.2 Close Rx Drain Tank Makeup Water Isol (2CV-4693).
-BOP7.2.4 Throttle open Quench Tank Supply (2CV-4685).
+BOP             7.2.3 Open Containment Makeup Water Supply (2CV-4690-2).
-BOP7.2.5 WHEN desired level is reached (maximum log level is 87%),THEN close the following valves:2CV-46852CV-4690-2 BOP7.2.6 Open Rx Drain Tank Makeup Water Isol (2CV-4693).Termination criteria: When 2CV-4693 is open or at lead examiner's discretion.
+BOP             7.2.4 Throttle open Quench Tank Supply (2CV-4685).
-Appendix D Scenario 1Form ES-D-2Revision 0Page 4 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   2 & 3Event
+BOP             7.2.5 WHEN desired level is reached (maximum log level is 87%),
+THEN close the following valves:
+CV-4685 2CV-4690-2 BOP             7.2.6 Open Rx Drain Tank Makeup Water Isol (2CV-4693).
+Termination criteria: When 2CV-4693 is open or at lead examiners discretion.
+Revision 0                                                                       Page 3 of 22
+Appendix D                               Scenario 1                                       Form ES-D-2 Op-Test No.: 2011-1                      Scenario No.: 1                       Event No.: 2 & 3 Event
 == Description:==
-  #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec forSRO.Shutdown required due to 15 gpm Reactor Coolant system leak on 'A' cold leg.Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYReport #1 MTG CV is failed Closed.
+ #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.
-SROEnter and direct actions of AOP 2203.024, Loss of Turbine Load.1. Open Placekeeping page.
+Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.
-SRO2. Notify Control Board Operators to monitor floating steps.ATC*3. Reduce Reactor power to match TAVE within 2&deg;F of TREF using2104.003 Exhibit 3, normal boration.ANY*4. Check RCS pressure 2025 to 2275 psia.Cue: If asked, report that the MTG #1 CV indicates closed by local verification and If ask, reportthat the wires for the connector to the servo for # 1 CV are broken off and hanging to the side.ANY*5. Verify SDBCS maintaining SG pressure at setpoint.ANY*8.Check RCS TC 542 to 554.7&deg;F using CPC PID 5, 6, 160, or 161.(not met perform contingencies)
+Tech Spec for SRO.
-SRO*8.Refer to TS 3.2.6, Reactor Coolant Cold Leg Temperature.Examiner note:  The SRO must enter TS 3.2.6 or if boration haslowered temperature below the limit the SRO must log the TS 3.2.6 asbeen entered and exited.Examiner note:  The following steps may or may not be completed based on the timing of theExcess RCS leak and implementation of the Excess RCS leakage procedure.ANY*9.Check ASI within limits as specified in Core Operating LimitsReport (COLR).ANY*10. Check CEA positions as follows:
+Time         Position                          Applicant's Actions or Behavior Cued by          ANY        Report #1 MTG CV is failed Closed.
-A.ALL Regulating Group 6 CEAs above 112.5 inches.B. ALL Regulating Group 1 through 5 CEAs fully withdrawn.C. ALL Group P CEAs above 135 inches.
+lead examiner SRO        Enter and direct actions of AOP 2203.024, Loss of Turbine Load.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 5 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   2 & 3Event
+: 1. Open Placekeeping page.
+SRO        2. Notify Control Board Operators to monitor floating steps.
+ATC        *3. Reduce Reactor power to match TAVE within 2&deg;F of TREF using 2104.003 Exhibit 3, normal boration.
+ANY        *4. Check RCS pressure 2025 to 2275 psia.
+Cue: If asked, report that the MTG #1 CV indicates closed by local verification and If ask, report that the wires for the connector to the servo for # 1 CV are broken off and hanging to the side.
+ANY        *5. Verify SDBCS maintaining SG pressure at setpoint.
+ANY        *8.      Check RCS TC 542 to 554.7&deg;F using CPC PID 5, 6, 160, or 161.
+(not met perform contingencies)
+SRO        *8.      Refer to TS 3.2.6, Reactor Coolant Cold Leg Temperature.
+Examiner note: The SRO must enter TS 3.2.6 or if boration has lowered temperature below the limit the SRO must log the TS 3.2.6 as been entered and exited.
+Examiner note: The following steps may or may not be completed based on the timing of the Excess RCS leak and implementation of the Excess RCS leakage procedure.
+ANY        *9.      Check ASI within limits as specified in Core Operating Limits Report (COLR).
+ANY        *10. Check CEA positions as follows:
+A. ALL Regulating Group 6 CEAs above 112.5 inches.
+B. ALL Regulating Group 1 through 5 CEAs fully withdrawn.
+C. ALL Group P CEAs above 135 inches.
+Revision 0                                                                          Page 4 of 22
+Appendix D                               Scenario 1                                         Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 1                         Event No.: 2 & 3 Event
 == Description:==
-  #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec forSRO.Shutdown required due to 15 gpm Reactor Coolant system leak on 'A' cold leg.Tech Spec for SRO.ANY*11. Check Reactor NOT tripped.ANY*12. Verify Feedwater Control System restoring SG levels to setpoint.ANY*13. Check PZR level within 5% of setpoint:ANY 15.Check Condenser pressure less than 5.3 inches Hg Abs.ANY16. Verify ALL required actions have been completed based onpower level; refer to 2102.004, Power Operation.ANY 18.Notify Chemistry to sample RCS for Iodine 2 to 6 Hrs followingReactor power change greater than 15% in 1 Hr, refer to TS 4.4.8,RCS Activity.Cue:  When called as Chemistry, report that you will sample the RCS for Iodine at the timerequested.
+ #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.
-SRO 19.IF Main Turbine has NOT tripped,THEN perform the following:Re-establish Turbine control onLoad Limit Pot.Refer to TRM 3.3.4.1,Turbine Overspeed Protection.IF desired to fail a Turbine Control Valve closed, THEN referto 2106.009, Turbine Generator Operations.Examiner note:  The SRO may decide to pull up this step to fail a TurbineControl valve closed but it is not required to be performed.Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist infailing #1 Main Turbine Generator Control valve closed.If requested, after 5 minutes have the communicator enter the simulator control room andperform as requested by the crew.Examiner Note:  The following Steps are for Event 3 Excess RCS leakage and not all of the abovesteps from Loss of Turbine load AOP are required to be completed due to the scenarioprogression.ANYReport any the following indications:Containment dew point risingPressurizer Level lowing.Letdown flow lowering.
+Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 6 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   2 & 3Event
+Tech Spec for SRO.
+ANY       *11. Check Reactor NOT tripped.
+ANY       *12. Verify Feedwater Control System restoring SG levels to setpoint.
+ANY       *13. Check PZR level within 5% of setpoint:
+ANY       15.      Check Condenser pressure less than 5.3 inches Hg Abs.
+ANY         16. Verify ALL required actions have been completed based on power level; refer to 2102.004, Power Operation.
+ANY       18.      Notify Chemistry to sample RCS for Iodine 2 to 6 Hrs following Reactor power change greater than 15% in 1 Hr, refer to TS 4.4.8, RCS Activity.
+Cue: When called as Chemistry, report that you will sample the RCS for Iodine at the time requested.
+SRO       19.      IF Main Turbine has NOT tripped, THEN perform the following:
+Re-establish Turbine control on Load Limit Pot.
+Refer to TRM 3.3.4.1, Turbine Overspeed Protection.
+IF desired to fail a Turbine Control Valve closed, THEN refer to 2106.009, Turbine Generator Operations.
+Examiner note: The SRO may decide to pull up this step to fail a Turbine Control valve closed but it is not required to be performed.
+Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist in failing #1 Main Turbine Generator Control valve closed.
+If requested, after 5 minutes have the communicator enter the simulator control room and perform as requested by the crew.
+Examiner Note: The following Steps are for Event 3 Excess RCS leakage and not all of the above steps from Loss of Turbine load AOP are required to be completed due to the scenario progression.
+ANY       Report any the following indications:
+Containment dew point rising Pressurizer Level lowing.
+Letdown flow lowering.
+Revision 0                                                                            Page 5 of 22
+Appendix D                             Scenario 1                                        Form ES-D-2 Op-Test No.: 2011-1                      Scenario No.: 1                      Event No.: 2 & 3 Event
 == Description:==
-  #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec forSRO.Shutdown required due to 15 gpm Reactor Coolant system leak on 'A' cold leg.Tech Spec for SRO.
+ #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.
-SROPerform the following actions:Assess Critical parameters.Determine RCS leak is present and enter Excess RCS LeakageAOP.SROEnter and direct the actions of AOP OP-2203.016, Excess RCS Leakage:1. Open Placekeeping page.
+Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.
-SRO2. Notify Control Board Operators to monitor floating steps.ANY*3. Determine RCS leakrate by ANY of the following: Computer LKRT programs. Check PZR level stable and use Charging and Letdownmismatch minus Controlled Bleed Off. Check Letdown isolated and estimate RCS leak rate by totalCharging flow minus Controlled Bleed Off. CNTMT Sump level rate of rise.Examiner note: The SRO may secure boration to assist in performing anRCS leak rate.ATC*4. Maintain PZR level within 5% of setpoint by performing thefollowing as necessary:A. Cycle Charging pumps.B. Isolate Letdown as follows:1) Verify at least ONE Letdown Isolation valve closed:2CV-4820-22CV-4821-12CV-4823-2 (least preferred)2) Record Charging Header Data in 2202.010 Attachment 44,Charging Header Data.Examiner note:  The ATC may discover that at least one back upcharging pump is not going to start based on PZR level during theexcess RCS leak. Typically the SRO will give a more restrictive PZRlevel band of within 3% of setpoint and the ATC may not determinethat the backup charging pumps will not start based on PZR level. Seeevent #8 Appendix D Scenario 1Form ES-D-2Revision 0Page 7 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   2 & 3Event
+Tech Spec for SRO.
+SRO      Perform the following actions:
+Assess Critical parameters.
+Determine RCS leak is present and enter Excess RCS Leakage AOP.
+SRO      Enter and direct the actions of AOP OP-2203.016, Excess RCS Leakage:
+: 1. Open Placekeeping page.
+SRO      2.      Notify Control Board Operators to monitor floating steps.
+ANY       *3. Determine RCS leakrate by ANY of the following:
+Computer LKRT programs.
+Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.
+Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.
+CNTMT Sump level rate of rise.
+Examiner note: The SRO may secure boration to assist in performing an RCS leak rate.
+ATC      *4. Maintain PZR level within 5% of setpoint by performing the following as necessary:
+A. Cycle Charging pumps.
+B. Isolate Letdown as follows:
+: 1) Verify at least ONE Letdown Isolation valve closed:
+* 2CV-4820-2
+* 2CV-4821-1
+* 2CV-4823-2 (least preferred)
+: 2) Record Charging Header Data in 2202.010 Attachment 44, Charging Header Data.
+Examiner note: The ATC may discover that at least one back up charging pump is not going to start based on PZR level during the excess RCS leak. Typically the SRO will give a more restrictive PZR level band of within 3% of setpoint and the ATC may not determine that the backup charging pumps will not start based on PZR level. See event #8 Revision 0                                                                        Page 6 of 22
+Appendix D                                Scenario 1                                          Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 1                         Event No.: 2 & 3 Event
 == Description:==
-  #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec forSRO.Shutdown required due to 15 gpm Reactor Coolant system leak on 'A' cold leg.Tech Spec for SRO.Cue: If requested, then report that seal water pump is running for requested charging pump.Cue: if requested as WCO, then report running Charging pump post start checks aresatisfactory.ATC*5. Check PZR level maintained within 10% of setpoint.ATC*7. Maintain VCT level 60% to 75%; refer to 2104.003, ChemicalAddition.SRO*10. Refer to 1903.010,Emergency Action Level Classification.Examiner note: The SRO will direct the SM to refer to EALs.*11. IF location of leak known,THEN perform the applicable following steps (12.A through 12.J):CNTMTstep 12.A SROIf this step entered from step 11, then only perform substep for identifiedleak path.*12. IF location of leak unknown, THEN locate and isolate leak asfollows:A. Perform the following:1) IF leakage is within allowable limits of TS 3.4.6.2,THEN,Attempt to locate leak in CNTMT by monitoringCAMS suction points and CNTMT Area Radiationmonitors.Examiner note: 15 gpm is not within the allowable limits of TS 3.4.6.2.ATC2) Verify leak NOT in Letdown line inside CNTMT byperforming the following:a) Isolate Letdown by verifying at least ONE LetdownIsolation valve closed:-4820-2-4821-1-4823-2 (least preferred) b)IF RCS leakage NOT stopped, THEN letdown may berestored at discretion of SM using 2104.002, Chemicaland Volume Control.Examiners Note:  Isolating Letdown will not isolate the leak andLetdown should be restored to service.
+ #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 8 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   2 & 3Event
+Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.
+Tech Spec for SRO.
+Cue: If requested, then report that seal water pump is running for requested charging pump.
+Cue: if requested as WCO, then report running Charging pump post start checks are satisfactory.
+ATC       *5. Check PZR level maintained within 10% of setpoint.
+ATC       *7. Maintain VCT level 60% to 75%; refer to 2104.003, Chemical Addition.
+SRO       *10. Refer to 1903.010, Emergency Action Level Classification.
+Examiner note: The SRO will direct the SM to refer to EALs.
+                            *11. IF location of leak known, THEN perform the applicable following steps (12.A through 12.J):
+CNTMT                                               step 12.A SRO       If this step entered from step 11, then only perform substep for identified leak path.
+                            *12. IF location of leak unknown, THEN locate and isolate leak as follows:
+A. Perform the following:
+: 1)     IF leakage is within allowable limits of TS 3.4.6.2, THEN, Attempt to locate leak in CNTMT by monitoring CAMS suction points and CNTMT Area Radiation monitors.
+Examiner note: 15 gpm is not within the allowable limits of TS 3.4.6.2.
+ATC                  2)     Verify leak NOT in Letdown line inside CNTMT by performing the following:
+a) Isolate Letdown by verifying at least ONE Letdown Isolation valve closed:
+* 2CV-4820-2
+* 2CV-4821-1
+* 2CV-4823-2 (least preferred) b) IF RCS leakage NOT stopped, THEN letdown may be restored at discretion of SM using 2104.002, Chemical and Volume Control.
+Examiners Note: Isolating Letdown will not isolate the leak and Letdown should be restored to service.
+Revision 0                                                                             Page 7 of 22
+Appendix D                             Scenario 1                                         Form ES-D-2 Op-Test No.: 2011-1                     Scenario No.: 1                        Event No.: 2 & 3 Event
 == Description:==
-  #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec forSRO.Shutdown required due to 15 gpm Reactor Coolant system leak on 'A' cold leg.Tech Spec for SRO.
+ #1 Main Turbine Generator (MTG) Control Valve fails Closed. Tech Spec for SRO.
-SRO*13. Check leakage within allowable limits; refer to TS 3.4.6.2,Reactor Coolant System Leakage.Examiners Note:  SRO must enter Tech Spec 3.4.6.2 action b.ALL*13. Perform the following:A. Continue efforts to locate and isolate leak.
+Shutdown required due to 15 gpm Reactor Coolant system leak on A cold leg.
-B. IF plant shutdown required,THEN perform EITHER of the following using 2102.004,Power Operations:
+Tech Spec for SRO.
-: 1) IF leakage greater than 10 gpm, THEN perform RCSboration using2104.003, Chemical Addition,Attachment R, RCS Boration from the RWT or BAMT.
+SRO     *13. Check leakage within allowable limits; refer to TS 3.4.6.2, Reactor Coolant System Leakage.
-: 2) IF RCS leakage less than 10 gpm,THEN perform RCS boration using2104.003, Chemical Addition,Exhibit 3, Normal RCS Boration atPower.Examiners Note:  The ATC should start a shutdown using 2104.003,Chemical Addition, Attachment R. The ATC may already beborating using Exhibit 3 but must change the boration method due tothe leakrate value. This does not have to be accomplished prior tomoving to the next event.Termination criteria: When letdown has been isolated and verified the RCS leak is still on going,or Letdown is restored, or at lead examiner's discretion.
+Examiners Note: SRO must enter Tech Spec 3.4.6.2 action b.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 9 of 22Op-Test No.:  2011-1                                 Scenario No.:  1                                   Event No.:   4Event
+ALL     *13. Perform the following:
+A. Continue efforts to locate and isolate leak.
+B. IF plant shutdown required, THEN perform EITHER of the following using 2102.004, Power Operations:
+: 1)   IF leakage greater than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Attachment R, RCS Boration from the RWT or BAMT.
+: 2)   IF RCS leakage less than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at Power.
+Examiners Note: The ATC should start a shutdown using 2104.003, Chemical Addition, Attachment R. The ATC may already be borating using Exhibit 3 but must change the boration method due to the leakrate value. This does not have to be accomplished prior to moving to the next event.
+Termination criteria: When letdown has been isolated and verified the RCS leak is still on going, or Letdown is restored, or at lead examiners discretion.
+Revision 0                                                                         Page 8 of 22
+Appendix D                                Scenario 1                                        Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 1                      Event No.: 4 Event
 == Description:==
-Main Turbine Generator lube oil controller setpoint fails high. Main TurbineGenerator Vibrations increase.TimePositionApplicant's Actions or BehaviorCued byexaminerANYDetermine that Turbine Lube oil temperature is rising.ANYIF 2K02-B7 TURB BRNG TEMP HI comes in alarm then announce thealarm.SROIF 2K02-B7 TURB BRNG TEMP HI comes in alarm then implementsactions of the Turbine bearing temp high alarm.ANY2.1 Monitor bearing temperatures on 2TRS-0211 and Plant computer.
+Main Turbine Generator lube oil controller setpoint fails high. Main Turbine Generator Vibrations increase.
-BOP2.2 Verify Lube Oil 2E-15A/B Temperature controller (2TIC-1602) setto control temperature at 115&deg;F.Examiner note: The SRO should direct manual control of 2TIC-1602Lube Oil temperature controller.Cue: If contacted as the NLO for 2CV-1602 status, then report valve position based on the actualvalve position and report flow noise is heard through the valve if it is open.
+Time         Position                           Applicant's Actions or Behavior Cued by           ANY        Determine that Turbine Lube oil temperature is rising.
-SRO2.4 IF bearing metal temperature reaches 230&deg;FOR Bearing Oil Pressure Low in alarm (2K02-A7),THEN perform the following:2.4.1IF Reactor power greater than SDBCS capacity,                THEN trip Reactor.Examiner Note: Depending on how soon that manual control is taken for turbine lube oilcooling, the crew may have to trip the reactor based on bearing metal temperatures. If theydo not have to trip the reactor, then the malfunction for turbine vibrations should betriggered.ANYDirect NLOs to perform the following:
+examiner ANY        IF 2K02-B7 TURB BRNG TEMP HI comes in alarm then announce the alarm.
-.6Check lube oil flow and temperature at affected bearings.Cue: If contacted as the NLO, then report that Lube oil flows to bearings are normal buttemperatures are elevated (report temperatures based on actual simulator temperatures).ANYContact work management to repair 2TIC-1602.ANYReport Turbine Vibrations trending higher.
+SRO        IF 2K02-B7 TURB BRNG TEMP HI comes in alarm then implements actions of the Turbine bearing temp high alarm.
-SROThe SRO may take conservative action to trip the turbine and reactor ifvibrations are noted to be trending higher.ANYReport Turbine Bearing Vibration Hi alarm BOPReport Turbine Tripped.
+ANY        2.1 Monitor bearing temperatures on 2TRS-0211 and Plant computer.
-SRODirect Reactor trip due to the turbine trip. Termination Criteria:  2TIC-1602 in manual and controlling lube oil temperatures, or crewtripped the reactor due to elevated bearing temperatures, or at leadexaminer's discretion.
+BOP        2.2   Verify Lube Oil 2E-15A/B Temperature controller (2TIC-1602) set to control temperature at 115&deg;F.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 10 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+Examiner note: The SRO should direct manual control of 2TIC-1602 Lube Oil temperature controller.
+Cue: If contacted as the NLO for 2CV-1602 status, then report valve position based on the actual valve position and report flow noise is heard through the valve if it is open.
+SRO        2.4 IF bearing metal temperature reaches 230&deg;F OR Bearing Oil Pressure Low in alarm (2K02-A7),
+THEN perform the following:
+.4.1      IF Reactor power greater than SDBCS capacity, THEN trip Reactor.
+Examiner Note: Depending on how soon that manual control is taken for turbine lube oil cooling, the crew may have to trip the reactor based on bearing metal temperatures. If they do not have to trip the reactor, then the malfunction for turbine vibrations should be triggered.
+ANY        Direct NLOs to perform the following:
+.6        Check lube oil flow and temperature at affected bearings.
+Cue: If contacted as the NLO, then report that Lube oil flows to bearings are normal but temperatures are elevated (report temperatures based on actual simulator temperatures).
+ANY        Contact work management to repair 2TIC-1602.
+ANY        Report Turbine Vibrations trending higher.
+SRO        The SRO may take conservative action to trip the turbine and reactor if vibrations are noted to be trending higher.
+ANY        Report Turbine Bearing Vibration Hi alarm BOP        Report Turbine Tripped.
+SRO        Direct Reactor trip due to the turbine trip.
+Termination Criteria: 2TIC-1602 in manual and controlling lube oil temperatures, or crew tripped the reactor due to elevated bearing temperatures, or at lead examiner's discretion.
+Revision 0                                                                           Page 9 of 22
+Appendix D                                Scenario 1                                       Form ES-D-2 Op-Test No.: 1                        Scenario No.: 1                     Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorCued byexaminerANYReport Reactor Tripped.
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-SROEnter and implement EOP 2202.001, Standard Post Trip Actions.
+Time          Position                         Applicant's Actions or Behavior Cued by           ANY       Report Reactor Tripped.
-SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.
+examiner SRO       Enter and implement EOP 2202.001, Standard Post Trip Actions.
-.Open Safety Function Tracking page.ANYClose MSIVs due to LOOP and an unisolated flow path from Main steamto the condenser.Examiner Note: The SRO will probably pull up the step to closeMSIVs from RCS heat removal due to the known flow path.ReactivitycontrolsafetyfunctionATC 3.Check Reactivity Control established as follows:A. Reactor power lowering.B. ALL CEAs fully inserted.(The CEAs will be fully inserted andcan be verified by CEAC indications)VitalAuxiliariessafetyfunction BOP 4.Check Maintenance of Vital Auxiliaries satisfied:A. Main Turbine tripped.B. Generator Output breakers open.C. Exciter Field breaker open.D. At least ONE 6900v AC bus energized.(Not met)E. At least ONE 4160v Non-vital AC bus energized.F. BOTH 4160v Vital AC buses energized.(2A-4 Vital bus willbe energized but 2A-3 will not be energized until #1 EDG outputbreaker is closed.)G. BOTH DGs secured. (Both DGs will be running, Servicewater will be aligned to #2 EDG and after #1 EDG outputbreaker is closed service water will be aligned.)H. At least ONE 125v Vital DC bus energized:2D01 - SPDS point E2D012D02 - SPDS point E2D02 Appendix D Scenario 1Form ES-D-2Revision 0Page 11 of 22
+SRO      1.      Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.
-______Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+: 2.      Open Safety Function Tracking page.
+ANY       Close MSIVs due to LOOP and an unisolated flow path from Main steam to the condenser.
+Examiner Note: The SRO will probably pull up the step to close MSIVs from RCS heat removal due to the known flow path.
+Reactivity        ATC      3.      Check Reactivity Control established as follows:
+control safety                             A. Reactor power lowering.
+function B. ALL CEAs fully inserted. (The CEAs will be fully inserted and can be verified by CEAC indications)
+BOP     4.      Check Maintenance of Vital Auxiliaries satisfied:
+A. Main Turbine tripped.
+B. Generator Output breakers open.
+C. Exciter Field breaker open.
+D. At least ONE 6900v AC bus energized. (Not met)
+E. At least ONE 4160v Non-vital AC bus energized.
+Vital Auxiliaries                        F. BOTH 4160v Vital AC buses energized. (2A-4 Vital bus will safety function                           be energized but 2A-3 will not be energized until #1 EDG output breaker is closed.)
+G. BOTH DGs secured. (Both DGs will be running, Service water will be aligned to #2 EDG and after #1 EDG output breaker is closed service water will be aligned.)
+H. At least ONE 125v Vital DC bus energized:
+D01 - SPDS point E2D01 2D02 - SPDS point E2D02 Revision 0                                                                         Page 10 of 22
+Appendix D                               Scenario 1                                        Form ES-D-2 Op-Test No.: 1                       Scenario No.: 1                      Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorATC 5.Check RCS Inventory Control established as follows:A. PZR level:10 to 80%.Trending to setpoint.(May not be met due to ESD Event#5 perform contingency if not met)B. RCS MTS 30&deg;F or greater.
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-RCSInventoryControlSafetyfunction SROExaminers Note: This may or may not be performed depending on thePZR level trend at the time this safety function isassessed.Direct the following as necessary:A. Perform as necessary:
+Time          Position                          Applicant's Actions or Behavior ATC      5. Check RCS Inventory Control established as follows:
-: 1) IF SIAS actuated on PPS inserts, THEN GO TOStep 6.2) Verify PZR Level Control system restoring level to setpoint.ATC 6.Check RCS Pressure Control:1800 to 2250 psia.Trending to setpoint
+A. PZR level:
-. (May not be met due to ESD Event #6.Perform contingency if not met)
+to 80%.
-RCSPressureControlSafetyfunction SROExaminers Note: This may or may not be performed depending on thePressurizer level trend at the time this safety functionis assessed.Direct the following actions as necessary:
+Trending to setpoint. (May not be met due to ESD Event
-.Perform as necessary:C. IF valid CNTMT Spray in progress,THEN verify ALL RCPs tripped.(Should be performed ifspray is actuated.)D. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.(Should be performed if RCPs are secured.)
+                                            #5 perform contingency if not met)
-E. IF RCS pressure lowers to 1650 psia or less,THEN perform the following:1) Verify SIAS actuated on PPS inserts.
+RCS                               B. RCS MTS 30&deg;F or greater.
-)GO TO Step 7.
+Inventory Control                    Examiners Note: This may or may not be performed depending on the Safety            SRO PZR level trend at the time this safety function is function                                      assessed.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 12 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+Direct the following as necessary:
+A. Perform as necessary:
+: 1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.
+: 2) Verify PZR Level Control system restoring level to setpoint.
+ATC      6. Check RCS Pressure Control:
+___
+* 1800 to 2250 psia.
+___
+* Trending to setpoint. (May not be met due to ESD Event #6.
+Perform contingency if not met)
+SRO      Examiners Note: This may or may not be performed depending on the Pressurizer level trend at the time this safety function is assessed.
+Direct the following actions as necessary:
+RCS                        6. Perform as necessary:
+Pressure Control                            C. IF valid CNTMT Spray in progress, Safety                                 THEN verify ALL RCPs tripped. (Should be performed if function spray is actuated.)
+D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed. (Should be performed if RCPs are secured.)
+E. IF RCS pressure lowers to 1650 psia or less, THEN perform the following:
+: 1) Verify SIAS actuated on PPS inserts.
+: 2) GO TO Step 7.
+Revision 0                                                                          Page 11 of 22
+Appendix D                                Scenario 1                                         Form ES-D-2 Op-Test No.: 1                        Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorATC 7.Check Core Heat Removal by forced circulation:
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-A.At least ONE RCP running.(RCPs will be secured due LOOPand CRS should perform the contingency)
+Time          Position                           Applicant's Actions or Behavior ATC      7.      Check Core Heat Removal by forced circulation:
-SROIf required, direct the contingency for step 7. ECore HeatRemovalsafetyfunction.ATC A.IF ALL RCPs stopped,                THEN perform the following:
+A. At least ONE RCP running. (RCPs will be secured due LOOP and CRS should perform the contingency)
-)Verify BOTH PZR Spray valves in MANUAL and closed.
+Core Heat Removal safety function.         SRO      If required, direct the contingency for step 7. E ATC              A.         IF ALL RCPs stopped, THEN perform the following:
-)GO TO Step 8.ANY 8.Check RCS Heat Removal:A. Check SG available by BOTH of the following:At least ONE SG level 10 to 90%.FW maintaining SG level.(Should not be met due toMSIS, perform contingency if necessary)B. Check MFW in RTO.(Should not be met due to MSIS,perform contingency if necessary)C. Check Feedwater line intact by the following:(Not met butthese conditions can not be assessed due to plantconfiguration)SG level stable or rising.NO unexplained step changes or erratic FW flow.NO unexplained step changes or erratic Condensate flow.D. Check Condensate Pump discharge header pressure < 753 psig.E. Check SG pressure 950 to 1050 psia.(Not Met, performContingency)F. Check RCS TC 540 to 555&deg;F.RCS HeatRemovalSafetyFunctionANYPerform step 8 contingency actions that are applicable:A. Perform the following:
+: 1)         Verify BOTH PZR Spray valves in MANUAL and closed.
-)IF SG level lowering,THEN verify EFAS actuated.(To the 'A' S/G only)
+: 2)         GO TO Step 8.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 13 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+: 8.      Check RCS Heat Removal:
+A. Check SG available by BOTH of the following:
+* At least ONE SG level 10 to 90%.
+* FW maintaining SG level. (Should not be met due to MSIS, perform contingency if necessary)
+B. Check MFW in RTO. (Should not be met due to MSIS, perform contingency if necessary)
+RCS Heat                           C. Check Feedwater line intact by the following: (Not met but Removal ANY                  these conditions can not be assessed due to plant Safety Function                               configuration)
+* SG level stable or rising.
+* NO unexplained step changes or erratic FW flow.
+* NO unexplained step changes or erratic Condensate flow.
+D. Check Condensate Pump discharge header pressure < 753 psig.
+E. Check SG pressure 950 to 1050 psia. (Not Met, perform Contingency)
+F. Check RCS TC 540 to 555&deg;F.
+ANY      Perform step 8 contingency actions that are applicable:
+A. Perform the following:
+: 1) IF SG level lowering, THEN verify EFAS actuated. (To the A S/G only)
+Revision 0                                                                           Page 12 of 22
+Appendix D                              Scenario 1                                         Form ES-D-2 Op-Test No.: 1                      Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorANYB. Verify EITHER of the following:BOTH MFW pumps tripped.SG levels controlling at setpointRCS HeatRemovalSafetyFunctionANYE. Perform as necessary:
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-: 1) IF SG pressure 751 psia or less, THEN perform thefollowing:a) Verify MSIS actuated onPPS inserts.b) Maintain RCS post-cooldown conditions as follows:Maintain RCS pressure within P-T limits with PZRheaters and spray usingAttachment 27, PZR Spray Operation.Maintain RCS temperature by steaming intact SGusing Upstream ADV or Upstream ADV IsolationMOV.c)GO TO Step 9.
+Time          Position                       Applicant's Actions or Behavior ANY             B. Verify EITHER of the following:
-Appendix D Scenario 1Form ES-D-2Revision 0Page 14 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+* BOTH MFW pumps tripped.
+* SG levels controlling at setpoint E. Perform as necessary:
+: 1) IF SG pressure 751 psia or less, THEN perform the following:
+a) Verify MSIS actuated on PPS inserts.
+RCS Heat                                 b) Maintain RCS post-cooldown conditions as follows:
+Removal ANY                                Maintain RCS pressure within P-T limits with PZR Safety Function                                          heaters and spray using Attachment 27, PZR Spray Operation.
+Maintain RCS temperature by steaming intact SG using Upstream ADV or Upstream ADV Isolation MOV.
+c) GO TO Step 9.
+Revision 0                                                                         Page 13 of 22
+Appendix D                              Scenario 1                                         Form ES-D-2 Op-Test No.: 1                      Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorContainmentSafetyFunctionANY 9.Check CNTMT parameters:A. Temperature and Pressure:(Not met due to ESD Event #6.Perform contingency)Temperature less than 140&deg;F.Pressure less than 16 psia.B. Check CNTMT Spray pumps secured.(Not met, performcontingency)C. NO CNTMT radiation alarms or unexplained rise in activity:1) CAMS alarms:"CNTMT PART/GAS RAD HI/LO" annunciator(2K10-B6) clear.2) RCS leakage alarms:"AREA RADIATION HI/LO" annunciator (2K11-B10)clear."PROC LIQUID RADIATION HI/LO" annunciator(2K11-C10) clear.3) Check the following radiation monitors trend stable:CNTMT AreaMSProcess LiquidD. NO secondary system radiation alarms or unexplained rise inactivity: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.2) Secondary Systems Radiation monitors trend stable:Main Steam linesSG SampleCondenser Off Gas Appendix D Scenario 1Form ES-D-2Revision 0Page 15 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
+Time          Position                         Applicant's Actions or Behavior ANY      9. Check CNTMT parameters:
+A. Temperature and Pressure: (Not met due to ESD Event #6.
+Perform contingency)
+* Temperature less than 140&deg;F.
+* Pressure less than 16 psia.
+B. Check CNTMT Spray pumps secured. (Not met, perform contingency)
+C. NO CNTMT radiation alarms or unexplained rise in activity:
+: 1) CAMS alarms:
+                                          * "CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.
+: 2) RCS leakage alarms:
+Containment                              * "AREA RADIATION HI/LO" annunciator (2K11-B10)
+Safety                                         clear.
+Function
+                                          * "PROC LIQUID RADIATION HI/LO" annunciator (2K11-C10) clear.
+: 3) Check the following radiation monitors trend stable:
+* CNTMT Area
+* CAMS
+* Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:
+: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.
+: 2) Secondary Systems Radiation monitors trend stable:
+* Main Steam lines
+* SG Sample
+* Condenser Off Gas Revision 0                                                                         Page 14 of 22
+Appendix D                              Scenario 1                                         Form ES-D-2 Op-Test No.: 1                      Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorANYContingency for Containment parameters not being met.A. Perform the following:2) IF CNTMT pressure 18.3 psia or greater,THEN verify the following:CIAS, CCAS, and SIAS actuated on PPS inserts.At least ONE Emergency Penetration Room Vent Fanrunning.CNTMT Cooling fans running in Emergency Mode.ANY3) IF CNTMT pressure 23.3 psia or greater,THEN verify the following:CSAS actuated on PPS inserts.Spray flow greater than1875 gpm per header.ALL RCPs stopped AND BOTH PZR Spray valves inMANUAL and closed.Examiner note: See Event #9 SRO10. Notify STA to report to control room.11. Verify NLOs informed of Reactor trip.12. Verify Reactor trip announced on Plant page.13. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.
+Time          Position                         Applicant's Actions or Behavior ANY       Contingency for Containment parameters not being met.
-SRO15. Check ALL safety function acceptance criteria satisfied.(All safetyfunctions are not satisfied, perform contingency)15. IF ANY safety function acceptance criteria NOT satisfied,THEN perform the following:A. Notify control room staff ofsafety functions NOT satisfied.B. GO TO Exhibit 8, Diagnostic Actions.
+A. Perform the following:
-SRODiagnose Functional Recovery EOP 2202.009.
+: 2) IF CNTMT pressure 18.3 psia or greater, THEN verify the following:
-SROEnter and implement Functional Recovery EOP 2202.009.
+* CIAS, CCAS, and SIAS actuated on PPS inserts.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 16 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+* At least ONE Emergency Penetration Room Vent Fan running.
+* CNTMT Cooling fans running in Emergency Mode.
+ANY                 3) IF CNTMT pressure 23.3 psia or greater, THEN verify the following:
+* CSAS actuated on PPS inserts.
+* Spray flow greater than 1875 gpm per header.
+* ALL RCPs stopped AND BOTH PZR Spray valves in MANUAL and closed.
+Examiner note: See Event #9 SRO      10. Notify STA to report to control room.
+: 11. Verify NLOs informed of Reactor trip.
+: 12. Verify Reactor trip announced on Plant page.
+: 13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
+SRO      14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.
+SRO      15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)
+: 15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:
+A. Notify control room staff of safety functions NOT satisfied.
+B. GO TO Exhibit 8, Diagnostic Actions.
+SRO      Diagnose Functional Recovery EOP 2202.009.
+SRO      Enter and implement Functional Recovery EOP 2202.009.
+Revision 0                                                                         Page 15 of 22
+Appendix D                               Scenario 1                                        Form ES-D-2 Op-Test No.: 1                       Scenario No.: 1                      Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or Behavior SRO2. Record present time:Time                            .
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-SRO* 3. Notify SM to refer toTechnical Specifications and 1903.010,Emergency Action Level Classification.ANY* 4. Check RCS pressure greater than 1400 psia.ANYIf not performed in SPTA's, then perform contingency to secure 2 RCPs* 4. Perform the following:A. IF RCS pressure less than 1400 psia, THEN perform thefollowing:1) Verify maximum of ONE RCP running in EACH loop.
+Time          Position                          Applicant's Actions or Behavior SRO       2. Record present time:
-: 2) IF RCP 2P32A or 2P32B stopped, THEN verify associatedPZR Spray valve in MANUAL and closed.Examiner Note:The SRO should have directed the ATC and BOP actions for maintaining post-cooldownconditions from SPTAs and therefore may not implement the following floating step.
+* Time                   .
-SROThe SRO should pull up the floating step for maintaining post-cooldownconditions if not directed from SPTAs. HR-2 Step 33.Maintainpost-cooldownconditions CRITICAL TASK BOP33. Maintain RCS post-cooldown conditions as follows:A. Maintain RCS temperature by steaming intact SG usingEITHER of the following:Upstream ADV.Upstream ADV Isolation MOV.RCS temperature must be maintained within 40&#xba;F of 'B' SteamGenerator Tc when generator boiled dry.Maintainpost-cooldownconditions CRITICAL TASKATCB. Maintain RCS pressure within P-T limits using PZR heaters and2202.010 Attachment 27, PZR Spray Operation.Post steam generator blow down, use attachment 27 to maintain RCSpressure within the Pressure-Temperature limits of 200&deg;F and 30&deg;FMargin to Saturation.ANY* 5. IF SIAS or MSIS actuated,THEN perform the following:A. Verify at least ONE SW pump running on EACH loop.ANYB. Check EITHER DG running.ANYC. Verify running DG SW Outlet valve open:
+SRO
-Appendix D Scenario 1Form ES-D-2Revision 0Page 17 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+* 3. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
+ANY
+* 4. Check RCS pressure greater than 1400 psia.
+ANY       If not performed in SPTAs, then perform contingency to secure 2 RCPs
+* 4. Perform the following:
+A. IF RCS pressure less than 1400 psia, THEN perform the following:
+: 1) Verify maximum of ONE RCP running in EACH loop.
+: 2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.
+Examiner Note:
+The SRO should have directed the ATC and BOP actions for maintaining post-cooldown conditions from SPTAs and therefore may not implement the following floating step.
+SRO      The SRO should pull up the floating step for maintaining post-cooldown conditions if not directed from SPTAs. HR-2 Step 33.
+BOP        33. Maintain RCS post-cooldown conditions as follows:
+Maintain                           A. Maintain RCS temperature by steaming intact SG using post-                                  EITHER of the following:
+cooldown
+* Upstream ADV.
+conditions
+* Upstream ADV Isolation MOV.
+CRITICAL TASK RCS temperature must be maintained within 40&#xba;F of B Steam Generator Tc when generator boiled dry.
+Maintain          ATC              B. Maintain RCS pressure within P-T limits using PZR heaters and post-                                  2202.010 Attachment 27, PZR Spray Operation.
+cooldown conditions                 Post steam generator blow down, use attachment 27 to maintain RCS CRITICAL                   pressure within the Pressure-Temperature limits of 200&deg;F and 30&deg;F TASK                       Margin to Saturation.
+ANY
+* 5. IF SIAS or MSIS actuated, THEN perform the following:
+A. Verify at least ONE SW pump running on EACH loop.
+ANY              B. Check EITHER DG running.
+ANY              C. Verify running DG SW Outlet valve open:
+Revision 0                                                                          Page 16 of 22
+Appendix D                               Scenario 1                                        Form ES-D-2 Op-Test No.: 1                       Scenario No.: 1                      Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or Behavior-1503-1-1504-2ANYD. Verify SW pump suction aligned to Lake.ANYE. Check 4160v Non-vital bus 2A1 OR 2A2 energized from offsitepower.ANYF. Check 4160v Vital buses2A3 AND 2A4 energized from offsite power.ANYG. Start SW pumps as needed to maintain SW header pressure.ANYH. Check SW to CCW restored.(CCW is not restored, performcontingency)ANYI. Check ACW restored.(ACW is not restored, performcontingency)
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-BOPI. Restore SW to ACW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.ANYJ. Maintain SW header pressure greater than 85 psig.ANY6. Notify Chemistry to sample BOTH SGs for activity.ANY7. Verify SG Sample valves open.ANY8. Check ALL available Hydrogen Analyzers in service; refer to2104.044, Containment Hydrogen Control Operations - Exhibit 1,Hydrogen Analyzer Auto Start.(perform contingency)ANY8. Verify all available Hydrogen Analyzers in service within 70minutes from start of event.Record time fromEntry Section step 2:Time ______________Examiner note: This step may not be performed due to 70 minuteallowance for start.ANY9. Open Functional Recovery Success Path Tracking page.
+Time          Position                         Applicant's Actions or Behavior
-SRO 10.Notify Control Board Operators to perform the following:A. Monitor floating steps.B. Verify actuated ESFAS componentsusing 2202.010 Exhibit 9,ESFAS Actuation.ANY 11.Determine safety function status as follows:A. Check Reactivity Control satisfied by EITHER of the following:
+* 2CV-1503-1
-Appendix D Scenario 1Form ES-D-2Revision 0Page 18 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+* 2CV-1504-2 ANY             D. Verify SW pump suction aligned to Lake.
+ANY             E. Check 4160v Non-vital bus 2A1 OR 2A2 energized from offsite power.
+ANY             F. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.
+ANY             G. Start SW pumps as needed to maintain SW header pressure.
+ANY             H. Check SW to CCW restored. (CCW is not restored, perform contingency)
+ANY             I. Check ACW restored. (ACW is not restored, perform contingency)
+BOP            I. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.
+ANY             J. Maintain SW header pressure greater than 85 psig.
+ANY       6. Notify Chemistry to sample BOTH SGs for activity.
+ANY       7. Verify SG Sample valves open.
+ANY       8. Check ALL available Hydrogen Analyzers in service; refer to 2104.044, Containment Hydrogen Control Operations - Exhibit 1, Hydrogen Analyzer Auto Start. (perform contingency)
+ANY       8. Verify all available Hydrogen Analyzers in service within 70 minutes from start of event.
+Record time from Entry Section step 2:
+Time ______________
+Examiner note: This step may not be performed due to 70 minute allowance for start.
+ANY       9. Open Functional Recovery Success Path Tracking page.
+SRO       10. Notify Control Board Operators to perform the following:
+A. Monitor floating steps.
+B. Verify actuated ESFAS components using 2202.010 Exhibit 9, ESFAS Actuation.
+ANY       11.      Determine safety function status as follows:
+A. Check Reactivity Control satisfied by EITHER of the following:
+Revision 0                                                                         Page 17 of 22
+Appendix D                              Scenario 1                                         Form ES-D-2 Op-Test No.: 1                      Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorMaximum of ONE CEA NOT fully inserted and Reactor powerlowering.Reactor power less than 10-1% and stable or lowering.Examiners note: Reactivity will be satisfied.ANYB. Check Vital DC Auxiliaries satisfied:1) At least ONE 125v Vital DC bus energized:2D01-SPDS point E2D012D02-SPDS point E2D022) At least ONE 120v Vital AC bus energized:2RS1 - SPDS point E2RS1 or E2RS1RS32RS2 - SPDS point E2RS2 or E2RS2RS42RS3 - SPDS point E2RS3 or E2RS1RS32RS4 - SPDS point E2RS4 or E2RS2RS4Examiners note: Vital DC will be satisfied.ANYC. Check Vital AC Auxiliaries satisfied:1) At least ONE 4160v Vital AC bus (2A3/2A4) energized.Examiners note: Vital AC will be satisfied.ANYD. Check RCS Inventory Control satisfied:1) CVCS maintaining PZR level10 to 80% [40 to 70%] andlevel stable or trending to setpoint.2) RCS MTS 30&deg;F or greater.3) RVLMS LVL 03 or higher elevation indicates WET.Examiners note: Inventory Control may not be satisfied due to ESD.ANYE. Check RCS Pressure Control satisfied:1) RCS pressure maintained withinP-T limits, refer toAttachment 1, P-T Limits.Examiners note: P-T limits will be satisfied.
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 19 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+Time          Position                        Applicant's Actions or Behavior
+* Maximum of ONE CEA NOT fully inserted and Reactor power lowering.
+* Reactor power less than 10-1% and stable or lowering.
+Examiners note: Reactivity will be satisfied.
+ANY             B. Check Vital DC Auxiliaries satisfied:
+: 1) At least ONE 125v Vital DC bus energized:
+* 2D01-SPDS point E2D01
+* 2D02-SPDS point E2D02
+: 2) At least ONE 120v Vital AC bus energized:
+* 2RS1 - SPDS point E2RS1 or E2RS1RS3
+* 2RS2 - SPDS point E2RS2 or E2RS2RS4
+* 2RS3 - SPDS point E2RS3 or E2RS1RS3
+* 2RS4 - SPDS point E2RS4 or E2RS2RS4 Examiners note: Vital DC will be satisfied.
+ANY             C. Check Vital AC Auxiliaries satisfied:
+: 1) At least ONE 4160v Vital AC bus (2A3/2A4) energized.
+Examiners note: Vital AC will be satisfied.
+ANY             D. Check RCS Inventory Control satisfied:
+: 1) CVCS maintaining PZR level 10 to 80% [40 to 70%] and level stable or trending to setpoint.
+: 2) RCS MTS 30&deg;F or greater.
+: 3) RVLMS LVL 03 or higher elevation indicates WET.
+Examiners note: Inventory Control may not be satisfied due to ESD.
+ANY             E. Check RCS Pressure Control satisfied:
+: 1) RCS pressure maintained within P-T limits, refer to Attachment 1, P-T Limits.
+Examiners note: P-T limits will be satisfied.
+Revision 0                                                                         Page 18 of 22
+Appendix D                              Scenario 1                                         Form ES-D-2 Op-Test No.: 1                      Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorANYF. Check RCS and Core Heat Removal satisfied:1) At least ONE intact SG available for Heat Removal byEITHER of the following:Level 10 to 90% [20 to 90%] with FW available.Level being restored with total FW flow of 485 gpm orgreater.2) IF ANY RCP operating, THEN RCST less than 10&deg;F and NOT rising.3) IF ALL RCPs secured, THEN RCST less than 50&deg;F and NOT rising.4) RCS T C less than 555&deg;F and NOT rising.5) RCS MTS 30&deg;F or greater.6) RVLMS LVL 01 indicates WET.ANYG. Check CNTMT Isolation satisfied:1) CNTMT parameters normal:a) "CNTMT RADIATION HI" annunciator (2K10-A6)clear.b) NO unexplained rise in CNTMT radiation.c) CNTMT pressure less than18.3 psia.2) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.3) NO unexplained rise in Secondary Systems Radiationmonitor trends:Main Steam linesSG SampleCondenser Off GasExaminers note: CNTMT Isolation will not be satisfied due to ESD.
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 20 of 22Op-Test No.:  1                                  Scenario No.:  1                                 Event No.:   5, 6 & 7Event
+Time          Position                       Applicant's Actions or Behavior ANY             F. Check RCS and Core Heat Removal satisfied:
+: 1) At least ONE intact SG available for Heat Removal by EITHER of the following:
+* Level 10 to 90% [20 to 90%] with FW available.
+* Level being restored with total FW flow of 485 gpm or greater.
+: 2) IF ANY RCP operating, THEN RCS T less than 10&deg;F and NOT rising.
+: 3) IF ALL RCPs secured, THEN RCS T less than 50&deg;F and NOT rising.
+: 4) RCS TC less than 555&deg;F and NOT rising.
+: 5) RCS MTS 30&deg;F or greater.
+: 6) RVLMS LVL 01 indicates WET.
+ANY             G. Check CNTMT Isolation satisfied:
+: 1) CNTMT parameters normal:
+a) "CNTMT RADIATION HI" annunciator (2K10-A6) clear.
+b) NO unexplained rise in CNTMT radiation.
+c) CNTMT pressure less than 18.3 psia.
+: 2) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.
+: 3) NO unexplained rise in Secondary Systems Radiation monitor trends:
+* Main Steam lines
+* SG Sample
+* Condenser Off Gas Examiners note: CNTMT Isolation will not be satisfied due to ESD.
+Revision 0                                                                         Page 19 of 22
+Appendix D                                 Scenario 1                                          Form ES-D-2 Op-Test No.: 1                        Scenario No.: 1                       Event No.: 5, 6 & 7 Event
 == Description:==
-Loss of Offsite Power causing natural circulation of the RCS.  'B' Main Feed waterline break inside containment.  #1 EDG output breaker fails to automatically close.TimePositionApplicant's Actions or BehaviorANYH. Check CNTMT Temperature and Pressure Control satisfied:1) CNTMT pressure less than 16 psia.2) CNTMT temperature less than 140&deg;F.Examiners note: CNTMT Temperature and Pressure Control will notbe satisfied due to ESD.ANY12. Locally remove danger tags and close the following breakers.2B51-E4 "LTOP RELIEF ISOL2CV-4730-1"2B51-K2 "LTOP RELIEF ISOL2CV-4741-1"ANY*13. Check ALL Safety Function acceptance criteria satisfied.
+Loss of Offsite Power causing natural circulation of the RCS. B Main Feed water line break inside containment. #1 EDG output breaker fails to automatically close.
-SRO*13. Perform the following:A. Determine appropriate success paths using Success PathDecision Trees.B. Initiate success paths for ALL Safety Functions in the followingorder:1) Jeopardized.2) Challenged.3) Satisfied.
+Time          Position                           Applicant's Actions or Behavior ANY              H. Check CNTMT Temperature and Pressure Control satisfied:
-C. IF higher priority Safety Function jeopardized AND lowerpriority safety function success path in progress, THEN GO TOappropriate success path for highest priority safety function injeopardy.D. WHEN success path implemented for EACH Safety Function,THEN RETURN TO Step 14 ofEntry procedure.Examiner Note: The SRO should complete the safety functions in order of hierarchy that arechallenged first, and then the satisfied safety functions.Examiner Note: The SRO may discuss Tech Spec 3.4.1.2 RCS loops and 3.4.9.1 RCS cooldownlimits to due the excess steam demand event.Termination criteria:  When post-cooldown conditions have been stabilized and safety functionsprioritized or at examiner's discretion.
+: 1) CNTMT pressure less than 16 psia.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 21 of 22Op-Test No.:  2011-1                                  Scenario No.:  1                                 Event No.:   8Event
+: 2) CNTMT temperature less than 140&deg;F.
+Examiners note: CNTMT Temperature and Pressure Control will not be satisfied due to ESD.
+ANY        12. Locally remove danger tags and close the following breakers.
+B51-E4 LTOP RELIEF ISOL 2CV-4730-1 2B51-K2 LTOP RELIEF ISOL 2CV-4741-1 ANY        *13. Check ALL Safety Function acceptance criteria satisfied.
+SRO        *13. Perform the following:
+A. Determine appropriate success paths using Success Path Decision Trees.
+B. Initiate success paths for ALL Safety Functions in the following order:
+: 1) Jeopardized.
+: 2) Challenged.
+: 3) Satisfied.
+C. IF higher priority Safety Function jeopardized AND lower priority safety function success path in progress, THEN GO TO appropriate success path for highest priority safety function in jeopardy.
+D. WHEN success path implemented for EACH Safety Function, THEN RETURN TO Step 14 of Entry procedure.
+Examiner Note: The SRO should complete the safety functions in order of hierarchy that are challenged first, and then the satisfied safety functions.
+Examiner Note: The SRO may discuss Tech Spec 3.4.1.2 RCS loops and 3.4.9.1 RCS cooldown limits to due the excess steam demand event.
+Termination criteria: When post-cooldown conditions have been stabilized and safety functions prioritized or at examiners discretion.
+Revision 0                                                                            Page 20 of 22
+Appendix D                              Scenario 1                                      Form ES-D-2 Op-Test No.: 2011-1                      Scenario No.: 1                     Event No.: 8 Event
 == Description:==
-Backup Charging pump fail to start on SIAS or Low PZR level.TimePositionApplicant's Actions or BehaviorANYRecognize the Backup Charging pumps failed to automatically start.
+Backup Charging pump fail to start on SIAS or Low PZR level.
-SRODirect the ATC to manually start the Backup charging pumps during theESD event using OP-2202.010 Standard Attachment, Exhibit 9.ATCPerform the following to start backup charging pumps:
+Time        Position                          Applicant's Actions or Behavior ANY        Recognize the Backup Charging pumps failed to automatically start.
-.0 IF SIAS, THEN verify the following:Available Charging Pumps in service with proper dischargepressure and flow.Examiner note:  Charging pumps may be secured after the ESD eventto maintain PZR level in the desired control band.Examiner note: The ATC may discover the failure of the backup charging pumps during theLoss of Turbine load AOP, excess RCS leakage AOP, or post reactor trip. The actions should beto start the back up charging pumps IAW with the procedure in use. See Loss of Turbine loadand Excess RCS leakage charging steps below.Examiner note: Loss of Turbine Load AOP steps for charging controlANY*13.Check PZR level within 5% of setpoint:ATC 13.Perform the following as needed:Check auto operation of Charging and Letdown.Take manual control of Charging and Letdown to restorePZR level to within 5% of setpoint.IF PZR level >67%,THEN refer to TS 3.4.4Examiner note: Excess RCS leakage AOP steps for charging controlATC*4. Maintain PZR level within 5% of setpoint by performing thefollowing as necessary:A. Cycle Charging pumps.Termination criteria:  Charging pumps controlled as needed to maintain pressurizer level withingiven bands or at examiner's discretion.
+SRO        Direct the ATC to manually start the Backup charging pumps during the ESD event using OP-2202.010 Standard Attachment, Exhibit 9.
-Appendix D Scenario 1Form ES-D-2Revision 0Page 22 of 22Op-Test No.:  2011-1                                  Scenario No.:  1                                 Event No.:   9Event
+ATC        Perform the following to start backup charging pumps:
+.0     IF SIAS, THEN verify the following:
+Available Charging Pumps in service with proper discharge pressure and flow.
+Examiner note: Charging pumps may be secured after the ESD event to maintain PZR level in the desired control band.
+Examiner note: The ATC may discover the failure of the backup charging pumps during the Loss of Turbine load AOP, excess RCS leakage AOP, or post reactor trip. The actions should be to start the back up charging pumps IAW with the procedure in use. See Loss of Turbine load and Excess RCS leakage charging steps below.
+Examiner note: Loss of Turbine Load AOP steps for charging control ANY        *13.        Check PZR level within 5% of setpoint:
+ATC        13.         Perform the following as needed:
+Check auto operation of Charging and Letdown.
+Take manual control of Charging and Letdown to restore PZR level to within 5% of setpoint.
+IF PZR level >67%,
+THEN refer to TS 3.4.4 Examiner note: Excess RCS leakage AOP steps for charging control ATC        *4. Maintain PZR level within 5% of setpoint by performing the following as necessary:
+A. Cycle Charging pumps.
+Termination criteria: Charging pumps controlled as needed to maintain pressurizer level within given bands or at examiners discretion.
+Revision 0                                                                       Page 21 of 22
+Appendix D                            Scenario 1                                        Form ES-D-2 Op-Test No.: 2011-1                    Scenario No.: 1                      Event No.: 9 Event
 == Description:==
-P-35B Spray pump failed to automatically start and 2P-35A trips upon start.TimePositionApplicant's Actions or BehaviorANYRecognize the 2P-35B has failed to auto start.ANYRecognize the 2P-35A has tripped after start.
+P-35B Spray pump failed to automatically start and 2P-35A trips upon start.
-SRODirect BOP to verify Red Train Containment Spray pump running andCSAS actuated IAW 2202.010 Exhibit 9.
+Time         Position                       Applicant's Actions or Behavior ANY     Recognize the 2P-35B has failed to auto start.
-CRITICAL TASK BOP 4.0IF CSAS, THEN verify the following:CSS Pump 2P35B in service with proper discharge pressure and flow.CSS Header Isolation (2CV-5613-1) open.Examiner Note: 2P-35B should be started prior to containmentexceeding the design pressure of 59 psig or 73.7 psia.Cue: if requested as WCO, then report that 2P-35B Containment Spray pump post start checksare satisfactory.Termination criteria:  2P-35B Containment Spray Pump running or at examiner's discretion.
+ANY     Recognize the 2P-35A has tripped after start.
-Appendix D Scenario 2Form ES-D-1Revision 0Page 1 of 31Facility: ANO-2Scenario No.:  2 (New)Op-Test No.:  2011-1Examiners:Operators:Initial Conditions:100% MOL; All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure ControlValve 2PCV-0231 jacked closed. RED Train Maintenance WeekTurnover:100%. 250 EFPD. EOOS indicates 'Minimal Risk'. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed; manually control seal steam pressure. RED Train Maintenance Week.EventNo.Malf. No.EventType*EventDescription 1 XSI2LT-5637 I (BOP)I (SRO)RWT level transmitter fails low. Tech Spec for SRO.
+SRO     Direct BOP to verify Red Train Containment Spray pump running and CSAS actuated IAW 2202.010 Exhibit 9.
-SW2P4AWNDC (BOP)C (SRO)2P-4A Service water pump high winding temperaturecausing pump swap.
+CRITICAL          BOP     4.0     IF CSAS, THEN verify the following:
-SGATUBER (ATC)N (BOP)N (SRO)Shutdown required due to 4 gpm steam generator tubeleak on 'A' steam generator. Tech Spec for SRO.
+TASK CSS Pump 2P35B in service with proper discharge pressure and flow.
-CVC2P39BC(ATC)C(SRO)2P-39B Boric Acid Makeup pump will trip when it isstarted.5SGATUBEM (ALL)'A' Steam Generator tube leakage ramps up to 200 gpmover 5 minutes. Manual reactor trip criteria whengreater than 44 gpm.
+CSS Header Isolation (2CV-5613-1) open.
-CEA35STUCKCV48731CVC4916SIASC (ATC)C (SRO)Control Element Assembly #35 remains fullywithdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will notautomatically open.
+Examiner Note: 2P-35B should be started prior to containment exceeding the design pressure of 59 psig or 73.7 psia.
-ESFK401AAF416A406 K05-C03C (BOP)C (SRO)2CV-5017-1, 2CV-5015-1 Low pressure safetyinjection (LPSI) and High pressure safety injectionvalves (HPSI) fail to open and the "B" HPSI pump tripsdue to motor overload.*   (N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajorTotal malfunctions. = 7, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 1,EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 3.
+Cue: if requested as WCO, then report that 2P-35B Containment Spray pump post start checks are satisfactory.
-Appendix D Scenario 2Form ES-D-1Revision 0Page 2 of 31Scenario #2 Objectives 1)Evaluate individual response to a failure of a Refueling water tank level transmitter.
+Termination criteria: 2P-35B Containment Spray Pump running or at examiners discretion.
-)Evaluate individual response to a failure of a Service Water pump motor.
+Revision 0                                                                      Page 22 of 22
-)Evaluate individual ability to operate safety related equipment.(swap service water pump) 4)Evaluate individual response to a primary to secondary leak.
-)Evaluate individual ability to perform a reduction in plant power.
+Appendix D                                   Scenario 2                                            Form ES-D-1 Facility: ANO-2                            Scenario No.: 2 (New)                     Op-Test No.: 2011-1 Examiners:                                                Operators:
-)Evaluate individual response to a failure of a Boric Acid Makeup pump.
+Initial Conditions:
-)Evaluate individual response to a stuck out CEA after a Reactor Trip.
+% MOL; All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed. RED Train Maintenance Week Turnover:
-)Evaluate individual response to failed ESF relays causing multiple high pressure and lowpressure injection valve to not automatically reposition.
+%. 250 EFPD. EOOS indicates Minimal Risk. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed; manually control seal steam pressure. RED Train Maintenance Week.
-)Evaluate individual ability to mitigate a Steam Generator Tube rupture.
+Event           Malf. No.           Event                                      Event No.                                Type*                                   Description 1      XSI2LT-5637               I (BOP)         RWT level transmitter fails low. Tech Spec for SRO.
-)Evaluate individual ability to monitor operation of Engineered Safety Features equipment.
+I (SRO) 2      SW2P4AWND                 C (BOP)         2P-4A Service water pump high winding temperature C (SRO)         causing pump swap.
-SCENARIO #2 NARRATIVESimulator session begins with the plant at 100% power steady state Gland Seal Regulator; 2PCV-0231 is jacked closed.When the crew has completed their control room walk down and brief, the RWT level transmitter2LT-5637-2 will fail low. The SRO should enter Tech Specs 3.3.2.1 ESF Actuation systeminstrumentation and 3.3.3.6 Post accident instrumentation. The BOP will be required to bypass thePlant Protection System channel 2 for RWT level point 18.When the appropriate Tech specs have been entered and the BOP goes to the back panel to bypasspoint 18 and cued by lead examiner; the 'A' Service Water Pump (2P-4A) winding temperature willcome into alarm. The SRO will use the Annunciator Corrective action and direct swapping servicewater pumps. The BOP will swap service water pumps by placing 2P-4B Service Water Pump inservice supplying loop 1 Service Water.After the Crew has swapped service water pumps and cued by lead examiner, a primary tosecondary leak will start. The SRO will enter the primary to secondary leakage AOP, OP 2203.038.ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2.The SRO will direct the NLO's to control secondary contamination using standard attachment 19and direct the chemists to sample the SG's for activity. The crew will isolate Main steam from 'A'Steam Generator to 2P-7A EFW pump and commence a plant shutdown using boration from BoricAcid Make up tank.
+      SGATUBE                   R (ATC)         Shutdown required due to 4 gpm steam generator tube N (BOP)         leak on A steam generator. Tech Spec for SRO.
-Appendix D Scenario 2Form ES-D-1Revision 0Page 3 of 31SCENARIO #2 NARRATIVE (continued)When the boration is started 2P-39B Boric Acid Makeup pump will trip and the ATC will need toswap boric acid make up pumps. If the ATC attempts to use the gravity feed boration method, itwill not work due to the Volume Control tank outlet valve not closing. The SRO may refer to theTRM for boration flow paths.After the ATC has performed the required power reduction and cued by the lead examiner, theprimary to secondary leak value will ramp up to 200 GPM. The Crew will recognize that the leakrate is greater than reactor trip criteria of 44 GPM. The SRO will direct tripping the reactor andactuating Safety Injection Actuation Signal and Containment Cooling Actuation Signal.The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactortrips one CEA will remain withdrawn which requires emergency boration. The VCT outlet willremain open and emergency borate valve will fail to auto open from SIAS. The ATC willcommence emergency boration by opening 2CV-4916-2 emergency borate valve. Two LPSI andHPSI injection valve fail to automatically open. The BOP will open HPSI valves and the crew maydetermine to open the LPSI even though they are not currently required for plant conditions. TheATC will secure two Reactor coolant Pumps when RCS pressure goes below 1400 psia. The Crewwill lower Steam Dump master controller setpoint during SPTAs to aid in maintaining margin tosaturation. The BOP will also override Service Water to Component Cooling water to allow RCPoperation.The SRO will diagnose a Steam Generator Tube Rupture event and enter OP 2202.004, SteamGenerator Tube Rupture. The ATC will cool down the RCS to less than 535&deg;F using the bypassvalves to the condenser. The BOP will override Service Water to Auxiliary Cooling Water. TheBOP will isolate the 'A' SG using standard attachment 10 when RCS Thot is less than 535&deg;F.
+N (SRO) 4      CVC2P39B                  C(ATC)          2P-39B Boric Acid Makeup pump will trip when it is C(SRO)          started.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 4 of 31Simulator Instructions for Scenario 2Reset simulator to MOL 100% power IC steady state.Ensure that AACG is secured and annunciators clear.Place MINIMAL RISK, Green Train Protected and RED Train Maintenance Week signs on 2C11.'A' CCP lead charging pump. 'C' CCP aligned to green train.2PCV-0231, Gland Sealing Steam Pressure Control Valve failed closed.T1, T2, T3, T4, T5 set to false.T4 = SIAS2T5 = hf3b4928 ( 2HS-4928 mode select switch in borate)EventNo.Malf. No.Value/RampTimeEventDescription 1 XSI2LT-5637Trigger = T1 0RWT level transmitter fails low.
+      SGATUBE                   M (ALL)         A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
-SW2P4AWNDTrigger = T2True 2P-4A Service water pump high winding temperaturecausing pump swap.
+      CEA35STUCK                C (ATC)         Control Element Assembly #35 remains fully CV48731                   C (SRO)         withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not CVC4916SIAS                               automatically open.
-SGATUBETrigger = T3 4/2 min.Shutdown required due to 4 gpm steam generator tubeleak on 'A' steam generator. Tech Spec for SRO.
+      ESFK401AAF                C (BOP)         2CV-5017-1, 2CV-5015-1 Low pressure safety 416A406                   C (SRO)         injection (LPSI) and High pressure safety injection valves (HPSI) fail to open and the B HPSI pump trips K05-C03                                   due to motor overload.
-CVC2P39BTrigger = T5True 2P-39B Boric Acid Makeup pump will trip when it isstarted.5SGATUBE 200/5 min.'A' Steam Generator tube leakage ramps up to 200 gpmover 5 minutes. Manual reactor trip criteria when greaterthan 44 gpm.
+ * (N)ormal,      (R)eactivity,   (I)nstrument,    (C)omponent,      (M)ajor Total malfunctions. = 7, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 1, EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 3.
-CEA35STUCKCV48731CVC4916SIAS 0%1 TrueControl Element Assembly #35 remains fully withdrawnwhen the reactor trips. The VCT outlet will not close andthe emergency borate valve will not automatically open.
+Revision 0                                                                                  Page 1 of 31
-ESFK401AAF416A406 K05-C03Trigger 4 for "B"HPSI breaker andalarm TrueLck_Op/ Delay15 secOn /Delay15 sec2CV-5017-1, 2CV-5015-1 Low pressure safety injection(LPSI) and High pressure safety injection valves (HPSI)fail to open and the "B" HPSI pump trips due to motoroverload.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 5 of 31Simulator Operator CUEsAt T=0Trigger T1RWT level transmitter fails low.Cue: When contacted as the WWM, then report that I&C will start planning a work package torepair the failed instrument.Cued byleadexaminerTrigger T22P-4A Service water pump high winding temperature causing pumpswap.Cue: If asked, report that the motor for 'A' Service Water Pump is very hot to touch.Cue: When contacted as NLO, report that intake Door louvers open, Space heaters secured, IntakeHeater (2VEH-1) ON/OFF toggle switch in OFF (down), Sheet metal plates above SW pump motorsremoved.Cue: NLO reports that oil level is between Min and Max mark for 2P-4B service water pump.Cue: NLO report that SW pump packing leakoff is acceptable, Air/Vacuum Release valve ventedpump and is closed, solid stream of pressurized water issuing from the constant vent line.Cue: If contacted as Chemistry, then respond by telling the control room that you will realignchemical injection to the appropriate pumps.Cue: When contacted as the WWM, then report that electrical maintenance will investigate thehigh winding temperature.Cued byleadexaminerTrigger T3Shutdown required due to 4 gpm steam generator tube leak on 'A'steam generator.Cue: If contacted as NLO to investigate N-16 monitors locally, report that you do not see anyproblems with the N-16 monitor but their readings are elevated(give them the CR N-16 readings).Cue:  If contacted as Chemistry, then report you will sample Secondary system for activity using1604.013, Measurement of Primary to Secondary Leak Rate.Cue:  If contacted as the AO, then report you are commencing Standard Attachment 19 control ofsecondary contamination.Trigger T52P-39B Boric Acid Makeup pump will trip when it is started.Cue: If contacted as NLO, report the 2P-39B breaker 2B62-B6 breaker is trip free and 2P-39Bmotor has an acrid odor.Cued byleadexaminer'A' Steam Generator tube leakage ramps up to 200 gpm over 5minutes. Manual reactor trip criteria when greater than 44 gpm.Cue: When contacted as Chemistry, then report you will sample both S/G for activity and MonitorRDACS for off site dose releases.Cue:   If contacted as the AO, then report after 5 min that the local portions of Attachment 10 for'A' S/G are complete.Control Element Assembly #35 remains fully withdrawn when thereactor trips. The VCT outlet will not close and the emergency boratevalve will not automatically open.SIAS2Trigger T42CV-5017-1, 2CV-5015-1 Low pressure safety injection (LPSI) andHigh pressure safety injection valves (HPSI) fail to open and the "B"HPSI pump trips due to motor overload.
+Appendix D                             Scenario 2                                     Form ES-D-1 Scenario #2 Objectives
-Appendix D Scenario 2Form ES-D-2Revision 0Page 6 of 31Cue: If asked, report that the motor for 'B' High Pressure Injection pump is hot to touch, but nofire or smoke is evident.Cue: If asked, report that the over current drop flags for 'B' High Pressure Injection pump aredropped.
+: 1)  Evaluate individual response to a failure of a Refueling water tank level transmitter.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 7 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   1Event
+: 2)  Evaluate individual response to a failure of a Service Water pump motor.
+: 3)  Evaluate individual ability to operate safety related equipment.(swap service water pump)
+: 4)  Evaluate individual response to a primary to secondary leak.
+: 5)  Evaluate individual ability to perform a reduction in plant power.
+: 6)  Evaluate individual response to a failure of a Boric Acid Makeup pump.
+: 7)  Evaluate individual response to a stuck out CEA after a Reactor Trip.
+: 8)  Evaluate individual response to failed ESF relays causing multiple high pressure and low pressure injection valve to not automatically reposition.
+: 9) Evaluate individual ability to mitigate a Steam Generator Tube rupture.
+: 10) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.
+SCENARIO #2 NARRATIVE Simulator session begins with the plant at 100% power steady state Gland Seal Regulator; 2PCV-0231 is jacked closed.
+When the crew has completed their control room walk down and brief, the RWT level transmitter 2LT-5637-2 will fail low. The SRO should enter Tech Specs 3.3.2.1 ESF Actuation system instrumentation and 3.3.3.6 Post accident instrumentation. The BOP will be required to bypass the Plant Protection System channel 2 for RWT level point 18.
+When the appropriate Tech specs have been entered and the BOP goes to the back panel to bypass point 18 and cued by lead examiner; the A Service Water Pump (2P-4A) winding temperature will come into alarm. The SRO will use the Annunciator Corrective action and direct swapping service water pumps. The BOP will swap service water pumps by placing 2P-4B Service Water Pump in service supplying loop 1 Service Water.
+After the Crew has swapped service water pumps and cued by lead examiner, a primary to secondary leak will start. The SRO will enter the primary to secondary leakage AOP, OP 2203.038.
+ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2.
+The SRO will direct the NLOs to control secondary contamination using standard attachment 19 and direct the chemists to sample the SGs for activity. The crew will isolate Main steam from A Steam Generator to 2P-7A EFW pump and commence a plant shutdown using boration from Boric Acid Make up tank.
+Revision 0                                                                      Page 2 of 31
+Appendix D                                 Scenario 2                                  Form ES-D-1 SCENARIO #2 NARRATIVE (continued)
+When the boration is started 2P-39B Boric Acid Makeup pump will trip and the ATC will need to swap boric acid make up pumps. If the ATC attempts to use the gravity feed boration method, it will not work due to the Volume Control tank outlet valve not closing. The SRO may refer to the TRM for boration flow paths.
+After the ATC has performed the required power reduction and cued by the lead examiner, the primary to secondary leak value will ramp up to 200 GPM. The Crew will recognize that the leak rate is greater than reactor trip criteria of 44 GPM. The SRO will direct tripping the reactor and actuating Safety Injection Actuation Signal and Containment Cooling Actuation Signal.
+The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactor trips one CEA will remain withdrawn which requires emergency boration. The VCT outlet will remain open and emergency borate valve will fail to auto open from SIAS. The ATC will commence emergency boration by opening 2CV-4916-2 emergency borate valve. Two LPSI and HPSI injection valve fail to automatically open. The BOP will open HPSI valves and the crew may determine to open the LPSI even though they are not currently required for plant conditions. The ATC will secure two Reactor coolant Pumps when RCS pressure goes below 1400 psia. The Crew will lower Steam Dump master controller setpoint during SPTAs to aid in maintaining margin to saturation. The BOP will also override Service Water to Component Cooling water to allow RCP operation.
+The SRO will diagnose a Steam Generator Tube Rupture event and enter OP 2202.004, Steam Generator Tube Rupture. The ATC will cool down the RCS to less than 535&deg;F using the bypass valves to the condenser. The BOP will override Service Water to Auxiliary Cooling Water. The BOP will isolate the A SG using standard attachment 10 when RCS Thot is less than 535&deg;F.
+Revision 0                                                                      Page 3 of 31
+Appendix D                                 Scenario 2                                        Form ES-D-2 Simulator Instructions for Scenario 2 Reset simulator to MOL 100% power IC steady state.
+Ensure that AACG is secured and annunciators clear.
+Place MINIMAL RISK, Green Train Protected and RED Train Maintenance Week signs on 2C11.
+A CCP lead charging pump. C CCP aligned to green train.
+PCV-0231, Gland Sealing Steam Pressure Control Valve failed closed.
+T1, T2, T3, T4, T5 set to false.
+T4 = SIAS2 T5 = hf3b4928 ( 2HS-4928 mode select switch in borate)
+Event          Malf. No.         Value/                                Event No.                             Ramp                               Description Time 1       XSI2LT-5637               0       RWT level transmitter fails low.
+Trigger = T1 2       SW2P4AWND                True     2P-4A Service water pump high winding temperature Trigger = T2                      causing pump swap.
+       SGATUBE                   4/      Shutdown required due to 4 gpm steam generator tube Trigger = T3            2 min. leak on A steam generator. Tech Spec for SRO.
+       CVC2P39B                 True     2P-39B Boric Acid Makeup pump will trip when it is Trigger = T5                      started.
+       SGATUBE                  200/     A Steam Generator tube leakage ramps up to 200 gpm 5 min. over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+       CEA35STUCK               0%       Control Element Assembly #35 remains fully withdrawn CV48731                   1       when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+CVC4916SIAS              True 7       ESFK401AAF               True     2CV-5017-1, 2CV-5015-1 Low pressure safety injection 416A406                Lck_Op     (LPSI) and High pressure safety injection valves (HPSI)
+                                    / Delay    fail to open and the B HPSI pump trips due to motor 15 sec    overload.
+On /
+K05-C03                 Delay Trigger 4 for B       15 sec HPSI breaker and alarm Revision 0                                                                            Page 4 of 31
+Appendix D                              Scenario 2                                         Form ES-D-2 Simulator Operator CUEs At T=0          Trigger T1       RWT level transmitter fails low.
+Cue: When contacted as the WWM, then report that I&C will start planning a work package to repair the failed instrument.
+Cued by         Trigger T2       2P-4A Service water pump high winding temperature causing pump lead                             swap.
+examiner Cue: If asked, report that the motor for A Service Water Pump is very hot to touch.
+Cue: When contacted as NLO, report that intake Door louvers open, Space heaters secured, Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down), Sheet metal plates above SW pump motors removed.
+Cue: NLO reports that oil level is between Min and Max mark for 2P-4B service water pump.
+Cue: NLO report that SW pump packing leakoff is acceptable, Air/Vacuum Release valve vented pump and is closed, solid stream of pressurized water issuing from the constant vent line.
+Cue: If contacted as Chemistry, then respond by telling the control room that you will realign chemical injection to the appropriate pumps.
+Cue: When contacted as the WWM, then report that electrical maintenance will investigate the high winding temperature.
+Cued by         Trigger T3       Shutdown required due to 4 gpm steam generator tube leak on A lead                             steam generator.
+examiner Cue: If contacted as NLO to investigate N-16 monitors locally, report that you do not see any problems with the N-16 monitor but their readings are elevated(give them the CR N-16 readings).
+Cue: If contacted as Chemistry, then report you will sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.
+Cue: If contacted as the AO, then report you are commencing Standard Attachment 19 control of secondary contamination.
+Trigger T5       2P-39B Boric Acid Makeup pump will trip when it is started.
+Cue: If contacted as NLO, report the 2P-39B breaker 2B62-B6 breaker is trip free and 2P-39B motor has an acrid odor.
+Cued by                          A Steam Generator tube leakage ramps up to 200 gpm over 5 lead                             minutes. Manual reactor trip criteria when greater than 44 gpm.
+examiner Cue: When contacted as Chemistry, then report you will sample both S/G for activity and Monitor RDACS for off site dose releases.
+Cue: If contacted as the AO, then report after 5 min that the local portions of Attachment 10 for A S/G are complete.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+SIAS2           Trigger T4       2CV-5017-1, 2CV-5015-1 Low pressure safety injection (LPSI) and High pressure safety injection valves (HPSI) fail to open and the B HPSI pump trips due to motor overload.
+Revision 0                                                                          Page 5 of 31
+Appendix D                              Scenario 2                                      Form ES-D-2 Cue: If asked, report that the motor for B High Pressure Injection pump is hot to touch, but no fire or smoke is evident.
+Cue: If asked, report that the over current drop flags for B High Pressure Injection pump are dropped.
+Revision 0                                                                       Page 6 of 31
+Appendix D                             Scenario 2                                         Form ES-D-2 Op-Test No.: 2011-1                     Scenario No.: 2                       Event No.: 1 Event
 == Description:==
-RWT level transmitter fails low. Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce annunciators:2K04-A4 CH B RPS/ESF/PRETRIP/TRIP2K04-B3 PPS Channel TRIP2K06-A9 RWT level Lo Lo RAS pretrip.ANYReport RAS pretrip/trip on PPS insert.Also, report channel 2 RWT level reading 0.
+RWT level transmitter fails low. Tech Spec for SRO.
-BOPCompare all four channels and report 2LT-5637-2 indicates zero.Cue:  If contacted as the WCO, report that 2LT-5637-2 is not leaking and there are no localindications of a problem.
+Time         Position                         Applicant's Actions or Behavior Cued by          ANY      Announce annunciators:
-SROImplement Annunciator Corrective Action 2203.012D.2K04-A5 CH B RPS/ESF/PRETRIP/TRIP applicable actions:
+lead                      2K04-A4 CH B RPS/ESF/PRETRIP/TRIP examiner                  2K04-B3 PPS Channel TRIP 2K06-A9 RWT level Lo Lo RAS pretrip.
-.1Refer to PPS insert on 2C03 to determine cause.
+ANY      Report RAS pretrip/trip on PPS insert.
-.2Compare all Channels to validate alarm.
+Also, report channel 2 RWT level reading 0.
-.6 IF channel failed,THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5,3.3.3.6, and TRM 3.3.1.1.2K04-B3 PPS Channel TRIP applicable actions:
+BOP     Compare all four channels and report 2LT-5637-2 indicates zero.
-.1Determine which RPS or ESFAS trips have occurred onPPS inserts.
+Cue: If contacted as the WCO, report that 2LT-5637-2 is not leaking and there are no local indications of a problem.
-.3 IF channel failed,THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM3.3.1.1.SROEnter Tech 3.3.2.1, and 3.3.3.6.Direct BOP to bypass bistable points for the associated functional units:RWT level low (Bistable 18).Examiner Note:  SRO must enter Tech Spec 3.3.2.1 action 10 and3.3.3.6 action 1 for Post Accident Instrumentation.
+SRO     Implement Annunciator Corrective Action 2203.012D.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 8 of 31Bypass point 18 on PPS Channel B:
+K04-A5 CH B RPS/ESF/PRETRIP/TRIP applicable actions:
-.1Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 andTRM 3.3.1.1.
+.1        Refer to PPS insert on 2C03 to determine cause.
-.2Circle channel and functional units (points) to bebypassed below:Channel to be bypassed: A B C DPoints to be bypassed:1  2  3  4  5  6  7  8  9  10  11  12  13  16  17 18  19  20 11.3Enter appropriate Tech Spec/TRM actions.
+.2        Compare all Channels to validate alarm.
-.4Verify points to be bypassed NOT bypassed in ANYother channel.
+.6        IF channel failed, THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6, and TRM 3.3.1.1.
-.5Place desired points in BYPASS for selected channelon 2C23.Examiners Note: Key 12 required.ANYVerify annunciator 2K04-C3 PPS CHANNEL BYPASSEDVerify correct channels in bypass.
+K04-B3 PPS Channel TRIP applicable actions:
-SROContact work management.Cue: When contacted as the WWM, then report that I&C will start planning a work package torepair the failed instrument.Termination criteria: Affected channel points placed in bypassor at lead examiner's discretion.
+.1        Determine which RPS or ESFAS trips have occurred on PPS inserts.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 9 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   2Event
+.3        IF channel failed, THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM 3.3.1.1.
+SRO     Enter Tech 3.3.2.1, and 3.3.3.6.
+Direct BOP to bypass bistable points for the associated functional units:
+RWT level low (Bistable 18).
+Examiner Note: SRO must enter Tech Spec 3.3.2.1 action 10 and 3.3.3.6 action 1 for Post Accident Instrumentation.
+Revision 0                                                                        Page 7 of 31
+Appendix D                             Scenario 2                                          Form ES-D-2 Bypass point 18 on PPS Channel B:
+.1       Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 and TRM 3.3.1.1.
+.2       Circle channel and functional units (points) to be bypassed below:
+Channel to be bypassed:     A      B       C       D Points to be bypassed:
+2 3 4 5 6 7 8 9 10 11 12 13 16 17 18 19 20 11.3       Enter appropriate Tech Spec/TRM actions.
+.4       Verify points to be bypassed NOT bypassed in ANY other channel.
+.5       Place desired points in BYPASS for selected channel on 2C23.
+Examiners Note: Key 12 required.
+ANY       Verify annunciator 2K04-C3 PPS CHANNEL BYPASSED Verify correct channels in bypass.
+SRO      Contact work management.
+Cue: When contacted as the WWM, then report that I&C will start planning a work package to repair the failed instrument.
+Termination criteria: Affected channel points placed in bypass or at lead examiner's discretion.
+Revision 0                                                                         Page 8 of 31
+Appendix D                                Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                      Event No.: 2 Event
 == Description:==
-P-4A Service water pump high winding temperature causing pump swap.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYReport alarm 2K10-K2 SW PUMPS BRG/WDG TEMP HIExaminer Note: Should be cued as soon as point 18 is bypassed due totime for temperature to trend up to the alarm setpoint.
+P-4A Service water pump high winding temperature causing pump swap.
-BOP2.1  Check 2TR-1428 to determine affected pump.
+Time         Position                          Applicant's Actions or Behavior Cued by          ANY        Report alarm 2K10-K2 SW PUMPS BRG/WDG TEMP HI lead examiner Examiner Note: Should be cued as soon as point 18 is bypassed due to time for temperature to trend up to the alarm setpoint.
-BOP2.2 Press ACK ALM1 2TRS-1428 to acknowledge alarm and allowreflash.ANY2.3 Verify the following as necessary to ensure adequate IntakeStructure Ventilation:BothIntake Structure Exhaust Fans running:-  2VEF-25A-  2VEF-25B(should be started)Doorlouversopen.Spaceheaters secured.Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down).Sheet metal plates above SW pump motors removed.Cue: If asked, report that the motor for 'A' Service Water Pump is very hot to touch.Cue: When contacted as NLO, wait ~ 2 minutes and report that intake Door louvers open, Spaceheaters secured, Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down), and Sheetmetal plates above SW pump motors removed previously but have been checked.
+BOP        2.1   Check 2TR-1428 to determine affected pump.
-BOP2.4 IF unable to reduce temperature,THEN shift to standby Service Water pump.Examiners note: The Crew may elect to not use the normal procedure due to the rate oftemperature rise.
+BOP        2.2   Press ACK ALM1 2TRS-1428 to acknowledge alarm and allow reflash.
-BOPExcept from OP-2104.029 Service water system operation.19.0 STARTING AND STOPPING SERVICE WATER PUMPS19.1 IF desired to START Service Water Pump (2P-4A, 2P-4B or2P-4C),THEN perform the following:
+ANY        2.3   Verify the following as necessary to ensure adequate Intake Structure Ventilation:
-BOP19.1.2 IF NOT starting SW pump to pump down bay, Appendix D Scenario 2Form ES-D-2Revision 0Page 10 of 31THEN verify suction source aligned to ECP or Lake per ShiftingService Water Suction Sources section of this procedure.
+Both Intake Structure Exhaust Fans running:
-BOPCalls NLO to verify the following:19.1.3 Verify motor oil levels between Min and Max mark.Cue: NLO reports that oil level is between Min and Max mark for 2P-4B service water pump.
+                                         - 2VEF-25A
-BOP19.1.4 Start selected SW Pump (2P-4A/B/C).
+                                         - 2VEF-25B (should be started)
-BOP19.1.5 Check appropriate pressures rise:Loop 1 SW: 2PIS-1417-1 or P1417-1Loop2 SW: 2PIS-1423-2 or P1423-2ACW: 2PI-1603 or P1603 BOPCalls NLO to verify the following:19.1.6 Check the following for proper response:SW pump packing leakoff acceptable (enough to cool thepacking, not so excessive that a safety hazard is created).Air/Vacuum Release valve vents pump for maximum of twominutes, then closes (verified by audible response).Solid stream of pressurized water issuing from the ConstantVent line.Cue: NLO report that SW pump packing leakoff is acceptable, Air/Vacuum Release valve ventedpump and is closed, solid stream of pressurized water issuing from the constant vent line.
+Door louvers open.
-BOP 19.2IF desired to STOP Service Water Pump (2P-4A),THEN perform the following:19.2.1 Verify ANY of the following:2P-4B aligned to Loop 1 SW per Attachment I andrunning.(This condition is satisfied)Requirements of 1015.008, Unit 2 SDC Control met.Appropriate Tech Specs entered for inoperable SWloop. Refer to 2203.022, Loss of Service Water.
+Space heaters secured.
-BOP19.2.2 Secure Service Water pump (2P-4A).Examiner Note: The crew may determine to place 2P-4A service water pump in PTL due to thehigh winding temperature.
+Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down).
-BOP19.2.3 IF 2P-4B in operation on Loop 1 SW,THEN check header pressures reading as follows:Loop 1 SW (2PIS-1417-1 or P1417-1) (55 to 118 psig)ACW (2PI-1603 or P1603) (35 to 118 psig)
+Sheet metal plates above SW pump motors removed.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 11 of 31 BOPCalls NLO to verify the following:19.2.4 Check 2P-4A Discharge Check Valve (2SW-2A) closes.19.2.5 Verify 2P-4A shaft rotation stops.Cue: NLO report that 2P-4A SW pump discharge check valve is closed as indicated by a slamand the 2P-4A shaft rotation has stopped.
+Cue: If asked, report that the motor for A Service Water Pump is very hot to touch.
-BOP19.2.6 IF SW pump manipulations complete,THEN inform Chemistry of present SW pump configuration.Cue: If contacted as Chemistry, then respond by telling the control room that you will realignchemical injection to the appropriate pumps.
+Cue: When contacted as NLO, wait ~ 2 minutes and report that intake Door louvers open, Space heaters secured, Intake Heater (2VEH-1) ON/OFF toggle switch in OFF (down), and Sheet metal plates above SW pump motors removed previously but have been checked.
-SROContact Work Week Manager to investigate/ repair 2P-4A service waterpump.Cue: When contacted as the WWM, then report that electrical maintenance will investigate thehigh winding temperature.Termination criteria: When 2P-4B is running and 2P-4A is secured or at lead examiner'sdiscretion.
+BOP        2.4   IF unable to reduce temperature, THEN shift to standby Service Water pump.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 12 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   3 & 4Event
+Examiners note: The Crew may elect to not use the normal procedure due to the rate of temperature rise.
+BOP        Except from OP-2104.029 Service water system operation.
+.0 STARTING AND STOPPING SERVICE WATER PUMPS 19.1 IF desired to START Service Water Pump (2P-4A, 2P-4B or 2P-4C),
+THEN perform the following:
+BOP        19.1.2 IF NOT starting SW pump to pump down bay, Revision 0                                                                          Page 9 of 31
+Appendix D                               Scenario 2                                          Form ES-D-2 THEN verify suction source aligned to ECP or Lake per Shifting Service Water Suction Sources section of this procedure.
+BOP        Calls NLO to verify the following:
+.1.3 Verify motor oil levels between Min and Max mark.
+Cue: NLO reports that oil level is between Min and Max mark for 2P-4B service water pump.
+BOP        19.1.4 Start selected SW Pump (2P-4A/B/C).
+BOP        19.1.5 Check appropriate pressures rise:
+Loop 1 SW: 2PIS-1417-1 or P1417-1 Loop 2 SW: 2PIS-1423-2 or P1423-2 ACW: 2PI-1603 or P1603 BOP        Calls NLO to verify the following:
+.1.6 Check the following for proper response:
+SW pump packing leakoff acceptable (enough to cool the packing, not so excessive that a safety hazard is created).
+Air/Vacuum Release valve vents pump for maximum of two minutes, then closes (verified by audible response).
+Solid stream of pressurized water issuing from the Constant Vent line.
+Cue: NLO report that SW pump packing leakoff is acceptable, Air/Vacuum Release valve vented pump and is closed, solid stream of pressurized water issuing from the constant vent line.
+BOP        19.2     IF desired to STOP Service Water Pump (2P-4A),
+THEN perform the following:
+.2.1 Verify ANY of the following:
+P-4B aligned to Loop 1 SW per Attachment I and running. (This condition is satisfied)
+Requirements of 1015.008, Unit 2 SDC Control met.
+Appropriate Tech Specs entered for inoperable SW loop. Refer to 2203.022, Loss of Service Water.
+BOP        19.2.2 Secure Service Water pump (2P-4A).
+Examiner Note: The crew may determine to place 2P-4A service water pump in PTL due to the high winding temperature.
+BOP        19.2.3 IF 2P-4B in operation on Loop 1 SW, THEN check header pressures reading as follows:
+Loop 1 SW (2PIS-1417-1 or P1417-1) (55 to 118 psig)
+ACW (2PI-1603 or P1603) (35 to 118 psig)
+Revision 0                                                                           Page 10 of 31
+Appendix D                              Scenario 2                                     Form ES-D-2 BOP        Calls NLO to verify the following:
+.2.4 Check 2P-4A Discharge Check Valve (2SW-2A) closes.
+.2.5 Verify 2P-4A shaft rotation stops.
+Cue: NLO report that 2P-4A SW pump discharge check valve is closed as indicated by a slam and the 2P-4A shaft rotation has stopped.
+BOP        19.2.6 IF SW pump manipulations complete, THEN inform Chemistry of present SW pump configuration.
+Cue: If contacted as Chemistry, then respond by telling the control room that you will realign chemical injection to the appropriate pumps.
+SRO        Contact Work Week Manager to investigate/ repair 2P-4A service water pump.
+Cue: When contacted as the WWM, then report that electrical maintenance will investigate the high winding temperature.
+Termination criteria: When 2P-4B is running and 2P-4A is secured or at lead examiners discretion.
+Revision 0                                                                      Page 11 of 31
+Appendix D                             Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                     Scenario No.: 2                       Event No.: 3 & 4 Event
 == Description:==
-Shutdown required due to 4 gpm steam generator tube leak on 'A' steam generator.Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce alarmSEC SYS RADIATION HI
+Shutdown required due to 4 gpm steam generator tube leak on A steam generator.
-.Cue: If contacted as NLO to investigate N-16 monitors locally, report that you do not see anyproblems with the N-16 monitor but their readings are elevated(give them the CR N-16readings).
+Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.
-SROEnter and Implement AOP 2203.038, Primary to Secondary leakage.
+Time         Position                        Applicant's Actions or Behavior Cued by          ANY      Announce alarm SEC SYS RADIATION HI.
-SRO 2.Notify Control Board Operators to monitor floating steps.ATC*3.Cycle Charging pumps to maintain PZR level within 5% ofsetpoint.ANY*4.Check PZR level maintained within 10% of setpoint.ANY 6.Notify Chemistry to sample Secondary system for activity using1604.013, Measurement of Primary to Secondary Leak Rate.Cue:  If contacted as Chemistry, then report you will sample Secondary system for activity using1604.013, Measurement of Primary to Secondary Leak Rate.ATC 7.Initiate secondary contamination control using 2202.010Attachment 19,Control of Secondary Contamination.Cue:  If contacted as the AO, then report you are commencing Standard Attachment 19 controlof secondary contamination.ATC*8.Maintain VCT level 60 to 75%; refer to 2104.003, ChemicalAddition.ANY 9.Determine Primary to Secondary leakrate by ANY of thefollowing:Computer RCS LKRT programs.Check PZR level stable and use Charging and Letdownmismatch minus Controlled Bleed Off.Check Letdown isolated and estimate RCS leak rate by totalCharging flow minus Controlled Bleed Off. Chemistry leakrate calculation using 1604.013, Measurementof Primary to Secondary Leakage. SG Tube Leak N-16 monitors.Manual leakrate calculation.
+lead examiner Cue: If contacted as NLO to investigate N-16 monitors locally, report that you do not see any problems with the N-16 monitor but their readings are elevated(give them the CR N-16 readings).
-Appendix D Scenario 2Form ES-D-2Revision 0Page 13 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   3 & 4Event
+SRO      Enter and Implement AOP 2203.038, Primary to Secondary leakage.
+SRO      2.       Notify Control Board Operators to monitor floating steps.
+ATC      *3.      Cycle Charging pumps to maintain PZR level within 5% of setpoint.
+ANY      *4.      Check PZR level maintained within 10% of setpoint.
+ANY      6.       Notify Chemistry to sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.
+Cue: If contacted as Chemistry, then report you will sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.
+ATC      7.       Initiate secondary contamination control using 2202.010 Attachment 19, Control of Secondary Contamination.
+Cue: If contacted as the AO, then report you are commencing Standard Attachment 19 control of secondary contamination.
+ATC      *8.      Maintain VCT level 60 to 75%; refer to 2104.003, Chemical Addition.
+ANY      9.       Determine Primary to Secondary leakrate by ANY of the following:
+Computer RCS LKRT programs.
+Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.
+Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.
+Chemistry leakrate calculation using 1604.013, Measurement of Primary to Secondary Leakage.
+SG Tube Leak N-16 monitors.
+Manual leakrate calculation.
+Revision 0                                                                       Page 12 of 31
+Appendix D                              Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                     Scenario No.: 2                       Event No.: 3 & 4 Event
 == Description:==
-Shutdown required due to 4 gpm steam generator tube leak on 'A' steam generator.Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.TimePositionApplicant's Actions or BehaviorANY*10. Refer to TS 3.4.6.2, Reactor Coolant System Leakage.Examiner Note: SRO must enter Tech Spec 3.4.6.2 action a due toprimary to secondary leakageATC 12.Determine leaking SG by ANY of the following:
+Shutdown required due to 4 gpm steam generator tube leak on A steam generator.
-A.Secondary Systems Radiation Trend recorder: 2RR-1057 B.SG Sample Radiation monitors: 2RITS-5854 2RITS-5864 C.Main Steam Line Radiation monitors: 2RI-1007 2RI-1057 D.SG water sample results.
+Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.
-E.SG Tube Leak N-16 monitors.
+Time        Position                          Applicant's Actions or Behavior ANY       *10.      Refer to TS 3.4.6.2, Reactor Coolant System Leakage.
-SROWhen the Leakrate is determined to be greater than 44 gpm the SRO willdirect the Reactor trip.13. IF RCS leakage greater than 44 gpmAND in Mode 1 OR 2,THEN perform the following:
+Examiner Note: SRO must enter Tech Spec 3.4.6.2 action a due to primary to secondary leakage ATC      12.       Determine leaking SG by ANY of the following:
-A.Trip Reactor.B. Actuate SIAS.C. Actuate CCASD. GO TO 2202.001,Standard Post Trip Actions.
+A.      Secondary Systems Radiation Trend recorder:
-Appendix D Scenario 2Form ES-D-2Revision 0Page 14 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   3 & 4Event
+RR-1057 B.      SG Sample Radiation monitors:
+RITS-5854 2RITS-5864 C.      Main Steam Line Radiation monitors:
+RI-1007 2RI-1057 D.      SG water sample results.
+E.      SG Tube Leak N-16 monitors.
+SRO      When the Leakrate is determined to be greater than 44 gpm the SRO will direct the Reactor trip.
+: 13. IF RCS leakage greater than 44 gpm AND in Mode 1 OR 2, THEN perform the following:
+A. Trip Reactor.
+B. Actuate SIAS.
+C. Actuate CCAS D. GO TO 2202.001, Standard Post Trip Actions.
+Revision 0                                                                        Page 13 of 31
+Appendix D                              Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                      Scenario No.: 2                      Event No.: 3 & 4 Event
 == Description:==
-Shutdown required due to 4 gpm steam generator tube leak on 'A' steam generator.Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.TimePositionApplicant's Actions or Behavior BOP15. Isolate EFW pump 2P7A Steam supply as follows:A. Close Main Steam Supply valve to 2P7A from leaking SG: 2CV-1000-1 2CV-1050-2 SROB. Refer to TS 3.7.1.2,Emergency Feedwater System.Examiner Note: The SRO must enter TS 3.7.1.2 when the Main steamsupply valve to 2P-7A is closed.ANY 16.Check SG Blowdown aligned to SU/BD DI.Cue:  If requested as NLO for S/G blowdown alignment then, report S/G blowdown is aligned toSU/BD DI SRO*21. IF confirmed primary to secondary leakage on ANY SGquantified to meet ANY of the following:> 75 gpd (.052 gpm) AND rate of leak rise is> 30 gpd/hr (.021 gpm)Leakspike of >150 gpd (>0.1 gpm)Leakage in any one SG that exceeds 100 gpd (0.07 gpm)during allowed 24 hour period of operation after ACTIONLEVEL TWO entry.        THEN perform ACTION LEVEL THREE section of Attachment A.
+Shutdown required due to 4 gpm steam generator tube leak on A steam generator.
-SROAttachment A:ACTION LEVEL THREEA. IF leakage > 75 gpd (> 0.052 gpm) AND rising by > 30 gpd/hr,THEN perform the following as necessary:1) IF at power, THEN commence power reduction asnecessary to be < 50% power within one hour.2) Be in Mode 3 within the next two hours.B. For all other cases concerning ACTION LEVEL THREErequired entry, commence power reduction as necessary to be inMode 3 within six hours.C. Ensure any out of service leak monitoring equipment returned toservice as soon as practical.
+Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 15 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   3 & 4Event
+Time        Position                          Applicant's Actions or Behavior BOP       15. Isolate EFW pump 2P7A Steam supply as follows:
+A. Close Main Steam Supply valve to 2P7A from leaking SG:
+CV-1000-1 2CV-1050-2 SRO           B. Refer to TS 3.7.1.2, Emergency Feedwater System.
+Examiner Note: The SRO must enter TS 3.7.1.2 when the Main steam supply valve to 2P-7A is closed.
+ANY       16.      Check SG Blowdown aligned to SU/BD DI.
+Cue: If requested as NLO for S/G blowdown alignment then, report S/G blowdown is aligned to SU/BD DI SRO      *21. IF confirmed primary to secondary leakage on ANY SG quantified to meet ANY of the following:
+                                            > 75 gpd (.052 gpm) AND rate of leak rise is
+                                            > 30 gpd/hr (.021 gpm)
+Leak spike of >150 gpd (>0.1 gpm)
+Leakage in any one SG that exceeds 100 gpd (0.07 gpm) during allowed 24 hour period of operation after ACTION LEVEL TWO entry.
+THEN perform ACTION LEVEL THREE section of Attachment A.
+SRO      Attachment A:
+ACTION LEVEL THREE A. IF leakage > 75 gpd (> 0.052 gpm) AND rising by > 30 gpd/hr, THEN perform the following as necessary:
+: 1)     IF at power, THEN commence power reduction as necessary to be < 50% power within one hour.
+: 2)     Be in Mode 3 within the next two hours.
+B. For all other cases concerning ACTION LEVEL THREE required entry, commence power reduction as necessary to be in Mode 3 within six hours.
+C. Ensure any out of service leak monitoring equipment returned to service as soon as practical.
+Revision 0                                                                        Page 14 of 31
+Appendix D                             Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                     Scenario No.: 2                       Event No.: 3 & 4 Event
 == Description:==
-Shutdown required due to 4 gpm steam generator tube leak on 'A' steam generator.Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.TimePositionApplicant's Actions or BehaviorALL 22.IF required by Attachment A,THEN commence power reduction using 2102.004, PowerOperations as follows:B. IF RCS leakage less than 10 gpm,THEN perform RCS boration using2104.003, Chemical Addition,Exhibit 3, Normal RCS Boration atPower.Examiners Note:  The ATC should start a shutdown using 2104.003,Chemical Addition, Exhibit 3, Normal RCS Boration at power.
+Shutdown required due to 4 gpm steam generator tube leak on A steam generator.
-.004Poweroperations SROExaminer Note: Excerpt from Power Operations for power reduction.12.2 Commence Power reduction by performing the following asnecessary:Boration using Normal Borate Mode to Charging pumpsuction (unless directed otherwise by Abnormal OperatingProcedure)Refer to Chemical Addition (2104.003), Exhibit 3, NormalRCS Boration at Power.CEA insertion using CEDMCS Control System Operation(2105.009), Exhibit 3 CEDMCS Operations (normally forASI control).* 12.3 Lower Turbine load as necessary to hold Tave within +/- 2&deg;F ofprogram Tref using Exhibit 1, TAVE VS TREF.12.5 IF Shutdown directed by TECH SPECS,THEN initiate ATTACHMENT L to determine mode specifictime limits and continue with shutdown.Examiner Note: The SRO should give attachment L to the ShiftManager to perform.ATC 1.0VerifyBoric Acid Makeup Flow controller (2FIC-4926) set asfollows:In MANUAL OR AUTO.Setpoint set to desired flowrate.2.0. Verify desired BAM pump (2P-39A OR 2P-39B) selected forautomatic operation using BAM pump Select switch(2HS-4911-2).
+Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 16 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   3 & 4Event
+Time        Position                         Applicant's Actions or Behavior ALL      22.      IF required by Attachment A, THEN commence power reduction using 2102.004, Power Operations as follows:
+B. IF RCS leakage less than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at Power.
+Examiners Note: The ATC should start a shutdown using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at power.
+SRO      Examiner Note: Excerpt from Power Operations for power reduction.
+.2     Commence Power reduction by performing the following as necessary:
+Boration using Normal Borate Mode to Charging pump suction (unless directed otherwise by Abnormal Operating Procedure)
+Refer to Chemical Addition (2104.003), Exhibit 3, Normal RCS Boration at Power.
+.004                                  CEA insertion using CEDMCS Control System Operation Power                                     (2105.009), Exhibit 3 CEDMCS Operations (normally for operations                                ASI control).
+* 12.3   Lower Turbine load as necessary to hold Tave within +/- 2&deg;F of program Tref using Exhibit 1, TAVE VS TREF.
+.5     IF Shutdown directed by TECH SPECS, THEN initiate ATTACHMENT L to determine mode specific time limits and continue with shutdown.
+Examiner Note: The SRO should give attachment L to the Shift Manager to perform.
+ATC      1.0    Verify Boric Acid Makeup Flow controller (2FIC-4926) set as follows:
+In MANUAL OR AUTO.
+Setpoint set to desired flowrate.
+.0. Verify desired BAM pump (2P-39A OR 2P-39B) selected for automatic operation using BAM pump Select switch (2HS-4911-2).
+Revision 0                                                                       Page 15 of 31
+Appendix D                             Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                    Scenario No.: 2                       Event No.: 3 & 4 Event
 == Description:==
-Shutdown required due to 4 gpm steam generator tube leak on 'A' steam generator.Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.TimePositionApplicant's Actions or BehaviorATC3.0 Operate Mode Select Switch (2HS-4928) as follows:3.1 Place to BORATE.3.2 Verify the following:ChargingPump Suction From Boric Acid (2CV-4930)opens.Selected BAM pump (2P-39A OR 2P-39B) running.Examiner Note: When the Mode Select Switch is placed in the Borateposition 2P-39B will start and then trip.ATCRecognize and report 2P-39B tripped after start.Cue: If contacted as NLO, report the 2P-39B breaker 2B62-B6 breaker is trip free and 2P-39Bmotor has an acrid odor.
+Shutdown required due to 4 gpm steam generator tube leak on A steam generator.
-SRODirect another boration method i.e. 2P-39A preferred, gravity feed.Examiner Note: gravity feed boration will not be available due to theVCT outlet valve not closing.ATC2.0. Verify desired BAM pump (2P -39A OR 2P -39B) selected forautomatic operation using BAM pump Select switch(2HS-4911-2).
+Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 17 of 31Op-Test No.:  2011-1                                 Scenario No.:  2                                   Event No.:   3 & 4Event
+Time        Position                         Applicant's Actions or Behavior ATC      3.0    Operate Mode Select Switch (2HS-4928) as follows:
+.1 Place to BORATE.
+.2 Verify the following:
+Charging Pump Suction From Boric Acid (2CV-4930) opens.
+Selected BAM pump (2P-39A OR 2P-39B) running.
+Examiner Note: When the Mode Select Switch is placed in the Borate position 2P-39B will start and then trip.
+ATC      Recognize and report 2P-39B tripped after start.
+Cue: If contacted as NLO, report the 2P-39B breaker 2B62-B6 breaker is trip free and 2P-39B motor has an acrid odor.
+SRO      Direct another boration method i.e. 2P-39A preferred, gravity feed.
+Examiner Note: gravity feed boration will not be available due to the VCT outlet valve not closing.
+ATC      2.0. Verify desired BAM pump (2P -39A OR 2P -39B) selected for automatic operation using BAM pump Select switch (2HS-4911-2).
+Revision 0                                                                       Page 16 of 31
+Appendix D                               Scenario 2                                      Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 2                     Event No.: 3 & 4 Event
 == Description:==
-Shutdown required due to 4 gpm steam generator tube leak on 'A' steam generator.Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.TimePositionApplicant's Actions or BehaviorATC3.0 Operate Mode Select Switch (2HS-4928) as follows:3.1 Place to BORATE.3.2 Verify the following:ChargingPump Suction From Boric Acid (2CV-4930)opens.Selected BAM pump (2P-39A OR 2P-39B) running.Examiner Note: Step 3 may not need to be performed again but theSRO may direct securing normal lineup prior to swapping BAMpumps*4.0 IF additional boric acid flow required,THEN manually start additional BAM pump (2P-39A OR 2P-39B).*5.0 Verify BAM Tank Recirc Valve (2CV-4903-2 OR 2CV-4915-2)open for running pumps.6.0 Operate Boric Acid Makeup Flow Batch controller (2FQIS-4926)as follows:6.1 Depress Red pushbutton.6.2 Verify 2FQIS-4926 set for desired quantity.6.3 Verify 2FIC-4926 indicates desired flow rate.*7.0 Monitor the following parameters:RCS TaveAxial Shape IndexReactor powerExaminer Note: The SRO may enter the TRM 3.1.2.2 for boration flow path or TRM 3.1.2.6 for2P-39B if it is discovered that the VCT outlet valve 2CV-4873-1 will not close or if 2T-6A Boricacid tank level lowers below the limit. Termination Criteria:  When reactivity manipulations are satisfied or at the discretion of thelead examiner.
+Shutdown required due to 4 gpm steam generator tube leak on A steam generator.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 18 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYCrew determines the leak rate has risen to >44gpm.ALL13. IF RCS leakage greater than 44 gpmAND in Mode 1 OR 2,THEN perform the following:
+Tech Spec for SRO. 2P-39B Boric Acid Makeup pump will trip when it is started.
-A.Trip Reactor.B. Actuate SIAS.C. Actuate CCASD. GO TO 2202.001,Standard Post Trip Actions.
+Time          Position                        Applicant's Actions or Behavior ATC       3.0   Operate Mode Select Switch (2HS-4928) as follows:
-SROEnter and implement EOP 2202.001, Standard Post Trip Actions.
+.1 Place to BORATE.
-SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.
+.2 Verify the following:
-.Open Safety Function Tracking page.ReactivitycontrolsafetyfunctionATC 3.Check Reactivity Control established as follows:A. Reactor power lowering._____B. ALL CEAs fully inserted by observing Rod bottom lightsilluminated. (Not met due to Event #6, performcontingency)Reactivitycontrolsafetyfunction SRODirect ATC to perform emergency boration in progress using Exhibit 1,Emergency Boration._____B. Perform the following as necessary:_____1)Check CEACs 1 AND 2 indicates ALL CEAs fullyinserted.(Not met due to Event #6, perform contingency)_____2)Verify emergency boration in progress using Exhibit 1,Emergency Boration.
+Charging Pump Suction From Boric Acid (2CV-4930) opens.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 19 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorATC1. Select ONE of the following Emergency Boration flowpaths:FLOWPATHACTIONS REQUIRED A.Gravity Feed A.Verify at least ONE BAMTank Gravity Feed valve open:2CV-4920-12CV-4921-1B. BAM pumps B.1) Start at least ONE BAM pump.2) Open Emergency Borate valve     (2CV-4916-2).3) Verify Boric Acid Makeup    Flow Control valve    (2CV-4926) closed.
+Selected BAM pump (2P-39A OR 2P-39B) running.
-C.RWT to Charging pumpsC. Open Charging Pump Suction     Source From RWT valve     (2CV-4950-2).Examiner Note: 2P-39A Boric Acid Makeup pump will be required tobe used and should already be running.ATC2. Close VCT Outlet valve (2CV-4873-1).Examiner Note: The VCT outlet valve will not close and ATC shouldperform step 3.ATC 3. IF VCT Outlet valve does NOT close,THEN verify BAM Pumps Emergency Boration flowpath selected.Examiner Note: The emergency borate valve 2CV-4916-2 will notautomatically open and must be manually opened by ATC.EmergencyBorationCritical Task:EmergencyBorationmust be startedprior tocompletionof SPTAsATC4. Verify Reactor Makeup Water Flow Control valve (2CV-4927)closed.5. Verify at least ONE Charging pump running and charging headerflow greater than 40 gpm.
+Examiner Note: Step 3 may not need to be performed again but the SRO may direct securing normal lineup prior to swapping BAM pumps
-BOPComplete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.
+                              *4.0 IF additional boric acid flow required, THEN manually start additional BAM pump (2P-39A OR 2P-39B).
-Appendix D Scenario 2Form ES-D-2Revision 0Page 20 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorVitalAuxiliariessafetyfunction BOP 4.Check Maintenance of Vital Auxiliaries satisfied:A. Check Main Turbine tripped by BOTH of the following:ALL Main Stop Valves closed.Generator megawatts indicate zero.B. Generator Output breakers open.C. Exciter Field breaker open.D. At least ONE 6900v AC bus energizedE. At least ONE 4160v Non-vital AC bus energized.F. BOTH 4160v Vital AC buses energized.
+                              *5.0 Verify BAM Tank Recirc Valve (2CV-4903-2 OR 2CV-4915-2) open for running pumps.
-G.BOTH DGs secured.Both DGs will be running with servicewater aligned
+.0 Operate Boric Acid Makeup Flow Batch controller (2FQIS-4926) as follows:
-)H. At least ONE 125v Vital DC bus energized:2D01 - SPDS point E2D012D02 - SPDS point E2D02 RCSInventoryControlSafetyfunctionATC 5.Check RCS Inventory Control established as follows:A. PZR level:10 to 80%.Trending to setpoint.(Will not be met due to SGTR Event#5 perform contingency)B. RCS MTS 30&deg;F or greater.
+.1 Depress Red pushbutton.
-RCSInventoryControlSafetyfunction SRODirect the following as necessary:A. Perform as necessary:
+.2 Verify 2FQIS-4926 set for desired quantity.
-: 1) IF SIAS actuated on PPS inserts, THEN GO TOStep 6.2) Verify PZR Level Control system restoring level to setpoint.
+.3 Verify 2FIC-4926 indicates desired flow rate.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 21 of 31
+                              *7.0 Monitor the following parameters:
-______Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or Behavior RCSPressureControlSafetyfunction BOP 6.Check RCS Pressure Control:1800 to 2250 psia.Trending to setpoint
+RCS Tave Axial Shape Index Reactor power Examiner Note: The SRO may enter the TRM 3.1.2.2 for boration flow path or TRM 3.1.2.6 for 2P-39B if it is discovered that the VCT outlet valve 2CV-4873-1 will not close or if 2T-6A Boric acid tank level lowers below the limit.
-. (Not met due to SGTR Event #5,perform contingency)
+Termination Criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.
-RCSPressureControlSafetyfunction SRODirect the following actions as necessary:
+Revision 0                                                                        Page 17 of 31
-.Perform as necessary:A. IF RCS pressure lowers to less than 1400 psia,THEN trip ONE RCP in EACH loop.D. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.E. IF RCS pressure lowers to 1650 psia or less,THEN perform the following:1) Verify SIAS actuated on PPS inserts.
-)GO TO Step 7.F. Verify PZR Pressure Control system restoring pressure tosetpoint.ATC 7.Check Core Heat Removal by forced circulation:
+Appendix D                              Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
-A.At least ONE RCP running.B. CCW flow aligned to RCPs
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
-.C. Loop delta T less than 10&deg;F.D. RCS MTS 30&deg;F or greater.E. Check SW aligned to CCW
+Time         Position                          Applicant's Actions or Behavior Cued by           ANY      Crew determines the leak rate has risen to >44gpm.
-.(SW will not be aligned due toSIAS and should perform contingency)F. IF SIAS or MSIS actuated,THEN maintain SW header pressure greater than 85 psig.Core HeatRemovalsafetyfunction.SRODirect the contingency for step 7. E Appendix D Scenario 2Form ES-D-2Revision 0Page 22 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or Behavior BOPE. IF CCW available,THEN restore SW to CCW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.Examiner Note: The SRO may decide to pull up the step to align SWto ACW to maintain condenser vacuum pump working properly.RCS HeatRemovalSafetyFunctionBOP/ATC 8.Check RCS Heat Removal:A. Check SG available by BOTH of the following:At least ONE SG level 10 to 90%.FW maintaining SG levelB. Check MFW in RTO(MFW may not be in RTO due to steamgenerator levels being at setpoint, and the contingencies aresatisfied if steam generator levels are controlling near thesetpoint)C. Check Feedwater line intact by the following:SG level stable or rising.NO unexplained step changes or erratic FW flow.NO unexplained step changes or erratic Condensate flow.D. Check SG pressure 950 to 1050 psia.E. IF desired,THEN perform the following for SDBCS Master Controllerusing 2105.008 Exhibit 3:1) Place controller in Auto/Local.2) Set setpoint at 960 psia.F. Check RCS TC 540 to 555&deg;F.
+lead examiner ALL        13. IF RCS leakage greater than 44 gpm AND in Mode 1 OR 2, THEN perform the following:
-Appendix D Scenario 2Form ES-D-2Revision 0Page 23 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorContainmentSafetyFunctionANY 9.Check CNTMT parameters:A. Temperature and Pressure:Temperature less than 140&deg;F.Pressure less than 16 psia.B. Check CNTMT Spray pumps secured.C. NO CNTMT radiation alarms or unexplained rise in activity:1) CAMS alarms:"CNTMT PART/GAS RAD HI/LO" annunciator(2K10-B6) clear.2) RCS leakage alarms:"AREA RADIATION HI/LO" annunciator (2K11-B10)clear."PROC LIQUID RADIATION HI/LO" annunciator(2K11-C10) clear.3) Check the following radiation monitors trend stable:CNTMT AreaMSProcess LiquidD. NO secondary system radiation alarms or unexplained rise inactivity:(Not met due to SGTR Event #5)
+A. Trip Reactor.
-: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.2) Secondary Systems Radiation monitors trend stable:Main Steam linesSG SampleCondenser Off Gas Appendix D Scenario 2Form ES-D-2Revision 0Page 24 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or Behavior SRO10. Notify STA to report to control room.11. Verify NLOs informed of Reactor trip.12. Verify Reactor trip announced on Plant page.13. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.
+B. Actuate SIAS.
-SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.
+C. Actuate CCAS D. GO TO 2202.001, Standard Post Trip Actions.
-SRO15. Check ALL safety function acceptance criteria satisfied.(All safetyfunctions are not satisfied, perform contingency)15. IF ANY safety function acceptance criteria NOT satisfied,THEN perform the following:A. Notify control room staff ofsafety functions NOT satisfied.B. GO TO Exhibit 8,Diagnostic Actions.
+SRO      Enter and implement EOP 2202.001, Standard Post Trip Actions.
-SRODiagnose Steam Generator Tube Rupture EOP 2202.004 SROEnter and implement Steam Generator Tube Rupture EOP 2202.004 SRO* 1. Confirm diagnosis of SGTR:A. Check SFSC acceptance criteria satisfied every 15 minutes.B. Refer to 2202.010 Attachment 20,Break Identification Chart.C. Verify SG Sample valves open.D. Notify Chemistry to perform BOTH of the following:SampleBOTH SGs for activity
+: 1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.
-.Monitor RDACS for off site dose releases
+SRO
-.Cue: When contacted as Chemistry, then report you will sample both S/G for activity andMonitor RDACS for off site dose releases.
+: 2. Open Safety Function Tracking page.
-SRO* 2. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.
+Reactivity        ATC     3. Check Reactivity Control established as follows:
-SRO 3.Open Placekeeping Page.
+control safety                                   A. Reactor power lowering.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 25 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or Behavior SRO 4.Record present time:TimeANY 5.Verify SIAS and CCAS actuated on PPS inserts.
+function
-SRO 6.Notify Control Board Operators to perform the following:A. Monitor floating steps.B. Verify actuated ESFAS components using 2202.010, Exhibit 9,ESFAS Actuation.ANY*7. Check CCW aligned to RCPs.
+_____B. ALL CEAs fully inserted by observing Rod bottom lights illuminated. (Not met due to Event #6, perform contingency)
-SROMay elect to pull up the floating step for commencing a cooldown. Step 12.It is possible that the SRO will implement step 11 at the same time heimplements step 8.ATC12. Commence RCS cooldown to less than 535&deg;F TH as follows:A. Reset Low SG Pressure setpoints during cooldown anddepressurization.B. Commence RCS depressurization to maintain RCS MTS 30 to 45&deg;F.C. Monitor cooldown rate as follows:Record RCS T C and PZR temperature using Attachment 8,RCS Cooldown Table.Plot RCS pressure versus RCS T C using 2202.010Attachment 1, P-T Limits every 15 minutes.D. IF ANY RCPs running,THEN initiate RCS cooldown using EITHER of the following:1) SDBCS Bypass valves (condenser available) - mostpreferred.2) SDBCS ADV from intact SG to atmosphere - leastpreferred IF necessary, THEN supplement with SDBCS ADV fromruptured SG to atmosphere as needed.           Examiner Note:  The SDBCS Bypass valves should be used tominimize off site release.
+Reactivity        SRO      Direct ATC to perform emergency boration in progress using Exhibit 1, control                    Emergency Boration.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 26 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorANYF. IF SDBCS Bypass valves available for RCS cooldown, THENplace ALL ADV Permissive switches in OFF.
+safety function                   _____B. Perform the following as necessary:
-BOPG. Control S/G levels with EFW or AFW using 2106.006,Emergency Feedwater System Operations.ANYH. Secure running MFW pump.
+_____1) Check CEACs 1 AND 2 indicates ALL CEAs fully inserted. (Not met due to Event #6, perform contingency)
-BOPI. Close ALL MFW Block valves.ANY8. Restore ESF/Non-ESF systems post-SIAS as follows:A. Verify at least ONE SW pump running on EACH loop.ANYB. Verify DG SW Outlet valves open.ANYC. Verify SW pump suction aligned to Lake.ANYD. Check 4160v Non-vital bus 2A1 or 2A2 energized fromoffsite power.ANYE. Check 4160v Vital buses 2A3 AND 2A4 energized from offsitepower.BOPF. Start SW pumps as needed to maintain SW header pressure.ANYG. Check SW to CCW restored.ANYH. Check ACW restored.(Not met, perform contingency)
+_____2) Verify emergency boration in progress using Exhibit 1, Emergency Boration.
-BOPH. Restore SW to ACW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.
+Revision 0                                                                         Page 18 of 31
-BOPI. Maintain SW header pressure greater than 85 psig.ANY*9. Verify Safety Injection flow to RCS as follows:A. Check total HPSI flow acceptable using 2202.010 Exhibit 2,HPSI Flow Curve.B. Check total LPSI flow acceptable using 2202.010 Exhibit 3,LPSI Flow Curve.Examiner Note: will not be met see event #7 actionsANY10. Check RCS pressure greater than 1400 psia.(May not be met, ifnot met perform contingency)
-Appendix D Scenario 2Form ES-D-2Revision 0Page 27 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorANY10. Perform the following: (Contingency)A. IF RCS pressure less than 1400 psia, THEN perform thefollowing:1) Verify maximum of ONE RCP running in EACH loop.
+Appendix D                              Scenario 2                                          Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 2                    Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
-: 2) IF RCP 2P32A or 2P32B stopped, THEN verify associatedPZR Spray valve in MANUAL and closed.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
-B.IF NPSH requirements violated ORRCS MTS less than 30&deg;F,THEN perform the following:1) Stop ALL RCPs.2) Verify BOTH PZR Spray valves in MANUAL and closed.ANY11. Check IA pressure greater than 65 psig.ANY*13. Minimize primary to secondary break flow as follows:A. Check ANY RCP running.B. Maintain RCS pressure within the following criteria:Within 100 psia above minimumRCP NPSH requirement, refer to 2202.010 Attachment 1,P-T Limits.Less than 1000 psia as conditions allow.Within 50 psi of rupturedSG pressure as RCP NPSH requirements allow.Examiners Note: The criteria to minimize break flow can not beestablished until HPSI is overridden. Then the crew should establishthese limits.ANYC. Use EITHER of the following to depressurize RCS:
+Time        Position                          Applicant's Actions or Behavior ATC      1. Select ONE of the following Emergency Boration flowpaths:
-)2202.010 Attachment 27,PZR Spray Operation.
+FLOWPATH                       ACTIONS REQUIRED A. Gravity Feed             A.      Verify at least ONE BAM Tank Gravity Feed valve open:
-)IF HPSI termination criteria met, THEN cycle Chargingpumps or throttle HPSI flow to lowerPZR pressure.
+* 2CV-4920-1
-Appendix D Scenario 2Form ES-D-2Revision 0Page 28 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorANYD. IF RCS pressure less than ruptured SG pressure,THEN sample RCS Boron concentration every 30 minutes.ANY 14.Determine ruptured SG by comparing ANY of the following:A. Secondary Systems Radiation Trend recorder (2RR-1057).B. Main Steam Line Radiation Monitors:C. SG Sample Radiation Monitors:D. SG Tube Leak N-16 Monitor history trends.E. SG levels.1) Level rising faster in ONE SG with similar FW flow ratesand steaming rates in BOTH SGs.2) Rising SG level withALL FW isolated.F. Steam flow and FW flow prior to Reactor trip.G. SG water sample results.ANYDirect the NLO's to perform the following:
+* 2CV-4921-1 B. BAM pumps                B.      1) Start at least ONE BAM pump.
-.Minimize secondary contamination by performing BOTH of thefollowing:A. Commence isolation of ruptured SG by performing local actionsONLY of 2202.010 Attachment 10, SG Isolation.B. 2202.010 Attachment 19,Control of Secondary Contamination.Examiner Note: Standard Att. 19 should already be started and maynot be communicated again to NLOs.Cue:  If contacted as the AO, then report after 5 min that the local portions of Attachment 10 for'A' S/G are complete.
+: 2) Open Emergency Borate valve (2CV-4916-2).
-Appendix D Scenario 2Form ES-D-2Revision 0Page 29 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or BehaviorANY16. Isolate ruptured SG Steam Supply toEFW pump 2P7A as follows:ANYA. Verify EFW pump 2P7B running.
+Emergency                                                            3) Verify Boric Acid Makeup Boration                                                                Flow Control valve (2CV-4926) closed.
-B. IF 2P7B NOT running,THEN verify AFW pump 2P75 running.ANYC. Stop EFW pump 2P7A:1) Override and close Steam Supply to 2P7A valve(2CV-0340-2).
+Critical                         C. RWT to Charging pumps            C. Open Charging Pump Suction Task:
-)Close Main Steam Supply valve from ruptured SG toEFW pump 2P7A:"SG A TO EMER FW PMP TURB" 2CV-1000-1"SG B TO EMER FW PMP TURB" 2CV-1050-2ALL19. Isolate ruptured SG as follows:A. Monitor RCS TH during cooldown with ANY of the following:PMS point T4614PMS point T4714SPDS displayB. WHEN RCS TH less than 535&deg;F,THEN isolate ruptured SG using2202.010 Attachment 10,      SG Isolation.C. Maintain ruptured SG less than1050 psia with ONE of the following
+Emergency                                                                Source From RWT valve Boration                                                                 (2CV-4950-2).
-:MSIV Bypass valveUpstreamADV Appendix D Scenario 2Form ES-D-2Revision 0Page 30 of 31Op-Test No.:  2011-1                                   Scenario No.:  2                            Event No.:   5 & 6'A' Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteriawhen greater than 44 gpm.Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet willnot close and the emergency borate valve will not automatically open.TimePositionApplicant's Actions or Behavior CRITICAL TASKControlRoomactions for 2202.010StandardAttachment 10 BOP2. Verify each component in the following table in the indicatedposition:COMPONENT DESCRIPTION1.0NUMBER2.0LOCATION3.0POSITIONADV UPSTRM ISOL2CV-1002*2C02CLOSED (1)2CV-1001 PERMISSIVE2CV-1001 2C02OFF       (1)MSIV HEADER #12SV-1010-1A 2C17CLOSEDMSIV HEADER #12SV-1010-2A 2C16CLOSEDMSIV HEADER #1 BYP2CV-1040-1 2C17CLOSED (1)MAIN STEAM TO EFWP TURB 2K032CV-1000-1 2C17CLOSEDFEEDWATER BLOCK VALVE TO SG-A2CV-1024-1 2C17CLOSEDFEEDWATER BLOCK VALVE TO SG-A2CV-1023-2 2C16CLOSEDSG BLOWDOWN ISOLATION2CV-1016-1 2C17CLOSED (1)2P7B DISCHARGE TO SG-A2CV-1038-2* 2C17CLOSED (1)FLOW CONTROL VALVE TO SG-A2CV-1025-1* 2C17CLOSED (1)SAMPLE ISOLATION VALVE SG-A2CV-5850 2C17CLOSED (1)2P7A DISCHARGE TO SG-A2CV-1026-2* 2C16CLOSED (1)2P7A DISCHARGE TO SG-A2CV-1037-1* 2C16CLOSED (1)SAMPLE ISOLATION VALVE STEAM GEN A 2CV-5852-2* 2C16CLOSED (1)* Denotes override capability.NOTE #1:  Valves may be open at SM/CRS discretion.Examiner Note: 2202.010 Attachment 10 local and control roomactions must be complete within 30 minutes of entering the SteamGenerator Tube Rupture EOP.Termination criteria:  RCS Cool down to less than 535&deg;F Th and 'A' SG isolated or at thediscretion of the lead examiner.
+must be                    Examiner Note: 2P-39A Boric Acid Makeup pump will be required to started                    be used and should already be running.
-Appendix D Scenario 2Form ES-D-2Revision 0Page 31 of 31Op-Test No.:  2011-1                                  Scenario No.:  2                                 Event No.:   7Event
+prior to completion        ATC      2. Close VCT Outlet valve (2CV-4873-1).
+of SPTAs Examiner Note: The VCT outlet valve will not close and ATC should perform step 3.
+ATC      3. IF VCT Outlet valve does NOT close, THEN verify BAM Pumps Emergency Boration flowpath selected.
+Examiner Note: The emergency borate valve 2CV-4916-2 will not automatically open and must be manually opened by ATC.
+ATC      4. Verify Reactor Makeup Water Flow Control valve (2CV-4927) closed.
+: 5. Verify at least ONE Charging pump running and charging header flow greater than 40 gpm.
+BOP      Complete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.
+Revision 0                                                                           Page 19 of 31
+Appendix D                              Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                  Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior BOP     4. Check Maintenance of Vital Auxiliaries satisfied:
+A. Check Main Turbine tripped by BOTH of the following:
+ALL Main Stop Valves closed.
+Generator megawatts indicate zero.
+B. Generator Output breakers open.
+C. Exciter Field breaker open.
+D. At least ONE 6900v AC bus energized Vital Auxiliaries                      E. At least ONE 4160v Non-vital AC bus energized.
+safety function                         F. BOTH 4160v Vital AC buses energized.
+G. BOTH DGs secured. Both DGs will be running with service water aligned)
+H. At least ONE 125v Vital DC bus energized:
+D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC     5. Check RCS Inventory Control established as follows:
+A. PZR level:
+RCS Inventory                                 10 to 80%.
+Control                                   Trending to setpoint. (Will not be met due to SGTR Event Safety                                    #5 perform contingency) function                         B. RCS MTS 30&deg;F or greater.
+SRO     Direct the following as necessary:
+RCS                              A. Perform as necessary:
+Inventory Control Safety                                1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.
+function
+: 2) Verify PZR Level Control system restoring level to setpoint.
+Revision 0                                                                         Page 20 of 31
+Appendix D                              Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior RCS               BOP     6. Check RCS Pressure Control:
+___
+Pressure
+* 1800 to 2250 psia.
+___
+* Trending to setpoint. (Not met due to SGTR Event #5, Control Safety                                perform contingency) function SRO     Direct the following actions as necessary:
+: 6. Perform as necessary:
+A. IF RCS pressure lowers to less than 1400 psia, THEN trip ONE RCP in EACH loop.
+D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and RCS                                   closed.
+Pressure Control                           E. IF RCS pressure lowers to 1650 psia or less, Safety                                THEN perform the following:
+function                              1) Verify SIAS actuated on PPS inserts.
+: 2) GO TO Step 7.
+F. Verify PZR Pressure Control system restoring pressure to setpoint.
+ATC     7. Check Core Heat Removal by forced circulation:
+A. At least ONE RCP running.
+B. CCW flow aligned to RCPs.
+C. Loop delta T less than 10&deg;F.
+Core Heat Removal D. RCS MTS 30&deg;F or greater.
+safety function.
+E. Check SW aligned to CCW. (SW will not be aligned due to SIAS and should perform contingency)
+F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.
+SRO     Direct the contingency for step 7. E Revision 0                                                                         Page 21 of 31
+Appendix D                               Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                           Applicant's Actions or Behavior BOP             E. IF CCW available, THEN restore SW to CCW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.
+Examiner Note: The SRO may decide to pull up the step to align SW to ACW to maintain condenser vacuum pump working properly.
+BOP/ATC    8. Check RCS Heat Removal:
+A. Check SG available by BOTH of the following:
+* At least ONE SG level 10 to 90%.
+* FW maintaining SG level B. Check MFW in RTO (MFW may not be in RTO due to steam generator levels being at setpoint, and the contingencies are satisfied if steam generator levels are controlling near the setpoint)
+C. Check Feedwater line intact by the following:
+RCS Heat Removal
+* SG level stable or rising.
+Safety Function
+* NO unexplained step changes or erratic FW flow.
+* NO unexplained step changes or erratic Condensate flow.
+D. Check SG pressure 950 to 1050 psia.
+E. IF desired, THEN perform the following for SDBCS Master Controller using 2105.008 Exhibit 3:
+: 1)      Place controller in Auto/Local.
+: 2)      Set setpoint at 960 psia.
+F. Check RCS TC 540 to 555&deg;F.
+Revision 0                                                                          Page 22 of 31
+Appendix D                               Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                  Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior ANY     9. Check CNTMT parameters:
+A. Temperature and Pressure:
+* Temperature less than 140&deg;F.
+* Pressure less than 16 psia.
+B. Check CNTMT Spray pumps secured.
+C. NO CNTMT radiation alarms or unexplained rise in activity:
+: 1) CAMS alarms:
+                                           * "CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.
+: 2) RCS leakage alarms:
+                                           * "AREA RADIATION HI/LO" annunciator (2K11-B10)
+Containment                                    clear.
+Safety                                    * "PROC LIQUID RADIATION HI/LO" annunciator Function                                       (2K11-C10) clear.
+: 3) Check the following radiation monitors trend stable:
+* CNTMT Area
+* CAMS
+* Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity: (Not met due to SGTR Event #5)
+: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.
+: 2) Secondary Systems Radiation monitors trend stable:
+* Main Steam lines
+* SG Sample
+* Condenser Off Gas Revision 0                                                                         Page 23 of 31
+Appendix D                               Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                  Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior SRO     10. Notify STA to report to control room.
+: 11. Verify NLOs informed of Reactor trip.
+: 12. Verify Reactor trip announced on Plant page.
+: 13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
+SRO     14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.
+SRO     15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)
+: 15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:
+A. Notify control room staff of safety functions NOT satisfied.
+B. GO TO Exhibit 8, Diagnostic Actions.
+SRO     Diagnose Steam Generator Tube Rupture EOP 2202.004 SRO     Enter and implement Steam Generator Tube Rupture EOP 2202.004 SRO
+* 1. Confirm diagnosis of SGTR:
+A. Check SFSC acceptance criteria satisfied every 15 minutes.
+B. Refer to 2202.010 Attachment 20, Break Identification Chart.
+C. Verify SG Sample valves open.
+D. Notify Chemistry to perform BOTH of the following:
+* Sample BOTH SGs for activity.
+* Monitor RDACS for off site dose releases.
+Cue: When contacted as Chemistry, then report you will sample both S/G for activity and Monitor RDACS for off site dose releases.
+SRO
+* 2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
+SRO     3. Open Placekeeping Page.
+Revision 0                                                                         Page 24 of 31
+Appendix D                                Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                         Scenario No.: 2                  Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                           Applicant's Actions or Behavior SRO     4.       Record present time:
+Time ANY     5.       Verify SIAS and CCAS actuated on PPS inserts.
+SRO     6.       Notify Control Board Operators to perform the following:
+A. Monitor floating steps.
+B. Verify actuated ESFAS components using 2202.010, Exhibit 9, ESFAS Actuation.
+ANY     *7.      Check CCW aligned to RCPs.
+SRO      May elect to pull up the floating step for commencing a cooldown. Step 12.
+It is possible that the SRO will implement step 11 at the same time he implements step 8.
+ATC        12. Commence RCS cooldown to less than 535&deg;F TH as follows:
+A. Reset Low SG Pressure setpoints during cooldown and depressurization.
+B. Commence RCS depressurization to maintain RCS MTS 30 to 45&deg;F.
+C. Monitor cooldown rate as follows:
+* Record RCS TC and PZR temperature using Attachment 8, RCS Cooldown Table.
+* Plot RCS pressure versus RCS TC using 2202.010 Attachment 1, P-T Limits every 15 minutes.
+D. IF ANY RCPs running, THEN initiate RCS cooldown using EITHER of the following:
+: 1) SDBCS Bypass valves (condenser available) - most preferred.
+: 2) SDBCS ADV from intact SG to atmosphere - least preferred IF necessary, THEN supplement with SDBCS ADV from ruptured SG to atmosphere as needed.
+Examiner Note: The SDBCS Bypass valves should be used to minimize off site release.
+Revision 0                                                                          Page 25 of 31
+Appendix D                              Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                  Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior ANY            F. IF SDBCS Bypass valves available for RCS cooldown, THEN place ALL ADV Permissive switches in OFF.
+BOP            G. Control S/G levels with EFW or AFW using 2106.006, Emergency Feedwater System Operations.
+ANY            H. Secure running MFW pump.
+BOP            I. Close ALL MFW Block valves.
+ANY       8. Restore ESF/Non-ESF systems post-SIAS as follows:
+A. Verify at least ONE SW pump running on EACH loop.
+ANY            B. Verify DG SW Outlet valves open.
+ANY            C. Verify SW pump suction aligned to Lake.
+ANY            D. Check 4160v Non-vital bus 2A1 or 2A2 energized from offsite power.
+ANY            E. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.
+BOP            F. Start SW pumps as needed to maintain SW header pressure.
+ANY            G. Check SW to CCW restored.
+ANY            H. Check ACW restored. (Not met, perform contingency)
+BOP            H. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.
+BOP            I. Maintain SW header pressure greater than 85 psig.
+ANY     *9. Verify Safety Injection flow to RCS as follows:
+A. Check total HPSI flow acceptable using 2202.010 Exhibit 2, HPSI Flow Curve.
+B. Check total LPSI flow acceptable using 2202.010 Exhibit 3, LPSI Flow Curve.
+Examiner Note: will not be met see event #7 actions ANY       10. Check RCS pressure greater than 1400 psia. (May not be met, if not met perform contingency)
+Revision 0                                                                         Page 26 of 31
+Appendix D                               Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior ANY       10. Perform the following: (Contingency)
+A. IF RCS pressure less than 1400 psia, THEN perform the following:
+: 1) Verify maximum of ONE RCP running in EACH loop.
+: 2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.
+B. IF NPSH requirements violated OR RCS MTS less than 30&deg;F, THEN perform the following:
+: 1) Stop ALL RCPs.
+: 2) Verify BOTH PZR Spray valves in MANUAL and closed.
+ANY       11. Check IA pressure greater than 65 psig.
+ANY     *13. Minimize primary to secondary break flow as follows:
+A. Check ANY RCP running.
+B. Maintain RCS pressure within the following criteria:
+* Within 100 psia above minimum RCP NPSH requirement, refer to 2202.010 Attachment 1, P-T Limits.
+* Less than 1000 psia as conditions allow.
+* Within 50 psi of ruptured SG pressure as RCP NPSH requirements allow.
+Examiners Note: The criteria to minimize break flow can not be established until HPSI is overridden. Then the crew should establish these limits.
+ANY            C. Use EITHER of the following to depressurize RCS:
+: 1) 2202.010 Attachment 27, PZR Spray Operation.
+: 2) IF HPSI termination criteria met, THEN cycle Charging pumps or throttle HPSI flow to lower PZR pressure.
+Revision 0                                                                         Page 27 of 31
+Appendix D                               Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior ANY            D. IF RCS pressure less than ruptured SG pressure, THEN sample RCS Boron concentration every 30 minutes.
+ANY      14. Determine ruptured SG by comparing ANY of the following:
+A. Secondary Systems Radiation Trend recorder (2RR-1057).
+B. Main Steam Line Radiation Monitors:
+* 2RI-1007
+* 2RI-1057 C. SG Sample Radiation Monitors:
+* 2RITS-5854
+* 2RITS-5864 D. SG Tube Leak N-16 Monitor history trends.
+E. SG levels.
+: 1) Level rising faster in ONE SG with similar FW flow rates and steaming rates in BOTH SGs.
+: 2) Rising SG level with ALL FW isolated.
+F. Steam flow and FW flow prior to Reactor trip.
+G. SG water sample results.
+ANY      Direct the NLOs to perform the following:
+: 15. Minimize secondary contamination by performing BOTH of the following:
+A. Commence isolation of ruptured SG by performing local actions ONLY of 2202.010 Attachment 10, SG Isolation.
+B. 2202.010 Attachment 19, Control of Secondary Contamination.
+Examiner Note: Standard Att. 19 should already be started and may not be communicated again to NLOs.
+Cue: If contacted as the AO, then report after 5 min that the local portions of Attachment 10 for A S/G are complete.
+Revision 0                                                                         Page 28 of 31
+Appendix D                               Scenario 2                                       Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time         Position                          Applicant's Actions or Behavior ANY     16. Isolate ruptured SG Steam Supply to EFW pump 2P7A as follows:
+ANY            A. Verify EFW pump 2P7B running.
+B. IF 2P7B NOT running, THEN verify AFW pump 2P75 running.
+ANY            C. Stop EFW pump 2P7A:
+: 1) Override and close Steam Supply to 2P7A valve (2CV-0340-2).
+: 2) Close Main Steam Supply valve from ruptured SG to EFW pump 2P7A:
+                                           *   "SG A TO EMER FW PMP TURB" 2CV-1000-1
+                                           *   "SG B TO EMER FW PMP TURB" 2CV-1050-2 ALL     19. Isolate ruptured SG as follows:
+A. Monitor RCS TH during cooldown with ANY of the following:
+* PMS point T4614
+* PMS point T4714
+* SPDS display B. WHEN RCS TH less than 535&deg;F, THEN isolate ruptured SG using 2202.010 Attachment 10, SG Isolation.
+C. Maintain ruptured SG less than 1050 psia with ONE of the following:
+* MSIV Bypass valve
+* Upstream ADV Revision 0                                                                         Page 29 of 31
+Appendix D                                 Scenario 2                                        Form ES-D-2 Op-Test No.: 2011-1                          Scenario No.: 2                   Event No.: 5 & 6 A Steam Generator tube leakage ramps up to 200 gpm over 5 minutes. Manual reactor trip criteria when greater than 44 gpm.
+Control Element Assembly #35 remains fully withdrawn when the reactor trips. The VCT outlet will not close and the emergency borate valve will not automatically open.
+Time        Position                           Applicant's Actions or Behavior BOP       2. Verify each component in the following table in the indicated position:
+COMPONENT DESCRIPTION              1.0          2.0       3.0 NUMBER       LOCATION  POSITION ADV UPSTRM ISOL                     2CV-1002*    2C02     CLOSED (1) 2CV-1001 PERMISSIVE                 2CV-1001     2C02     OFF    (1)
+MSIV HEADER #1                      2SV-1010-1A  2C17     CLOSED MSIV HEADER #1                      2SV-1010-2A  2C16     CLOSED MSIV HEADER #1 BYP                  2CV-1040-1   2C17     CLOSED (1)
+MAIN STEAM TO EFWP TURB 2K03        2CV-1000-1   2C17     CLOSED CRITICAL                      FEEDWATER BLOCK VALVE TO SG-A       2CV-1024-1   2C17     CLOSED TASK Control                       FEEDWATER BLOCK VALVE TO SG-A       2CV-1023-2   2C16     CLOSED Room actions for                   SG BLOWDOWN ISOLATION               2CV-1016-1   2C17     CLOSED (1) 2202.010 2P7B DISCHARGE TO SG-A              2CV-1038-2*  2C17     CLOSED (1)
+Standard Attachment                    FLOW CONTROL VALVE TO SG-A          2CV-1025-1*  2C17     CLOSED (1) 10 SAMPLE ISOLATION VALVE SG-A         2CV-5850     2C17     CLOSED (1) 2P7A DISCHARGE TO SG-A              2CV-1026-2*  2C16     CLOSED (1) 2P7A DISCHARGE TO SG-A              2CV-1037-1*  2C16     CLOSED (1)
+SAMPLE ISOLATION VALVE STEAM GEN A  2CV-5852-2*  2C16     CLOSED (1)
+* Denotes override capability.
+NOTE #1: Valves may be open at SM/CRS discretion.
+Examiner Note: 2202.010 Attachment 10 local and control room actions must be complete within 30 minutes of entering the Steam Generator Tube Rupture EOP.
+Termination criteria: RCS Cool down to less than 535&deg;F Th and A SG isolated or at the discretion of the lead examiner.
+Revision 0                                                                            Page 30 of 31
+Appendix D                                 Scenario 2                                      Form ES-D-2 Op-Test No.: 2011-1                         Scenario No.: 2                    Event No.: 7 Event
 == Description:==
-CV-5017-1, 2CV-5015-1 Low pressure safety injection (LPSI) and High pressuresafety injection valves (HPSI) fail to open and the "B" HPSI pump trips due to motor overload.TimePositionApplicant's Actions or BehaviorANYReport that 2P-89B High pressure safety injection pump has tripped.ANYDispatchNLO to investigate 2P-89B breaker for overcurrent drop flagsand to investigate 2P-89B locallyCue:If asked, report that the over current relays for 2P-89B High Pressure Safety Injectionpump are dropped.Cue:If asked, report that 2P-89B High Pressure Safety Injection pump looks normal locally.ANYReport that 2CV-5017-1, and 2CV-5015-1 did not open during SIAS SRODirect BOP to place 2CV-5017-1 and 2CV-5015-1 in their actuatedpositionsExaminer Note:  The SRO may direct the BOP to use StandardAttachment's Exhibit 2 or Standard Attachment's Exhibit 9 to verifyactuated components. Both exhibits are directed from 2202.004 SteamGenerator Tube rupture.
+CV-5017-1, 2CV-5015-1 Low pressure safety injection (LPSI) and High pressure safety injection valves (HPSI) fail to open and the B HPSI pump trips due to motor overload.
-CRITICAL TASK BOPOpen 2CV-5017-1 and 2CV-5015-1 to establish minimum design safetyinjection flow.Examiner Note:  2CV-5015-1 HPSI valve must be opened prior toreaching 10&#xba;F Margin to Saturation.Examiner Note: The SRO may discuss Tech Spec 3.5.2 or 3.5.3 due to failure of 2P-89B, 2CV-5015-1, and 2CV-5017-1.Termination criteria:  When 2CV-5015-1 HPSI valve has been fully opened or at examiner'sdiscretion.
+Time          Position                          Applicant's Actions or Behavior ANY       Report that 2P-89B High pressure safety injection pump has tripped.
-Appendix D Scenario 3Form ES-D-1Revision 1Page 1 of 3Facility: ANO-2Scenario No.:  3 (New)Op-Test No.:  2011-1Examiners:Operators:Initial Conditions:60% MOL, All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure ControlValve 2PCV-0231 jacked closed. RED Train Maintenance Week.Turnover:  60% power for repair of 2P-1B Feedwater pump. 250 EFPD. EOOS indicates 'Minimal Risk'.Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed, manually control seal steampressure. RED Train Maintenance Week. 'B' Main Feedwater pump PMT is complete and is idling foroxygen control. Evolution scheduled:  Place 'B' Main Feedwater pump in service and raise power to100%. Step 10.1 of 2106.007, Main Feedwater pump and FWCS operation, for placing the 'B' MainFeedwater pump in service is complete. Commence power escalation using applicable 2104.002 steps9.1 through 9.11 are complete and steps 9.13 to 9.18 and 9.20 to 9.29 are not applicable or complete withthe exception of placing 'B' Main feedwater pump in service (step 9.25).(provide markup copy ofPower OPS procedure 2104.002 Section 9)EventNo.Malf. No.EventType*EventDescription 1 N (BOP)N (SRO)Place 'B' MFWP in service.
+ANY       Dispatch NLO to investigate 2P-89B breaker for overcurrent drop flags and to investigate 2P-89B locally Cue: If asked, report that the over current relays for 2P-89B High Pressure Safety Injection pump are dropped.
-R (ATC)N (SRO)Power Ascension.
+Cue: If asked, report that 2P-89B High Pressure Safety Injection pump looks normal locally.
-XRC2TE46111 I (BOP)I (SRO)Tc temperature transmitter fails high. Tech Spec forSRO.4CVC4817DEMI (ATC)I (SRO)Letdown Hand Indicating Controller (HIC) demandfails high causing low pressurizer level.
+ANY       Report that 2CV-5017-1, and 2CV-5015-1 did not open during SIAS SRO       Direct BOP to place 2CV-5017-1 and 2CV-5015-1 in their actuated positions Examiner Note: The SRO may direct the BOP to use Standard Attachments Exhibit 2 or Standard Attachments Exhibit 9 to verify actuated components. Both exhibits are directed from 2202.004 Steam Generator Tube rupture.
-XRCCHBPLVLI (ATC)I (SRO)Channel 'B' Pressurizer level channel fails low. TechSpec for SRO.
+CRITICAL           BOP      Open 2CV-5017-1 and 2CV-5015-1 to establish minimum design safety TASK                        injection flow.
-EHSYSLEAKM (ALL)Leak in the Electro Hydraulic system causing a turbinetrip, reactor trip and a loss of main feedwater pumps.
+Examiner Note: 2CV-5015-1 HPSI valve must be opened prior to reaching 10&#xba;F Margin to Saturation.
-XMSHDRPRS I (BOP)I(SRO)SDBCS input fails low after the Reactor trip.
+Examiner Note: The SRO may discuss Tech Spec 3.5.2 or 3.5.3 due to failure of 2P-89B, 2CV-5015-1, and 2CV-5017-1.
-CV0332EFW2P7BFLTC (BOP)C (SRO)2P-7A Emergency Feedwater pump overspeed trips onstart and 2P-7B motor trips due to a winding failure.*   (N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajorTotal malfunctions. = 6, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 1,EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 2.
+Termination criteria: When 2CV-5015-1 HPSI valve has been fully opened or at examiners discretion.
-Appendix D Scenario 3Form ES-D-1Revision 1Page 2 of 3Scenario #3 Objectives 1)Evaluate individual ability to place a Main Feedwater pump in service.
+Revision 0                                                                          Page 31 of 31
-)Evaluate individual ability to perform a power escalation.
-)Evaluate individual response to a RCS temperature instrument failure.
+Appendix D                                   Scenario 3                                            Form ES-D-1 Facility: ANO-2                            Scenario No.: 3 (New)                      Op-Test No.: 2011-1 Examiners:                                                Operators:
-)Evaluate individual response to a failure of a Hand indicating controller failure.
+Initial Conditions:
-)Evaluate individual response to a failure of a Pressurizer level control channel.
+% MOL, All Engineered Safety Features systems are in standby. Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed. RED Train Maintenance Week.
-)Evaluate individual response to an Electro Hydraulic system leak.
+Turnover: 60% power for repair of 2P-1B Feedwater pump. 250 EFPD. EOOS indicates Minimal Risk.
-)Evaluate individual response to a failure of the Steam Dump Bypass control system to functionin automatic.
+Gland Seal Steam Pressure Control Valve 2PCV-0231 jacked closed, manually control seal steam pressure. RED Train Maintenance Week. B Main Feedwater pump PMT is complete and is idling for oxygen control. Evolution scheduled: Place B Main Feedwater pump in service and raise power to 100%. Step 10.1 of 2106.007, Main Feedwater pump and FWCS operation, for placing the B Main Feedwater pump in service is complete. Commence power escalation using applicable 2104.002 steps 9.1 through 9.11 are complete and steps 9.13 to 9.18 and 9.20 to 9.29 are not applicable or complete with the exception of placing B Main feedwater pump in service (step 9.25). (provide markup copy of Power OPS procedure 2104.002 Section 9)
-)Evaluate individual ability to mitigate a Loss of Feedwater event.
+Event           Malf. No.           Event                                       Event No.                                Type*                                    Description 1                                N (BOP)         Place B MFWP in service.
-)Evaluate individual ability to monitor operation of Engineered Safety Features equipment.
+N (SRO) 2                                R (ATC)         Power Ascension.
-SCENARIO #3 NARRATIVESimulator session begins with the plant at 60% power steady state Gland Seal Regulator, 2PCV-0231 is jacked closed.When the crew has completed their control room walk down and brief, The BOP will place the 2P-1B feedwater pump in service. Also, while the BOP is placing 2P-1B feedwater pump in servicethe ATC will raise reactor power using RCS dilution.After the BOP has placed the 'B' feedwater pump in service and the ATC has completed therequired reactivity manipulation and cued by lead examiner, 2TE-4611-1(2TI-4605-1) RCStemperature transmitter will fail high. The ATC/BOP will announce Trip and Pretrip alarms on 'A'PPS channel. The SRO will refer to the ACA for RPS Pretrip-Trip alarms and TechnicalSpecifications. Then the SRO will direct that points on 'A' channel PPS for LPD, and DNBR mustbe bypassed in 1 hour as required by Tech Specs.After the 'A' channel PPS points have been bypassed and cued by lead examiner, the demand onthe Letdown Hand Indicating controller (HIC) will ramp to 100%. This will result in letdown goingto maximum flow. The elevated letdown flow will cause pressurizer level to lower and the volumecontrol tank level to trend up until the automatic setpoint is reached to divert the excess letdownflow to the online holdup tank. Eventually, a backup charging pump will start based on lowpressurizer level causing the low oil pressure alarm to come in and then clear. The ATC and SROshould diagnose that the letdown controller demand does not match the demand from thepressurizer level controller. The ATC will take the letdown flow controller to manual and controlPZR level.After letdown has been placed in manual and pressurizer level is being restored to set point bymanual control and cued by the lead examiner, the 'B' channel pressurizer level instrument will faillow. This will cause the backup charging pumps to automatically start and will de-energize allpressurizer heaters. AOP 2203.028, PZR Systems Malfunctions, will be entered and actionsdirected by the SRO. The ATC will verify that the other level control channel is reading correctlyand select that channel for control and place the PZR low level cutoff switch to the unaffectedchannel. The ATC will also restore the pressurizer proportional heaters to service. The SRO willenter Tech Spec 3.3.3.5 Remote Shutdown instrumentation and 3.3.3.6 Post AccidentInstrumentation.
+N (SRO) 3      XRC2TE46111               I (BOP)         Tc temperature transmitter fails high. Tech Spec for I (SRO)         SRO.
-Appendix D Scenario 3Form ES-D-1Revision 1Page 3 of 3SCENARIO #3 NARRATIVE (continued)After the ATC has placed 'A' Channel pressurizer level control in service and restored pressurizerproportional heaters, an EH leak will start down stream of isolation valve 2EH-1A (on EH PumpSkid) on the common header. EH pressure will degrade to ~1300 psig over the next 3 minutes.Annunciator 2K02-A9, LOW EH Pressure, will alarm and the standby EH pump will automaticallystart. EH pressure will rise and then lower again as the leak degrades. Annunciator 2K02-C10, EHTank Low Level will alarm about 5 minutes after the start of the malfunction. The Main TurbineGenerator will automatically trip at 1100 psig EH pressure. The Main Feed Pumps willautomatically trip at 400 psig EH pressure. The crew will secure the EH pumps and the CRS willenter SPTA's.The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactortrips, the input to the Steam Dump Bypass Control System (SDBCS) will fail low. This will causethe SDBCS valves to have no demand and remain closed. The crew should take manual control ofthe SDBCS valves to control S/G pressure. 2P-7B Emergency Feedwater pump will trip when itstarts due to a motor fault. During SPTAs, 2P-7A will overspeed trip due to an oil leak. The ATCwill secure two Reactor Coolant Pumps (RCP) during SPTAs based on no available feedwater andthe BOP will close the Steam Generator blowdown valves. If the SRO directs all RCPs securedduring SPTAs, the ATC will align for Auxiliary spray to control RCS pressure.The SRO will diagnose Loss of Feedwater due no feedwater feeding the Steam Generators andenter OP 2202.006, Loss of Feedwater.The crew will secure all RCPs if not secured during SPTAs. The ATC will align for Auxiliaryspray to control RCS pressure if not aligned during SPTAs.
+      CVC4817DEM                I (ATC)         Letdown Hand Indicating Controller (HIC) demand I (SRO)         fails high causing low pressurizer level.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 1 of 22Simulator Instructions for Scenario 3Reset simulator to MOL 60% power IC steady state.Ensure that AACG is secured and annunciators clear.Place MINIMAL RISK and RED Train Maintenance Week signs on 2C11.Swing ESF equipment aligned to the RED train.'A' CCP lead charging pump. 'C' CCP aligned to green train.2PCV-0231, Gland Sealing Steam Pressure Control Valve failed closed.'B' Channel Pressurizer level and pressure in service.'B' MFWP recirc valve is throttled open maintaining 1 gpm/1 rpmT1, T2, T3, T4, T5, & T6 set to false.T5 = Reactor trip.T6 = EFAS-1EventNo.Malf. No.Value/RampTimeEventDescription 1Place 'B' MFWP in service.
+      XRCCHBPLVL                I (ATC)         Channel B Pressurizer level channel fails low. Tech I (SRO)         Spec for SRO.
-Power Ascension.
+      EHSYSLEAK                 M (ALL)         Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps.
-XRC2TE46111Trigger = T1 616Tc temperature transmitter fails high. Tech Spec forSRO.4CVC4817DEMTrigger = T2 1003 min.Letdown Hand Indicating Controller (HIC) demand failshigh causing low pressurizer level.
+      XMSHDRPRS                 I (BOP)         SDBCS input fails low after the Reactor trip.
-XRCCHBPLVLTrigger = T3 0Channel 'B' Pressurizer level channel fails low. TechSpec for SRO.
+I(SRO) 8      CV0332                    C (BOP)         2P-7A Emergency Feedwater pump overspeed trips on EFW2P7BFLT                C (SRO)         start and 2P-7B motor trips due to a winding failure.
-EHSYSLEAKTrigger = T4 TrueLeak in the Electro Hydraulic system causing a turbinetrip, reactor trip and a loss of main feedwater pumps.
+ * (N)ormal,      (R)eactivity,   (I)nstrument,    (C)omponent,       (M)ajor Total malfunctions. = 6, Malfunctions after EOP entry = 2, Abnormal events = 3, Major transient = 1, EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 2.
-XMSHDRPRSTrigger = T5 650SDBCS input fails low after the Reactor trip.
+Revision 1                                                                                   Page 1 of 3
-CV0332EFW2P7BFLTTrigger = T60 / Delay= 3 min.True /Delay =1 min.2P-7A Emergency Feedwater pump overspeed trips onstart and 2P-7B motor trips due to a winding failure.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 2 of 22Simulator Operator CUEsAt T=0Place 'B' MFWP in service.Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump pre-start checks aresatisfactory.Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump is running sat.Cued byleadexaminerTrigger T1Tc temperature transmitter fails high. Tech Spec for SRO.Cue: When contacted as the WWM, then report that I&C is developing a work package totroubleshoot the failed temperature transmitter.Cued byleadexaminerTrigger T2Letdown Hand Indicating Controller (HIC) demand fails high causinglow pressurizer level.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed controller.Cued byleadexaminerTrigger T3Control Channel "B" Pressurizer Level fails Low.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed level instrument.Cued byleadexaminerTrigger T4Leak in the Electro Hydraulic system causing a turbine trip, reactor tripand a loss of main feedwater pumps.Cue: When contacted by CRS, report that EH fluid is spraying into EH pit area from a break onthe common EH discharge header down stream of isolation valve 2EH-1A and is a large leak.Reactor Trip Trigger T5SDBCS input fails low after the Reactor trip.EFAS-1Trigger T62P-7A Emergency Feedwater pump overspeed trips on start and 2P-7Bmotor trips due to a winding failure.Cue: If contacted as the WCO, then report after 2 min. that 2P-7A can not be reset due to a bentlinkage and a loss of all governor control oil.Cue: If contacted as the AO, then report that 2P-7B breaker has over current flags dropped on thebreaker relays.Cue: If contacted as the WCO, then report that 2P-7B motor has black residue coming from all themotor vents but there is no fire or significant smoke present.Cue: If contacted as NLO, report pre-start checks are sat for 2P-75 AFW pump and after the 2P-75is started report post start checks are sat.Cue: When contacted as the AO, wait approximately 4 min, then contact the Control Room andreport that the breakers for the LTOP relief isolation valves are closed.  (Simulator booth operatorshould close the breakers prior to calling the Control Room by using remote functions under RCS.)
+Appendix D                              Scenario 3                                      Form ES-D-1 Scenario #3 Objectives
-Appendix D Scenario 3Form ES-D-2Revision 1Page 3 of 22Op-Test No.:  2011-1                                 Scenario No.:  3                                   Event No.:   1Event
+: 1)  Evaluate individual ability to place a Main Feedwater pump in service.
+: 2)  Evaluate individual ability to perform a power escalation.
+: 3)  Evaluate individual response to a RCS temperature instrument failure.
+: 4)  Evaluate individual response to a failure of a Hand indicating controller failure.
+: 5)  Evaluate individual response to a failure of a Pressurizer level control channel.
+: 6)  Evaluate individual response to an Electro Hydraulic system leak.
+: 7)  Evaluate individual response to a failure of the Steam Dump Bypass control system to function in automatic.
+: 8) Evaluate individual ability to mitigate a Loss of Feedwater event.
+: 9) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.
+SCENARIO #3 NARRATIVE Simulator session begins with the plant at 60% power steady state Gland Seal Regulator, 2PCV-0231 is jacked closed.
+When the crew has completed their control room walk down and brief, The BOP will place the 2P-1B feedwater pump in service. Also, while the BOP is placing 2P-1B feedwater pump in service the ATC will raise reactor power using RCS dilution.
+After the BOP has placed the B feedwater pump in service and the ATC has completed the required reactivity manipulation and cued by lead examiner, 2TE-4611-1(2TI-4605-1) RCS temperature transmitter will fail high. The ATC/BOP will announce Trip and Pretrip alarms on A PPS channel. The SRO will refer to the ACA for RPS Pretrip-Trip alarms and Technical Specifications. Then the SRO will direct that points on A channel PPS for LPD, and DNBR must be bypassed in 1 hour as required by Tech Specs.
+After the A channel PPS points have been bypassed and cued by lead examiner, the demand on the Letdown Hand Indicating controller (HIC) will ramp to 100%. This will result in letdown going to maximum flow. The elevated letdown flow will cause pressurizer level to lower and the volume control tank level to trend up until the automatic setpoint is reached to divert the excess letdown flow to the online holdup tank. Eventually, a backup charging pump will start based on low pressurizer level causing the low oil pressure alarm to come in and then clear. The ATC and SRO should diagnose that the letdown controller demand does not match the demand from the pressurizer level controller. The ATC will take the letdown flow controller to manual and control PZR level.
+After letdown has been placed in manual and pressurizer level is being restored to set point by manual control and cued by the lead examiner, the B channel pressurizer level instrument will fail low. This will cause the backup charging pumps to automatically start and will de-energize all pressurizer heaters. AOP 2203.028, PZR Systems Malfunctions, will be entered and actions directed by the SRO. The ATC will verify that the other level control channel is reading correctly and select that channel for control and place the PZR low level cutoff switch to the unaffected channel. The ATC will also restore the pressurizer proportional heaters to service. The SRO will enter Tech Spec 3.3.3.5 Remote Shutdown instrumentation and 3.3.3.6 Post Accident Instrumentation.
+Revision 1                                                                         Page 2 of 3
+Appendix D                             Scenario 3                                   Form ES-D-1 SCENARIO #3 NARRATIVE (continued)
+After the ATC has placed A Channel pressurizer level control in service and restored pressurizer proportional heaters, an EH leak will start down stream of isolation valve 2EH-1A (on EH Pump Skid) on the common header. EH pressure will degrade to ~1300 psig over the next 3 minutes.
+Annunciator 2K02-A9, LOW EH Pressure, will alarm and the standby EH pump will automatically start. EH pressure will rise and then lower again as the leak degrades. Annunciator 2K02-C10, EH Tank Low Level will alarm about 5 minutes after the start of the malfunction. The Main Turbine Generator will automatically trip at 1100 psig EH pressure. The Main Feed Pumps will automatically trip at 400 psig EH pressure. The crew will secure the EH pumps and the CRS will enter SPTAs.
+The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactor trips, the input to the Steam Dump Bypass Control System (SDBCS) will fail low. This will cause the SDBCS valves to have no demand and remain closed. The crew should take manual control of the SDBCS valves to control S/G pressure. 2P-7B Emergency Feedwater pump will trip when it starts due to a motor fault. During SPTAs, 2P-7A will overspeed trip due to an oil leak. The ATC will secure two Reactor Coolant Pumps (RCP) during SPTAs based on no available feedwater and the BOP will close the Steam Generator blowdown valves. If the SRO directs all RCPs secured during SPTAs, the ATC will align for Auxiliary spray to control RCS pressure.
+The SRO will diagnose Loss of Feedwater due no feedwater feeding the Steam Generators and enter OP 2202.006, Loss of Feedwater.
+The crew will secure all RCPs if not secured during SPTAs. The ATC will align for Auxiliary spray to control RCS pressure if not aligned during SPTAs.
+Revision 1                                                                     Page 3 of 3
+Appendix D                                Scenario 3                                          Form ES-D-2 Simulator Instructions for Scenario 3 Reset simulator to MOL 60% power IC steady state.
+Ensure that AACG is secured and annunciators clear.
+Place MINIMAL RISK and RED Train Maintenance Week signs on 2C11.
+Swing ESF equipment aligned to the RED train.
+A CCP lead charging pump. C CCP aligned to green train.
+PCV-0231, Gland Sealing Steam Pressure Control Valve failed closed.
+B Channel Pressurizer level and pressure in service.
+B MFWP recirc valve is throttled open maintaining 1 gpm/1 rpm T1, T2, T3, T4, T5, & T6 set to false.
+T5 = Reactor trip.
+T6 = EFAS-1 Event          Malf. No.        Value/                                   Event No.                            Ramp                                  Description Time 1                                         Place B MFWP in service.
+                                         Power Ascension.
+      XRC2TE46111              616      Tc temperature transmitter fails high. Tech Spec for Trigger = T1                      SRO.
+       CVC4817DEM               100      Letdown Hand Indicating Controller (HIC) demand fails Trigger = T2            3 min. high causing low pressurizer level.
+       XRCCHBPLVL                 0      Channel B Pressurizer level channel fails low. Tech Trigger = T3                      Spec for SRO.
+       EHSYSLEAK                True     Leak in the Electro Hydraulic system causing a turbine Trigger = T4                      trip, reactor trip and a loss of main feedwater pumps.
+       XMSHDRPRS                650      SDBCS input fails low after the Reactor trip.
+Trigger = T5 8       CV0332                0 / Delay   2P-7A Emergency Feedwater pump overspeed trips on
+                                   = 3 min. start and 2P-7B motor trips due to a winding failure.
+EFW2P7BFLT              True /
+Delay =
+Trigger = T6            1 min.
+Revision 1                                                                              Page 1 of 22
+Appendix D                               Scenario 3                                        Form ES-D-2 Simulator Operator CUEs At T=0                            Place B MFWP in service.
+Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump pre-start checks are satisfactory.
+Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump is running sat.
+Cued by          Trigger T1       Tc temperature transmitter fails high. Tech Spec for SRO.
+lead examiner Cue: When contacted as the WWM, then report that I&C is developing a work package to troubleshoot the failed temperature transmitter.
+Cued by          Trigger T2       Letdown Hand Indicating Controller (HIC) demand fails high causing lead                              low pressurizer level.
+examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed controller.
+Cued by          Trigger T3       Control Channel B Pressurizer Level fails Low.
+lead examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.
+Cued by          Trigger T4       Leak in the Electro Hydraulic system causing a turbine trip, reactor trip lead                              and a loss of main feedwater pumps.
+examiner Cue: When contacted by CRS, report that EH fluid is spraying into EH pit area from a break on the common EH discharge header down stream of isolation valve 2EH-1A and is a large leak.
+Reactor Trip Trigger T5           SDBCS input fails low after the Reactor trip.
+EFAS-1           Trigger T6       2P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.
+Cue: If contacted as the WCO, then report after 2 min. that 2P-7A can not be reset due to a bent linkage and a loss of all governor control oil.
+Cue: If contacted as the AO, then report that 2P-7B breaker has over current flags dropped on the breaker relays.
+Cue: If contacted as the WCO, then report that 2P-7B motor has black residue coming from all the motor vents but there is no fire or significant smoke present.
+Cue: If contacted as NLO, report pre-start checks are sat for 2P-75 AFW pump and after the 2P-75 is started report post start checks are sat.
+Cue: When contacted as the AO, wait approximately 4 min, then contact the Control Room and report that the breakers for the LTOP relief isolation valves are closed. (Simulator booth operator should close the breakers prior to calling the Control Room by using remote functions under RCS.)
+Revision 1                                                                          Page 2 of 22
+Appendix D                               Scenario 3                                           Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 3                          Event No.: 1 Event
 == Description:==
-Place 'B' MFWP in service.TimePositionApplicant's Actions or BehaviorT = 0 SRODirect the BOP to place 'B' Main Feedwater pump in service.Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump pre-start checks aresatisfactory.
+Place B MFWP in service.
-BOP*10.2 Verify Condensate header pressure 650 to 750 psig.
+Time        Position                           Applicant's Actions or Behavior T=0              SRO       Direct the BOP to place B Main Feedwater pump in service.
-BOP10.3 Verify S/G levels and flows stable enough to place second MFWPon line.BOP*10.4 Verify selected MFWP flow maintained ~ 1 gal/1 rpm at all times.Examiner Note:  The BOP may elect to initially throttle open theMain feedwater pump recirc to >3000 gpm because the feedwaterpump should start feeding the steam generators at about 3000 RPM.
+Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump pre-start checks are satisfactory.
-BOP10.5 Slowly raise oncoming pump speed until pump speed controllerdemand matches Speed tracking Demand for respective FWCS.WHEN automatic operation desired,THEN place speed controller for this pump in Automatic.
+BOP       *10.2 Verify Condensate header pressure 650 to 750 psig.
-BOP10.6 WHEN flow and S/G levels stabilized,THEN bump selected MFWP Recirc closed while performing thefollowing:10.6.1 Between bumps allow flows and S/G levels to stabilize.10.6.2 Continue bumping selected MFWP Recirc until closed.
+BOP       10.3     Verify S/G levels and flows stable enough to place second MFWP on line.
-BOP10.7 Adjust MFWP/CNDP Recirc Auto Close setpoint for both MFWPrecirc valve controllers (pg 3 of controller) to ~ 850 psig: 2FIC-0742 2FIC-0735 BOP10.8 Place HIC for affected MFWP Recircs in AUTO as desired.Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump is running sat.Termination criteria:  When 2P-1B speed controller placed in automatic or at lead examiner'sdiscretion.
+BOP       *10.4 Verify selected MFWP flow maintained ~ 1 gal/1 rpm at all times.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 4 of 22Op-Test No.:  2011-1                                 Scenario No.:  3                                   Event No.:   2Event
+Examiner Note: The BOP may elect to initially throttle open the Main feedwater pump recirc to >3000 gpm because the feedwater pump should start feeding the steam generators at about 3000 RPM.
+BOP       10.5 Slowly raise oncoming pump speed until pump speed controller demand matches Speed tracking Demand for respective FWCS.
+WHEN automatic operation desired, THEN place speed controller for this pump in Automatic.
+BOP       10.6     WHEN flow and S/G levels stabilized, THEN bump selected MFWP Recirc closed while performing the following:
+.6.1 Between bumps allow flows and S/G levels to stabilize.
+.6.2 Continue bumping selected MFWP Recirc until closed.
+BOP       10.7     Adjust MFWP/CNDP Recirc Auto Close setpoint for both MFWP recirc valve controllers (pg 3 of controller) to ~ 850 psig:
+FIC-0742 2FIC-0735 BOP       10.8     Place HIC for affected MFWP Recircs in AUTO as desired.
+Cue: When contacted as the NLO, then report 2P-1B Main Feedwater pump is running sat.
+Termination criteria: When 2P-1B speed controller placed in automatic or at lead examiners discretion.
+Revision 1                                                                             Page 3 of 22
+Appendix D                             Scenario 3                                        Form ES-D-2 Op-Test No.: 2011-1                    Scenario No.: 3                        Event No.: 2 Event
 == Description:==
-Power Ascension.TimePositionApplicant's Actions or Behavior SRODirect BOP to perform the following:9.25 WHEN at ~ 40% power,THEN place second MFWP in service using Main FeedwaterPump and FWCS Operations (2106.007).
+Power Ascension.
-SRODirect ATC to commence raising power IAW the reactivity plan and2102.004 Power operations.ATC9.12 IF NOT specified otherwise by Reactor Engineering,THEN commence raising power using Attachment A of thisprocedure forASI Control and power escalation limits:Commence RCS dilution.  [Refer to Chemical Addition (2104.003)]Raise turbine load as necessary to maintain Tref within +/-2&deg;F of program Tave using Exhibit 1, TAVE VS TREF.
+Time        Position                        Applicant's Actions or Behavior SRO      Direct BOP to perform the following:
-Appendix D Scenario 3Form ES-D-2Revision 1Page 5 of 22ATCOP-2104.003, Chemical Addition Exhibit 2 for dilution.
+.25 WHEN at ~ 40% power, THEN place second MFWP in service using Main Feedwater Pump and FWCS Operations (2106.007).
-.0Verify EITHER Reactor Makeup pump (2P-109A OR 2P-109B)running.2.0Verify Mode Select switch (2HS-4928) in DILUTE.
+SRO      Direct ATC to commence raising power IAW the reactivity plan and 2102.004 Power operations.
-.0Verify Reactor Makeup Water Flow controller (2FIC-4927) set upas follows:In MANUAL OR AUTO.Demand set to less than Charging flow.
+ATC      9.12 IF NOT specified otherwise by Reactor Engineering, THEN commence raising power using Attachment A of this procedure for ASI Control and power escalation limits:
-.0Verify VCT Makeup Isol valve (2CV-4941-2) open.
+Commence RCS dilution. [Refer to Chemical Addition (2104.003)]
-.0Operate Reactor Makeup Water Flow Batch controller(2FQIS-4927) as follows:
+Raise turbine load as necessary to maintain Tref within +/-
-.1Depress Red pushbutton.
+&deg;F of program Tave using Exhibit 1, TAVE VS TREF.
-.2Verify 2FQIS-4927 set for desired quantity.
+Revision 1                                                                        Page 4 of 22
-.3Verify 2FIC-4927 indicates desired flow rate.
-.0Monitor the following parameters:RCS TaveAxial Shape IndexReactor power 7.0IF desired to terminate dilution,THEN reset 2FQIS-4927 to zero.
+Appendix D                             Scenario 3                                        Form ES-D-2 ATC       OP-2104.003, Chemical Addition Exhibit 2 for dilution.
-.0WHEN 2FQIS-4927 at zero,THEN verify the following:RMW Flow Control valve (2CV-4927) closes.No flow indicated on 2FIC-4927.
+.0     Verify EITHER Reactor Makeup pump (2P-109A OR 2P-109B) running.
-.0Repeat steps 5.0 through 8.0 as required.10.0 Close 2CV-4941-2.11.0 Verify 2FQIS-4927 Batch Volume placard updated to currentbatch volume.ANYDirect a NLO to perform the following:* 9.19 Perform the following:Monitor secondary chemistry during power escalationAdjust chemical feed as necessary using Secondary System                 Chemical Addition (2106.028).Termination criteria: When the required reactivity manipulation is complete or at leadexaminer's discretion.
+.0     Verify Mode Select switch (2HS-4928) in DILUTE.
-* Appendix D Scenario 3Form ES-D-2Revision 1Page 6 of 22Op-Test No.:  1                                 Scenario No.:  3                                   Event No.:   3Event
+.0     Verify Reactor Makeup Water Flow controller (2FIC-4927) set up as follows:
+In MANUAL OR AUTO.
+Demand set to less than Charging flow.
+.0     Verify VCT Makeup Isol valve (2CV-4941-2) open.
+.0     Operate Reactor Makeup Water Flow Batch controller (2FQIS-4927) as follows:
+.1     Depress Red pushbutton.
+.2     Verify 2FQIS-4927 set for desired quantity.
+.3     Verify 2FIC-4927 indicates desired flow rate.
+* 6.0     Monitor the following parameters:
+RCS Tave Axial Shape Index Reactor power 7.0     IF desired to terminate dilution, THEN reset 2FQIS-4927 to zero.
+.0     WHEN 2FQIS-4927 at zero, THEN verify the following:
+RMW Flow Control valve (2CV-4927) closes.
+No flow indicated on 2FIC-4927.
+.0     Repeat steps 5.0 through 8.0 as required.
+.0    Close 2CV-4941-2.
+.0    Verify 2FQIS-4927 Batch Volume placard updated to current batch volume.
+ANY       Direct a NLO to perform the following:
+* 9.19 Perform the following:
+Monitor secondary chemistry during power escalation Adjust chemical feed as necessary using Secondary System Chemical Addition (2106.028).
+Termination criteria: When the required reactivity manipulation is complete or at lead examiners discretion.
+Revision 1                                                                       Page 5 of 22
+Appendix D                               Scenario 3                                       Form ES-D-2 Op-Test No.: 1                     Scenario No.: 3                        Event No.: 3 Event
 == Description:==
-Tc temperature transmitter fails high. Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorCued byLeadExaminerANYAnnounce annunciators:2K04-A4 CH A RPS/ESF/PRETRIP/TRIP2K04-B3 PPS Channel TRIP2K04-G4 Channel Sensor FailureANYReport A LPD and DNBR trip on PPS insert.ANYCompare all four channels and report Core delta T power indicates lowand determines that 2TE-4611-1(2TI-4605-1) is failed low.ALLImplement Annunciator Corrective Action 2203.012D.2K04-H4 PPS Channel TRIP applicable actions:
+Tc temperature transmitter fails high. Tech Spec for SRO.
-.1Determine affected channel by checking CPC TROUBLElights on CPC Operator Modules.
+Time         Position                             Applicant's Actions or Behavior Cued by          ANY         Announce annunciators:
-.3Examine PIDs 415, 416, 417, and 418 as necessary todetermine affected CPC Channel and SensorClassification.
+Lead Examiner                     2K04-A4 CH A RPS/ESF/PRETRIP/TRIP 2K04-B3 PPS Channel TRIP 2K04-G4 Channel Sensor Failure ANY         Report A LPD and DNBR trip on PPS insert.
-.4Select CPC Maintenance Page menu and check Option 1,Failed Sensor Status Report and Option 4, CPC SensorStatus Words to determine affected sensor and presentstatus.SROImplement Annunciator Corrective Action 2203.012D.2K04-A4 CH A RPS/ESF/PRETRIP/TRIP applicable actions:
+ANY         Compare all four channels and report Core delta T power indicates low and determines that 2TE-4611-1(2TI-4605-1) is failed low.
-.1Refer to PPS insert on 2C03 to determine cause.
+ALL         Implement Annunciator Corrective Action 2203.012D.
-.2Compare all Channels to validate alarm.
+K04-H4 PPS Channel TRIP applicable actions:
-.6 IF channel failed,THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5,3.3.3.6, and TRM 3.3.1.1.
+.1       Determine affected channel by checking CPC TROUBLE lights on CPC Operator Modules.
-.8 IF a Linear Power, Log Power or CPC Channel isinoperable,THEN refer to 2105.001, CPC/CEAC Operations.
+.3       Examine PIDs 415, 416, 417, and 418 as necessary to determine affected CPC Channel and Sensor Classification.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 7 of 22Op-Test No.:  1                                 Scenario No.:  3                                   Event No.:   3Event
+.4       Select CPC Maintenance Page menu and check Option 1, Failed Sensor Status Report and Option 4, CPC Sensor Status Words to determine affected sensor and present status.
+SRO         Implement Annunciator Corrective Action 2203.012D.
+K04-A4 CH A RPS/ESF/PRETRIP/TRIP applicable actions:
+.1       Refer to PPS insert on 2C03 to determine cause.
+.2       Compare all Channels to validate alarm.
+.6       IF channel failed, THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6, and TRM 3.3.1.1.
+.8       IF a Linear Power, Log Power or CPC Channel is inoperable, THEN refer to 2105.001, CPC/CEAC Operations.
+Revision 1                                                                          Page 6 of 22
+Appendix D                               Scenario 3                                          Form ES-D-2 Op-Test No.: 1                     Scenario No.: 3                         Event No.: 3 Event
 == Description:==
-Tc temperature transmitter fails high. Tech Spec for SRO.TimePositionApplicant's Actions or Behavior SRO2K04-B3 PPS Channel TRIP applicable actions:
+Tc temperature transmitter fails high. Tech Spec for SRO.
-.1Determine which RPS or ESFAS trips have occurred onPPS inserts.
+Time         Position                             Applicant's Actions or Behavior SRO         2K04-B3 PPS Channel TRIP applicable actions:
-.3 IF channel failed,THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM3.3.1.1.SROEnter Tech Spec3.3.1.1 action 2Direct BOP to bypass bistable points for the associated functional units:LPD (Bistable 3)DNBR (Bistable 4)
+.1       Determine which RPS or ESFAS trips have occurred on PPS inserts.
-BOPBypass the point 3, and 4 on Channel 'A' IAW OP-2105.001 CPC/CEACoperations 11.1Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6and TRM 3.3.1.1.
+.3       IF channel failed, THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM 3.3.1.1.
-.2Circle channel and functional units (points) to bebypassed below:Channel to be bypassed:A B C DPoints to be bypassed:1  2  3  4  5  6  7  8  9  10  11  12  13  16  17  18  19  20 11.3Enter appropriate Tech Spec/TRM actions.
+SRO         Enter Tech Spec 3.3.1.1 action 2 Direct BOP to bypass bistable points for the associated functional units:
-.4Verify points to be bypassed NOT bypassed in ANYother channel.
+LPD (Bistable 3)
-.5Place desired points in BYPASS for selected channelon 2C23.
+DNBR (Bistable 4)
-Appendix D Scenario 3Form ES-D-2Revision 1Page 8 of 22Op-Test No.:  1                                 Scenario No.:  3                                   Event No.:   3Event
+BOP         Bypass the point 3, and 4 on Channel A IAW OP-2105.001 CPC/CEAC operations 11.1         Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 and TRM 3.3.1.1.
+.2       Circle channel and functional units (points) to be bypassed below:
+Channel to be bypassed:       A      B       C       D Points to be bypassed:
+2 3 4 5 6 7 8 9 10 11 12 13 16 17 18 19 20 11.3         Enter appropriate Tech Spec/TRM actions.
+.4         Verify points to be bypassed NOT bypassed in ANY other channel.
+.5         Place desired points in BYPASS for selected channel on 2C23.
+Revision 1                                                                            Page 7 of 22
+Appendix D                              Scenario 3                                        Form ES-D-2 Op-Test No.: 1                     Scenario No.: 3                        Event No.: 3 Event
 == Description:==
-Tc temperature transmitter fails high. Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorANYVerify annunciator 2K04-C3 PPS CHANNEL BYPASSEDVerify correct channels in bypass.
+Tc temperature transmitter fails high. Tech Spec for SRO.
-SROContact work management.Cue:  When contacted as the WWM, then report that I & C planner will begin planningwork on failed temperature instrument. Termination Criteria:    Affected channel points placed in bypassor at lead examiner'sdiscretion.
+Time         Position                             Applicant's Actions or Behavior ANY          Verify annunciator 2K04-C3 PPS CHANNEL BYPASSED Verify correct channels in bypass.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 9 of 22Op-Test No.:  2011-1                                 Scenario No.:  3                                   Event No.:   4Event
+SRO          Contact work management.
+Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed temperature instrument.
+Termination Criteria:    Affected channel points placed in bypass or at lead examiner's discretion.
+Revision 1                                                                          Page 8 of 22
+Appendix D                                 Scenario 3                                      Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 3                      Event No.: 4 Event
 == Description:==
-Letdown Hand Indicating Controller (HIC) demand fails high causing lowpressurizer level.TimePositionApplicant's Actions or BehaviorCued byleadexaminerATCDetermine that the letdown flow is elevated causing pressurizer level tolower.SRODirect manual control of letdown.Examiner Note:  The guidance to take manual control of letdown flow is contained in the ACAfor 2K-12 B1 Regen Hx to 2E-29 Temperature HI, 2K-12 C1 Letdown Heat exchangertemperature HI, and 2K-12 F1 Letdown to Purification Filters Flow HI but the letdown alarmsmay not come in this case prior to the crew recognizing the failure.The SRO may elect to use the guidance contained in EN-OP-115 Conduct of Operations whichstates the following.If an automatic control malfunctions, immediately place that control in manual.ANY2.1 Check temperature on 2TI-4820 and Computer Point (T4820).2K-12 B1ATC2.2 IF Letdown Flow Controller (2HIC-4817) NOT controlling in           AUTOMATIC, THEN perform the following per Chemical and           Volume Control (2104.002):2.2.1Place 2HIC-4817 in MANUAL.2.2.2Stabilize flow.ANY2.1 Check temperature on 2TI-4815 and Computer Point (T4805).
+Letdown Hand Indicating Controller (HIC) demand fails high causing low pressurizer level.
-K-12 C1ATC2.2 Verify letdown flow (2FIS-4801) within 10 gpm of charging flow          (2FIS-4863). Refer to Chemical and Volume Control (2104.002).Examiner Note:  The ATC will be required to control letdown inmanual until completion of the drill.ANY2.1 Check flow on 2FIS-4801 and Computer Point (F4801).
+Time        Position                           Applicant's Actions or Behavior Cued by           ATC        Determine that the letdown flow is elevated causing pressurizer level to lead                         lower.
-K-12 F1ATC2.2 IF Letdown Flow Controller (2HIC-4817) NOT controlling in           AUTOMATIC,  THEN perform the following per Chemical and           Volume Control (2104.002):2.2.1Place 2HIC-4817 in MANUAL.2.2.2Reduce flow to < 128 gpm.
+examiner SRO        Direct manual control of letdown.
-SROContact Work Week Manager to repair 2HIC-4817.
+Examiner Note: The guidance to take manual control of letdown flow is contained in the ACA for 2K-12 B1 Regen Hx to 2E-29 Temperature HI, 2K-12 C1 Letdown Heat exchanger temperature HI, and 2K-12 F1 Letdown to Purification Filters Flow HI but the letdown alarms may not come in this case prior to the crew recognizing the failure.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 10 of 22Op-Test No.:  2011-1                                 Scenario No.:  3                                   Event No.:   4Event
+The SRO may elect to use the guidance contained in EN-OP-115 Conduct of Operations which states the following.
+If an automatic control malfunctions, immediately place that control in manual.
+K-12 B1          ANY        2.1     Check temperature on 2TI-4820 and Computer Point (T4820).
+ATC        2.2     IF Letdown Flow Controller (2HIC-4817) NOT controlling in AUTOMATIC, THEN perform the following per Chemical and Volume Control (2104.002):
+.2.1        Place 2HIC-4817 in MANUAL.
+.2.2        Stabilize flow.
+K-12 C1          ANY        2.1     Check temperature on 2TI-4815 and Computer Point (T4805).
+ATC        2.2     Verify letdown flow (2FIS-4801) within 10 gpm of charging flow (2FIS-4863). Refer to Chemical and Volume Control (2104.002).
+Examiner Note: The ATC will be required to control letdown in manual until completion of the drill.
+K-12 F1          ANY        2.1     Check flow on 2FIS-4801 and Computer Point (F4801).
+ATC        2.2     IF Letdown Flow Controller (2HIC-4817) NOT controlling in AUTOMATIC, THEN perform the following per Chemical and Volume Control (2104.002):
+.2.1        Place 2HIC-4817 in MANUAL.
+.2.2        Reduce flow to < 128 gpm.
+SRO        Contact Work Week Manager to repair 2HIC-4817.
+Revision 1                                                                           Page 9 of 22
+Appendix D                               Scenario 3                                       Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 3                      Event No.: 4 Event
 == Description:==
-Letdown Hand Indicating Controller (HIC) demand fails high causing lowpressurizer level.TimePositionApplicant's Actions or Behavior 2K-12 J1ANYRadmonitor Flow Low applicable actions:2.3 Verify letdown flow (2FIS-4801) > 28 gpm. Refer to Chemical and           Volume Control (2104.002).2.4 Verify L/D to Rad Monitor (2CV-4804) open.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed controller. Termination Criteria:  Letdown being controlled in manual or at lead examiner's discretion.
+Letdown Hand Indicating Controller (HIC) demand fails high causing low pressurizer level.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 11 of 22Op-Test No.:  2011-1                                 Scenario No.:  3                                   Event No.:   5Event
+Time        Position                          Applicant's Actions or Behavior 2K-12 J1          ANY        Radmonitor Flow Low applicable actions:
+.3 Verify letdown flow (2FIS-4801) > 28 gpm. Refer to Chemical and Volume Control (2104.002).
+.4    Verify L/D to Rad Monitor (2CV-4804) open.
+Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed controller.
+Termination Criteria: Letdown being controlled in manual or at lead examiner's discretion.
+Revision 1                                                                         Page 10 of 22
+Appendix D                               Scenario 3                                       Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 3                      Event No.: 5 Event
 == Description:==
- 'B' Pressurizer level channel fails Low. Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce alarm 2K10-J6 CNTRL CH 2 LEVEL LO.Report 2LI-4627-1 and 2LR-4625 indicate normal.All charging pumps are running.
+B Pressurizer level channel fails Low. Tech Spec for SRO.
-SROEnter and implement AOP 2203.028, PZR Systems Malfunctions SRO6. Check the following PZR level annunciators clear:"CNTRL CH 1/2 LEVEL LO" 2K10-G6/G7(Annunciators not clear, implementcontingency)"CNTRL CH 1/2 LEVEL HI" 2K10-J6/J7ANY6. Perform the following:A. Compare PZR level instruments to determine the affectedchannel.ATC C. IF selected control channel failed, THEN perform the following:1) Place Letdown Flow controller (2HIC-4817) in MANUAL.Examiner Note: Letdown will already be in manual due to previousfailure but this does not significantly impact the PZR level failurebecause if letdown was in auto it would only lower 12 gpm.ATC2) Place PZR Level Channel Select switch (2HS-4628) tounaffected channel.(Channel 1)ATC 3)Place PZR Low Level Cutoff select switch (2HS-4642) tounaffected channel.(Channel A)ANY 4)Verify PZR heaters and Normal Spray operating to restoreRCS pressure 2025 to 2275 psia.Examiners Note: The ATC should restore the PZR proportionalheater to operation.ATC 5) WHEN Letdown Flow controller (2HIC-4817)automaticAND manual signals match, THEN place Letdown Flowcontroller in AUTO.Examiner Note:  Letdown can not be restored to auto based on theearlier demand failure.
+Time        Position                           Applicant's Actions or Behavior Cued by         ANY         Announce alarm 2K10-J6 CNTRL CH 2 LEVEL LO.
-SROE. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and3.3.3.6, Post-Accident Instrumentation.
+lead                        Report 2LI-4627-1 and 2LR-4625 indicate normal.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 12 of 22Op-Test No.:  2011-1                                 Scenario No.:  3                                   Event No.:   5Event
+examiner All charging pumps are running.
+SRO        Enter and implement AOP 2203.028, PZR Systems Malfunctions SRO        6. Check the following PZR level annunciators clear:
+                                    *   "CNTRL CH 1/2 LEVEL LO" 2K10-G6/G7 (Annunciators not clear, implement contingency)
+                                    *   "CNTRL CH 1/2 LEVEL HI" 2K10-J6/J7 ANY         6. Perform the following:
+A. Compare PZR level instruments to determine the affected channel.
+ATC               C. IF selected control channel failed, THEN perform the following:
+: 1) Place Letdown Flow controller (2HIC-4817) in MANUAL.
+Examiner Note: Letdown will already be in manual due to previous failure but this does not significantly impact the PZR level failure because if letdown was in auto it would only lower 12 gpm.
+ATC                   2) Place PZR Level Channel Select switch (2HS-4628) to unaffected channel. (Channel 1)
+ATC                   3) Place PZR Low Level Cutoff select switch (2HS-4642) to unaffected channel. (Channel A)
+ANY                    4) Verify PZR heaters and Normal Spray operating to restore RCS pressure 2025 to 2275 psia.
+Examiners Note: The ATC should restore the PZR proportional heater to operation.
+ATC                   5) WHEN Letdown Flow controller (2HIC-4817) automatic AND manual signals match, THEN place Letdown Flow controller in AUTO.
+Examiner Note: Letdown can not be restored to auto based on the earlier demand failure.
+SRO               E. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and 3.3.3.6, Post-Accident Instrumentation.
+Revision 1                                                                         Page 11 of 22
+Appendix D                               Scenario 3                                       Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 3                      Event No.: 5 Event
 == Description:==
- 'B' Pressurizer level channel fails Low. Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorExaminer Note:  SRO must enter Tech Spec 3.3.3.5 Remote ShutdownInstrumentation and 3.3.3.6 action 1 for Post AccidentInstrumentation.
+B Pressurizer level channel fails Low. Tech Spec for SRO.
-SROContact work management.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed level instrument. Termination Criteria:  PZR level control selected to channel 1 or at lead examiner's discretion.
+Time         Position                         Applicant's Actions or Behavior Examiner Note: SRO must enter Tech Spec 3.3.3.5 Remote Shutdown Instrumentation and 3.3.3.6 action 1 for Post Accident Instrumentation.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 13 of 22Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+SRO       Contact work management.
+Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.
+Termination Criteria: PZR level control selected to channel 1 or at lead examiner's discretion.
+Revision 1                                                                         Page 12 of 22
+Appendix D                               Scenario 3                                         Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 3                  Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYReport Annunciators 2K02-A9, EH Header Press LO and 2K02-B9, EHPump 2P14A/B Auto Start are in alarm and report that Standby EH Pump2P14B automatically started.
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-SRORefer to ACA for 2K02-A9 and direct appropriate actions.
+Time        Position                           Applicant's Actions or Behavior Cued by         ANY         Report Annunciators 2K02-A9, EH Header Press LO and 2K02-B9, EH lead                        Pump 2P14A/B Auto Start are in alarm and report that Standby EH Pump examiner                    2P14B automatically started.
-BOP 2.1Check EH pressure on 2PI-9650 and Computer point P9650.
+SRO        Refer to ACA for 2K02-A9 and direct appropriate actions.
-BOP 2.2Verify standby EH pump (2P-14A or 2P-14B) started.ANYDirect NLO to investigate locally and perform the following step if it canbe accomplished.2.3 Adjust header pressure to between 1580 and 1620 psig using2106.012, Electrohydraulic Oil System Operation.Cue: When contacted by CRS, report that EH fluid is spraying into EH pit area from a break onthe common EH discharge header down stream of isolation valve 2EH-1A and is a large leak.ANYReport Annunciator 2K02-C10, EH Tank 2T38 Level Hi/LO is in alarm.
+BOP        2.1      Check EH pressure on 2PI-9650 and Computer point P9650.
-SRORefer to ACA for 2K02-C10 and direct appropriate actions.ANYDirect NLOs to perform the following as needed.2.3 IF Low level,THEN perform the following:2.3.1 IF EH pumps are running,THEN immediately add EH to 2T-38 using 2106.012,Electrohydraulic Oil System Operation.2.3.2 Check system for leaks. Refer to Limits and Precautionssection of 2106.012, Electrohydraulic Oil SystemOperation for hazard associated with EH fluid.2.3.3 Station Operator locally to monitor for EH pumpcavitation.2.3.4 IF EH pump cavitating,THEN pump should be secured.
+BOP        2.2      Verify standby EH pump (2P-14A or 2P-14B) started.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 14 of 22Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+ANY         Direct NLO to investigate locally and perform the following step if it can be accomplished.
+.3 Adjust header pressure to between 1580 and 1620 psig using 2106.012, Electrohydraulic Oil System Operation.
+Cue: When contacted by CRS, report that EH fluid is spraying into EH pit area from a break on the common EH discharge header down stream of isolation valve 2EH-1A and is a large leak.
+ANY         Report Annunciator 2K02-C10, EH Tank 2T38 Level Hi/LO is in alarm.
+SRO        Refer to ACA for 2K02-C10 and direct appropriate actions.
+ANY         Direct NLOs to perform the following as needed.
+.3    IF Low level, THEN perform the following:
+.3.1    IF EH pumps are running, THEN immediately add EH to 2T-38 using 2106.012, Electrohydraulic Oil System Operation.
+.3.2    Check system for leaks. Refer to Limits and Precautions section of 2106.012, Electrohydraulic Oil System Operation for hazard associated with EH fluid.
+.3.3    Station Operator locally to monitor for EH pump cavitation.
+.3.4    IF EH pump cavitating, THEN pump should be secured.
+Revision 1                                                                         Page 13 of 22
+Appendix D                               Scenario 3                                          Form ES-D-2 Op-Test No.: 2011-1                         Scenario No.: 3                     Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or Behavior BOPMonitor EH pressure and report that pressure is approaching Main TurbineGenerator (MTG) trip set point and recommend manually tripping theplant.Examiner Note:  The crew should take conservative action and tripthe reactor prior to the Turbine trip. If the Turbine trips the reactorshould trip shortly afterward if not automatically tripped.ANYIf the Turbine automatically trips, then trip the reactor.
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-BOPPlace both EH pump in PTL to stop the EH leak.Cue:  If the crew does not place both EH pumps in PTL then 3 minutes after the reactor trip callas the NLO and report that the running EH pumps are cavitating.ANYReport Reactor Tripped SROEnter and implement EOP 2202.001, Standard Post Trip Actions.
+Time        Position                           Applicant's Actions or Behavior BOP        Monitor EH pressure and report that pressure is approaching Main Turbine Generator (MTG) trip set point and recommend manually tripping the plant.
-SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.
+Examiner Note: The crew should take conservative action and trip the reactor prior to the Turbine trip. If the Turbine trips the reactor should trip shortly afterward if not automatically tripped.
-.Open Safety Function Tracking page.ReactivitycontrolsafetyfunctionATC 3.Check Reactivity Control established as follows:A. Reactor power lowering.B. ALL CEAs fully inserted.
+ANY         If the Turbine automatically trips, then trip the reactor.
-BOPComplete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.
+BOP        Place both EH pump in PTL to stop the EH leak.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 15 of 22
+Cue: If the crew does not place both EH pumps in PTL then 3 minutes after the reactor trip call as the NLO and report that the running EH pumps are cavitating.
-______Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+ANY         Report Reactor Tripped SRO        Enter and implement EOP 2202.001, Standard Post Trip Actions.
+SRO      1.       Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.
+: 2.       Open Safety Function Tracking page.
+ATC      3.       Check Reactivity Control established as follows:
+Reactivity control                            A. Reactor power lowering.
+safety function B. ALL CEAs fully inserted.
+BOP        Complete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.
+Revision 1                                                                            Page 14 of 22
+Appendix D                              Scenario 3                                          Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 3                  Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or BehaviorVitalAuxiliariessafetyfunction BOP 4.Check Maintenance of Vital Auxiliaries satisfied:A. Main Turbine tripped.B. Generator Output breakers open.C. Exciter Field breaker open.D. At least ONE 6900v AC bus energizedE. At least ONE 4160v Non-vital AC bus energized.F. BOTH 4160v Vital AC buses energized.G. BOTH DGs secured.H. At least ONE 125v Vital DC bus energized:2D01 - SPDS point E2D012D02 - SPDS point E2D02 RCSInventoryControlSafetyfunctionATC 5.Check RCS Inventory Control established as follows:A. PZR level:10 to 80%.Trending to setpoint.B. RCS MTS 30&deg;F or greater.Examiner Note:  Letdown will still be in manual and will need to becontrolled by the ATC RCSPressureControlSafetyfunctionATC 6.Check RCS Pressure Control:1800 to 2250 psia.Trending to setpoint
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-.
+Time        Position                          Applicant's Actions or Behavior BOP      4.      Check Maintenance of Vital Auxiliaries satisfied:
-Appendix D Scenario 3Form ES-D-2Revision 1Page 16 of 22Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+A. Main Turbine tripped.
+B. Generator Output breakers open.
+C. Exciter Field breaker open.
+D. At least ONE 6900v AC bus energized Vital Auxiliaries                       E. At least ONE 4160v Non-vital AC bus energized.
+safety function                          F. BOTH 4160v Vital AC buses energized.
+G. BOTH DGs secured.
+H. At least ONE 125v Vital DC bus energized:
+D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC      5.      Check RCS Inventory Control established as follows:
+A. PZR level:
+RCS Inventory                                 10 to 80%.
+Control                                   Trending to setpoint.
+Safety function                          B. RCS MTS 30&deg;F or greater.
+Examiner Note: Letdown will still be in manual and will need to be controlled by the ATC RCS              ATC      6.      Check RCS Pressure Control:
+___
+Pressure
+* 1800 to 2250 psia.
+___
+* Trending to setpoint.
+Control Safety function Revision 1                                                                         Page 15 of 22
+Appendix D                               Scenario 3                                         Form ES-D-2 Op-Test No.: 2011-1                       Scenario No.: 3                   Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or BehaviorCore HeatRemovalsafetyfunction.ATC 7.Check Core Heat Removal by forced circulation:
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-A.At least ONE RCP running.B. CCW flow aligned to RCPs
+Time        Position                          Applicant's Actions or Behavior ATC      7.      Check Core Heat Removal by forced circulation:
-.C. Loop delta T less than 10&deg;F.D. RCS MTS 30&deg;F or greater.E. Check SW aligned to CCW
+A. At least ONE RCP running.
-.F. IF SIAS or MSIS actuated,THEN maintain SW header pressure greater than 85 psig.RCS HeatRemovalSafetyFunction BOP 8.Check RCS Heat Removal:A. Check SG available by BOTH of the following:At least ONE SG level 10 to 90%.FW maintaining SG level.(Should not be met due to lossof EFW and main feed water, perform contingency)B. Check MFW in RTO.(Should not be met due to loss of mainfeed water, perform contingency as necessary)C. Check Feedwater line intact by the following:SG level stable or rising.NO unexplained step changes or erratic FW flow.NO unexplained step changes or erratic Condensate flow.D. Check SG pressure 950 to 1050 psia.(Contingency should beperformed due to SDBCS failure)
+B. CCW flow aligned to RCPs.
-F.Check RCS TC 540 to 555&deg;F.
+Core Heat                         C. Loop delta T less than 10&deg;F.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 17 of 22Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+Removal safety                            D. RCS MTS 30&deg;F or greater.
+function.
+E. Check SW aligned to CCW.
+F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.
+BOP      8.      Check RCS Heat Removal:
+A. Check SG available by BOTH of the following:
+* At least ONE SG level 10 to 90%.
+* FW maintaining SG level. (Should not be met due to loss of EFW and main feed water, perform contingency)
+B. Check MFW in RTO. (Should not be met due to loss of main feed water, perform contingency as necessary)
+RCS Heat Removal                           C. Check Feedwater line intact by the following:
+Safety Function
+* SG level stable or rising.
+* NO unexplained step changes or erratic FW flow.
+* NO unexplained step changes or erratic Condensate flow.
+D. Check SG pressure 950 to 1050 psia. (Contingency should be performed due to SDBCS failure)
+F. Check RCS TC 540 to 555&deg;F.
+Revision 1                                                                         Page 16 of 22
+Appendix D                                Scenario 3                                        Form ES-D-2 Op-Test No.: 2011-1                         Scenario No.: 3                  Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or BehaviorCue: If contacted as the WCO, then report after 2 min. that 2P-7A can not be reset due to a bentlinkage and a loss of all governor control oil.Cue: If contacted as the AO, then report that 2P-7B breaker has over current flags dropped onthe breaker relays.Cue: If contacted as the WCO, then report that 2P-7B motor has black residue coming from allthe motor vents but there is no fire or significant smoke present.RCS HeatRemovalSafetyFunction SRODirect the following actions as necessary:
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-.Check RCS Heat Removal:A. Perform the following:1) IF SG level lowering,THEN verify EFAS actuated.(should be automaticallyactuated previously)2) IF SG level less than 10%,THEN verify total flow greaterthan 485 gpm.(Can not be verified due to Loss ofFeedwater)5) IF FW NOT available,THEN perform the following:
+Time        Position                            Applicant's Actions or Behavior Cue: If contacted as the WCO, then report after 2 min. that 2P-7A can not be reset due to a bent linkage and a loss of all governor control oil.
-a)Verify maximum of ONE RCP running in eachloop.(SRO may elect to secure all RCPs tominimize heat input) b)Close SG Blowdown Isolation valves:2CV-1016-12CV-1066-1 c)GO TO Step 8.C.D. Perform as necessary:2) Verify SDBCS restoringSG pressure 950 to 1050 psia.Examiner Note: Step 5 may not be implemented when the crewassesses RCS heat removal to due to timing of the EFW pumpstripping after the actuation but the SRO should return and completestep 5.
+Cue: If contacted as the AO, then report that 2P-7B breaker has over current flags dropped on the breaker relays.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 18 of 22Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+Cue: If contacted as the WCO, then report that 2P-7B motor has black residue coming from all the motor vents but there is no fire or significant smoke present.
+SRO        Direct the following actions as necessary:
+: 8. Check RCS Heat Removal:
+A. Perform the following:
+: 1)   IF SG level lowering, THEN verify EFAS actuated. (should be automatically actuated previously)
+: 2)  IF SG level less than 10%,
+THEN verify total flow greater than 485 gpm. (Can not be verified due to Loss of Feedwater)
+: 5)  IF FW NOT available, THEN perform the following:
+RCS Heat Removal                                      a)       Verify maximum of ONE RCP running in each Safety                                                loop. (SRO may elect to secure all RCPs to Function                                              minimize heat input) b)       Close SG Blowdown Isolation valves:
+* 2CV-1016-1
+* 2CV-1066-1 c)       GO TO Step 8.C.
+D. Perform as necessary:
+: 2)  Verify SDBCS restoring SG pressure 950 to 1050 psia.
+Examiner Note: Step 5 may not be implemented when the crew assesses RCS heat removal to due to timing of the EFW pumps tripping after the actuation but the SRO should return and complete step 5.
+Revision 1                                                                          Page 17 of 22
+Appendix D                               Scenario 3                                         Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 3                   Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or BehaviorContainmentSafetyFunctionANY 9.Check CNTMT parameters:A. Temperature and Pressure:Temperature less than 140&deg;F.Pressure less than 16 psia.B. Check CNTMT Spray pumps secured.C. NO CNTMT radiation alarms or unexplained rise in activity:1) CAMS alarms:"CNTMT PART/GAS RAD HI/LO" annunciator(2K10-B6) clear.2) RCS leakage alarms:"AREA RADIATION HI/LO" annunciator (2K11-B10)clear."PROC LIQUID RADIATION HI/LO" annunciator(2K11-C10) clear.3) Check the following radiation monitors trend stable:CNTMT AreaMSProcess LiquidD. NO secondary system radiation alarms or unexplained rise inactivity: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.2) Secondary Systems Radiation monitors trend stable:Main Steam linesSG SampleCondenser Off Gas SRO10. Notify STA to report to control room.11. Verify NLOs informed of Reactor trip.12. Verify Reactor trip announced on Plant page.13. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 19 of 22Op-Test No.:  2011-1                                   Scenario No.:  3                            Event No.:   6 & 7Event
+Time        Position                            Applicant's Actions or Behavior ANY       9.      Check CNTMT parameters:
+A. Temperature and Pressure:
+* Temperature less than 140&deg;F.
+* Pressure less than 16 psia.
+B. Check CNTMT Spray pumps secured.
+C. NO CNTMT radiation alarms or unexplained rise in activity:
+: 1) CAMS alarms:
+                                           * "CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.
+: 2) RCS leakage alarms:
+                                           * "AREA RADIATION HI/LO" annunciator (2K11-B10)
+Containment clear.
+Safety                                    * "PROC LIQUID RADIATION HI/LO" annunciator Function                                        (2K11-C10) clear.
+: 3) Check the following radiation monitors trend stable:
+* CNTMT Area
+* CAMS
+* Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:
+: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.
+: 2) Secondary Systems Radiation monitors trend stable:
+* Main Steam lines
+* SG Sample
+* Condenser Off Gas SRO      10. Notify STA to report to control room.
+: 11. Verify NLOs informed of Reactor trip.
+: 12. Verify Reactor trip announced on Plant page.
+: 13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
+Revision 1                                                                          Page 18 of 22
+Appendix D                              Scenario 3                                          Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 3                  Event No.: 6 & 7 Event
 == Description:==
-Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a lossof main feedwater pumps. SDBCS input fails low after the Reactor trip.TimePositionApplicant's Actions or Behavior SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.
+Leak in the Electro Hydraulic system causing a turbine trip, reactor trip and a loss of main feedwater pumps. SDBCS input fails low after the Reactor trip.
-SRO15. Check ALL safety function acceptance criteria satisfied.(All safetyfunctions are not satisfied, perform contingency)15. IF ANY safety function acceptance criteria NOT satisfied,THEN perform the following:A. Notify control room staff ofsafety functions NOT satisfied.B. GO TO Exhibit 8,Diagnostic Actions.
+Time        Position                           Applicant's Actions or Behavior SRO      14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.
-SRODiagnose Loss of Feedwater EOP 2202.006. Termination Criteria:  Feedwater has been restored per event #8or at lead examiner'sdiscretion.
+SRO      15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)
-Appendix D Scenario 3Form ES-D-2Revision 1Page 20 of 22Op-Test No.:  2011-1                                  Scenario No.:  3                                 Event No.:   8Event
+: 15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:
+A. Notify control room staff of safety functions NOT satisfied.
+B. GO TO Exhibit 8, Diagnostic Actions.
+SRO      Diagnose Loss of Feedwater EOP 2202.006.
+Termination Criteria: Feedwater has been restored per event #8or at lead examiner's discretion.
+Revision 1                                                                         Page 19 of 22
+Appendix D                              Scenario 3                                       Form ES-D-2 Op-Test No.: 2011-1                      Scenario No.: 3                      Event No.: 8 Event
 == Description:==
-P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor tripsdue to a winding failure.TimePositionApplicant's Actions or BehaviorCued byleadexaminer SRODirect Actions of 2202.006 Loss of Feedwater.
+P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.
-SRODirect STA to perform the following:* 1. Confirm diagnosis of Loss Of Feedwater by checking SFSCacceptance criteria satisfied every 15 minutes.
+Time        Position                         Applicant's Actions or Behavior Cued by          SRO       Direct Actions of 2202.006 Loss of Feedwater.
-SRO* 2. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.
+lead examiner SRO       Direct STA to perform the following:
-.Open Placekeeping page.
+* 1. Confirm diagnosis of Loss Of Feedwater by checking SFSC acceptance criteria satisfied every 15 minutes.
-.Notify Control Board Operators to monitor floating steps.ATC 5.Reduce RCS heat input as follows:A. Stop ALL RCPs.B. Verify BOTH PZR Spray valves in MANUAL and closed.
+SRO
-BOP 6.Conserve SG inventory as follows:A. Verify SG Blowdown Isolation valves closed:2CV-1016-12CV-1066-1B. Verify SG Sample valves closed.ANY 7. Check ALL AC and Vital DC buses energized.CriticalTaskATC* 8. Maintain RCS pressure 1800 to 2250 psia with the following:PZR heaters.Aux spray using 2202.010 Attachment 27, PZR SprayOperation.Use attachment 27 to maintain RCS pressure within the Pressure-Temperature limits of 200&deg;F and 30&deg;F Margin to Saturation.
+* 2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
-SRODirect a NLO to perform the following:
+: 3. Open Placekeeping page.
-.Locally remove danger tags and close the following breakers:2B51-E4 "LTOP RELIEF ISOL2CV-4730-1"2B51-K2 "LTOP RELIEF ISOL2CV-4741-1" Appendix D Scenario 3Form ES-D-2Revision 1Page 21 of 22Op-Test No.:  2011-1                                  Scenario No.:  3                                 Event No.:   8Event
+: 4. Notify Control Board Operators to monitor floating steps.
+ATC      5. Reduce RCS heat input as follows:
+A. Stop ALL RCPs.
+B. Verify BOTH PZR Spray valves in MANUAL and closed.
+BOP      6. Conserve SG inventory as follows:
+A. Verify SG Blowdown Isolation valves closed:
+* 2CV-1016-1
+* 2CV-1066-1 B. Verify SG Sample valves closed.
+ANY          7. Check ALL AC and Vital DC buses energized.
+Critical         ATC
+* 8. Maintain RCS pressure 1800 to 2250 psia with the following:
+Task
+* PZR heaters.
+* Aux spray using 2202.010 Attachment 27, PZR Spray Operation.
+Use attachment 27 to maintain RCS pressure within the Pressure-Temperature limits of 200&deg;F and 30&deg;F Margin to Saturation.
+SRO        Direct a NLO to perform the following:
+: 9.       Locally remove danger tags and close the following breakers:
+B51-E4 LTOP RELIEF ISOL 2CV-4730-1 2B51-K2 LTOP RELIEF ISOL 2CV-4741-1 Revision 1                                                                        Page 20 of 22
+Appendix D                                Scenario 3                                        Form ES-D-2 Op-Test No.: 2011-1                        Scenario No.: 3                       Event No.: 8 Event
 == Description:==
-P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor tripsdue to a winding failure.TimePositionApplicant's Actions or BehaviorCue: When contacted as the AO, wait approximately 4 min, then contact the Control Room andreport that the breakers for the LTOP relief isolation valves are closed.  (Simulator boothoperator should close the breakers prior to calling the Control Room by using remote functionsunder RCS.)
+P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.
-SRO11. Establish EFW flow to SGs fromEFW pump 2P7B as follows:A. Check 2P7B available.(Not met perform contingency)
+Time         Position                          Applicant's Actions or Behavior Cue: When contacted as the AO, wait approximately 4 min, then contact the Control Room and report that the breakers for the LTOP relief isolation valves are closed. (Simulator booth operator should close the breakers prior to calling the Control Room by using remote functions under RCS.)
-SROA. IF 2P7B NOT available,THEN GO TO Step 12.
+SRO        11. Establish EFW flow to SGs from EFW pump 2P7B as follows:
-SRO12. Establish EFW flow to SGs fromEFW pump 2P7A as follows:Examiner Note: 2P-7A is not available and the SRO will continue onto step 13.
+A. Check 2P7B available. (Not met perform contingency)
-SRO13. Establish AFW flow to SGs from AFW pump 2P75 as follows:ANYA. Check 4160v non-vital bus 2A1 energized.ANYC. Check MSIS AND CSAS reset.
+SRO               A. IF 2P7B NOT available, THEN GO TO Step 12.
-BOPD. Start AFW Lube Oil pump 2P225 AND check 2P225 amberlight OFF.Cue: If contacted as NLO, report pre-start checks are sat for 2P-75 AFW pump and after the 2P-75 is started report post start checks are sat.
+SRO        12. Establish EFW flow to SGs from EFW pump 2P7A as follows:
-BOPE. IF SG level less than 49%,THEN verify following valves closed: 2P75to EFW Train "A" Flow Control Valve (2CV-0761)2P75 to EFW Train "B" Flow Control Valve ( 2CV-0760)
+Examiner Note: 2P-7A is not available and the SRO will continue on to step 13.
-BOPF. Start 2P75.
+SRO        13. Establish AFW flow to SGs from AFW pump 2P75 as follows:
-BOPG. Place AFW Lube Oil Pump 2P225 handswitch 2HS-0766 inOFF, then in AUTO.
+ANY               A. Check 4160v non-vital bus 2A1 energized.
-BOPH. IF a SG level was less than 49%, THEN perform the following:
+ANY               C. Check MSIS AND CSAS reset.
-)Throttle open associated "2P75 to EFW Train Flow ControlValve" to establish flow of less than 150 gpm:"A" EFW - 2CV-0761"B" EFW - 2CV-0760CriticalTaskRestoreFeedwaterusing 2P-75 AFWpump priorto bothS/Gsreaching70 incheswide rangelevel.BOP2) Maintain feed flow to SG less than 150 gpm until level risenoted or feed flow has been maintained for greater than 5minutes.
+BOP               D. Start AFW Lube Oil pump 2P225 AND check 2P225 amber light OFF.
-Appendix D Scenario 3Form ES-D-2Revision 1Page 22 of 22Op-Test No.:  2011-1                                  Scenario No.:  3                                 Event No.:   8Event
+Cue: If contacted as NLO, report pre-start checks are sat for 2P-75 AFW pump and after the 2P-75 is started report post start checks are sat.
+BOP               E. IF SG level less than 49%,
+THEN verify following valves closed:
+P75 to EFW Train A Flow Control Valve (2CV-0761) 2P75 to EFW Train B Flow Control Valve ( 2CV-0760)
+Critical         BOP               F. Start 2P75.
+Task                               G. Place AFW Lube Oil Pump 2P225 handswitch 2HS-0766 in BOP OFF, then in AUTO.
+Restore          BOP               H. IF a SG level was less than 49%,
+Feedwater                              THEN perform the following:
+using 2P-75 AFW                                 1) Throttle open associated 2P75 to EFW Train Flow Control pump prior                                 Valve to establish flow of less than 150 gpm:
+to both                                        A EFW - 2CV-0761 S/Gs reaching                                       B EFW - 2CV-0760 70 inches wide range       BOP                   2) Maintain feed flow to SG less than 150 gpm until level rise level.                                     noted or feed flow has been maintained for greater than 5 minutes.
+Revision 1                                                                           Page 21 of 22
+Appendix D                           Scenario 3                                       Form ES-D-2 Op-Test No.: 2011-1                   Scenario No.: 3                     Event No.: 8 Event
 == Description:==
-P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor tripsdue to a winding failure.TimePositionApplicant's Actions or Behavior BOPI. Restore SG level to 60% using 2202.010 Attachment 46,Establishing EFW Flow.Termination criteria:  Feedwater restored to both S/Gs with level restoring to setpoint or atexaminer's discretion.}}
+P-7A Emergency Feedwater pump overspeed trips on start and 2P-7B motor trips due to a winding failure.
+Time        Position                       Applicant's Actions or Behavior BOP           I. Restore SG level to 60% using 2202.010 Attachment 46, Establishing EFW Flow.
+Termination criteria: Feedwater restored to both S/Gs with level restoring to setpoint or at examiners discretion.
+Revision 1                                                                     Page 22 of 22}}

ML110820680: Difference between revisions

Revision as of 01:47, 13 November 2019

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