ML110820680

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)

Text

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)

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)

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

REFERENCE:

2.1.32APPROVED FOR ADMINISTRATION TO:

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:PLANTSITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:

15MinutesREFERENCE(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.

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.

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:

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."

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."

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

REFERENCE:

2.1.37APPROVED 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__________________________________

DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

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°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.

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°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.

481980 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

(+/- 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.

(+/- 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°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."

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°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."

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. = _______________________°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:

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 (_______________)

( )

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°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)

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 (%)

100F 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

REFERENCE:

2.2.37APPROVED FOR ADMINISTRATION TO:

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.

ANO-2-JPM-NRC-ADMIN-EFWTS Page 2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS

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.

ANO-2-JPM-NRC-ADMIN-EFWTS Page 3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Determine any additional TS for the given plant conditions.

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.

ENDSTOP TIME:

ANO-2-JPM-NRC-ADMIN-EFWTS Page 4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

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_______________

ANO-2-JPM-NRC-ADMIN-EFWTS Page 5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

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: __________________________________________________

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

REFERENCE:

2.3.15APPROVED FOR ADMINISTRATION TO:

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.

ANO-2-JPM-NRC-ADMIN-CRADMON Page 2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM INITIAL TASK CONDITIONS

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.

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:

ANO-2-JPM-NRC-ADMIN-CRADMON Page 4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

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_______________________

ANO-2-JPM-NRC-ADMIN-CRADMON Page 5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

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: ______________________________

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)

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)

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

REFERENCE:

2.1.23APPROVED 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.

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°F instead of 320.038°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°F must be calculated.TASK PERFORMANCE AIDS:1. OP 2105.009 Exhibit 2 (completed)2. Calculator.

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°F (value for 10.9ohms) instead of 320.038°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°F.Calculated the correct CEA 01upper gripper coil temperatureas 506.665°F (acceptancecriteria is 500.050°F). N/A SAT UNSAT ENDSTOP TIME:

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."

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."

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

REFERENCE:

2.1.29APPROVED FOR ADMINISTRATION TO:

RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:CLASSROOM:PerformPOSITION EVALUATED:

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.

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: __________

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.

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

/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.

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

/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

REFERENCE:

2.2.37APPROVED 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): 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.

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM 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 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.

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.

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:

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM 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 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.

ANO-2-JPM-NRC-ADMIN-CREVSTS Page 5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM 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 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:________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

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

REFERENCE:

2.3.14APPROVED 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: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.

ANO-2-JPM-NRC-ADMIN-KI Page 2 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREJPM 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-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.

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.

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:

ANO-2-JPM-NRC-ADMIN-KI Page 5 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM 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-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.

ANO-2-JPM-NRC-ADMIN-KI Page 6 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM 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-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.

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:POTASSIUM IODIDE ADMINISTRATION CHANGE:.1903.035AREV.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:

2.9SRO: 4.6KA

REFERENCE:

2.4.41APPROVED 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: 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.

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

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.4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> following the trip, High Range containment radiation monitors read 74450 R/hr and77730 R/hr respectively.RCS average Core Exit Thermocouples are reading 430°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):

1.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).

.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

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.4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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°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

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.4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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°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:

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

@ (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

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

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

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

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

@ (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

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

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

REFERENCE:

010 A2.02APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION:INSIDE CR:

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: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.

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.

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:

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".

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".

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)

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.

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

REFERENCE:

006 A1.13APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:

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.

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)

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:

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."

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."

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

REFERENCE:

064 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: 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__________________________________

DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

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 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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-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.

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:

ANO-2-JPM-NRC-EDG06PAGE 5 OF 6JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS: 2DG2 has been supplying 2A4 for 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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-EDG06PAGE 6 OF 6JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS: 2DG2 has been supplying 2A4 for 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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.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-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

REFERENCE:

012 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.

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:

6.(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.

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

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

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:

15.(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.

21.(Step 2.2)Reset Reflash unit 2K426 in 2C14.EXAMINER CUE

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

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:

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. "

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. "

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

REFERENCE:

001 A4.03APPROVED FOR ADMINISTRATION TO: RO: X SRO: XTASK 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 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__________________________________

DATE: _____________________SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

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

1. 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 (>

5").Inserted CEA seven steps (>

5").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.

10.(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:

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."

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."

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

REFERENCE:

103 A3.01APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION:INSIDE CR:

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: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.

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.

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:

-2T-20A (2LIS-2010)

-2T-20B (2LIS-2012)On panel 2C14, monitored AuxBuilding sump level (2LIS-2000or 2LIS-2000B), and 2T-20A(2LIS-2010) waste tank.

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:

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".

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".

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

REFERENCE:

003 A4.08APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:

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.

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

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)

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 >180ºF and step 3 will be NA.On panel 2C14 or on PMScomputer determined that RCPseal temperatures is > 180ºFand 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.

8.(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:

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."

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."

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

REFERENCE:

008 A4.01APPROVED FOR ADMINISTRATION TO: RO:

XSRO:TASK LOCATION:INSIDE CR:

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: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.

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.

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:

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."

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."

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

REFERENCE:

064 A4.01APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:

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: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:

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.

3.(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.

9.(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:

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.

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.

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")

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

3.0SRO: 3.1 KA

REFERENCE:

041 A4.08APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:

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:

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 valvestrokes 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 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:

1.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.

2.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.

2.Positioner output to theoperating diaphragm. N/A SAT UNSATEXAMINER'S NOTES:

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

2.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.

3.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:

033 A2.03APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:

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:

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:

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:

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.

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:

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.

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.

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.

2CV0242R (ATC)C (SRO)#1 Main Turbine Generator Control Valve fails Closed.Tech Spec for SRO.

3RCSLOCATCAC (ATC)C (SRO)Shutdown required due to 15 gpm Reactor Coolantsystem leak on 'A' cold leg. Tech Spec for SRO.

4 2C-11AI_TIC_1602MTGVIBINC I (BOP)I (SRO)Main Turbine Generator lube oil controller setpoint failshigh.Main Turbine Generator Vibrations increase causing areactor trip.

5 500LOSE500 500LOSE161M (ALL)Loss of Offsite Power causing natural circulation of theRCS.6FW2PW5BAFTM(ALL)'B' Main Feed water line breaks inside containment.

7416 A308C (BOP)C (SRO)#1 EDG output breaker fails to automatically close.

8CVC2P36LOLVLCVC2P36BSIASCVC2P36CSIASI (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.

Appendix D Scenario 1Form ES-D-1Revision 0Page 2 of 3Scenario #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 toautomatically 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 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.

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 225ºF) 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.

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.

2SV0242Trigger = T1 0#1 Main Turbine Generator Control Valve fails Closed.Tech Spec for SRO.

3RCSLOCATCATrigger = T1 15 /Delay 5min.Shutdown required due to 15 gpm Reactor Coolant systemleak on 'A' cold leg. Tech Spec for SRO.

4 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.

5 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.

7416 A308NO_AUTO_CL#1 EDG output breaker fails to automatically close.

8CVC2P36LOLVLCVC2P36BSIASCVC2P36CSIAS 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.

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 3 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 1Event

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).

BOP7.2.3 Open Containment Makeup Water Supply (2CV-4690-2).

BOP7.2.4 Throttle open Quench Tank Supply (2CV-4685).

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 4 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3Event

Description:

1. 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.

SROEnter and direct actions of AOP 2203.024, Loss of Turbine Load.1. Open Placekeeping page.

SRO2. Notify Control Board Operators to monitor floating steps.ATC*3. Reduce Reactor power to match TAVE within 2°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°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 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:

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 5 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3Event

Description:

1. 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.

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 6 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3Event

Description:

1. 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.

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.

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

Description:

1. 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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 8 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 & 3Event

Description:

1. 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.

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 RCSboration using2104.003, Chemical Addition,Attachment R, RCS Boration from the RWT or BAMT.

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 9 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 4Event

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.

BOP2.2 Verify Lube Oil 2E-15A/B Temperature controller (2TIC-1602) setto control temperature at 115°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.

SRO2.4 IF bearing metal temperature reaches 230°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:

2.6Check 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.

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.

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 10 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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.

SROEnter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.

2.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

______Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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°F or greater.

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:

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

. (May not be met due to ESD Event #6.Perform contingency if not met)

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:

6.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.)

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 12 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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:

A.At least ONE RCP running.(RCPs will be secured due LOOPand CRS should perform the contingency)

SROIf required, direct the contingency for step 7. ECore HeatRemovalsafetyfunction.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.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°F.RCS HeatRemovalSafetyFunctionANYPerform 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)

Appendix D Scenario 1Form ES-D-2Revision 0Page 13 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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:

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 14 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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°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

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.

SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.

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.

SRODiagnose Functional Recovery EOP 2202.009.

SROEnter and implement Functional Recovery EOP 2202.009.

Appendix D Scenario 1Form ES-D-2Revision 0Page 16 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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 .

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.

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.

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 40ºF 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°F and 30°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:

Appendix D Scenario 1Form ES-D-2Revision 0Page 17 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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)

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.

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:

Appendix D Scenario 1Form ES-D-2Revision 0Page 18 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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°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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 19 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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°F and NOT rising.3) IF ALL RCPs secured, THEN RCST less than 50°F and NOT rising.4) RCS T C less than 555°F and NOT rising.5) RCS MTS 30°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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 20 of 22Op-Test No.: 1 Scenario No.: 1 Event No.: 5, 6 & 7Event

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°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.

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.

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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 21 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 8Event

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.

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:

3.0 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.

Appendix D Scenario 1Form ES-D-2Revision 0Page 22 of 22Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 9Event

Description:

2P-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.

SRODirect BOP to verify Red Train Containment Spray pump running andCSAS actuated IAW 2202.010 Exhibit 9.

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.

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.

2SW2P4AWNDC (BOP)C (SRO)2P-4A Service water pump high winding temperaturecausing pump swap.

3SGATUBER (ATC)N (BOP)N (SRO)Shutdown required due to 4 gpm steam generator tubeleak on 'A' steam generator. Tech Spec for SRO.

4CVC2P39BC(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.

6CEA35STUCKCV48731CVC4916SIASC (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.

7ESFK401AAF416A406 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.

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.

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 lowpressure 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 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.

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°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°F.

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.

2SW2P4AWNDTrigger = T2True 2P-4A Service water pump high winding temperaturecausing pump swap.

3SGATUBETrigger = T3 4/2 min.Shutdown required due to 4 gpm steam generator tubeleak on 'A' steam generator. Tech Spec for SRO.

4CVC2P39BTrigger = 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.

6CEA35STUCKCV48731CVC4916SIAS 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.

7ESFK401AAF416A406 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 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.

Appendix D Scenario 2Form ES-D-2Revision 0Page 7 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 1Event

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.

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.

SROImplement Annunciator Corrective Action 2203.012D.2K04-A5 CH B RPS/ESF/PRETRIP/TRIP applicable actions:

2.1Refer to PPS insert on 2C03 to determine cause.

2.2Compare 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:

2.1Determine which RPS or ESFAS trips have occurred onPPS inserts.

2.3 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.

Appendix D Scenario 2Form ES-D-2Revision 0Page 8 of 31Bypass point 18 on PPS Channel B:

11.1Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 andTRM 3.3.1.1.

11.2Circle 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.

11.4Verify points to be bypassed NOT bypassed in ANYother channel.

11.5Place desired points in BYPASS for selected channelon 2C23.Examiners Note: Key 12 required.ANYVerify annunciator 2K04-C3 PPS CHANNEL BYPASSEDVerify correct channels in bypass.

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.

Appendix D Scenario 2Form ES-D-2Revision 0Page 9 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 2Event

Description:

2P-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.

BOP2.1 Check 2TR-1428 to determine affected pump.

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.

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.

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:

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.

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.

BOP19.1.4 Start selected SW Pump (2P-4A/B/C).

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.

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.

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.

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)

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.

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.

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.

Appendix D Scenario 2Form ES-D-2Revision 0Page 12 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4Event

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

.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).

SROEnter 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% 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.

Appendix D Scenario 2Form ES-D-2Revision 0Page 13 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4Event

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:

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.

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:

A.Trip Reactor.B. Actuate SIAS.C. Actuate CCASD. GO TO 2202.001,Standard Post Trip Actions.

Appendix D Scenario 2Form ES-D-2Revision 0Page 14 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4Event

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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period of operation after ACTIONLEVEL TWO entry. THEN perform ACTION LEVEL THREE section of Attachment A.

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.

Appendix D Scenario 2Form ES-D-2Revision 0Page 15 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4Event

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.

2102.004Poweroperations 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°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).

Appendix D Scenario 2Form ES-D-2Revision 0Page 16 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4Event

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.

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).

Appendix D Scenario 2Form ES-D-2Revision 0Page 17 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 3 & 4Event

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.

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:

A.Trip Reactor.B. Actuate SIAS.C. Actuate CCASD. GO TO 2202.001,Standard Post Trip Actions.

SROEnter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.

2.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.

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.

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.

BOPComplete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.

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.

G.BOTH DGs secured.Both DGs will be running with servicewater aligned

)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°F or greater.

RCSInventoryControlSafetyfunction SRODirect the following as necessary:A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TOStep 6.2) Verify PZR Level Control system restoring level to setpoint.

Appendix D Scenario 2Form ES-D-2Revision 0Page 21 of 31

______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

. (Not met due to SGTR Event #5,perform contingency)

RCSPressureControlSafetyfunction SRODirect 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 andclosed.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.F. Verify PZR Pressure Control system restoring pressure tosetpoint.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.D. RCS MTS 30°F or greater.E. Check SW aligned to CCW

.(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°F.

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°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)

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.

SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.

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.

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

.Monitor RDACS for off site dose releases

.Cue: When contacted as Chemistry, then report you will sample both S/G for activity andMonitor 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.

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.

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.

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°F TH as follows:A. Reset Low SG Pressure setpoints during cooldown anddepressurization.B. Commence RCS depressurization to maintain RCS MTS 30 to 45°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.

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.

BOPG. Control S/G levels with EFW or AFW using 2106.006,Emergency Feedwater System Operations.ANYH. Secure running MFW pump.

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)

BOPH. Restore SW to ACW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.

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.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associatedPZR Spray valve in MANUAL and closed.

B.IF NPSH requirements violated ORRCS MTS less than 30°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:

1)2202.010 Attachment 27,PZR Spray Operation.

2)IF HPSI termination criteria met, THEN cycle Chargingpumps or throttle HPSI flow to lowerPZR pressure.

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:

15.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.

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.

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).

2)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°F,THEN isolate ruptured SG using2202.010 Attachment 10, SG Isolation.C. Maintain ruptured SG less than1050 psia with ONE of the following

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°F Th and 'A' SG isolated or at thediscretion of the lead examiner.

Appendix D Scenario 2Form ES-D-2Revision 0Page 31 of 31Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 7Event

Description:

2CV-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.

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 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 examiner'sdiscretion.

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.

2R (ATC)N (SRO)Power Ascension.

3 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.

5XRCCHBPLVLI (ATC)I (SRO)Channel 'B' Pressurizer level channel fails low. TechSpec for SRO.

6EHSYSLEAKM (ALL)Leak in the Electro Hydraulic system causing a turbinetrip, reactor trip and a loss of main feedwater pumps.

7XMSHDRPRS I (BOP)I(SRO)SDBCS input fails low after the Reactor trip.

8CV0332EFW2P7BFLTC (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.

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.

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 functionin 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 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

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.

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.

2Power Ascension.

3 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.

5XRCCHBPLVLTrigger = T3 0Channel 'B' Pressurizer level channel fails low. TechSpec for SRO.

6EHSYSLEAKTrigger = T4 TrueLeak in the Electro Hydraulic system causing a turbinetrip, reactor trip and a loss of main feedwater pumps.

7XMSHDRPRSTrigger = T5 650SDBCS input fails low after the Reactor trip.

8CV0332EFW2P7BFLTTrigger = 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 3Form ES-D-2Revision 1Page 3 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 1Event

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.

BOP*10.2 Verify Condensate header pressure 650 to 750 psig.

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.

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.

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.

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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 4 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 2Event

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).

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°F of program Tave using Exhibit 1, TAVE VS TREF.

Appendix D Scenario 3Form ES-D-2Revision 1Page 5 of 22ATCOP-2104.003, Chemical Addition Exhibit 2 for dilution.

1.0Verify EITHER Reactor Makeup pump (2P-109A OR 2P-109B)running.2.0Verify Mode Select switch (2HS-4928) in DILUTE.

3.0Verify Reactor Makeup Water Flow controller (2FIC-4927) set upas follows:In MANUAL OR AUTO.Demand set to less than Charging flow.

4.0Verify VCT Makeup Isol valve (2CV-4941-2) open.

5.0Operate Reactor Makeup Water Flow Batch controller(2FQIS-4927) as follows:

5.1Depress Red pushbutton.

5.2Verify 2FQIS-4927 set for desired quantity.

5.3Verify 2FIC-4927 indicates desired flow rate.

6.0Monitor the following parameters:RCS TaveAxial Shape IndexReactor power 7.0IF desired to terminate dilution,THEN reset 2FQIS-4927 to zero.

8.0WHEN 2FQIS-4927 at zero,THEN verify the following:RMW Flow Control valve (2CV-4927) closes.No flow indicated on 2FIC-4927.

9.0Repeat 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.

• Appendix D Scenario 3Form ES-D-2Revision 1Page 6 of 22Op-Test No.: 1 Scenario No.: 3 Event No.: 3Event

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:

2.1Determine affected channel by checking CPC TROUBLElights on CPC Operator Modules.

2.3Examine PIDs 415, 416, 417, and 418 as necessary todetermine affected CPC Channel and SensorClassification.

2.4Select 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:

2.1Refer to PPS insert on 2C03 to determine cause.

2.2Compare 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 isinoperable,THEN refer to 2105.001, CPC/CEAC Operations.

Appendix D Scenario 3Form ES-D-2Revision 1Page 7 of 22Op-Test No.: 1 Scenario No.: 3 Event No.: 3Event

Description:

Tc temperature transmitter fails high. Tech Spec for SRO.TimePositionApplicant's Actions or Behavior SRO2K04-B3 PPS Channel TRIP applicable actions:

2.1Determine which RPS or ESFAS trips have occurred onPPS inserts.

2.3 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)

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.

11.2Circle 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.

11.4Verify points to be bypassed NOT bypassed in ANYother channel.

11.5Place desired points in BYPASS for selected channelon 2C23.

Appendix D Scenario 3Form ES-D-2Revision 1Page 8 of 22Op-Test No.: 1 Scenario No.: 3 Event No.: 3Event

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.

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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 9 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 4Event

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).

2K-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).

2K-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.

SROContact Work Week Manager to repair 2HIC-4817.

Appendix D Scenario 3Form ES-D-2Revision 1Page 10 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 4Event

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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 11 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 5Event

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.

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.

SROE. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and3.3.3.6, Post-Accident Instrumentation.

Appendix D Scenario 3Form ES-D-2Revision 1Page 12 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 5Event

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.

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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 13 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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.

SRORefer to ACA for 2K02-A9 and direct appropriate actions.

BOP 2.1Check EH pressure on 2PI-9650 and Computer point P9650.

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.

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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 14 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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.

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.

SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.

2.Open Safety Function Tracking page.ReactivitycontrolsafetyfunctionATC 3.Check Reactivity Control established as follows:A. Reactor power lowering.B. ALL CEAs fully inserted.

BOPComplete Post Trip contingencies to align gland seal steam using 2CV-0233 Gland Seal Bypass Valve.

Appendix D Scenario 3Form ES-D-2Revision 1Page 15 of 22

______Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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°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

.

Appendix D Scenario 3Form ES-D-2Revision 1Page 16 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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:

A.At least ONE RCP running.B. CCW flow aligned to RCPs

.C. Loop delta T less than 10°F.D. RCS MTS 30°F or greater.E. Check SW aligned to CCW

.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)

F.Check RCS TC 540 to 555°F.

Appendix D Scenario 3Form ES-D-2Revision 1Page 17 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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:

8.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:

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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 18 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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°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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 19 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 6 & 7Event

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.

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.

SRODiagnose Loss of Feedwater EOP 2202.006. Termination Criteria: Feedwater has been restored per event #8or at lead examiner'sdiscretion.

Appendix D Scenario 3Form ES-D-2Revision 1Page 20 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 8Event

Description:

2P-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.

SRODirect STA to perform the following:* 1. Confirm diagnosis of Loss Of Feedwater by checking SFSCacceptance 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-1016-12CV-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°F and 30°F Margin to Saturation.

SRODirect a NLO to perform the following:

9.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

Description:

2P-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.)

SRO11. Establish EFW flow to SGs fromEFW pump 2P7B as follows:A. Check 2P7B available.(Not met perform contingency)

SROA. IF 2P7B NOT available,THEN GO TO Step 12.

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.

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.

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.

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)

BOPF. Start 2P75.

BOPG. Place AFW Lube Oil Pump 2P225 handswitch 2HS-0766 inOFF, then in AUTO.

BOPH. IF a SG level was less than 49%, THEN perform the following:

1)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.

Appendix D Scenario 3Form ES-D-2Revision 1Page 22 of 22Op-Test No.: 2011-1 Scenario No.: 3 Event No.: 8Event

Description:

2P-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.