ML020940829

ANO2-2-2002-Draft RO Admin Outline & Questions

ML020940829
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/17/2002
From:	NRC Region 4
To:	Entergy Operations
References
-RFPFR, 50-368/02301
Download: ML020940829 (28)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO-2 Date of Examination: February 11, 2002 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Topic/Subject Describe method of evaluation:

Description 1. ONE Administrative JPM, OR

2. TWO Administrative Questions A.1 Conduct Of Operations Ability to execute procedure steps.

2.1.20 Old Question (determine adequate HPSI flow) (OPEN)

Conduct Of Operations Knowledge of operator responsibilities during all modes of operation.

2.1.2 New Question (Manual safety system actuation) (CLOSED)

Conduct Of Operations Ability to perform specific and integrated plant procedures during all 2.1.23 modes of operation.

New Admin JPM (1015.008 time to boil LOSDC calculation)

A.2 Equipment Control Knowledge of the process for making configuration changes.

2.2.13 Modified Admin JPM (Identify errors on Clearance)

A.3 Radiation Controls Ability to control radiation releases.

2.3.11 Modified Old Question (Isolate letdown with failed fuel determination AOP) (OPEN)

Radiation Controls Knowledge of radiation exposure limits and contamination control, 2.3.4 including permissible levels in excess of those authorized.

Modified Old Question (authorization to exceed admin Radiation limits. Includes calculation and determination) (OPEN)

A.4 Emergency Plan Knowledge of emergency communication systems and techniques.

2.4.43 Old Question (Time limits to notify ADH and NRC) (OPEN)

Emergency Plan Knowledge of the Emergency Plan.

2.4.29 Modified Old Question ( Identify methods to determine failed fuel)

(OPEN)

NUREG-1021, Rev. 8, Supplement 1

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 4.3 SRO: 4.2 KA

REFERENCE:

2.1.20

REFERENCE:

EOP 2202.010, REV 4, EXHIBIT 2 RO OPERATING ADMIN TEST 1 SUBJECT A.1 QUESTION 1:

Is HPSI flow acceptable for the given conditions?

• Mode 3

• Post trip from full power

• RCS leak in progress

• Electrical Bus 2A4 lockout

• RCS pressure 1100 psia.

• HPSI flow 400 gpm.

• 2CV-5015-1, HPSI injection MOV, will not move from 10% OPEN position.

• 2P89C aligned to green bus.

• HPSI termination criteria is NOT met.

ANSWER:

NO, since one HPSI pump is running, ALL injection MOVs NOT open and HPSI termination Criteria is NOT met.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY RO OPERATING ADMIN TEST 1 SUBJECT A.1 TYPE: OPEN REFERENCE QUESTION 1:

Is HPSI flow acceptable for the given conditions?

• Mode 3

• Post trip from full power

• RCS leak in progress

• Electrical Bus 2A4 lockout

• RCS pressure 1100 psia.

• HPSI flow 400 gpm.

• 2CV-5015-1, HPSI injection MOV, will not move from 10% OPEN position.

• 2P89C aligned to green bus.

• HPSI termination criteria is NOT met.

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: CLOSED REFERENCE KA VALUE RO: 3.0 SRO: 4.0 KA

REFERENCE:

2.1.2

REFERENCE:

EOP 2202.003, REV 005-01-0, SECTION 3 STEP 20 AND 2202.010 ATTACHMENT 20. STM 2-08 REV 7, SECTION 5.2.2 RO OPERATING ADMIN TEST 1 SUBJECT A.1 QUESTION 2:

After a Large Break LOCA, the following conditions are observed:

• RCS pressure is 350 psia

• Pressurizer is empty

• All ESF pumps operating with all their recirculation valves open

• Containment pressure is 24 psia

• RWT outlet valves are open

• Containment Sump outlet valves outside containment are closed

• Containment Flood Level reads 7 feet

• RWT level is 5.4% and dropping What actions are required and describe any changes to safety system components?

ANSWER:

Manually initiate Recirc Actuation Signal (RAS) and verify RAS component actuation.

Automatic component actuations include (Valve numbers not required for full credit):

• Containment Sump outlet valves open (2CV-5647-1 & 2CV5647-1, 2CV-5648-2 &

2CV-5650-2)

• RWT outlet valves close (2CV-5630-1 & 2CV5631-2)

• LPSI pumps stop (2P-60A & 2P-60B)

• Closes the ESF pumps minimum recirculation isolations (2CV-5123-1 & 2CV-5124-1 &

2CV-5673-1 & 2CV-5672-1 & 2CV5626-1 & 2CV5628-1 & 2CV5627-1, 2CV-5628-2)

• Opens the Service Water isolation valves to the SDC Heat Exchangers (2CV-1453-1 &

2CV1456-2)

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY RO OPERATING ADMIN TEST 1 SUBJECT A.1 TYPE: CLOSED REFERENCE QUESTION 2:

After a Large Break LOCA, the following conditions are observed:

• RCS pressure is 350 psia

• Pressurizer is empty

• All ESF pumps operating with all their recirculation valves open

• Containment pressure is 24 psia

• RWT outlet valves are open

• Containment Sump outlet valves outside containment are closed

• Containment Flood Level reads 7 feet

• RWT level is 5.4% and dropping What actions are required and describe any changes to safety system components?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 2.7 SRO: 3.2 KA

REFERENCE:

2.3.11

REFERENCE:

AOP 2203.020, REVISION 007-05-0, STEP 8.F RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 1:

Given the following:

• 100% full power

• 2RITS-4806A (Letdown Radiation Gross Activity Monitor) reads 4.3E5 CPM and 2RITS-4806B (Letdown Radiation Iodine-131 Activity Monitor) reads 3.1E5 CPM.

• Auxiliary building general area radiation is 300 mr/hr.

• Letdown has been isolated using 2CV-4820-2.

What action should be performed to directly prevent RCS fluid from leaving the Containment Building?

ANSWER:

With SM concurrence:

• Isolate Reactor Coolant Pump controlled bleedoff to VCT.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 1:

Given the following:

• 100% full power

• 2RITS-4806A (Letdown Radiation Gross Activity Monitor) reads 4.3E5 CPM and 2RITS-4806B (Letdown Radiation Iodine-131 Activity Monitor) reads 3.1E5 CPM.

• Auxiliary building general area radiation is 300 mr/hr.

• Letdown has been isolated using 2CV-4820-2.

What action should be performed to directly prevent RCS fluid from leaving the Containment Building?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 2.5 SRO: 3.1 KA

REFERENCE:

2.

3.4 REFERENCES

1012.021, Exposure Limits and Controls, Rev 004-02-0, Steps 4.5, 4.7, 4.19, 6.2.2 & 6.3.1.B.1 RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 2:

A radiation worker has been assigned the task of breaking Incore Flanges. The general area dose rate on the Reactor Vessel Head area work platform is 1 R/Hr gamma radiation. The time needed for this worker to break the incore flanges is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The year to date dose for the radiation worker is:

• Deep Dose Equivalent (DDE) = 0.2 Rem

• Committed Effective Dose Equivalent (CEDE) = 0.3 Rem

• Shallow Dose Equivalent (SDE) = 0.8 Rem

• Eye Dose Equivalent (LDE) = 0.6 Rem What would be the radiation workers Total Effective Dose Equivalent (TEDE) after completion of this task and who is required to authorize any dose control level extensions for this task?

ANSWER:

TEDE = DDE + CEDE TEDE = 0.2 Rem + 0.3 Rem Before task TEDE = 0.5 Rem 1 R/Hr dose rate for 2 Hour task = 2 Rem TEDE = 2 Rem + 0.5 Rem After task TEDE = 2.5 Rem Admin TEDE limit for radiation worker is 2 Rem/yr.

To exceed 2.0 Rem for the year requires designated Radiation Protection Manager authorization for up to 3 Rem.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 2:

A radiation worker has been assigned the task of breaking Incore Flanges. The general area dose rate on the Reactor Vessel Head area work platform is 1 R/Hr gamma radiation. The time needed for this worker to break the incore flanges is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The year to date dose for the radiation worker is:

• Deep Dose Equivalent (DDE) = 0.2 Rem

• Committed Effective Dose Equivalent (CEDE) = 0.3 Rem

• Shallow Dose Equivalent (SDE) = 0.8 Rem

• Eye Dose Equivalent (LDE) = 0.6 Rem What would be the radiation workers Total Effective Dose Equivalent (TEDE) after completion of this task and who is required to authorize any dose control level extensions for this task?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: __2.8__ SRO: __3.5__ KA

REFERENCE:

_2.4.43_

REFERENCE:

OP 1903.011 REVISION 026-00-0, INITIAL NOTIFICATION CHECKLIST (1903.011BB) AND ATTACHMENT 10, TIME REQUIREMENTS RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 1 After the declaration of a Notification of Unusual Event (NUE), how much time is allowed to notify the:

• Arkansas Department of Health (ADH) and

• Nuclear Regulatory Commission (NRC)?

ANSWER:

• Initial Notification Message (1905.011Y) to ADH within 15 minutes

• To NRC immediately following ADH and not to exceed one (1) hour from declaration.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 1 After the declaration of a Notification of Unusual Event (NUE), how much time is allowed to notify the:

• Arkansas Department of Health (ADH) and

• Nuclear Regulatory Commission (NRC)?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 2.6 SRO: 4.0 KA

REFERENCE:

2.4.29

REFERENCES:

1903.010, EAL Classification, Rev 036-03-0, Step 4.16.1.B.

1903.010, EAL Classification, Rev 036-03-0, Attachments 6 and 8 1905.003, Post Accident Sampling of RCS, Rev 008-00-0, Steps 5.1.3, 5.1.4 & Att. 2 1903.011, Emergency Response/Notifications, Rev 026-00-0, Attachment 8 RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 2:

Given the following plant conditions:

• Plant operating in Mode 3.

• Manual reactor trip initiated ten (10) minutes ago due to B RCP seal failure.

• RCS leakage calculated at 62 gpm inside Containment.

• Post SPTA brief in progress.

The Shift Manager states during the brief that an Alert EAL has been declared and the conditions for upgrade to Site Area Emergency (SAE) include greater than 1% fuel cladding failure.

State two methods that could be used to determine when 1% fuel cladding failure is exceeded.

ANSWER:

(any 2 of the following for full credit)

1. Nuclear Chemistry analysis of RCS Sample.

2. Radiation Levels at 2TCD-19 (RCS Sample Tubing in hallway behind door 230)

(1903.010 Attachment 8 and 1905.003)

3. Containment Radiation Levels above SAE levels (1903.010 Attachment 6)

4. Engineering assessment of core damage. (1903.011 Attachment 8)

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 2:

Given the following plant conditions:

• Plant operating in Mode 3.

• Manual reactor trip initiated ten (10) minutes ago due to B RCP seal failure.

• RCS leakage calculated at 62 gpm inside Containment.

• Post SPTA brief in progress.

The Shift Manager states during the brief that an Alert EAL has been declared and the conditions for upgrade to Site Area Emergency (SAE) include greater than 1% fuel cladding failure.

State two methods that could be used to determine when 1% fuel cladding failure is exceeded.

ANO-2-JPM-NRC-TTBC PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Conduct of Operations (A.1)

TASK: Calculate Time to Boil using computer program JTA#:

KA VALUE RO: 3.9 SRO: 4.0 KA

REFERENCE:

2.1.23 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: Perform Classroom: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): 1015.008 Attachment E, Rev 017-02-0 EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

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

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

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

ANO-2-JPM-NRC-TTBC PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

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

JPM INITIAL TASK CONDITIONS:

Plant shutdown for repair of Steam Generator Tube Leak. Making preparations for draining the RCS to 24 inches above the bottom of the hotleg to install nozzle dams. PZR level is 40% and open to atmosphere.

Time after shutdown = 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; one (1) PZR code safety valve is removed; PZR manway is installed; ECCS vent valves are de-energized OPEN; NO RCP seal work inprogress; NO RCS cold leg openings; RCS Temperature is 105°F.

TASK STANDARD:

Time to boil calculation has been calculated using the computer program.

TASK PERFORMANCE AIDS:

1015.008 attachment E, Computer operational with the current revision of LOSDC2 installed (SP-94-C-0001, Rev. 10)., set up shortcut to program on the desktop.

SIMULATOR SETUP:

NA EXAMINER'S NOTES:

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

The SM/CRS directs, "Using the computer program LOSDC2, calculate a projected time to boil 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> from now with RCS level 24 above bottom of Hot Leg, using current temperature and pressure.

CRITICAL ELEMENTS (C): 19 PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Start the LOSDC2 program. (it Double click on the shortcut to N/A SAT UNSAT is permissible to start the start the LOSDC2 program program using windows file OR manager or double click )

Go to file manager and start LOSDC2 program.

2. Verify that program is current. At question prompt, Is this the N/A SAT UNSAT current version of program?

(version SP-94-C-0001-01, Rev.

10) Type Y and hit ENTER.

3. Input that RCS pressure At Question prompt, Pressure N/A SAT UNSAT boundary is closed. Boundary Closed? , type N and hit ENTER.

4. Input that Reactor Head is not At Question prompt, Reactor N/A SAT UNSAT removed. Head removed? , type N and hit ENTER.

5. Input that ECCS valves are At Question prompt, ECCS N/A SAT UNSAT open. Valve Open? , type Y and hit ENTER.

6. Input that One PZR code safety At Question prompt, Number of N/A SAT UNSAT valve is removed. Code Safety Valves removed, 0,1,2? , type 1 and hit ENTER.

7. Input that the pressurizer At Question prompt, Pressurizer N/A SAT UNSAT manway is not removed. manway removed? , type N and hit ENTER.

8. Input that the RCS cold legs are At Question prompt, Cold Leg N/A SAT UNSAT not open. hole? , type N and hit ENTER.

9. Input that RCP seal work is not At Question prompt, RCP seal N/A SAT UNSAT in progress. work in progress? , type N and hit ENTER.

10. Input that A SG cold leg At Question prompt, A SG cold N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

11. Input that B SG cold leg At Question prompt, B SG cold N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

ANO-2-JPM-NRC-TTBC PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

12. Input that A SG hot leg At Question prompt, A SG hot N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

13. Input that B SG hot leg At Question prompt, B SG hot N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

14. Input that time after shutdown is At Question prompt, Enter time N/A SAT UNSAT 3 days 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. (note this is after shutdown? , type 3,7.5 the 3 days time after shutdown and hit ENTER.

given in initial conditions plus the 7.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> given in the initiating cue.)

15. Input that water level input is to At Question prompt, Enter water N/A SAT UNSAT be in inches above bottom of level above the bottom of the hot hot leg. leg? , type 1 and hit ENTER.

16. Input that projected water level At Question prompt, water level N/A SAT UNSAT is 24 above the bottom of the projected? , type 24 and hit hotleg. ENTER.

17. Input that current RCS At Question prompt, Current N/A SAT UNSAT temperature is 105°F. Coolant temperature? , type 105 and hit ENTER.

18. Input that this is not a refueling At Question prompt, Has core N/A SAT UNSAT outage and that core reload is shuffle/reload been completed? ,

not to be done. type N and hit ENTER.

C 19. Record / Report that Time to Report that the Time to boil the N/A SAT UNSAT Boil the RCS is 19 minutes 19 RCS is 19 minutes and 19 seconds. Acceptable value 3 2 seconds.

minutes EXAMINERS NOTE:

Prompt the Examinee that the file should not be printed but, may be saved and then reviewed. The file should be saved as Their First Name.dat. (Examinee will then open the file via file manager). This file should then be deleted after the JPM is over.

END

ANO-2-JPM-NRC-TTBC PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Given the following Plant conditions:

• Plant shutdown for repair of Steam Generator Tube Leak.

• Making preparations for draining the RCS to 24 inches above the bottom of the hot leg to install nozzle dams.

• PZR level is 40% and open to atmosphere.

• Time after shutdown = 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;

• One (1) PZR code safety valve is removed;

• PZR manway is installed;

• ECCS vent valves are de-energized OPEN;

• NO RCP seal work inprogress;

• NO RCS cold leg openings;

• RCS Temperature is 105°F.

INITIATING CUE:

The SM/CRS directs, "Using the computer program LOSDC2, calculate a projected time to boil 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> from now with RCS level 24 above bottom of Hot Leg, using current temperature and pressure.

ANO-2-JPM-NRC-HCARD1 PAGE 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Equipment Control (A.2)

TASK: Review Clearance Authorization Form for errors JTA#:

KA VALUE RO: 3.6 SRO: 3.8 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: Perform Classroom: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP 1000.027 Rev. 26-03-0 Sections 6.0 and Attachment A EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

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

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

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

ANO-2-JPM-NRC-HCARD1 PAGE 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

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

JPM INITIAL TASK CONDITIONS: Plant is at 100% power. D Condensate Pump is being tagged out to repack the pump and the Computerized Tagging System is not available.

TASK STANDARD: Identify at least two of three errors on the Clearance Installation Authorization Form. Errors include: (1) sequence wrong, should open breaker before closing pump discharge valve and suction valve; (2) no NO TAG entry made requiring review of the Special Instructions; (3) Preparer did not sign form.

TASK PERFORMANCE AIDS: OP 1000.027 Rev 026-03-0, P&ID M2204, Sheet 1, E2004 Sheet 1

ANO-2-JPM-NRC-HCARD1 PAGE 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, The Computer Tagging System is out of service, Perform a Clearance Review of the Manual Clearance for D Condensate pump (2P-2D) and identify at least two of three errors made by the Clearance Preparer.

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

EXAMINERS NOTE:

Examinee may be able to identify two of three errors without reviewing 1000.027, Protective Tagging Control procedure.

1. Review 1000.027, Protective Reviewed at least the following N/A SAT UNSAT Tagging Procedure, Section 6 and sections of 1000.027, Hold and Attachment A Caution Card Control Procedure.

- Section 6 - Clearance Reviewer

- Attachment A - General Tagging Requirements

2. Verified that the Tag number, Reviewed the first section of the N/A SAT UNSAT Clearance number, and purpose for clearance Installation Authorization the clearance were correct. Form and determined that the Tag number, Clearance number, and purpose for the clearance were correct.

C 3. Identify that Prepared By Identified that no name or signature N/A SAT UNSAT signature is not filled in. had been provided in the Prepared By blank.

C 4. Identify that there was not a NO Identified that a Special Instructions N/A SAT UNSAT TAG entry made that required entry was made but a NO TAG review of the Special Instructions. entry was not made that required a review of the special instructions.

5. Verify boundary isolations Reviewed appropriate P&IDs and N/A SAT UNSAT selected provide adequate plant Electrical prints to verify boundary and personnel safety for the work isolations selected provide activity listed. adequate plant and personnel safety for the work activity listed.

ANO-2-JPM-NRC-HCARD1 PAGE 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

C 6. Identify sequence for installing the Reviewed sequence for Clearance N/A SAT UNSAT Hold Cards is incorrect. installation on Clearance Installation Authorization Form. Identified that the Handswitch and the Breaker should have been placed in the Pull-to-Lock and Racked Down position respectively before the pump was isolated by the discharge and suction valves to prevent pump damage.

INSTRUCTORS NOTE If examinee asks about the Danger Tags, they have been printed exactly as the information appears on Clearance Installation Authorization Form.

END

ANO-2-JPM-NRC-HCARD1 PAGE 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS: Plant is at 100% power. D Condensate Pump is being tagged out to repack the pump and the Computerized Tagging System is not available.

INITIATING CUE:

The SM/CRS directs, The Computer Tagging System is out of service, perform a Clearance Review of the Manual Clearance for D Condensate pump (2P-2D) and identify at least two of three errors made by the Clearance Preparer.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO-2 Date of Examination: February 11, 2002 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Topic/Subject Describe method of evaluation:

Description 1. ONE Administrative JPM, OR

2. TWO Administrative Questions A.1 Conduct Of Operations Ability to execute procedure steps.

2.1.20 Old Question (determine adequate HPSI flow) (OPEN)

Conduct Of Operations Knowledge of operator responsibilities during all modes of operation.

2.1.2 New Question (Manual safety system actuation) (CLOSED)

Conduct Of Operations Ability to perform specific and integrated plant procedures during all 2.1.23 modes of operation.

New Admin JPM (1015.008 time to boil LOSDC calculation)

A.2 Equipment Control Knowledge of the process for making configuration changes.

2.2.13 Modified Admin JPM (Identify errors on Clearance)

A.3 Radiation Controls Ability to control radiation releases.

2.3.11 Modified Old Question (Isolate letdown with failed fuel determination AOP) (OPEN)

Radiation Controls Knowledge of radiation exposure limits and contamination control, 2.3.4 including permissible levels in excess of those authorized.

Modified Old Question (authorization to exceed admin Radiation limits. Includes calculation and determination) (OPEN)

A.4 Emergency Plan Knowledge of emergency communication systems and techniques.

2.4.43 Old Question (Time limits to notify ADH and NRC) (OPEN)

Emergency Plan Knowledge of the Emergency Plan.

2.4.29 Modified Old Question ( Identify methods to determine failed fuel)

(OPEN)

NUREG-1021, Rev. 8, Supplement 1

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 4.3 SRO: 4.2 KA

REFERENCE:

2.1.20

REFERENCE:

EOP 2202.010, REV 4, EXHIBIT 2 RO OPERATING ADMIN TEST 1 SUBJECT A.1 QUESTION 1:

Is HPSI flow acceptable for the given conditions?

• Mode 3

• Post trip from full power

• RCS leak in progress

• Electrical Bus 2A4 lockout

• RCS pressure 1100 psia.

• HPSI flow 400 gpm.

• 2CV-5015-1, HPSI injection MOV, will not move from 10% OPEN position.

• 2P89C aligned to green bus.

• HPSI termination criteria is NOT met.

ANSWER:

NO, since one HPSI pump is running, ALL injection MOVs NOT open and HPSI termination Criteria is NOT met.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY RO OPERATING ADMIN TEST 1 SUBJECT A.1 TYPE: OPEN REFERENCE QUESTION 1:

Is HPSI flow acceptable for the given conditions?

• Mode 3

• Post trip from full power

• RCS leak in progress

• Electrical Bus 2A4 lockout

• RCS pressure 1100 psia.

• HPSI flow 400 gpm.

• 2CV-5015-1, HPSI injection MOV, will not move from 10% OPEN position.

• 2P89C aligned to green bus.

• HPSI termination criteria is NOT met.

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: CLOSED REFERENCE KA VALUE RO: 3.0 SRO: 4.0 KA

REFERENCE:

2.1.2

REFERENCE:

EOP 2202.003, REV 005-01-0, SECTION 3 STEP 20 AND 2202.010 ATTACHMENT 20. STM 2-08 REV 7, SECTION 5.2.2 RO OPERATING ADMIN TEST 1 SUBJECT A.1 QUESTION 2:

After a Large Break LOCA, the following conditions are observed:

• RCS pressure is 350 psia

• Pressurizer is empty

• All ESF pumps operating with all their recirculation valves open

• Containment pressure is 24 psia

• RWT outlet valves are open

• Containment Sump outlet valves outside containment are closed

• Containment Flood Level reads 7 feet

• RWT level is 5.4% and dropping What actions are required and describe any changes to safety system components?

ANSWER:

Manually initiate Recirc Actuation Signal (RAS) and verify RAS component actuation.

Automatic component actuations include (Valve numbers not required for full credit):

• Containment Sump outlet valves open (2CV-5647-1 & 2CV5647-1, 2CV-5648-2 &

2CV-5650-2)

• RWT outlet valves close (2CV-5630-1 & 2CV5631-2)

• LPSI pumps stop (2P-60A & 2P-60B)

• Closes the ESF pumps minimum recirculation isolations (2CV-5123-1 & 2CV-5124-1 &

2CV-5673-1 & 2CV-5672-1 & 2CV5626-1 & 2CV5628-1 & 2CV5627-1, 2CV-5628-2)

• Opens the Service Water isolation valves to the SDC Heat Exchangers (2CV-1453-1 &

2CV1456-2)

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY RO OPERATING ADMIN TEST 1 SUBJECT A.1 TYPE: CLOSED REFERENCE QUESTION 2:

After a Large Break LOCA, the following conditions are observed:

• RCS pressure is 350 psia

• Pressurizer is empty

• All ESF pumps operating with all their recirculation valves open

• Containment pressure is 24 psia

• RWT outlet valves are open

• Containment Sump outlet valves outside containment are closed

• Containment Flood Level reads 7 feet

• RWT level is 5.4% and dropping What actions are required and describe any changes to safety system components?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 2.7 SRO: 3.2 KA

REFERENCE:

2.3.11

REFERENCE:

AOP 2203.020, REVISION 007-05-0, STEP 8.F RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 1:

Given the following:

• 100% full power

• 2RITS-4806A (Letdown Radiation Gross Activity Monitor) reads 4.3E5 CPM and 2RITS-4806B (Letdown Radiation Iodine-131 Activity Monitor) reads 3.1E5 CPM.

• Auxiliary building general area radiation is 300 mr/hr.

• Letdown has been isolated using 2CV-4820-2.

What action should be performed to directly prevent RCS fluid from leaving the Containment Building?

ANSWER:

With SM concurrence:

• Isolate Reactor Coolant Pump controlled bleedoff to VCT.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 1:

Given the following:

• 100% full power

• 2RITS-4806A (Letdown Radiation Gross Activity Monitor) reads 4.3E5 CPM and 2RITS-4806B (Letdown Radiation Iodine-131 Activity Monitor) reads 3.1E5 CPM.

• Auxiliary building general area radiation is 300 mr/hr.

• Letdown has been isolated using 2CV-4820-2.

What action should be performed to directly prevent RCS fluid from leaving the Containment Building?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 2.5 SRO: 3.1 KA

REFERENCE:

2.

3.4 REFERENCES

1012.021, Exposure Limits and Controls, Rev 004-02-0, Steps 4.5, 4.7, 4.19, 6.2.2 & 6.3.1.B.1 RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 2:

A radiation worker has been assigned the task of breaking Incore Flanges. The general area dose rate on the Reactor Vessel Head area work platform is 1 R/Hr gamma radiation. The time needed for this worker to break the incore flanges is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The year to date dose for the radiation worker is:

• Deep Dose Equivalent (DDE) = 0.2 Rem

• Committed Effective Dose Equivalent (CEDE) = 0.3 Rem

• Shallow Dose Equivalent (SDE) = 0.8 Rem

• Eye Dose Equivalent (LDE) = 0.6 Rem What would be the radiation workers Total Effective Dose Equivalent (TEDE) after completion of this task and who is required to authorize any dose control level extensions for this task?

ANSWER:

TEDE = DDE + CEDE TEDE = 0.2 Rem + 0.3 Rem Before task TEDE = 0.5 Rem 1 R/Hr dose rate for 2 Hour task = 2 Rem TEDE = 2 Rem + 0.5 Rem After task TEDE = 2.5 Rem Admin TEDE limit for radiation worker is 2 Rem/yr.

To exceed 2.0 Rem for the year requires designated Radiation Protection Manager authorization for up to 3 Rem.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.3 QUESTION 2:

A radiation worker has been assigned the task of breaking Incore Flanges. The general area dose rate on the Reactor Vessel Head area work platform is 1 R/Hr gamma radiation. The time needed for this worker to break the incore flanges is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The year to date dose for the radiation worker is:

• Deep Dose Equivalent (DDE) = 0.2 Rem

• Committed Effective Dose Equivalent (CEDE) = 0.3 Rem

• Shallow Dose Equivalent (SDE) = 0.8 Rem

• Eye Dose Equivalent (LDE) = 0.6 Rem What would be the radiation workers Total Effective Dose Equivalent (TEDE) after completion of this task and who is required to authorize any dose control level extensions for this task?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: __2.8__ SRO: __3.5__ KA

REFERENCE:

_2.4.43_

REFERENCE:

OP 1903.011 REVISION 026-00-0, INITIAL NOTIFICATION CHECKLIST (1903.011BB) AND ATTACHMENT 10, TIME REQUIREMENTS RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 1 After the declaration of a Notification of Unusual Event (NUE), how much time is allowed to notify the:

• Arkansas Department of Health (ADH) and

• Nuclear Regulatory Commission (NRC)?

ANSWER:

• Initial Notification Message (1905.011Y) to ADH within 15 minutes

• To NRC immediately following ADH and not to exceed one (1) hour from declaration.

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 1 After the declaration of a Notification of Unusual Event (NUE), how much time is allowed to notify the:

• Arkansas Department of Health (ADH) and

• Nuclear Regulatory Commission (NRC)?

ADMINISTRATIVE QUESTION PAGE 1 OF 2 TYPE: OPEN REFERENCE KA VALUE RO: 2.6 SRO: 4.0 KA

REFERENCE:

2.4.29

REFERENCES:

1903.010, EAL Classification, Rev 036-03-0, Step 4.16.1.B.

1903.010, EAL Classification, Rev 036-03-0, Attachments 6 and 8 1905.003, Post Accident Sampling of RCS, Rev 008-00-0, Steps 5.1.3, 5.1.4 & Att. 2 1903.011, Emergency Response/Notifications, Rev 026-00-0, Attachment 8 RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 2:

Given the following plant conditions:

• Plant operating in Mode 3.

• Manual reactor trip initiated ten (10) minutes ago due to B RCP seal failure.

• RCS leakage calculated at 62 gpm inside Containment.

• Post SPTA brief in progress.

The Shift Manager states during the brief that an Alert EAL has been declared and the conditions for upgrade to Site Area Emergency (SAE) include greater than 1% fuel cladding failure.

State two methods that could be used to determine when 1% fuel cladding failure is exceeded.

ANSWER:

(any 2 of the following for full credit)

1. Nuclear Chemistry analysis of RCS Sample.

2. Radiation Levels at 2TCD-19 (RCS Sample Tubing in hallway behind door 230)

(1903.010 Attachment 8 and 1905.003)

3. Containment Radiation Levels above SAE levels (1903.010 Attachment 6)

4. Engineering assessment of core damage. (1903.011 Attachment 8)

COMMENTS:

ADMINISTRATIVE QUESTION PAGE 2 OF 2 EXAMINEES COPY TYPE: OPEN REFERENCE RO OPERATING ADMIN TEST 1 SUBJECT A.4 QUESTION 2:

Given the following plant conditions:

• Plant operating in Mode 3.

• Manual reactor trip initiated ten (10) minutes ago due to B RCP seal failure.

• RCS leakage calculated at 62 gpm inside Containment.

• Post SPTA brief in progress.

The Shift Manager states during the brief that an Alert EAL has been declared and the conditions for upgrade to Site Area Emergency (SAE) include greater than 1% fuel cladding failure.

State two methods that could be used to determine when 1% fuel cladding failure is exceeded.

ANO-2-JPM-NRC-TTBC PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Conduct of Operations (A.1)

TASK: Calculate Time to Boil using computer program JTA#:

KA VALUE RO: 3.9 SRO: 4.0 KA

REFERENCE:

2.1.23 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: Perform Classroom: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): 1015.008 Attachment E, Rev 017-02-0 EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

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

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

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

ANO-2-JPM-NRC-TTBC PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

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

JPM INITIAL TASK CONDITIONS:

Plant shutdown for repair of Steam Generator Tube Leak. Making preparations for draining the RCS to 24 inches above the bottom of the hotleg to install nozzle dams. PZR level is 40% and open to atmosphere.

Time after shutdown = 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; one (1) PZR code safety valve is removed; PZR manway is installed; ECCS vent valves are de-energized OPEN; NO RCP seal work inprogress; NO RCS cold leg openings; RCS Temperature is 105°F.

TASK STANDARD:

Time to boil calculation has been calculated using the computer program.

TASK PERFORMANCE AIDS:

1015.008 attachment E, Computer operational with the current revision of LOSDC2 installed (SP-94-C-0001, Rev. 10)., set up shortcut to program on the desktop.

SIMULATOR SETUP:

NA EXAMINER'S NOTES:

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

The SM/CRS directs, "Using the computer program LOSDC2, calculate a projected time to boil 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> from now with RCS level 24 above bottom of Hot Leg, using current temperature and pressure.

CRITICAL ELEMENTS (C): 19 PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Start the LOSDC2 program. (it Double click on the shortcut to N/A SAT UNSAT is permissible to start the start the LOSDC2 program program using windows file OR manager or double click )

Go to file manager and start LOSDC2 program.

2. Verify that program is current. At question prompt, Is this the N/A SAT UNSAT current version of program?

(version SP-94-C-0001-01, Rev.

10) Type Y and hit ENTER.

3. Input that RCS pressure At Question prompt, Pressure N/A SAT UNSAT boundary is closed. Boundary Closed? , type N and hit ENTER.

4. Input that Reactor Head is not At Question prompt, Reactor N/A SAT UNSAT removed. Head removed? , type N and hit ENTER.

5. Input that ECCS valves are At Question prompt, ECCS N/A SAT UNSAT open. Valve Open? , type Y and hit ENTER.

6. Input that One PZR code safety At Question prompt, Number of N/A SAT UNSAT valve is removed. Code Safety Valves removed, 0,1,2? , type 1 and hit ENTER.

7. Input that the pressurizer At Question prompt, Pressurizer N/A SAT UNSAT manway is not removed. manway removed? , type N and hit ENTER.

8. Input that the RCS cold legs are At Question prompt, Cold Leg N/A SAT UNSAT not open. hole? , type N and hit ENTER.

9. Input that RCP seal work is not At Question prompt, RCP seal N/A SAT UNSAT in progress. work in progress? , type N and hit ENTER.

10. Input that A SG cold leg At Question prompt, A SG cold N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

11. Input that B SG cold leg At Question prompt, B SG cold N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

ANO-2-JPM-NRC-TTBC PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

12. Input that A SG hot leg At Question prompt, A SG hot N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

13. Input that B SG hot leg At Question prompt, B SG hot N/A SAT UNSAT manway is not removed. leg manway removed? , type N and hit ENTER.

14. Input that time after shutdown is At Question prompt, Enter time N/A SAT UNSAT 3 days 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. (note this is after shutdown? , type 3,7.5 the 3 days time after shutdown and hit ENTER.

given in initial conditions plus the 7.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> given in the initiating cue.)

15. Input that water level input is to At Question prompt, Enter water N/A SAT UNSAT be in inches above bottom of level above the bottom of the hot hot leg. leg? , type 1 and hit ENTER.

16. Input that projected water level At Question prompt, water level N/A SAT UNSAT is 24 above the bottom of the projected? , type 24 and hit hotleg. ENTER.

17. Input that current RCS At Question prompt, Current N/A SAT UNSAT temperature is 105°F. Coolant temperature? , type 105 and hit ENTER.

18. Input that this is not a refueling At Question prompt, Has core N/A SAT UNSAT outage and that core reload is shuffle/reload been completed? ,

not to be done. type N and hit ENTER.

C 19. Record / Report that Time to Report that the Time to boil the N/A SAT UNSAT Boil the RCS is 19 minutes 19 RCS is 19 minutes and 19 seconds. Acceptable value 3 2 seconds.

minutes EXAMINERS NOTE:

Prompt the Examinee that the file should not be printed but, may be saved and then reviewed. The file should be saved as Their First Name.dat. (Examinee will then open the file via file manager). This file should then be deleted after the JPM is over.

END

ANO-2-JPM-NRC-TTBC PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Given the following Plant conditions:

• Plant shutdown for repair of Steam Generator Tube Leak.

• Making preparations for draining the RCS to 24 inches above the bottom of the hot leg to install nozzle dams.

• PZR level is 40% and open to atmosphere.

• Time after shutdown = 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;

• One (1) PZR code safety valve is removed;

• PZR manway is installed;

• ECCS vent valves are de-energized OPEN;

• NO RCP seal work inprogress;

• NO RCS cold leg openings;

• RCS Temperature is 105°F.

INITIATING CUE:

The SM/CRS directs, "Using the computer program LOSDC2, calculate a projected time to boil 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> from now with RCS level 24 above bottom of Hot Leg, using current temperature and pressure.

ANO-2-JPM-NRC-HCARD1 PAGE 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Equipment Control (A.2)

TASK: Review Clearance Authorization Form for errors JTA#:

KA VALUE RO: 3.6 SRO: 3.8 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: Perform Classroom: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP 1000.027 Rev. 26-03-0 Sections 6.0 and Attachment A EXAMINEE'S NAME: SSN:

EVALUATOR'S NAME:

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

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

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

ANO-2-JPM-NRC-HCARD1 PAGE 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

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

JPM INITIAL TASK CONDITIONS: Plant is at 100% power. D Condensate Pump is being tagged out to repack the pump and the Computerized Tagging System is not available.

TASK STANDARD: Identify at least two of three errors on the Clearance Installation Authorization Form. Errors include: (1) sequence wrong, should open breaker before closing pump discharge valve and suction valve; (2) no NO TAG entry made requiring review of the Special Instructions; (3) Preparer did not sign form.

TASK PERFORMANCE AIDS: OP 1000.027 Rev 026-03-0, P&ID M2204, Sheet 1, E2004 Sheet 1

ANO-2-JPM-NRC-HCARD1 PAGE 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, The Computer Tagging System is out of service, Perform a Clearance Review of the Manual Clearance for D Condensate pump (2P-2D) and identify at least two of three errors made by the Clearance Preparer.

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

EXAMINERS NOTE:

Examinee may be able to identify two of three errors without reviewing 1000.027, Protective Tagging Control procedure.

1. Review 1000.027, Protective Reviewed at least the following N/A SAT UNSAT Tagging Procedure, Section 6 and sections of 1000.027, Hold and Attachment A Caution Card Control Procedure.

- Section 6 - Clearance Reviewer

- Attachment A - General Tagging Requirements

2. Verified that the Tag number, Reviewed the first section of the N/A SAT UNSAT Clearance number, and purpose for clearance Installation Authorization the clearance were correct. Form and determined that the Tag number, Clearance number, and purpose for the clearance were correct.

C 3. Identify that Prepared By Identified that no name or signature N/A SAT UNSAT signature is not filled in. had been provided in the Prepared By blank.

C 4. Identify that there was not a NO Identified that a Special Instructions N/A SAT UNSAT TAG entry made that required entry was made but a NO TAG review of the Special Instructions. entry was not made that required a review of the special instructions.

5. Verify boundary isolations Reviewed appropriate P&IDs and N/A SAT UNSAT selected provide adequate plant Electrical prints to verify boundary and personnel safety for the work isolations selected provide activity listed. adequate plant and personnel safety for the work activity listed.

ANO-2-JPM-NRC-HCARD1 PAGE 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

C 6. Identify sequence for installing the Reviewed sequence for Clearance N/A SAT UNSAT Hold Cards is incorrect. installation on Clearance Installation Authorization Form. Identified that the Handswitch and the Breaker should have been placed in the Pull-to-Lock and Racked Down position respectively before the pump was isolated by the discharge and suction valves to prevent pump damage.

INSTRUCTORS NOTE If examinee asks about the Danger Tags, they have been printed exactly as the information appears on Clearance Installation Authorization Form.

END

ANO-2-JPM-NRC-HCARD1 PAGE 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS: Plant is at 100% power. D Condensate Pump is being tagged out to repack the pump and the Computerized Tagging System is not available.

INITIATING CUE:

The SM/CRS directs, The Computer Tagging System is out of service, perform a Clearance Review of the Manual Clearance for D Condensate pump (2P-2D) and identify at least two of three errors made by the Clearance Preparer.

PAGE 42 OF 56 CLEARANCE INSTALLATION AUTHORIZATION FORM PAGE 1 OF 1 COMPONENT TO BE TAGGED CLEARANCE NUMBER:

2P2D PUMP MANUAL - 2/11/02 - 0800 CONDENSATE PUMP PURPOSE:

REPACK 2P-2D SPECIAL INSTRUCTIONS: DRAWING CROSS-

REFERENCE:

M-2204, SHEET 1; E2004, SHEET 1 Verify 2P2A, B and C are inservice and operating properly. Monitor condenser oxygen levels after pump isolated and vented to verify boundary valves are holding.

PREPARED BY: REVIEWED BY:

DATE/TIME DATE/TIME AUTHORIZED TO HANG: DATE/TIME:

TAG INSTALLATION SECTION SEQ TAG# DEVICE AND LOCATION TAGGED HUNG VERIFIED COMPONENT NAME POSITION BY BY 1 1 2CS-2D VALVE CLOSED 2P-2D Discharge EQUIPMENT AREA - TB Valve 2 2 2CS-2H VALVE CLOSED 2P-2D Discharge EQUIPMENT AREA - TB Bypass 3 3 2CS-15B VALVE CLOSED 2P-2D Equalizing EQUIPMENT AREA - TB FORM TITLE: FORM NO. CHANGE NO.

CLEARANCE INSTALLATION AUTHORIZATION FORM 1000.027A 026-03-0

PAGE 42 OF 56 vent to 2E11A

• -NO TAG FORM TITLE: FORM NO. CHANGE NO.

CLEARANCE INSTALLATION AUTHORIZATION FORM 1000.027A 026-03-0

PAGE 49 OF 56 CLEARANCE CONTINUATION AUTHORIZATION FORM PAGE 1 OF 1 TAGOUT NO. MANUAL - 2/11/02 - 0800 TAG INSTALLATION SECTION SEQ TAG# DEVICE AND LOCATION TAGGED HUNG VERIFIED COMPONENT NAME POSITION BY BY 4 4 2CS-24D VALVE CLOSED 2P-2D Seal Water EQUIPMENT AREA - TB Inlet 5 5 2CV-0626 VALVE CLOSED 2P-2D Suction EQUIPMENT AREA - TB Valve 6 6

• 2HS-0626 HANDSWITCH IN HANDSW U2 CONTROL RM - RAB PULL TO LOCK CFW Cond PP 2P2D 7 7 2A-206 BREAKER RACKED CKTBRK ELECTRICAL SWITCHGEAR - TB DOWN CONDENSATE PUMP 2P-2D 8 8

• 2CS-1001D VALVE OPEN 2P-2D Discharge EQUIPMENT AREA - TB line ATMOS. Drain 9 9 2CS-1054 VALVE OPEN 2P-2D ATMOS Vent EQUIPMENT AREA - TB FORM TITLE: FORM NO. CHANGE NO.

CLEARANCE CONTINUATION AUTHORIZATION FORM 1000.027H 026-03-0

PAGE 49 OF 56

• -NO TAG FORM TITLE: FORM NO. CHANGE NO.

CLEARANCE CONTINUATION AUTHORIZATION FORM 1000.027H 026-03-0