Text

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-301 Administrative Topics Outline Form ES-301-1 Facility: ____ANO-1_______________________ Date of Examination: __8/22/2016__

Examination Level: RO SRO Operating Test Number: _2016-1__

Administrative Topic (see Note) Type Describe activity to be performed Code*

A1 Given their work history, select the eligible Conduct of Operations R, N operators to fill vacancy due to illness of KA - 2.1.5, Importance rating 2.9 the on watch ATC.

(RO/SRO)

A2 Perform calculation for makeup to the Conduct of Operations R, D,P Spent Fuel Pool KA- 2.1.20, Importance 4.6 RO/SRO A3 Determine the mechanical and electrical Equipment Control R, N boundary isolations for P-36B Makeup KA - 2.2.13, Importance 4.1 Pump seal leak. (Do not need to drain the RO pump)

A4 Given a survey map and associated RWP, Radiation Control R, N determine the entry requirements to KA - 2.3.7, Importance 3.5 perform a task in the P-34A Decay Heat RO Removal Pump Room.

Not used Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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-301 Administrative Topics Outline Form ES-301-1 Facility: ____ANO-1_______________________ Date of Examination: __8/22/2016__

Examination Level: RO SRO Operating Test Number: __2016-1__

Administrative Topic (see Note) Type Describe activity to be performed Code*

Given their work history, select the eligible A5 R, N operators to fill vacancy due to illness of Conduct of Operations the on watch ATC.

KA - 2.1.5, Importance rating 3.9 (RO/SRO)

Perform calculation for makeup to the A6 R, D,P Spent Fuel Pool Conduct of Operations KA- 2.1.20, Importance 4.6 RO/SRO A7 Review and approve the tagout provided Equipment Control R, N for P-36B Makeup Pump seal leak. If not KA - 2.2.13, Importance 4.3 approved, provide the reasons why.

SRO A8 Provided with the dose history for each Radiation Control R, N individual. Determine which of the 5 are KA - 2.3.4, Importance 3.7 eligible for performing the task during an SRO emergency situation.

A9 R, D Determine the correct PAR and Emergency Plan evacuation/sheltering required for a given KA - 2.4.44, Importance 4.4 GE.

SRO NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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 Exam ADMIN JPM

1 of 6 A1JPM-NRC-WHHR (A1/A5)

UNIT: 1 REV # 1 DATE: ______________________________

TUOI NUMBER: A1JPM-NRC-WHHR (A1/A5)

SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: PERFORM WORKING HOUR HISTORY REVIEW AND SELECT ELIGIBLE OPERATORS TO FILL VACANCY DUE TO ILLNESS OF THE ONCOMING ATC WATCH JTA#: ANO-RO-ADMIN-NORM-195/ANO-SRO-ADMIN-NORM-191 KA VALUE RO: 2.9 SRO: 3.9 KA

REFERENCE:

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

PLANT SITE: SIMULATOR: CLASSROOM: PERFORM POSITION EVALUATED: RO:__________ SRO:___________

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

TESTING METHOD: SIMULATE:_________ PERFORM:___________

APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S): EN-OM-123 EXAMINEE'S NAME:_______________________________ Logon ID: ___________________

EVALUATOR'S NAME:__________________________________________________________________

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

SATISFACTORY:________________ UNSATISFACTORY:_________________

PERFORMANCE CHECKLIST COMMENTS:

____________ Start Time ____________ Stop Time ____________ Total Time SIGNED ________________________________ DATE: _______________________

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

2 of 6 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 Sheet EN-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 oncoming ATC 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 to come 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 covered individuals 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

3 of 6 A1JPM-NRC-WHHR (A1/A5)

INITIATING CUE:

The Shift Manager has directed you to review the given work history of five eligible qualified operators and determine 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 accordance with the Fatigue Management Program. Explain why any operator may be ineligible to fill the vacancy if any cannot.

CRITICAL ELEMENTS (C):

(C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A NOTE: Provide examinee with a copy of the work history or the five eligible candidates.

1. Review working hour history for Determines that Operator A is (C) Operator A. eligible to fill the oncoming ATC watch vacancy without exceeding any _____ _____ _____

working hour limits.

2. Review working hour history for Determines that Operator B is NOT (C) Operator B. eligible 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.

3. Review working hour history for Determines that Operator C is (C) Operator C. eligible to fill the oncoming ATC watch vacancy without exceeding any _____ _____ _____

working hour limits.

4. Review working hour history for Determines that Operator D is NOT (C) Operator D. eligible to fill the oncoming ATC watch vacancy because the operator _____ _____ _____

will not have had a Minimum 34-hour break in any 9-day period working hour limit.

5. Review working hour history for Determines that Operator E is (C) Operator E. eligible to fill the oncoming ATC watch vacancy without exceeding any working hour limits.

NOTE: Inform examinee that JPM is complete.

END

4 of 6 A1JPM-NRC-WHHR (A1/A5)

EXAMINER ANSWER KEY Operator Eligible/Not Eligible Reason (if not eligible)

Operator A Eligible (C)

Operator B Not 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 C Eligible (C)

Operator D Not 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 E Eligible (C)

5 of 6 A1JPM-NRC-WHHR (A1/A5)

EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100% power operations.

The scheduled day-shift oncoming ATC 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.

INITIATING CUE:

The Shift Manager has directed you to review the given work history of five eligible qualified operators and determine 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 accordance with the Fatigue Management Program.

Explain why any operator may be ineligible to fill the vacancy if any cannot.

6 of 6 A1JPM-NRC-WHHR (A1/A5)

EXAMINEES COPY Operator Eligible/Not Eligible Reason (if not eligible)

Operator A Operator B Operator C Operator D Operator E

Unit 1 2016 NRC Exam ADMIN JPM A2

A1JPM-RO-SFPMU (A2/A6) PAGE 1 OF 5 UNIT: 1 REV #: 2 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Perform Spent Fuel Pool Makeup Calculation.

JTA#: ANO1-RO-SFC-NORM-17 KA VALUE RO: 4.6 SRO: 4.6 KA

REFERENCE:

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

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

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): 1104.003, Att. C2 EXAMINEE'S NAME: Logon ID:

EVALUATOR'S NAME:

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

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

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

A1JPM-RO-SFPMU (A2/A6) PAGE 2 OF 5 THE 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 Closed TASK 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 C2 SIMULATOR SETUP:

NA EXAMINER'S NOTES:

A1JPM-RO-SFPMU (A2/A6) PAGE 3 OF 5 INITIATING CUE:

CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup to SFP to raise Boron concentration to 2400 ppm. Determine amount of Boric Acid volume needed. Determine final SFP Volume and Level.

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Determine initial SF Pool Determined volume is 362,843 SAT UNSAT N/A volume from Table 2. gallons from Table 2.

2. Record data. Recorded data. SAT UNSAT N/A (C) 3. Determine feed volume to be Determined feed volume to be SAT UNSAT N/A added to SF Pool. 3684 +/- 2 gallons.

(C) 4. Determine final SF Pool Determined final SF Pool volume SAT UNSAT N/A volume. to be 366,527 +/- 5 gallons.

(C) 5 Determine final SF Pool level Determined final SF Pool level is SAT UNSAT N/A from 0.0 to -0.1 ft.

END

A1JPM-RO-SFPMU (A2/A6) PAGE 4 OF 5 ANSWER KEY 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 Closed INITIATING CUE:

CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup to SFP 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) X X = - 0.1 (165) = - 0.017 feet 962 Final Level = - 0.017

A1JPM-RO-SFPMU (A2/A6) PAGE 5 OF 5 EXAMINEEES COPY 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 Closed INITIATING CUE:

CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup 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. PROCEDURE/WORK PLAN TITLE:

PAGE: 62 of 153 1104.003 CHEMICAL ADDITION CHANGE: 054 ATTACHMENT C2 Page 1 of 7 SF POOL FEED CALCULATIONS TABLE 1 Spent Fuel Pool and Systems Volume/Ft Depth SF Pool SF Pool SF Pool + Cask Pit Refueling Incore SF Pool + Cask Pit + Tilt Pit + Tilt Pit Canal Tank (gal/ft) (gal/ft) (gal/ft) (gal/ft) (gal/ft) (gal/ft) 7,570 8,349 8,845 9,624 11,070 1,141 TABLE 2 Spent Fuel Pool and Systems Volume (gallons)

SF Pool Elev. LI-2004 SF Pool SF Pool SF Pool + Cask Pit Refueling Incore (ft) + Cask Pit + Tilt Pit (1)

+ Tilt Pit (1) Canal Tank 401.5 +1.0 ft 298,120 330,899 343,537 376,316 401.4 +0.9 ft 297,363 330,064 342,653 375,354 During refueling, 401.3 +0.8 ft 296,606 329,229 341,768 374,392 canal level must be 401.2 +0.7 ft 295,849 328,394 340,884 373,429 maintained 401.1 +0.6 ft 295,092 327,559 339,999 372,467 between -0.5 and 401.0 +0.5 ft 294,335 326,725 339,115 371,504 0.0 on the SFP Level indicator 400.9 +0.4 ft 293,578 325,890 338,230 370,542 (LI-2004).

400.8 +0.3 ft 292,821 325,055 337,346 369,580 400.7 +0.2 ft 292,064 324,220 336,461 368,617 400.6 +0.1 ft 291,307 323,385 335,577 367,655 400.5 0.0 ft 290,550 322,550 334,692 366,692 342,800 27,400 400.4 -0.1 ft 289,793 321,715 333,808 365,730 341,693 27,286 400.3 -0.2 ft 289,036 320,880 332,923 364,768 340,586 27,172 400.2 -0.3 ft 288,279 320,045 332,039 363,805 339,479 27,058 400.1 -0.4 ft 287,522 319,210 331,154 362,843 338,372 26,944 400.0 -0.5 ft 286,765 318,376 330,270 361,880 337,265 26,830 399.9 -0.6 ft 286,008 317,541 329,385 360,918 336,158 26,715 399.8 -0.7 ft 285,251 316,706 328,501 359,956 335,051 26,601 399.7 -0.8 ft 284,494 315,871 327,616 358,993 333,944 26,487 399.6 -0.9 ft 283,737 315,036 326,732 358,031 332,837 26,373 399.5 -1.0 ft 282,980 314,201 325,847 357,068 331,730 26,259 399.4 -1.1 ft 282,223 313,366 324,963 356,106 330,623 26,145 399.3 -1.2 ft 281,466 312,531 324,078 355,143 329,516 26,031 399.2 -1.3 ft 280,709 311,696 323,194 354,181 328,409 25,917 399.1 -1.4 ft 279,952 310,861 322,309 353,219 327,302 25,803 399.0 -1.5 ft 279,195 310,026 321,425 352,256 326,195 25,689 (1) Tilt Pit volume from CR-ANO-1-2008-1859-CA2.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 63 of 153 1104.003 CHEMICAL ADDITION CHANGE: 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.

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

Ci = __________ppmB = Initial SF Pool concentration Cf = __________ppmB = Final desired SF Pool concentration Cfd = __________ppmB = Feed concentration to be added to SF Pool 1.3 Determine feed volume to be added to the SF Pool Vfd = ( Vi ) x ( Cf - Ci )

( Cfd - Cf )

Vfd = ( ) x ( - )

( - )

Vfd = __________gal.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 64 of 153 1104.003 CHEMICAL ADDITION CHANGE: 054 ATTACHMENT C2 Page 3 of 7 1.4 Determine final SF Pool volume Final volume = ( Vfd ) + ( Vi )

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 (Vfd) 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.

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

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

Vfd = __________gal.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 62 of 153 1104.003 CHEMICAL ADDITION CHANGE: 054 ATTACHMENT C2 Page 1 of 7 SF POOL FEED CALCULATIONS TABLE 1 Spent Fuel Pool and Systems Volume/Ft Depth SF Pool SF Pool SF Pool + Cask Pit Refueling Incore SF Pool + Cask Pit + Tilt Pit + Tilt Pit Canal Tank (gal/ft) (gal/if) (gal/ft) (gal/ft) (gal/if) (gal/if) 7,570 8,349 8,845 9,624 11,070 1,141 TABLE 2 Soent Fuel Pool an 1 Systems Volume (gallons)

, SFPool Elev. Ll-2004 SF Pool SF Pool SF Pool + Cask Pit Refueling Incore (1) (1)

(ft) + Cask Pit + Tilt Pit + Tilt Pit Canal Tank 401.5 +1.Oft 298,120 330,899 343,537 376,316 401.4 +0.9 ft 297,363 330,064 342,653 375,354 During refueling, 401.3 +O.8ft 296,606 329,229 341,768 374,392 canal level must be 401.2 +0.7 ft 295,849 328,394 340,884 373,429 maintained 401.1 +0.6 ft 295,092 327,559 339,999 372,467 between -0.5 and 401.0 +0.5ft 294335 326725 339115 371,504 0.Oon the SFP Level indicator 400.9 +0.4 ft 293,578 325,890 338,230 370,542 (Ll-2004).

400.8 +0.3 ft 292,821 325,055 337,346 369,580 400.7 +0.2 ft 292,064 324,220 336,461 368,617 400.6 --O.ift 291,307 323,385 335,577 367,655 400.5 /0f\ 290,550 322,550 334,692 366,692 342,800 J27400 400.4 400.3

-0.1 ft

- . ft 289,793 289,036 321,715 320,880 333,808 332,923 365,730 364,768 341,693 340,586 1 27,286 27,172 400.2 -0.3 ft 288,279 320,045 332,039 363 805 400.1 -0.4ft 287,522 319,210 331,154 362,843 338,372 26,944 400.0 -0.5 ft 286,765 318,376 330,270 3 , 0 337.265 26,830 399.9 -0.6 ft 286,008 317,541 329,385 360,918 336,158 26,715 399.8 -0.7 ft 285,251 316,706 328,501 359,956 335,051 26601 399.7 -0.8 ft 284,494 315,871 327,616 358,993 333,944 26,487 399.6 -0.9 ft 283,737 315,036 326,732 358,031 332,837 26,373 399.5 -lOft 282,980 314,201 325,847 357,068 331730 26,259 399.4 -1,1 ft 282,223 313,366 324,963 356,106 330,623 26145 399.3 -1.2 ft 281,466 312,531 324,078 355,143 329,516 26.031 399.2 -1.3ft 280,709 311,696 323,194 354,181 328,409 25,917 399.1 -1.4ft 279,952 310,861 322,309 353,219 399.0 -1.5 ft 279,195 310,026 321,425 352,256 (1) Tilt Pit volume from CR-ANO-1-2008-1859-0A2.

/ I

-3;; ?3C)

O17J

ATTACHMENT C2 Page 2 of 7 cIo Performance of this section requires erification that feed volume will not 2

result in overflowing of the SF? or other attached volumes.

i7 It is necessary to coordinate with Dry Fuel Personnel when makinc up to the Spent Fuel Fool during Ery Fuel Operations.

fSnep 1.0 Is solely performed no determine volume of boric acid at a known concentration to achieve a desired final SFP boron concentration, and generally would not be used.

JSt. 0/ IF it is desired to calculane the volume of boric acrd required to achieve a desired final SF? concenoration, THOM oerform the foilowinc:

Decermine initial SF Pool volume from TABLE 2. Interpolate if necessary.

IF appropriate, THEN add Refueling Canal and moore Tank volume.

V = $Lt$

g 3 al = Initial Volume from TABLE 2 Record the following data:

= ppn.LB = Initial SF Pool concentration

= = Final desired SF Pool concentration Cfd = ppmB = Feed concentration to be added to SF Pool r 21 Determine feed volume to be added to the SF Pool Vfd = 1 V ) x ( C Ci Cfd Vfd x ZØ2c2 - 1300 i00

= 33._Igal.

i PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 64 of 153

/

1104.003 CHEMICAL ADDITION CHANGE: 054 ATTACHMENT C2 Page 3 of 7 Determine final SF Pool volume Final volume = ( Vfd ) i ( Vi ra e =

e Final =i+r gal.

Volume jo*)

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

I Determe flal SC oo e e fro TBZC 2, teroate as recessarj IF final volume greater than table values THEN a second addition will have to be done following a level reduction.

Perform the other sections of this Attachment as required.

IF needed, C fo tbe oie 0: teed \C e CBZ tor S ;a_

IF Refueling Canal or Thcore Tank is connected to SF Cooling System THEN add the amoropriate gal/ft to the SF Pool gal/f:.

Vfd = r)Final level) - (Initial level)] x ( gal/ft Vfd = [(ft.) - K At/A ft.)] x ( gal/ft)

IA Vfd = /// gal.

Unit 1 2016 NRC Exam ADMIN JPM A3

1 of 6 A1JPM-RO-HCRD5 (A3)

UNIT: 1 REV # 2 DATE: ______________________________

TUOI NUMBER: A1JPM-RO-HCRD5 (A3)

SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - EQUIPMENT CONTROL TASK: PERFORM IDENTIFICATION OF COMPONENTS THAT NEED TO BE ISOLATED AND DANGER TAGGED FOR AN INBOARD SEAL LEAK ON MAKEUP PURIFICATION PUMP P-36A JTA#: ANO-RO-ADMIN-NORM-078 KA VALUE RO: 4.1 SRO: 4.3 KA

REFERENCE:

2.2.13 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

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

PLANT SITE: SIMULATOR: CLASSROOM:_ PERFORM_

POSITION EVALUATED: RO: : X SRO:___________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:_____ CLASSROOM: X TESTING METHOD: SIMULATE:_________ PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(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 STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY:________________ UNSATISFACTORY:_________________

PERFORMANCE CHECKLIST COMMENTS:

____________ Start Time ____________ Stop Time ____________ Total Time SIGNED ________________________________ DATE: _______________________

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

2 of 6 A1JPM-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 Sheet EN-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 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.

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 one line drawing for Engineered Safeguard Buses A3 and A4.

3 of 6 A1JPM-RO-HCRD5 (A3)

INITIATING CUE:

The SM/CRS has directed you to identify the components that need to be danger tagged to electrically and mechanically isolate Makeup Purification Pump P-36A to isolate this seal leak. Also provide the component danger tag position required.

CRITICAL ELEMENTS (C):

(C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A NOTE: Provide examinee with a copy of E-Print E-5 and P&ID M-231

1. Reviews controlled documentation Determines that Electrical Circuit (C) to determine source of power to P- Breaker A-306 will need to be 36A to add to the tagout (E-Print E- Breaker Racked Down and added _____ _____ _____

5 or OP-1107.002 Attachment A) to the tagout.

Note: The Candidate may add a Caution Tag to be placed on the MU Purification Pump P-36A Remote Hand Switch.

2. Reviews controlled documentation Determines that P-36A Discharge (C) to determine the P-36A pump Isolation MU-20A will need to be _____ _____ _____

discharge Isolation will need to be Closed and added to the tagout.

added to the tagout (P&ID M-231)

3. Reviews controlled documentation Determines that a P-36A Minimum (C) to determine that a P-36A minimum Recirc Isolation MU 21A or MU-22A recirc isolation will need to be (in series) will need to be Closed and _____ _____ _____

added to the tagout (P&ID M-231) added to the tagout.

4. Reviews controlled documentation Determines that P-36A Suction (C) to determine the P-36A pump Isolation MU-18A will need to be suction Isolation will need to be Closed and added to the tagout. _____ _____ _____

added to the tagout (P&ID M-231)

NOTE: Inform examinee that JPM is complete.

END

4 of 6 A1JPM-RO-HCRD5 (A3)

EXAMINER ANSWER KEY Component # Component Name Component Position A-306 MU Pump P-36A Electrical Circuit Breaker Breaker Racked Down MU-20A MU Pump P-36A Discharge Isolation Valve Closed MU-21A MU Pump P-36A Minimum Recirc Isolation Valve Closed MU-18A MU Pump P-36A Suction Isolation Valve Closed

5 of 6 A1JPM-RO-HCRD5 (A3)

EXAMINEES COPY JPM 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 danger tagged to electrically and mechanically isolate Makeup Purification Pump P-36A to isolate the seal leak.

Also provide the component danger tag position required.

6 of 6 A1JPM-RO-HCRD5 (A3)

EXAMINEES COPY Component # Component Name Danger 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 5 A1JPM-RO-ADMIN-RWP3 (A4)

ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 1 REV # 1 DATE: ______8/4/2016_________

JPM ID: A1JPM-RO-ADMIN-RWP3 (A4)

SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - Radiation Control TASK: Ability to comply with radiation work permit requirements JTA#: ANO1-RO-DHR-NORM-2 KA VALUE RO: 3.5 SRO: 3.6 KA

REFERENCE:

2.3.7 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR:_________ CLASSROOM: X SUGGESTED 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 MINUTES REFERENCE(S): RWP 2016-1002, P-34A survey map, EXAMINEE'S NAME:_______________________________ Logon ID: ___________________

EVALUATOR'S NAME:__________________________________________________________________

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

SATISFACTORY:________________ UNSATISFACTORY:_________________

PERFORMANCE CHECKLIST COMMENTS:

____________ Start Time ____________ Stop Time ____________ Total Time SIGNED ________________________________ DATE: _______________________

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

Page 2 of 5 A1JPM-RO-ADMIN-RWP3 (A4)

ADMINISTRATIVE JOB PERFORMANCE MEASURE THE 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.

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 5 A1JPM-RO-ADMIN-RWP3 (A4)

ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING 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 the required protective clothing for entry.

(C) PERFORMANCE STEP PERFORMANCE STANDARD SAT UNSAT N/A

1. Reviews P-34A Pump survey Examinee determined dose rate of map to determine dose rates in 115 mR/hr at the inboard pump seal.

the vicinity of the inboard pump seal. _____ _____ _____

(C) 2. Determines stay time based on Examinee determined stay time the given dose in the pump based on RWP limits of 50 mrem inboard seal area not to would allow him to stay at the pump exceed the RWP limits. inboard seal area for 26.1 minutes

(-0.1 minutes).

50 mR X 60 min = 26.1 minutes 115 mR/hr 1 hr (C) 3. Reviews P-34A Pump survey Examinee identified the map for contamination smear contamination levels are > 1000 data to determine the dpm/100 cm 2 but less than 100,000 _____ _____ _____

2 protective clothing (PC) dpm/100 cm ; therefore, a single set requirements for this task. of Anti-Cs is required to enter into the P-34A pump room.

END

Page 4 of 5 A1JPM-RO-ADMIN-RWP3 (A4)

ADMINISTRATIVE JOB PERFORMANCE MEASURE ANSWER KEY JPM INITIAL TASK 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 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 room survey map.

Using the above information, determine:

Your remaining available dose for the year based on ANO administrative 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 5 A1JPM-RO-ADMIN-RWP3 (A4)

ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Decay heat Removal Pump P-34A has indications of a leak on the pump inboard seal.

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 room survey map.

Using the above information, determine:

Your remaining available dose for the year based on ANO administrative limits.

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

Your Protective Clothing requirements:

Survey: ANO-1606-0004 ANO Thursday, June 30, 2016 Template: 1a1-05_jpg Page 1 of 1 Details Smear Data (DPM/100cm2) 1 20000 DPM Unit: 1 2 25000 DPM Building: RAB 3 30000 DPM Elevation: 317 4 35000 DPM Room: 13 RxPwr: 100 LAS Data (ccpm/LAS)

Template: 1a1-05_jpg 1 6000 ccpm/LAS Frequency: 10CFR50.75G Decomm 2 <100 ccpm/LAS Survey Date: 08/22/2016 15:58 3 <100 ccpm/LAS Status: In-Progress 4 <100 ccpm/LAS Rwp: 20161001 B/G to Alpha Ratio Hydro Inj Rate: NA Surveyed By: Harrell, John Alpha Data (DPM/100cm2) Badge: 20970 Reviewed By:

DPM Notes:

Instruments Used Instrument: LM-177 CHP-CR-148 Cal Due Date: 7/31/2016 SrcChk Date: 6/29/2016 DC & Bkg: NA NA MDA: NA Instrument: 9-3 CHP-DR-331 Cal Due Date: 12/31/2016 SrcChk Date: 6/29/2016 DC & Bkg: NA NA MDA: NA

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

- - - - NOT FOR FIELD WORK *****

Consult Posted Copy for Official Radiological Work Permit Information RWP

Title:

OPERATIONS ACTIVITIES UNIT-1 RWP No.:

20161002 Rev. 00 Comments:

20161002*

RWP Type: SPECIFIC RWP Status: Begin Date: Close On Date:

ACTIVE 1/1/2016 12/31/2016 Prepared By: NICKELS, THOMAS W Job Supervisor: Jeff Horton Estimated Dose: Estimated Hours: Actual Dose: Actual Hours:

528 mrem 14,400.00 293 mrem 9,041.99 Locations Buildings Elevations Rooms LOW LEVEL RADWASTE BUILDING 354 NON-LOCKED HIGH RADIATION AREA OLD RADWASTE BUILDING 354 NON-LOCKED HIGH RADIATION AREA OUTSIDE CONTROLLED ACCESS ALL OUTSIDE CONTROLLED ACCESS UNIT 1 AUXILIARY BUILDING ALL NON-LOCKED HIGH RADIATION AREA Radiological Conditions Description Value Unit Smear data is in dpm/100 cm2 unless otherwise noted. <1K - 40K DPM/100CM2 General area gamma dose rates are in mrem/hour unless otherwise noted. 0.1 - 200 MILLIREM/HOUR Tasks Task Description Status 1 OPERATIONS ACTIVITIES UNIT-1 Active 2 OPERATIONS TRAINEE ACTIVITIES UNIT-1 Active Requirements Requirement Groups Requirement Descriptions N/A Additional Instructions Instruction 1:

Instruction 2:

Instruction 3:

Approvals Approver Title Name Date ALARA REVIEW STELL, RANDALL E 12/22/2015 RWP PREPARER STELL, RANDALL E 12/22/2015 RP SUPERVISOR LYNCH, BERT A 12/22/2015 Attachments N/A Page 1 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

- - - - NOT FOR FIELD WORK *****

Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20161002 Task Number: 1 Rev.: 00 Task

Description:

OPERATIONS ACTIVITIES UNIT-1 Task Status: Active Estimate Dose: 420.00 Estimate Hours: 12,000.00 Hot Particle: Hi-Contamination:

Hi-Rad: Yes No Locked Hi-Rad: No No Alarm Settings Dose Alarm (mrem) 50.00 Dose Rate (mrem/hr) 150.00 Requirements Requirement Groups Requirement Descriptions Contamination Control All 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 Radiologically Controlled Area.

IF the RCA is a satellite RCA and a "Contamination Area" is entered, THEN the radworker should perform a whole body frisk and proceed to the nearest whole body contamination monitor (PCM-1B or equivalent).

IF the RCA is a satellite RCA with no whole body contamination monitor available, THEN the radworker should: a) perform a hand and foot frisk. b) IF the frisk indicates contamination is present, THEN contact RP. c) IF the frisk DOES NOT indicate the presence of contamination, THEN proceed to the nearest whole body contamination monitor and gamma sensitive monitor.

Notify RP prior to exposing a contaminated surface or opening a contaminated system.

Obey the monitoring instructions posted at the RCA exit point Upon exit of an RCA, whole body monitoring is required utilizing a whole body contamination monitor (PCM-1B or equivalent). A whole body gamma monitor must also be cleared (PM-7 or equivalent).

Upon exiting areas posted as "Contamination Area", perform a hand and foot frisk at the designated 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. These activities include working with contaminated components overhead, or having a body position that presents the potential for facial contamination.

With RP approval, reaching across a contamination boundary is permitted using surgeon's gloves OR cotton liners with rubber gloves. When reaching into the area of higher contamination, gloves must be removed when hands are returned to the lower level side of the boundary.

Dosimetry Requirements FOR WORK IN HIGH RADIATION AREAS - If your work conditions are in OR will cause hearing 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 RP.

If an EAD dose rate alarm occurs: 1) Secure Work. 2) Back out of the immediate area until the alarm clears. 3) Notify others in your work crew. 4) Immediately notify RP for further instructions.

Periodically check your EAD. This check should be performed more frequently in areas where your ability to hear is diminished.

Whole body DLR and EAD required for entry.

Additional Instructions Page 2 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

- - - - NOT FOR FIELD WORK *****

Consult Posted Copy for Official Radiological Work Permit Information Instruction 1:

RWP No.: 20161002 Task Number: 1 Rev.: 00 Requirements Requirement Groups Requirement Descriptions Engineering Controls When venting or draining, monitor the rate of system drain to ensure the rate of drain does NOT exceed the capacity of the floor drain.

Exposure Reduction Use Low Dose Waiting Areas whenever possible to minimize exposure.

Protective Requirements All 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 Coverage A "Cat 3 Advanced Radworker" may enter posted High Radiation Areas using a gamma sensitive RP instrument to monitor dose rates. (NOTE: An EAD is NOT an appropriate survey instrument. LHRA/ VHRA entry requires continuous RP coverage.).

Contact RP Supervisor or RP tech prior to entry to verify adequate RP coverage and contamination controls for your work activity. RP is not required to be notified for entries to the 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 electronic alarming 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 radiological conditions. For example venting/draining radioactive systems, performing degas or decay heat/shutdown cooling operations, or other non routine system functions.

Radiological Conditions Contact Radwaste Personnel for radiological conditions in the Radwaste Buildings.

Radiological conditions should be reviewed to ensure awareness of conditions in your work area. This information can be obtained from either a Status Board or RP personnel.

Respiratory Protection Based on historical and current data, the airborne radioactivity is less than 30 percent of a DAC. Respiratory protection is not required unless otherwise directed by RP Supervision.

Special Radiological Requirements Critical Step - Prior to movement of irradiated fuel or other irradiated materials, notify RP Shift 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 the adjacent 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 changes in pressure will not cause a spill. 2) Conduct a walkdown (pre-transfer) to ensure that hose connections and leak integrity is satisfactory. 3) Construct a berm sufficient to contain the material being transferred.

Additional Requirement: -Critical Step - Ensure ARM is installed on the bridge and is operation prior to performing any fuel movements. The ARM alarm set point is determined by RP supervision.

Stop Work Criteria Critical Step - Indications either from local samples or remote indication (CAM) of airborne radioactivity in quantities in excess of 30 percent of a DAC.

Critical Step - Loss of control of radioactive material such that loose surface contamination outside of any protective measures is greater than area postings Critical Step - Radiation dose rates in the immediate area are greater than the EAD dose rate alarm set point.

CRitical Step - Work involving alpha contamination greater than or equal to 100 dpm/100cm2 CAN NOT be worked on a General RWP.

Page 3 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

- - - - NOT FOR FIELD WORK *****

Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20161002 Task Number: 1 Rev.: 00 Additional Instructions Instruction 1:

Instruction 2:

Instruction 3:

Instruction 4:

Instruction 5:

Attachments N/A Page 4 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

- - - - NOT FOR FIELD WORK *****

Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20161002 Task Number: 2 Rev.: 00 Task

Description:

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

Hi-Rad: Yes No Locked Hi-Rad: No No Alarm Settings Dose Alarm (mrem) 10.00 Dose Rate (mrem/hr) 100.00 Requirements Requirement Groups Requirement Descriptions Contamination Control All 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 Radiologically Controlled Area.