Text

Arkansas Nuclear One, Unit 1-2016-09-FINAL Operating Test
	ML16259A379
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/01/2016
From:	Vincent Gaddy; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML16259A379 (491)
	v • d • e

ES-301Administrative Topics OutlineForm ES-301-1Facility: ____ANO-1_______________________Date of Examination: __8/22/2016__Examination Level:

RO SROOperating Test Number: _

2016-1__Administrative Topic (see Note)Type Code*Describe activity to be performed A1Conduct of OperationsKA - 2.1.5, Importance rating 2.9(RO/SRO)R, NGiven their work history, select the eligibleoperators to fill vacancy due to illness ofthe on watch ATC.

A2Conduct of OperationsKA- 2.1.20, Importance 4.6RO/SROR, D,PPerform calculation for makeup to theSpent Fuel Pool A3Equipment ControlKA - 2.2.13, Importance 4.1 RO R, NDetermine the mechanical and electricalboundary isolations for P-36B MakeupPump seal leak. (Do not need to drain thepump)A4Radiation ControlKA - 2.3.7, Importance 3.5 RO R, NGiven a survey map and associated RWP,determine the entry requirements toperform a task in the P-34A Decay HeatRemoval Pump Room.Emergency PlanNot usedNOTE: All items (five total) are required for SROs. RO applicants require only four itemsunless they are retaking only the administrative topics (which would require all fiveitems).* 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)

ES-301Administrative Topics OutlineForm ES-301-1Facility: ____ANO-1_______________________Date of Examination: __8/22/2016__Examination Level:

RO SROOperating Test Number: __

2016-1__Administrative Topic (see Note)Type Code*Describe activity to be performed A5Conduct of OperationsKA - 2.1.5, Importance rating 3.9(RO/SRO)R, NGiven their work history, select the eligibleoperators to fill vacancy due to illness ofthe on watch ATC.

A6Conduct of OperationsKA- 2.1.20, Importance 4.6RO/SROR, D,PPerform calculation for makeup to theSpent Fuel Pool A7Equipment ControlKA - 2.2.13, Importance 4.3 SROR, NReview and approve the tagout providedfor P-36B Makeup Pump seal leak. If notapproved, provide the reasons why.

A8Radiation ControlKA - 2.3.4, Importance 3.7 SRO R, NProvided with the dose history for eachindividual. Determine which of the 5 areeligible for performing the task during anemergency situation.

A9Emergency PlanKA - 2.4.44, Importance 4.4 SRO R, DDetermine the correct PAR andevacuation/sheltering required for a given GE.NOTE: All items (five total) are required for SROs. RO applicants require only four itemsunless they are retaking only the administrative topics (which would require all fiveitems).* 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)

Unit 1 2016 NRC ExamADMIN JPM A1JPM-NRC-WHHR (A1/A5)UNIT: 1REV # 1DATE: ______________________________TUOI NUMBER: A1JPM-NRC-WHHR (A1/A5)SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONSTASK: PERFORM WORKING HOUR HISTORY REVIEW AND SELECT ELIGIBLE OPERATORS TO FILLVACANCY DUE TO ILLNESS OF THE ONCOMING ATC WATCHJTA#: ANO-RO-ADMIN-NORM-195/ANO-SRO-ADMIN-NORM-191KA VALUE RO:2.9 SRO: 3.9 KA

REFERENCE:

2.1.5APPROVED FOR ADMINISTRATION TO: RO: X 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): EN-OM-123______________________________________________________________________EXAMINEE'S NAME:_______________________________ Logon ID: ___________________

EVALUATOR'S NAME:__________________________________________________________________THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDSCONTAINED IN THIS 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.

A1JPM-NRC-WHHR (A1/A5)THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner should verify that the examinee has been briefed on the JPM Examination Briefing SheetEN-TQ-114 Attachment 9.5 or NUREG-1021 App. E.JPM INITIAL TASK CONDITIONS: The plant is at 100% power operations. The scheduled day-shift oncomingATC operator has called in and stated he will not be able to come in to take the ATC watch due to an illness.The 54 hour6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months rolling average working limits in the last six weeks are met. PQ&S Computer program is not available.TASK STANDARD: The examinee has correctly selected operators A, C and E that are available tocome in to fill the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months dayshift ATC watch vacancy in accordance with the work hour limits for coveredindividuals and correctly stated why operators B and D cannot come in.TASK PERFORMANCE AIDS: Working Hour History for the last 14 days for Operators A,B,C,D, and E A1JPM-NRC-WHHR (A1/A5)INITIATING CUE:The Shift Manager has directed you to review the given work history of five eligible qualified operators anddetermine which one(s) would be available to fill the ATC vacancy for the upcoming 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day-shift in accordancewith the Fatigue Management Program. Explain why any operator may be ineligible to fill the vacancy if any cannot.CRITICAL ELEMENTS (C):(C)PERFORMANCE CHECKLISTSTANDARDSAT UNSAT N/A(C)1. Review working hour history for Operator 'A'.Determines that Operator 'A' is eligible to fill the oncoming ATC watch vacancy without exceeding any working hour limits._______________(C)2. Review working hour history forOperator 'B'.Determines that Operator 'B' is NOTeligible to fill the oncoming ATC watch vacancy because the operator will exceed the "Maximum of 72 work hours in any 7 day period" working hour limit._______________(C)3. Review working hour history forOperator 'C'.Determines that Operator 'C' is eligible to fill the oncoming ATC watch vacancy without exceeding any working hour limits.

._______________(C)4. Review working hour history forOperator 'D'.Determines that Operator 'D' is NOTeligible to fill the oncoming ATC watch vacancy because the operator will not have had a "Minimum 34-hourbreak in any 9-day period" workinghour limit._______________(C)5. Review working hour history forOperator 'E'.Determines that Operator 'E' iseligible to fill the oncoming ATC watch vacancy without exceeding any working hour limits.END A1JPM-NRC-WHHR (A1/A5)EXAMINER ANSWER KEYOperatorEligible/Not EligibleReason (if not eligible)Operator AEligible (C)Operator BNot Eligible (C)Will Exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period. (C)Operator CEligible (C)Operator DNot Eligible (C)No 34 hour3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months break in a 9 day period. (C)Operator EEligible (C)

A1JPM-NRC-WHHR (A1/A5)EXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The plant is at 100% power operations. The scheduled day-shift oncoming ATC operator has called in and stated he willnot be able to come in to take the ATC watch due to an illness. The 54 hour6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months rolling average working limits in the last six weeks are met. PQ&S computer program is not available.INITIATING CUE:The Shift Manager has directed you to review the given work history of five eligiblequalified operators and determine which one(s) would be available to fill the ATCvacancy for the upcoming 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day-shift in accordance with the Fatigue Management Program.Explain why any operator may be ineligible to fill the vacancy if any cannot.

A1JPM-NRC-WHHR (A1/A5)EXAMINEE'S COPYOperatorEligible/Not EligibleReason (if not eligible)Operator AOperator BOperator COperator DOperator E

Unit 1 2016 NRC Exam ADMIN JPM A2 A1JPM-RO-SFPMU (A2/A6)PAGE 1 OF 5 UNIT: 1 REV#: 2DATE:SYSTEM/DUTY AREA: Conduct of OperationsTASK: Perform Spent Fuel Pool Makeup Calculation.JTA#: ANO1-RO-SFC-NORM-17KA VALUERO:4.6SRO:4.6KA

REFERENCE:

2.1.20APPROVED FOR ADMINISTRATION TO: RO:

XSRO: 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: XAPPROXIMATE COMPLETION TIME IN MINUTES:20 MinutesREFERENCE(S): 1104.003, Att. C2EXAMINEE'S NAME:

Logon ID: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.

A1JPM-RO-SFPMU (A2/A6)PAGE 2 OF 5THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall ensure that the examinee has been briefed on the JPM Examination Briefing Sheet EN-TQ-114 Attachment 9.5 or NUREG 1021 Appendix E.JPM INITIAL TASK CONDITIONS:Given the following Plant conditions: Plant is in refueling Outage 1R26 SF Pool level is -0.4 ft. SF Pool Boron concentration 2300 ppm. BAAT Boron concentration 12,250 ppm. Tilt Pit and Cask Pit gates are removed. Fuel Transfer Tube Isolation SF-45 is ClosedTASK STANDARD:Determined initial SF Pool volume is 362,843 gallons from Table 2.Determined feed volume to be 3684 +/- 2 gallons.Determined final SF Pool volume to be 366,527 +/- 5 gallons.Determined final SF Pool level is 0.0 to -0.1 ft.TASK PERFORMANCE AIDS:1104.003, Attachment C2SIMULATOR SETUP:

NAEXAMINER'S NOTES:

A1JPM-RO-SFPMU (A2/A6)PAGE 3 OF 5INITIATING CUE:CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup to SFP to raise Boronconcentration to 2400 ppm. Determine amount of Boric Acid volume needed. Determine final SFP Volumeand Level.PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)1. Determine initial SF Poolvolume from Table 2.Determined volume is 362,843gallons from Table 2. SAT UNSAT N/A2. Record data.Recorded data. SAT UNSAT N/A (C)3. Determine feed volume to beadded to SF Pool.Determined feed volume to be3684 +/- 2 gallons. SAT UNSAT N/A (C)4. Determine final SF Poolvolume.Determined final SF Pool volumeto be 366,527 +/- 5 gallons. SAT UNSAT N/A (C)5Determine final SF Pool level Determined final SF Pool level isfrom 0.0 to -0.1 ft. SAT UNSAT N/A END A1JPM-RO-SFPMU (A2/A6)PAGE 4 OF 5ANSWER KEYJPM INITIAL TASK CONDITIONS:Given the following Plant conditions: Plant is in Refueling Outage 1R26. SF Pool level is -0.4 ft. SF Pool Boron concentration 2300 ppm. BAAT Boron concentration 12,250 ppm. Tilt Pit and Cask Pit gates are removed. Fuel Transfer Tube Isolation SF-45 is ClosedINITIATING CUE:CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup toSFP to raise Boron concentration to 2400 ppm.Determine amount of Boric Acid volume needed.Determine final SF Pool volume.Determine final SF Pool level.Document the results of the review below:(C) Determined initial SF Pool volume is currently 362,843 gallons from Table 2.(C) Determined feed volume to be 3684 +/- 2 gallons.(C) Determined final SF Pool volume to be 366,527 +/- 5 gallons.(C) Determined final SF Pool level is from 0.0 to -0.1 ft.Final Level interpolation:(366,692 - 365730) = - 0.1 .(366,692 - 366527) XX = - 0.1 (165) = - 0.017 feet 962Final Level = - 0.017 A1JPM-RO-SFPMU (A2/A6)PAGE 5 OF 5EXAMINEEE'S COPYJPM INITIAL TASK CONDITIONS:Given the following Plant conditions: Plant is in Refueling Outage 1R26. SF Pool level is -0.4 ft. SF Pool Boron concentration 2300 ppm. BAAT Boron concentration 12,250 ppm. Tilt Pit and Cask Pit gates are removed. Fuel Transfer Tube Isolation SF-45 is ClosedINITIATING CUE:CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, formakeup to SF Pool to raise Boron concentration to 2400 ppm.Determine amount of Boric Acid volume needed.Determine final SF Pool volume.Determine final SF Pool level.Document the results of the review below:

PROC./WORK PLAN NO.1104.003PROCEDURE/WORK PLAN TITLE:CHEMICAL ADDITIONPAGE:62 of 153CHANGE: 054ATTACHMENT C2Page 1 of 7SF POOL FEED CALCULATIONS TABLE 1Spent Fuel Pool and Systems Volume/Ft DepthSF Pool(gal/ft) SF Pool+ Cask Pit(gal/ft) SF Pool+ Tilt Pit(gal/ft) SF Pool+ Cask Pit+ Tilt Pit(gal/ft)Refueling Canal(gal/ft)IncoreTank(gal/ft)7,5708,3498,8459,62411,0701,141 TABLE 2Spent Fuel Pool and Systems Volume (gallons)Elev.(ft)LI-2004SF Pool SF Pool+ Cask Pit SF Pool+ Tilt Pit (1) SF Pool+ Cask Pit+ Tilt Pit (1)Refueling Canal IncoreTank401.5+1.0 ft298,120330,899343,537376,316401.4+0.9 ft297,363330,064342,653375,354401.3+0.8 ft296,606329,229341,768374,392401.2+0.7 ft295,849328,394340,884373,429401.1+0.6 ft295,092327,559339,999372,467401.0+0.5 ft294,335326,725339,115371,504400.9+0.4 ft293,578325,890338,230370,542400.8+0.3 ft292,821325,055337,346369,580400.7+0.2 ft292,064324,220336,461368,617400.6+0.1 ft291,307323,385335,577367,655400.5 0.0 ft290,550322,550334,692366,692342,80027,400400.4-0.1 ft289,793321,715333,808365,730341,69327,286400.3-0.2 ft289,036320,880332,923364,768340,58627,172400.2-0.3 ft288,279320,045332,039363,805339,47927,058400.1-0.4 ft287,522319,210331,154362,843338,37226,944400.0-0.5 ft286,765318,376330,270361,880337,26526,830399.9-0.6 ft286,008317,541329,385360,918336,15826,715399.8-0.7 ft285,251316,706328,501359,956335,05126,601399.7-0.8 ft284,494315,871327,616358,993333,94426,487399.6-0.9 ft283,737315,036326,732358,031332,83726,373399.5-1.0 ft282,980314,201325,847357,068331,73026,259399.4-1.1 ft282,223313,366324,963356,106330,62326,145399.3-1.2 ft281,466312,531324,078355,143329,51626,031399.2-1.3 ft280,709311,696323,194354,181328,40925,917399.1-1.4 ft279,952310,861322,309353,219327,30225,803399.0-1.5 ft279,195310,026321,425352,256326,19525,689(1) Tilt Pit volume from CR-ANO-1-2008-1859-CA2.During refueling,canal level must bemaintainedbetween -0.5 and0.0 on the SFPLevel indicator(LI-2004).

PROC./WORK PLAN NO.1104.003PROCEDURE/WORK PLAN TITLE:CHEMICAL ADDITIONPAGE:63 of 153CHANGE: 054 ATTACHMENT C2 Page 2 of 7 CAUTION Performance of this section requires verification that feed volume will not result in overflowing of the SFP or other attached volumes.

NOTE It is necessary to coordinate with Dry Fuel Personnel when making up to the Spent Fuel Pool during Dry Fuel Operations.

Step 1.0 is solely performed to determine volume of boric acid at a known concentration to achieve a desired final SFP boron concentration, and generally would not be used.1.0 IF it is desired to calculate the volume of boric acid required to achieve a desired final SFP concentration, THEN perform the following:

1.1 Determine initial SF Pool volume from TABLE 2. Interpolate if necessary.

1.1.1 IF appropriate, THEN add Refueling Canal and Incore Tank volume.

V i = _____________gal = Initial Volume from TABLE 2 1.2 Record the following data:

C i = __________ppmB = Initial SF Pool concentration C f = __________ppmB = Final desired SF Pool concentration C fd = __________ppmB = Feed concentration to be added to SF Pool 1.3 Determine feed volume to be added to the SF Pool V fd = ( V i ) x ( C f - C i ) ( C fd - C f)V fd = ( ) x ( - )

( - )

V fd = __________gal.

PROC./WORK PLAN NO.1104.003PROCEDURE/WORK PLAN TITLE:CHEMICAL ADDITIONPAGE:64 of 153CHANGE: 054 ATTACHMENT C2 Page 3 of 7 1.4 Determine final SF Pool volume Final volume = ( V fd) + ( V i )Final volume = ( ) + ( )

Final = __________gal.

Volume NOTE If final SF Pool level is determined to be greater than +1.0 ft or greater than zero when refueling, then the addition will have to be made in separate operations.

1.5 Determine final SF Pool level from TABLE 2, interpolate as necessary.

1.5.1 IF final volume greater than table values THEN a second addition will have to be done following a level reduction.

1.6 Perform the other sections of this Attachment as required.2.0 IF needed, THEN find the volume of feed (V fd) AND use TABLE 1 for SF Pool gal/ft.

IF Refueling Canal or Incore Tank is connected to SF Cooling System THEN add the appropriate gal/ft to the SF Pool gal/ft.

V fd = [(Final level) - (Initial level)] x ( gal/ft )

V fd = [(________ft.) - (__________ft.)] x (________gal/ft)

V fd = __________gal.

Unit 1 2016 NRC Exam ADMIN JPM A3 1 of 6A1JPM-RO-HCRD5 (A3)UNIT: 1REV # 2DATE: ______________________________TUOI NUMBER: A1JPM-RO-HCRD5 (A3)SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - EQUIPMENT CONTROLTASK: PERFORM IDENTIFICATION OF COMPONENTS THAT NEED TO BE ISOLATED AND DANGERTAGGED FOR AN INBOARD SEAL LEAK ON MAKEUP PURIFICATION PUMP P-36AJTA#: ANO-RO-ADMIN-NORM-078KA VALUE RO:4.1 SRO: 4.3 KA

REFERENCE:

2.2.13APPROVED FOR ADMINISTRATION TO: RO: X SRO:TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE: SIMULATOR: CLASSROOM:_ PERFORM_POSITION EVALUATED: RO: : XSRO:___________ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:_____ CLASSROOM: XTESTING METHOD: SIMULATE:_________ PERFORM: XAPPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTESREFERENCE(S): EN-OP-102, PROTECTIVE AND CAUTION TAGGING; P&ID M-231;ELECTRICAL PRINT E-5 ONE LINE DRAWING FOR ENGINEERED SAFEGUARD BUSES A3 AND A4.EXAMINEE'S NAME:_______________________________ Logon ID: ___________________EVALUATOR'S NAME:__________________________________________________________________THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDSCONTAINED IN THIS 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.

2 of 6A1JPM-RO-HCRD5 (A3)THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner should verify that the examinee has been briefed on the JPM Examination Briefing SheetEN-TQ-114 Attachment 9.5 or NUREG-1021 App. E.JPM INITIAL TASK CONDITIONS: The plant is at 100% power. A bad inboard seal leak is present on MakeupPurification Pump P-36A. A Danger Tag will need to be generated to isolate this inboard seal leak.No venting or draining of the pump is required at this time.TASK STANDARD: The applicant identified the following components at a minimum for danger tagging.A-306 - Racked Down, MU-20A - Closed, MU-21A - Closed, MU-18A - Closed.TASK PERFORMANCE AIDS: P&ID M-231 Makeup & Purification System Drawing; Electrical Print E-5 oneline drawing for Engineered Safeguard Buses A3 and A4.

3 of 6A1JPM-RO-HCRD5 (A3)INITIATING CUE:The SM/CRS has directed you to identify the components that need to be danger tagged to electrically andmechanically isolate Makeup Purification Pump P-36A to isolate this seal leak. Also provide the component dangertag position required.CRITICAL ELEMENTS (C): (C)PERFORMANCE CHECKLISTSTANDARDSAT UNSAT N/ANOTE: Provide examinee with a copy of E-Print E-5 and P&ID M-231 (C)1. Reviews controlled documentationto determine source of power to P-36A to add to the tagout (E-Print E-5 or OP-1107.002 Attachment A)Determines that Electrical CircuitBreakerA-306 will need to be"Breaker Racked Down" and addedto the tagout.

_______________Note: The Candidate may add a Caution Tag to be placed on the MU Purification Pump P-36A Remote HandSwitch.(C)2. Reviews controlled documentationto determine the P-36A pumpdischarge Isolation will need to beadded to the tagout (P&ID M-231)Determines that P-36A DischargeIsolationMU-20A will need to beClosed and added to the tagout.

_______________(C)3. Reviews controlled documentationto determine that a P-36A minimumrecirc isolation will need to beadded to the tagout (P&ID M-231)Determines that a P-36A MinimumRecirc IsolationMU 21A or MU-22A(in series) will need to beClosed andadded to the tagout.

_______________(C)4. Reviews controlled documentationto determine the P-36A pumpsuction Isolation will need to beadded to the tagout (P&ID M-231)Determines that P-36A SuctionIsolationMU-18A will need to beClosed and added to the tagout.

_______________NOTE: Inform examinee that JPM is complete.

END 4 of 6A1JPM-RO-HCRD5 (A3)EXAMINER ANSWER KEYComponent #Component NameComponent Position A-306MU Pump P-36A Electrical Circuit BreakerBreaker Racked DownMU-20AMU Pump P-36A Discharge Isolation ValveClosedMU-21AMU Pump P-36A Minimum Recirc Isolation ValveClosedMU-18AMU Pump P-36A Suction Isolation ValveClosed 5 of 6A1JPM-RO-HCRD5 (A3)EXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The plant is at 100% power. A bad inboard seal leak is present on Makeup Purification Pump P-36A. A Danger Tag will need to be generated to isolate this inboard seal leak.No venting or draining of the pump is required at this time.INITIATING CUE:The SM/CRS has directed you to identify the components that need to be dangertagged to electrically and mechanically isolate Makeup Purification Pump P-36A toisolate the seal leak.Also provide the component danger tag position required.

6 of 6A1JPM-RO-HCRD5 (A3)EXAMINEE'S COPYComponent #Component NameDanger Tag Position EPrint E-5 Sheet 1 M-231, sh. 1 EPrint E-5 Sheet 1 M-231, sh. 1 Unit 1 2016 NRC Exam ADMIN JPM A4 Page 1 of 5A1JPM-RO-ADMIN-RWP3 (A4)ADMINISTRATIVE JOB PERFORMANCE MEASUREUNIT: 1REV # 1DATE: ______8/4/2016_________JPM ID: A1JPM-RO-ADMIN-RWP3 (A4)SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - Radiation ControlTASK: Ability to comply with radiation work permit requirementsJTA#: ANO1-RO-DHR-NORM-2KA VALUE RO:3.5 SRO: 3.6 KA

REFERENCE:

2.3.7APPROVED FOR ADMINISTRATION TO: RO: X SRO:TASK LOCATION: INSIDE CR: OUTSIDE CR:_________ CLASSROOM: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:_____________ SIMULATOR: Classroom: ________X_______POSITION EVALUATED: RO:____X______ SRO:___________ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:______ Classroom:__X___TESTING METHOD: SIMULATE:_________ PERFORM:___X________APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTESREFERENCE(S): RWP 2016-1002, P-34A survey map,EXAMINEE'S NAME:_______________________________ Logon ID: ___________________EVALUATOR'S NAME:__________________________________________________________________THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDSCONTAINED IN THIS 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.

Page 2 of 5A1JPM-RO-ADMIN-RWP3 (A4)ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall ensure that the examinee has been briefed on the JPM Examination BriefingSheet EN-TQ-114 Attachment 9.5 or NUREG 1021 Appendix E.INITIAL PLANT CONDITIONS Decay Heat Removal Pump P-34A has indications of a leak on the pump inboard seal. The SM/CRS has directed you to quantify the leakage from the P-34A pump inboard seal. Your total dose for the year is currently 1950 mrem. You are a qualified CAT 3 Advanced Rad Worker.TASK STANDARD:Using the above information, applicant determined: Remaining available dose is 50 mR MAXIMUM stay time at the P-34A pump inboard seal area is 26.1 to 26.0 minutes. Required protective clothing requirements are single set of anti-Cs.TASK PERFORMANCE AIDS: RWP 2016-1002, P-34A survey map .SIMULATOR SETUP:

NA Page 3 of 5A1JPM-RO-ADMIN-RWP3 (A4)ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Use the attached RWP, 2016-1002 Task 1.Using the above information, determine your MAXIMUM stay time at the P-34A pump inboard seal area and therequired protective clothing for entry.(C)PERFORMANCE STEPPERFORMANCE STANDARDSAT UNSAT N/A1. Reviews P-34A Pump surveymap to determine dose rates inthe vicinity of the inboardpump seal.Examinee determined dose rate of115 mR/hr at the inboard pump seal.

_______________(C)2. Determines stay time based onthe given dose in the pumpinboard seal area not toexceed the RWP limits. 50 mR X 60 min = 26.1 minutes115 mR/hr 1 hrExaminee determined stay timebased on RWP limits of 50 mremwould allow him to stay at the pumpinboard seal area for 26.1 minutes(-0.1 minutes).

_______________(C)3. Reviews P-34A Pump surveymap for contamination smeardata to determine theprotective clothing (PC)requirements for this task.Examinee identified thecontamination levels are > 1000dpm/100 cm 2 but less than 100,000dpm/100 cm 2; therefore, a single setof Anti-Cs is required to enter into theP-34A pump room.

_______________END Page 4 of 5A1JPM-RO-ADMIN-RWP3 (A4)ADMINISTRATIVE JOB PERFORMANCE MEASUREANSWER KEYJPM INITIAL TASK CONDITIONS

Decay Heat Removal Pump P-34A has indications of a leak on the pump inboardseal. The SM/CRS has directed you to quantify the leakage from the P-34A seal. Your total dose for the year is currently 1950 mrem. You are a qualified CAT 3 Advanced Rad Worker.INITIATING CUE:Refer to the attached RWP, 20161002 Task 1 and the P-34A pump roomsurvey map.Using the above information, determine: Your remaining available dose for the year based on ANOadministrative limits.

50 mR Your "MAXIMUM" stay time at the P-34A pump inboard seal area.50 mR X 60 min =26.1 minutes (-0.1 minutes) (C)115 mR/hr 1 hr Your "Protective Clothing" requirements:Single set of Anti-Cs (C)

Page 5 of 5A1JPM-RO-ADMIN-RWP3 (A4)ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

Decay heat Removal Pump P-34A has indications of a leak on the pump inboardseal. The SS/CRS has directed you to quantify the leakage from the P-34A seal. Your total dose for the year is currently 1950 mrem. You are a qualified CAT 3 Advanced Rad Worker.INITIATING CUE:Refer to the attached RWP, 20161002 Task 1 and the P-34A pump roomsurvey map.Using the above information, determine: Your remaining available dose for the year based on ANOadministrative limits.

__________________________________________________________ Your "MAXIMUM" stay time at the P-34A pump inboard seal area.

__________________________________________________________ Your "Protective Clothing" requirements:

__________________________________________________________

1a1-05_jpgTemplate:Survey:ANO-1606-0004 ANOPage 1 of 1Thursday, June 30, 2016Details 1001a1-05_jpg10CFR50.75G Decomm 13 1RAB 31720970Harrell, John08/22/2016 15:58In-Progress20161001RxPwr:Template:Frequency:Room:Unit:Building:Elevation:Badge:Reviewed By:Notes:Surveyed By:Survey Date:Status: Rwp:Hydro Inj Rate:

NAInstruments Used NA NA NA 6/29/2016 7/31/2016CHP-CR-148 LM-177 MDA:DC & Bkg:SrcChk Date:Cal Due Date:Instrument:

NA NA NA 6/29/2016 12/31/2016CHP-DR-3319-3 MDA:DC & Bkg:SrcChk Date:Cal Due Date:Instrument:Smear Data (DPM/100cm2)

DPM 20000 1 DPM 25000 2 DPM 30000 3 DPM 35000 4LAS Data (ccpm/LAS)ccpm/LAS 6000 1ccpm/LAS<100 2ccpm/LAS<100 3ccpm/LAS<100 4B/G to Alpha RatioAlpha Data (DPM/100cm2)

DPM Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 1 of 7RWP Title:OPERATIONS ACTIVITIES UNIT-1RWP No.: 20161002Rev. 00Comments:*20161002*RWP Type:SPECIFICRWP Status:

ACTIVEBegin Date: 1/1/2016Close On Date: 12/31/2016Prepared By:NICKELS, THOMAS WJob Supervisor:Jeff HortonEstimated Dose:528 mremEstimated Hours:

14,400.00Actual Dose:293 mremActual Hours:

9,041.99Locations Buildings Elevations RoomsLOW LEVEL RADWASTE BUILDING 354NON-LOCKED HIGH RADIATIONAREAOLD RADWASTE BUILDING 354NON-LOCKED HIGH RADIATIONAREAOUTSIDE CONTROLLED ACCESS ALLOUTSIDE CONTROLLED ACCESSUNIT 1 AUXILIARY BUILDING ALLNON-LOCKED HIGH RADIATIONAREARadiological ConditionsDescriptionValueUnitSmear data is in dpm/100 cm2 unless otherwise noted.<1K - 40KDPM/100CM2General area gamma dose rates are in mrem/hour unless otherwise noted.0.1 - 200MILLIREM/HOUR Tasks TaskDescriptionStatus 1OPERATIONS ACTIVITIES UNIT-1Active 2OPERATIONS TRAINEE ACTIVITIES UNIT-1ActiveRequirements Requirement Groups Requirement Descriptions N/AAdditional Instructions Instruction 1: Instruction 2: Instruction 3:ApprovalsApprover TitleName DateALARA REVIEWSTELL, RANDALL E12/22/2015RWP PREPARERSTELL, RANDALL E12/22/2015RP SUPERVISORLYNCH, BERT A12/22/2015Attachments N/A Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 2 of 7Task Number:

1RWP No.: 201 61002Rev.: 00Task

Description:

OPERATIONS ACTIVITIES UNIT-1Task Status:

Active Estimate Dose:420.00Estimate Hours:12,000.00 Hi-Rad: YesHot Particle:

NoLocked Hi-Rad: No Hi-Contamination:

NoAlarm SettingsDose Alarm (mrem)50.00Dose Rate (mrem/hr) 150.00RequirementsRequirement GroupsRequirement DescriptionsContamination ControlAll materials are required to be surveyed in a small articles monitor or hand frisked by RP(with RP Supervisor approval) PRIOR TO unconditional release from a RadiologicallyControlled Area.IF the RCA is a satellite RCA and a "Contamination Area" is entered, THEN theradworkershould perform a whole body frisk and proceed to the nearest whole body contaminationmonitor (PCM-1B or equivalent).IF the RCA is a satellite RCA with no whole body contamination monitor available, THENtheradworker should: a) perform a hand and foot frisk. b) IF the frisk indicates contamination ispresent, THEN contact RP. c) IF the frisk DOES NOT indicate thepresence of contamination,THEN proceed to the nearest whole body contamination monitor and gamma sensitivemonitor.Notify RP prior to exposing a contaminated surface or opening a contaminated system.Obey the monitoring instructions posted at the RCA exit pointUpon exit of an RCA, whole body monitoring is required utilizing a whole bodycontaminationmonitor (PCM-1B or equivalent). A whole body gamma monitor must also be cleared (PM-7or equivalent).Upon exiting areas posted as "Contamination Area", perform a hand and foot frisk at thedesignated frisker location.Use RP approved mats or pads when kneeling, sitting or laying in contaminated areas.Use face shield for activities that have increased risk of facial contamination. Theseactivitiesinclude working with contaminated components overhead, or having a body position thatpresents the potential for facial contamination.With RP approval, reaching across a contamination boundary is permitted usingsurgeon'sgloves OR cotton liners with rubber gloves. When reaching into the area ofhighercontamination, gloves must be removed when hands are returned to the lower level side of theboundary.Dosimetry RequirementsFOR WORK IN HIGH RADIATION AREAS

-If your work conditions are in OR willcausehearing impairment (such as work in a high noise area, use of a communications headset, etc.)THEN the use of an EAD amplifying device (PAM) is required.If an EAD dose alarm occurs: 1) Secure Work. 2) Immediately leave the RCA. 3) NotifyRP.If an EAD dose rate alarm occurs: 1) Secure Work. 2) Back out of the immediate area untilthe alarm clears. 3) Notify others in your work crew. 4) Immediately notify RP for furtherinstructions.Periodically check your EAD. This check should be performed more frequently in areaswhereyour ability to hear is diminished.Periodically check your EAD. This check should be performed more frequently in areaswhereyour ability to hear is diminished.Whole body DLR and EAD required for entry.Additional Instructions Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 3 of 7Instruction 1:

Task Number:

1RWP No.: 201 61002Rev.: 00RequirementsRequirement GroupsRequirement DescriptionsEngineering ControlsWhen venting or draining, monitor the rate of system drain to ensure the rate of drain doesNOT exceed the capacity of the floor drain.Exposure ReductionUse Low Dose Waiting Areas whenever possible to minimize exposure.Protective RequirementsAll joints between Anti-C gloves /sleeves and Anti-C ankles/ booties must be taped.Entry into Contamination Areas require single Anti-Cs.Entry into High Contamination Areas require double Anti-Cs .RP CoverageA "Cat 3 Advanced Radworker" may enter posted High Radiation Areas using a gammasensitive RP instrument to monitor dose rates. (NOTE: An EAD is NOT an appropriatesurvey instrument. LHRA/ VHRA entry requires continuous RP coverage.).Contact RP Supervisor or RP tech prior to entry to verify adequate RP coverage andcontamination controls for your work activity. RP is not required to be notified for entries tothe Auxiliary Building to perform routine activities that do not involve High Radiation Areas,Contamination Areas, overhead entry or system breaches.Entry into High Radiation Areas requires a radiological brief from RP, AND an electronicalarming dosimeter (EAD) to meet Tech Spec monitoring requirements.Initial / Intermittent RP coverage is required for entry into High Radiation Areas.Notify RP when performing operations activities which could change plant radiologicalconditions. For example venting/draining radioactive systems, performing degas or decayheat/shutdown cooling operations, or other non routine system functions.Radiological ConditionsContact Radwaste Personnel for radiological conditions in the Radwaste Buildings.Radiological conditions should be reviewed to ensure awareness of conditions in your workarea. This information can be obtained from either a Status Board or RP personnel.Respiratory ProtectionBased on historical and current data, the airborne radioactivity is less than 30 percent of aDAC. Respiratory protection is not required unless otherwise directed by RP Supervision.Special Radiological RequirementsCritical Step - Prior to movement of irradiated fuel or other irradiated materials, notify RPShift Tech or RP Supervisor that movement of fuel / irradiated components is going to occur.DO NOT move fuel or irradiated components near cask loading gate or tilt pit gate when theadjacent pit is drained as this can result in high general area dose rates.The prerequisite for a secondary resin transfer include 1) Secure the fill head such that changesin pressure will not cause a spill. 2) Conduct a walkdown (pre-transfer) to ensure that hoseconnections and leak integrity is satisfactory. 3) Construct a berm sufficient to contain thematerial being transferred.Additional Requirement: -Critical Step - Ensure ARM is installed on the bridge and isoperation prior to performing any fuel movements. The ARM alarm set point is determined byRP supervision.Stop Work CriteriaCritical Step - Indications either from local samples or remote indication (CAM) of airborneradioactivity in quantities in excess of 30 percent of a DAC.Critical Step - Loss of control of radioactive material such that loose surface contaminationoutside of any protective measures is greater than area postingsCritical Step - Radiation dose rates in the immediate area are greater than the EAD dose ratealarm set point.CRitical Step - Work involving alpha contamination greater than or equal to 100 dpm/100cm2CAN NOT be worked on a General RWP.

Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 4 of 7 Task Number:

1RWP No.: 201 61002Rev.: 00Additional InstructionsInstruction 1: Instruction 2: Instruction 3: Instruction 4: Instruction 5:Attachments N/A Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 5 of 7Task Number:

2RWP No.: 201 61002Rev.: 00Task

Description:

OPERATIONS TRAINEE ACTIVITIES UNIT-1Task Status:Active Estimate Dose:108.00Estimate Hours:2,400.00 Hi-Rad: YesHot Particle:

NoLocked Hi-Rad: No Hi-Contamination:

NoAlarm SettingsDose Alarm (mrem)10.00Dose Rate (mrem/hr) 100.00RequirementsRequirement GroupsRequirement DescriptionsContamination ControlAll materials are required to be surveyed in a small articles monitor or hand frisked by RP(with RP Supervisor approval) PRIOR TO unconditional release from a RadiologicallyControlled Area.IF the RCA is a satellite RCA and a "Contamination Area" is entered, THEN theradworkershould perform a whole body frisk and proceed to the nearest whole body contaminationmonitor (PCM-1B or equivalent).IF the RCA is a satellite RCA with no whole body contamination monitor available, THENtheradworker should: a) perform a hand and foot frisk. b) IF the frisk indicates contamination ispresent, THEN contact RP. c) IF the frisk DOES NOT indicate thepresence of contamination,THEN proceed to the nearest whole body contamination monitor and gamma sensitivemonitor.Notify RP prior to exposing a contaminated surface or opening a contaminated system.Obey the monitoring instructions posted at the RCA exit pointUpon exit of an RCA, whole body monitoring is required utilizing a whole bodycontaminationmonitor (PCM-1B or equivalent). A whole body gamma monitor must also be cleared (PM-7or equivalent).Upon exiting areas posted as "Contamination Area",perform a hand and foot frisk at thedesignated frisker location.Use RP approved mats or pads when kneeling, sitting or laying in contaminated areas.Use face shield for activities that have increased risk of facial contamination. Theseactivitiesinclude working with contaminated components overhead, or having a body position thatpresents the potential for facial contamination.With RP approval, reaching across a contamination boundary is permitted usingsurgeon'sgloves OR cotton liners with rubber gloves. When reaching into the area ofhighercontamination, gloves must be removed when hands are returned to the lower level side of theboundary.Dosimetry RequirementsFOR WORK IN HIGH RADIATION AREAS

-If your work conditions are in OR wi llcausehearing impairment (such as work in a high noise area, use of a communications headset, etc.)THEN the use of an EAD amplifying device (PAM) is required.If an EAD dose alarm occurs: 1) Secure Work. 2) Immediately leave the RCA. 3) Notify R P.If an EAD dose rate alarm occurs: 1) Secure Work. 2) Back out of the immediate area untilthe alarm clears. 3) Notify others in your work crew. 4) Immediately notify RP for furtherinstructions.Periodically check your EAD. This check shouldbe performed more frequently in areaswhereyour ability to hear is diminished.Periodically check your EAD. This check should be performed more frequently in areaswhereyour ability to hear is diminished.Whole body DLR and EAD required for entry.Additional InstructionsInstruction 1:

Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 6 of 7 Task Number:

2RWP No.: 201 61002Rev.: 00RequirementsRequirement GroupsRequirement DescriptionsEngineering ControlsWhen venting or draining, monitor the rate of system drain to ensure the rate of drain doesNOT exceed the capacity of the floor drain.Exposure ReductionUse Low Dose Waiting Areas whenever possible to minimize exposure.Protective RequirementsAll joints between Anti-C gloves /sleeves and Anti-C ankles/ booties must be taped.Entry into Contamination Areas require single Anti-Cs.Entry into High Contamination Areas require double Anti-Cs .RP CoverageA "Cat 3 Advanced Radworker" may enter posted High Radiation Areas using a gammasensitive RP instrument to monitor dose rates. (NOTE: An EAD is NOT an appropriatesurvey instrument. LHRA/ VHRA entry requires continuous RP coverage.).Contact RP Supervisor or RP tech prior to entry to verify adequate RP coverage andcontamination controls for your work activity. RP is not required to be notified for entries tothe Auxiliary Building to perform routine activities that do not involve High Radiation Areas,Contamination Areas, overhead entry or system breaches.Entry into High Radiation Areas requires a radiological brief from RP, AND an electronicalarming dosimeter (EAD) to meet Tech Spec monitoring requirements.Initial / Intermittent RP coverage is required for entry into High Radiation Areas.Notify RP when performing operations activities which could change plant radiologicalconditions. For example venting/draining radioactive systems, performing degas or decayheat/shutdown cooling operations, or other non routine system functions.Radiological ConditionsContact Radwaste Personnel for radiological conditions in the Radwaste Buildings.Radiological conditions should be reviewed to ensure awareness of conditions in your workarea. This information can be obtained from either a Status Board or RP personnel.Respiratory ProtectionBased on historical and current data, the airborne radioactivity is less than 30 percent of aDAC. Respiratory protection is not required unless otherwise directed by RP Supervision.Special Radiological RequirementsCritical Step - Prior to movement of irradiated fuel or other irradiated materials, notify RPShift Tech or RP Supervisor that movement of fuel / irradiated components is going to occur.DO NOT move fuel or irradiated components near cask loading gate or tilt pit gate when theadjacent pit is drained as this can result in high general area dose rates.The prerequisite for a secondary resin transfer include 1) Secure the fill head such that changesin pressure will not cause a spill. 2) Conduct a walkdown (pre-transfer) to ensure that hoseconnections and leak integrity is satisfactory. 3) Construct a berm sufficient to contain thematerial being transferred.Additional Requirement: -Critical Step - Ensure ARM is installed on the bridge and isoperation prior to performing any fuel movements. The ARM alarm set point is determined byRP supervision.Stop Work CriteriaCritical Step - Indications either from local samples or remote indication (CAM) of airborneradioactivity in quantities in excess of 30 percent of a DAC.Critical Step - Loss of control of radioactive material such that loose surface contaminationoutside of any protective measures is greater than area postingsCritical Step - Radiation dose rates in the immediate area are greater than the EAD dose ratealarm set point.CRitical Step - Work involving alpha contamination greater than or equal to 100 dpm/100cm2CAN NOT be worked on a General RWP.

Entergy Arkansas Nuclear OneRADIOLOGICAL WORK PERMIT***** NOT FOR FIELD WORK *****Consult Posted Copy for Official Radiological Work Permit InformationPage 7 of 7 Task Number:

2RWP No.: 201 61002Rev.: 00Additional InstructionsInstruction 1: Instruction 2: Instruction 3: Instruction 4: Instruction 5:Attachments N/A Unit 1 2016 NRC Exam ADMIN JPM A5 A1JPM-NRC-WHHR (A1/A5)UNIT: 1REV # 1DATE: ______________________________TUOI NUMBER: A1JPM-NRC-WHHR (A1/A5)SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONSTASK: PERFORM WORKING HOUR HISTORY REVIEW AND SELECT ELIGIBLE OPERATORS TO FILLVACANCY DUE TO ILLNESS OF THE ONCOMING ATC WATCHJTA#: ANO-RO-ADMIN-NORM-195/ANO-SRO-ADMIN-NORM-191KA VALUE RO:2.9 SRO: 3.9 KA