Text

Draft - Section a Operating (All Procedures Are with Final - Section a)
	ML021690605
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	05/24/2002
From:	Wasong A; Exelon Nuclear
To:	Conte R; NRC/RGN-I/DRS/OSB
References
	Download: ML021690605 (32)
	v • d • e

EXELON NUCLEAR TITLE: Working Hour Limitations TASK PERFORMED BY:

EVALUATOR SIGNATURE:

DIRECTIONS TO EVALUATOR:

EVALUATOR:

DATE:

EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

Completion Time: 10 minutes IMPORTANCE RATING(S):

3.4 SYSTEM NUMBER(S):

2.

1.5 REFERENCES

1. A-C-40 Rev 1, WORKING HOUR LIMITATIONS (Common)

TASK STANDARD(S):

RPO determined to not be able to stand watch.

FHD determined to need working hour limit deviation form to permit helping with surveillance AI-1.doc Page 3 of 8 Af-l.doc Page 3 of 8

EXELON NUCLEAR TASK CONDITIONS:

1. The following Limerick Unit 1 outage working hour history is given for an on coming Fuel Handling Director (FHD) and a Refuel Platform Operator (RPO). The hours worked are on the Unit 2 Refueling Platform performing core alterations DS=Dayshift NS=Nightshift The RPO and FHD are scheduled to work dayshift today, 6/6 INITIATING CUES:

You are directed to evaluate the working hour history for the FHD and the RPO and determine whether one or both individuals can work a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A1-1.doc Page 4 of 8 Date FHD RPO 5/28 (Day 1) 12 hrs (DS) 12 hrs (NS) 5/29 12 hrs (DS)

OFF 5/30 12 hrs (DS)

OFF 5/31 OFF 12 hrs (DS) 6/1 12 hrs (DS) 12 hrs (DS) 6/2 12 hrs (DS) 12 hrs (DS) 6/3 12 hrs (DS) 12 hrs (DS) 614 12 hrs (DS) 12 hrs (DS) 6/5 12 hrs (DS) 12 hrs (DS)

A l-l. doc Page 4 of 8

EXELON NUCLEAR Critical Element(s) indicated by "*" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD

=SAT/UNSAT Assess working hour limitations in A-C-40 Note: The JPM steps below are excerpts from A-C-40 that represent the most likely steps the candidate will cite when performing the JPM. The entire procedure is not duplicated.

Fuel Handling comes under the control of Nuclear Safety Related work under the definitions section 42_2

1. Obtain A-C-40 A-C-40 obtained

2. The number of hours worked shall be Assess hours worked and conclude the controlled in accordance with the following:

limitations set in Working Hour Limitation The FHD may work the entire 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Deviation Form (Exhibit A-C-40-1) dayshift

3. *The number of hours worked shall be Assess hours worked and conclude the controlled in accordance with the following:

limitations set in Working Hour Limitation The RPO may not take the shift because Deviation Form (Exhibit A-C-40-1) the next hour worked will result in the RPO exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months period

4. CUE: Assume you have completed a 12 N/A hour shift as FHD and are in the NMD office. You have just received a call one hour after turnover from the refuel bridge that your help is needed in performing a partial ST on the bridge for about 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Assess whether you can assist with the ST

5. *The number of hours worked shall be Assess the conditions and conclude that controlled in accordance with the a working hour limitations deviation form limitations set in Working Hour Limitation would need to be filled out and approved Deviation Form (Exhibit A-C-40-1) to permit helping with the ST.

Performance of the ST would violate:

24 in 48 hrs, and 72 in168hrs A7-1.doc Page 5 of 8 A l-l.doc Page 5 of 8 I

EXELON NUCLEAR STEP STANDARD SAT/UNSAT

6. CUE: You have reached the termination N/A point for this JPM. You may stop here.

AI-1.doc Page 6 of 8 A l-l.doc Page 6 of 8

I EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A 1-1.doc Page 7 of 8 Al-l.doc Page 7 of 8

EXELON NUCLEAR I

TASK CONDITIONS:

1. The following Limerick Unit I outage working hour history is given for an on-coming Fuel Handling Director (FHD) and a Refuel Platform Operator (RPO). The hours worked are on the Unit 2 Refueling Platform performing core alterations DS=Dayshift NS=Nightshift The RPO and FHD are scheduled to work dayshift today, 6/6 INITIATING CUES:

You are directed to evaluate the working hour history for the FHD and the RPO and determine whether one or both individuals can work a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Date FHD RPO 5/28 (Day 1) 12 hrs (DS) 12 hrs (NS) 5/29 12 hrs (DS)

OFF 5/30 12 hrs (DS)

OFF 5/31 OFF 12 hrs (DS) 6/1 12 hrs (DS) 12 hrs (DS) 6/2 12 hrs (DS) 12 hrs (DS) 6/3 12 hrs (DS) 12 hrs (DS) 6/4 12 hrs (DS) 12 hrs (DS) 6/5 12 hrs (DS) 12 hrs (DS)

CANDIDATE

EXELON NUCLEAR TITLE: Fuel Handlinq Director Turnover Conditions Plant Differences TASK PERFORMED BY:

EVALUATOR SIGNATURE:

DIRECTIONS TO EVALUATOR:

EVALUATOR:

DATE:

EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

Completion Time: 10 minutes IMPORTANCE RATING(S):

3.5 SYSTEM NUMBER(S):

2.2.28 Generic

REFERENCES:

1. Exhibit NOM-L-4.1:13, Rev 0, FUEL HANDLING DIRECTOR SHIFT TURNOVER CHECKLIST TASK STANDARD(S):

Turnover conditions assessed with consideration of the different administrative limits. Determine that core alterations may proceed at PBAPS and may NOT proceed at LGS.

A 1-2.doc Page 3 of 7 A 1-2. doc Page 3 of 7

I EXELON NUCLEAR I

TASK CONDITIONS:

The following plant conditions for Limerick Unit 2 and Peach Bottom Unit 2 are provided Plant Condition Limerick Unit 2 Peach Bottom Unit 2 Plant Operating Condition OPCON 5 Mode 5 Activities Shuffle Part 2 to start Shuffle Part 2 to Start Core Status Per the Attached Map Per the Attached Map Recirc Pumps A and B Secured A and B Secured RHR "A" SDC 6200 gpm "A" SDC 6200 gpm Coolant Temp 110 degrees F 110 degrees F RPV Water Level 483" LR42-1 R608 460 " PRIFR-2-06-097 Fuel Pool Gates Removed Removed Control Rods All inserted All inserted INITIATING CUES:

Evaluate turnover conditions and determine whether core alterations are permitted and the basis for any discrepancy on Both Units A 1-2.doc Page 4 of 7 A 1-2. doc Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "*" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT

1. Obtain Exhibit NOM-L-4.1:13 Exhibit NOM-L-4.1:13 obtained

2. Assess plant conditions against requirements

a. *RHR SDC flow <6000 gpm at Determine RHR flow is too high at LGS or < 6500 gpm at PBAPS Limerick. Determine from the map that or all in-core instruments numerous instruments are not supported supported, and the flow limits apply Conclude that core alterations may not commence at Limerick

b. RHR SDC flow <6000 gpm at All conditions are satisfactory at Peach LGS or < 6500 gpm at PBAPS Bottom or all in-core instruments Conclude that core alterations my commence at Pach Bottom CUE: You have reached the termination point N/A N/A for this JPM. You may stop here.

i-i i-i. aoc Page 5 of 7

/A7-Z.aO1C Page 5 of 7

EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SATIUNSAT A1-2.doc Page 6 of 7 A1-2.doc Page 6 of 7

I EXELON NUCLEAR TASK CONDITIONS:

The following plant conditions for Limerick Unit 2 and Peach Bottom Unit 2 are provided INITIATING CUES:

Evaluate turnover conditions and determine whether core alterations are permitted and the basis for any discrepancy on Both Units Plant Condition Limerick Unit 2 Peach Bottom Unit 2 Plant Operating Condition OPCON 5 Mode 5 Activities Shuffle Part 2 to start Shuffle Part 2 to Start Core Status Per the Attached Map Per the Attached Map Recirc Pumps A and B Secured A and B Secured RHR "A" SDC 6200 gpm "A" SDC 6200 gpm Coolant Temp 110 degrees F 110 degrees F RPV Water Level 483" LR42-1 R608 460 "PRPFR-2-06-097 Fuel Pool Gates Removed Removed Control Rods All inserted All inserted CANDIDATE

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I EXELON NUCLEAR I

TITLE: Core Counting Locations at Limerick and Peach Bottom TASK PERFORMED BY:

EVALUATOR SIGNATURE:

DIRECTIONS TO EVALUATOR:

EVALUATOR:

DATE:

EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

Completion Time: 10 minutes

/\\.

2-IMPORTANCE RATING(S):

3.3 SYSTEM NUMBER(S):

2.2.3 Generic

REFERENCES:

1. RE-C-40 Rev 90, CORE COMPONENT TRANSFER AUTHORIZATION SHEET GENERATION AND ADMINISTRATION TASK STANDARD(S):

Component locations identified per the attached grading keys AZ.cfOC Page 3 of 7 A 2. doc Page 3 of 7

I EXELON NUCLEAR TASK CONDITIONS:

1. Overhead views of Peach Bottom and Limerick vessels are provided INITIATING CUES:

Circle the location of the following instruments and label with the respective core location:

Limerick - "A" Source Range Monitor (SRM)

Peach Bottom - "A" Wide Range Nuclear Monitor (WRNM)

AZ doc Page 4 of 7 A 2. doc Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP

]

STANDARD SAT/UNSAT

1. CUE: Provide the candidate with two blank core diagrams.

Note that the answer keys are attached to the JPM and are labeled. LGS and PBAPS cores are rotated 90 degrees from each other. LGS does not have WRNMs

2. *Mark the Limerick map at location 16-45 16-45 marked

3. *Mark the Peach Bottom map at location 16-53 marked 16-53 CUE: You have reached the termination point N/A

'N/A for this JPM. You may stop here.

A2.doc Page 5 of 7 A2.doc Page 5 of 7

I EXELON NUCLEAR I

Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A2.doc Page 6 of 7 A2.doc Page 6 of 7

I EXELON NUCLEAR I

TASK CONDITIONS:

1. Overhead views of Peach Bottom and Limerick vessels are provided INITIATING CUES:

Circle the location of the following instruments and label with the respective core location:

Limerick - "A" Source Range Monitor (SRM)

Peach Bottom - "A" Wide Range Nuclear Monitor (WRNM)

CANDIDATE

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EXELON NUCLEAR 1

Administrative Questions for PBAPS Cat A.3 Radiation Control

,3V A3.doc

Question A3-1 Candidate Copy Given the following conditions:

An Maintenance Technician has just exited the refueling platform and walked to the Personal Contamination Monitor (PCM)

The individual was handling poles and cables that were submerged in the spent fuel pool The operator alarmed the PCM one time

1. What are the operator's required actions?

(Wait for Part 1 answer)

2. If the monitor alarms a second time, what are the required actions?

CANDIDATE

Question A3-1 GRADING'KEY Given the following conditions:

An Maintenance Technician has just exited the refueling platform and walked to the Personal Contamination Monitor (PCM)

The individual was handling poles and cables that were submerged in the spent fuel pool The operator alarmed the PCM one time

1. What are the operators required actions?

(Wait for Part I answer)

2. If the monitor alarms a second time, what are the required actions?

Answer:

1. Re-monitor one time

2. If the monitor alarms for a second time, then

a. Remain in the area

b. Minimize contact with personnel, tools, or equipment

c. Contact Health Physics*

Minimum required answer K/A 2.3.2 (2.9) Knowledge of Facility ALARA program Source: New ANSWER KEY

Question A3-2 Candidate Copy Question:

Peach Bottom Unit 2 conditions are as follows:

LPRM exchange is scheduled to begin within the next 15 minutes Work is in progress in the drywell on Elevation 135' Assuming the drywell work must continue, what protective measures are taken by Health Physics to prevent those individuals from receiving excessive dose as the result of LPRM removal?

CANDIDATE

Question A3-2 GRADING KEY Peach Bottom Unit 2 conditions are as follows:

LPRM exchange is scheduled to begin within the next 15 minutes Work is in progress in the drywell on Elevation 135' Assuming the drywell work must continue, what protective measures are taken by Health Physics to prevent those individuals from receiving excessive dose as the result of LPRM removal?

1. *Access must be restricted to prevent access to the upper drywell elevations (194' and above and 184' inside the bioshield)

2. A radiological monitoring system must be installed and monitoring the upper drywell and bioshield access points with local alarms

3. Drywell workers must be briefed prior to entering the drywell How will the FHD be informed that the actions have been taken?

The drywell control point will contact the FHD

'Minimum required answer K/A 2.3.10 (3.3)

Source: New

Reference:

HP-321 ANSWER KEY

EXELON NUCLEAR TITLE: Determine EAL for refueling accident conditions TASK PERFORMED BY:

EVALUATOR SIGNATURE:

DIRECTIONS TO EVALUATOR:

EVALUATOR:

DATE:

EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

Completion Time: 10 minutes IMPORTANCE RATING(S):

4.1 SYSTEM NUMBER(S):

2.4.41

REFERENCES:

1. ERP-101 Rev.23, CLASSIFICATION OF EMERGENCIES TASK STANDARD(S):

Event is Classified as an Alert per ERP-101 Page 3 of 8

'k.4 A A J.

/-q.uOC

EXELON NUCLEAR TASK CONDITIONS:

1. Peach Bottom Unit 3 is in Mode 5

2. A breach of the bottom of the spent fuel pool liner has resulted in a loss of level in the reactor cavity and spent fuel pool

3. The spent fuel pool gates have been installed

4. RPV level is 430 inches above instrument zero and rising slowly due to ECCS manual initiation

5. Fuel pool level is at the 222' elevation and still lowering with maximum available emergency makeup injecting INITIATING CUES:

Determine the minimum required Emergency Action Level based on the above conditions A4.QOC Page 4 of 8 A4.a10C Page 4 of 8

EXELON NUCLEAR Critical Element(s) indicated by "'" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT

1. Obtain ERP-101 ERP-101 obtained

2. Locate Section 1.2, Irradiated or New Section 1.2 located Fuel

3. *Classify the Event per Section 1.2 of EAL determined to be an ALERT ERP-101 (Evaluator copy is attached)

CUE: You have reached the termination point N/A N/A for this JPM. You may stop here.

Aq.cloc Page 5 of 8

4.

C10 Page 5 of 8

I EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A A

,1-t. UVU Page 6 of 8

EXELON NUCLEAR I

TASK CONDITIONS:

1. Peach Bottom Unit 3 is in Mode 5

2. A breach of the bottom of the spent fuel pool liner has resulted in a loss of level in the reactor cavity and spent fuel pool

3. The spent fuel pool gates have been installed

4. RPV level is 430 inches above instrument zero and rising slowly due to ECCS manual initiation

5. Fuel pool level is at the 222' elevation and still lowering with maximum available emergency makeup injecting INITIATING CUES:

Determine the minimum required Emergency Action Level based on the above conditions CANDIDATE

EXELON NUCLEAR 1.0 Reactor Fuel 1.2 Irradiated Fuel or New Fuel CLASSIFICATION EMERGENCY ACTION LEVEL UNUSUAL EVENT IC Unexpected Rise in Plant Radiation or Airborne Concentration.

1.2.1.a Applicable Modes: ALL Uncontrolled water level drop in the spent fuel pool with all irradiated fuel assemblies remaining covered by water 1.2.1.b Applicable Modes: ALL Unexpected Skimmer Surge Tank low level alarm AND Visual observation of an uncontrolled water level drop below the fuel pool skimmer surge tank inlet IC Unexpected Rise in Plant Radiation 1.2.1.c Applicable Modes: ALL Radiological readings exceed 600 mR/hr one foot away OR 1200 mR/hr at the external surface of any dry storage system ALERT IC, Major Damage to Irradiated Fuel, or Loss of Water Level that Hap or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel 1.2.2.a Applicable Modes: ALL Unplanned general area radiation > 500 mR/hr on the refuel floor (Table 1-1) 1.2.2.b Applicable Modes: ALL Report of visual observation of irradiated fuel uncovered 1.2.2.c Applicable Modes: 5 (With Reactor Refueling Cavity Flooded)

Water Level < 458" above RPV instrument zero for the Reactor Refueling Cavity that will result in Irradiated Fuel uncovering 1.2.2.d Applicable Modes: ALL Water Level < 232ft 3 inches plant elevation for the Spent Fuel Pool that will resul in Irradiated Fuel uncovering SITE AREA EMERGENCY None GENERAL None EMERGENCY Table 1-1 Refuel Floor ARMs 3-7 (7-9) 3-8 (7-10) 3-9(7-11) 3-10(7-12)

ANSWER KEY I

Steam Separator Pool Refuel Slot Fuel Pool Refueling Bridge

ML021690605

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1.5 REFERENCES

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1.5 REFERENCES

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