Text

Final - Section a Operating
	ML031130629
Person / Time
Site:	Hope Creek
Issue date:	04/01/2003
From:	Reid J; Public Service Enterprise Group
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-354/03-301 50-354/03-301
	Download: ML031130629 (61)
	v • d • e

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION:

SYSTEM:

TASK:

HOPE CREEK Conduct of Operations - Ability to locate and use procedures and directives related to shift staffing and activities.

Apply working hour limitations for LSRO and platform operator.

TASK NUMBER:

294000 G 2.1.5 JPM NUMBER:

2003-NRC-LSRO-Admin Al-1 ALTERNATE PATH: E K/A NUMBER:

294000 APPLICABILITY:

IMPORTANCE FACTOR:

2.3 EO =

RO =

SRO Eli LSRO =

RO EVALUATION SETTINGIMETHOD:

CONTROL ROOM/SIMULATOR - PERFORM / SIMULATE

REFERENCES:

NC.NA-AP.ZZ-0005(Q) Rev 12 TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

15 min.

TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

N/A min.

APPROVED:

G2.1.5 3.4 SRO N/A SUPERVISOR Ott~IbS MANAGER De anee BARGAINING UNIT REPRESENTATIVE CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2.

Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

min.

ACTUAL TIME CRITICAL COMPLETION TIME:

Ni JPM PERFORMED BY:

REASON, IF UNSATISFACTORY:

PA min.

GRADE:

a SAT F

UNSAT EVALUATOR'S SIGNATURE:

DATE:

Nuclear Common 2003-NRC-LSRO-Admin Al-1 Page 1 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

Apply working hour limitations for LSRO and platform operator.

SYSTEM:

TASK:

TASK NUMBER:

294000 G 2.1.5 INITIAL CONDITIONS:

The following Hope Creek Generating Station outage working hour history is given for an on-coming Refueling SRO (LSRO) and a Refueling Platform Operator (RPO). The hours worked are on the Refueling Platform performing core alterations.

Date LSRO RPO 1/28 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Night Shift 1/29 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift OFF 1/30 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift OFF 1/31 OFF 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/5 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift The LSRO and RPO are scheduled to work Dayshift today, 2/6 INITIATING CUE:

You are directed to evaluate the working hour history for the LSRO and 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 .

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Nuclear Common 2003-NRC-LSRO-Admin Al-1 Page 2 Rev. 0

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NC.T1 AB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: _

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

Apply working hour limitations for LSRO and platform operator.

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l

(#Denotes a Sequential Step) l_l S/U UNSAT evaluation)

Operator obtains procedure NC.NA-Operator determines the correct procedure.

AP.ZZ-0005 START TIME 5.10 Working Hour Guidelines Operator determines 5.10 is appropriate section.

5.10.1 Adequate shift coverage shall be maintained Operator reads step.

without the routine heavy use of overtime.

5.10.2 The expectation is that all personnel will Operator reads step.

work nominal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months work weeks while the units are operating.

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(:

NC.+Ik JB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

TASK:

Apply working hour limitations for LSRO and platform operator.

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step) l_S/U_

UNSAT evaluation) 5.10.3 PRIOR TO performance of overtime in excess of the guidelines listed in step 5.10.4, authorization shall be obtained from the Department Manager and the Director - Operations (In the event that the Director - Operations is unavailable to provide this approval the "Director -

Operations" approval should only be delegated upward to a VP level position.

Authorization shall be documented on FORM - 1, Working Hour Guideline Deviation / Authorization.

Approvals may be obtained by telecon as follows:

Sign for the approval authority Document the statement "per telecon" Record the name of the individual granting approval.

Record the time and date the approval was received.

Completed forms should be retained by the initiating department (Time Administrator) and made available for NRC review for a full operating cycle.

EXAMINER NOTE: If the operator asks if a Working Hour Guideline Deviation/

Authorization FORM - 1 has already been approved, CUE: None has been approved.

Paqe 4 0

q C'rln(mmrn M uDG TV,,,,, TV,,

I 2003-NRC-LSRO-Admin Al-1

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NC.T4-vvi3.ZZ-0310(Z).

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

TASK:

Apply working hour limitations for LSRO and platform operator.

lSTEP NO.

lSTEP ll COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l

(#Denotes a Sequential Step) l S/Ul UNSAT evaluation) 5.10.4 In the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed by -

Licensed Senior Reactor Operators, Licensed Reactor Operators, Radiation Protection Technicians, Equipment Operators, Chemistry Technicians, and Key Maintenance Personnel (See Definition 7.3)

Reference:

Technical Specification 6.2.2 Determines limitations applicable to LSRO and RPO.

T

+

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

Verifies individual has not worked more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight.

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NC.T(~

.vd.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

TASK:

Apply working hour limitations for LSRO and platform operator.

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for ll___(#Denotes a Sequential Step) l S/U UNSAT evaluation)

An individual should not be permitted to Assess hours and conclude the following:

work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

The LSRO may work the entire 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 Dayshift of 2/6.

hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in Assess hours and conclude the following:

any seven day period (all excluding shift

The Refuel Platform Operator may not turnover time).

work the shift because 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 any 7 day period.

OR

Yes, the work may be performed provided a Working Hour Deviation/

Authorization Form is processed and approved prior to the overtime.

After making this determination, CUE:

Another Refuel Platform Operator is now available from 2 days off.

A break of at least eight hours should be Operator reads step.

allowed between work periods (including shift turnover time).

Nuclear Common Page 6 REV.: 0 2003-NRC-LSRO-Admin Al-1

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NC.TIL 1vt.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

TASK:

Apply working hour limitations for LSRO and platform operator.

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l

(#Denotes a Sequential Step) l l

l

_l SIUL UNSAT evaluation)

Except during extended shutdown Operator reads step.

periods, the use of overtime should be considered on an individual basis and not for the entire staff on shift.

Part 2:

EXAMINER CUE:

Two hours into the Dayshift, the refueling platform has broken. It is now 8 AM on 216. Maintenance expects the needed replacement part will arrive in 2 days. You call the Night Shift LSRO and tell him to stay home.

At 5 PM, Maintenance has found the needed part in the warehouse. They report the platform will be repaired by 6 PM. They request your assistance for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to perform the Surveillance Test to return the platform to operable status.

Assess whether the Dayshift LSRO can assist with the ST.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NC.Ti4.fB.ZZ-031o(Z))

NAME:

DATE:

SYSTEM:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

TASK:

Apply working hour limitations for LSRO and platform operator.

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step) ll_l SIU UNSAT evaluation) 5.10.4 Conclude that the Dayshift LSRO may NOT perform the ST due to exceeding working hour limits of:

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 day period OR Yes, the work may be performed provided a Working Hour Deviation/

Authorization Form is processed and approved prior to the overtime.

EXAMINER CUE: Take actions necessary for you to continue to perform the ST.

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NC.T..

wBv.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and activities.

TASK:

Apply working hour limitations for LSRO and platform operator.

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l

(#Denotes a Sequential Step)

WU l

SUUNSAT evaluation) 5.10.3 PRIOR TO performance of overtime in excess of the guidelines listed in step 5.10.4, authorization shall be obtained from the Department Manager and the Director-Operations (In the event that the Director - Operations is unavailable to provide this approval the "Director -

Operations" approval should only be delegated upward to a VP level position.

Authorization shall be documented on Form - 1, Working Hour Guideline Deviation / Authorization.

Approvals may be obtained by telecon as follows:

Sign for the approval authority Document the statement "per telecon" Record the name of the individual granting approval.

Record the time and date the approval was received.

Completed forms should be retained by the initiating department (Time Administrator) and made available for NRC review for a full operating cycle.

Operator returns to step 5.10.3 and determines FORM - 1 is required.

EXAMINER NOTE: Once operator determines FORM - 1 is required, provide blank copy of FORM - 1 to operator.

EXAMINER NOTE: If operator asks when the next scheduled day off is, CUE: 2/7 EXAMINER CUE: Your examiner will provide any approvals specified.

Operator completes FORM - 1.

EXAMINER NOTE: See attached FORM -

1 Key. Critical data marked with an Asterisk Pace 9 NhirI=4 Cclnmmnn Pr\\/i 0

By

^ALv-2003-NRC-LSRO-Admin Al-1

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NC..

nvvB.ZZ-0310(Z).

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Conduct of Operations -Ability to locate and use procedures and directives related to shift staffing and Apply working hour limitations for LSRO and platform operator.

NAME:

DATE:

activities.

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

TERMINATING CUE: This JPM is complete.

Nuclear Common 2003-NRC-LSRO-Admin Al-1 Page 10 REV.: 0

NC.NA-AP.ZZ-0005(Z)

FORM - 1 WORKING HOUR GUIDELINE DEVIATION / AUTHORIZATION Working Hour Guideline Deviation / Authorization Code Table Guideline Code Description I

More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a work period 2

More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period 4

More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period 5

Less than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months off between work periods

A~~

2/7 Date

LSRO Candidate Name Requesting Supervisor (print)

Requesting Supervisor (sign)

Department Manager (sign) 2/7 Date Examiner Name Department Manager (print)

Director - Operations (sign) 2/7 Date Examiner Name Director - Operations (print)

NOTE In the event that the Director - Operations is unavailable to provide this approval the "Director - Operations" approval should only be delegated upward to a VP level position.

Nuclear Common 2003-NRC-LSRO-Admin Al-1 Page 49 of 49 REV.: 12

INITIAL CONDITIONS:

The following Hope Creek Generating Station outage working hour history is given for an on-coming Refueling SRO (LSRO) and a Refueling Platform Operator (RPO). The hours worked are on the Refueling Platform performing core alterations.

Date LSRO RPO 1/28 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Night Shift 1/29 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift OFF 1/30 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift OFF 1/31 OFF 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 2/5 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift The LSRO and RPO are scheduled to work Dayshift today, 2/6 INITIATING CUE: You are directed to evaluate the working hour history for the LSRO and 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 .

NC.NA-AP.ZZ-0005(Z)

FORM-1 WORKING HOUR GUIDELINE DEVIATION / AUTHORIZATION Working Hour Guideline Deviation / Authorization Code Table Guiide-line Cnde

[ Description I

1 More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a work period 2

More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period 3

More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period 4

More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period 5

Less than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months off between work periods NAME Code Justification Last Next Scheduled Scheduled Day Off Day Off 4-i I

I-I 1

J Requesting Supervisor (sign)

Date Requesting Supervisor (print)

Department Manager (sign)

Date Department Manager (print)

Director - Operations (sign)

Date Director - Operations (print)

NOTE In the event that the Director - Operations is unavailable to provide this approval the "Director - Operations" approval should only be delegated upward to a VP level position.

Nuclear Common Page 49 of 49 REV.: 12

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION:

SYSTEM:

TASK:

HOPE CREEK Conduct of Operations Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations TASK NUMBER:

2.1.18 - Ability to make accurate I clear and concise logs / records / status boards /

and reports.

JPM NUMBER:

2003-NRC-LSRO-Admin Al-2 ALTFRNATE PATH:

l l1 KIA NUMBER:

2 APPLICABILITY:

IMPORTANCE FACTOR:

EO 2

RO =

SRO Fj LSRO rn I EVALUATION SETTING/METHOD:

CONTROL ROOM/SIMULATOR - PERFORM

REFERENCES:

HC.OP-DL.ZZ-0026 (Q) Attachment 2, Rev 86; HC.OP-ST.KE-0001 TOOLS AND EQUIPMENT:

HC.OP-ST.KE-0001 Marked up.

VALIDATED JPM COMPLETION TIME:

20 min.

TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

NIA min.

APPROVED:

/

)94000 G2.1.18

!.9 3.0 RO SKU N/A BARGAINING UNIT 0=D0=QrIM1TATIIV1 TRAINING SUPERVISOR OPwt~IS' MANAGER iggnee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2.

Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

JPM PERFORMED BY:

REASON, IF UNSATISFACTORY:

min.

N/A min.

GRADE:

m SAT EZjUNA EVALUATOR'S SIGNATURE:

DATE:

Nuclear Common 2003-N RC-LSRO-A1 -2 Page 1 Rev. 0

NC.TQ-WBI.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Conduct of Operations Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations SYSTEM:

TASK:

TASK NUMBER:

2.1.18 - Ability to make accurate / clear and concise logs / records / status boards /

and reports.

INITIAL CONDITIONS:

Operational Condition 5, with the reactor core fully loaded.

The One-Rod-Out Interlock is operable.

Control Rod Drive Mechanism 30-35 has been removed.

All other rods are at 00.

Control Rod Drive Mechanism 22-39 is scheduled to be replaced next.

The CRS directs HC.OP-DL.ZZ-0026 logs for ITEMS 12, 13, and 14 to be taken for the midnight shift.

The following Control Rods are hydraulically disarmed for this work.

14-31 18-31 22-31 26-27 30-27 34-27 38-27 14-35 18-35 22-35 26-31 30-31 34-31 38-31 14-39 18-39 22-39 26-35 30-35 34-35 38-35 14-43 18-43 22-43 26-39 30-39 34-39 38-39 14-47 18-47 22-47 26-43 30-43 34-43 38-43 26-47 30-47 1

INITIATING CUE:

Complete HC.OP-DL.ZZ-0026 Attachment 2, ITEMs 12, 13, & 14 for the midnight shift.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Nuclear Common 2003-N RC-LSRO-A1 -2 Page 2 Rev. 0

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Conduct of Operations Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NC.TQ-vvB.ZZ-031 0(Z)

NAME:

DATE:

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for lll___(#Denotes a Sequential Step) ll_l S/U UNSAT evaluation)_

Operator obtains procedure HC.OP-Operator obtains the correct procedure.

DL.ZZ-0026 (Q).

Operator reviews precautions and Operator reviews precautions and limitations.

limitations.

EXAMINER CUE: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator reviews all applicable prerequisites.

EXAMINER CUE: All applicable prerequisites have been met.

Operator determines beginning step of the Operator determines correct beginning step procedure.

to be 3.2.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NC.TQ-iB.ZZ-031 0(Z)

NAME:

DATE:

SYSTEM:

Conduct of Operations TASK:

Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation) 3.2 If in OP CON 4 or 5 then complete Operator obtains Attachment 2. as follows daily.

EXAMINER NOTE: Initialing steps is not critical.

EXAMINER NOTE: After operator obtains DL-26 Attachment 2, provide operator with copy to use.

ITEM 12 START TIME 4 FUEL ASSEMBLIES SURROUNDING EACH REMOVED CONTROL ROD OR MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL OR ALL OTHER CONTROL RODS IN A 5X5 ARRAY HAVE BEEN INSERTED AND DISARMED.

EXAMINER NOTE: Provide operator with copy of core map.

Operator uses list of hydraulically disarmed Control Rods to determine that Control Rod 30-35 DOES NOT meet this requirement.

The operator marks ITEM 12 in the MID column NO or UNSAT.

The operator red circles the out-of-spec condition. (Not critical)

Operator informs the CRS of the UNSAT EXAMINER CUE: Acknowledge the item.

operator report.

If necessary, CUE: Continue with the remaining items.

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NC.TQ-w B.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Conduct of Operations Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NAME:

DATE:

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l

_lll____(#Denotes a Sequential Step) ll S/U UNSAT evaluation)

ITEM 13 Operator obtains last performed copy of Operator obtains last performed copy of HC.OP-ST.SF-0001 from Completed ST HC.OP-ST.SF-0001 from Completed ST file drawer.

file drawer.

Obtain date of last completion from Operator obtains the last completion date HC.OP-ST.SF-0001 Attachment 1 POST of the last ACTUAL performance date from TEST INFORMATION. of HC.OP-ST.SF-0001.

EXAMINER NOTE: After operator obtains latest completion date, provide operator with marked up exam copy to use.

OPERATOR COMPARES Operator determines difference is 19 SATISFACTORY COMPLETION DATE months.

TO TODAYS DATE.

The difference between Satisfactory completion date and today's date are entered into Attachment 2 "MID" column.

The operator marks ITEM 13 in the MID column as 19 MO or UNSAT.

The operator red circles the out-of-spec condition. (Not critical)

Nuclear Common 2003-NRC-LSRO-A2 Page 5 REV.: 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Conduct of Operations Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NC.TQ-vvB.ZZ-031 0(Z)

NAME:

DATE:

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l _l l_l_(#Denotes a Sequential Step) ll_l S/U UNSAT evaluation)

Operator informs the CRS of the UNSAT Operator informs the CRS of the UNSAT

item, item.

EXAMINER CUE: Acknowledge the operator report.

If necessary, CUE: Continue with the remaining item.

ITEM 14 ALL OTHER CONTROL RODS ARE Operator determines from the initial INSERTED.

conditions that all other rods are inserted.

Operator marks ITEM 14 as YES or SAT.

Operator submits DL-26 log items 12, 13, and 14 to the CRS for review.

STOP TIME TERMINATING CUE: This JPM is complete.

Nuclear Common 2003-NRC-LSRO-A2 Page 6 REV.: 0

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Operational Condition 5, with the reactor core fully loaded.

The One-Rod-Out Interlock is operable.

Control Rod Drive Mechanism 30-35 has been removed.

All other rods are at 00.

Control Rod Drive Mechanism 22-39 is scheduled to be replaced next.

The CRS directs HC.OP-DL.ZZ-0026 logs for ITEMS 12, 13, and 14 to be taken for the midnight shift.

The following Control Rods are hydraulically disarmed for this work.

14-31 18-31 22-31 26-27 30-27 34-27 38-27 14-35 18-35 22-35 26-31 30-31 34-31 38-31 14-39 18-39 22-39 26-35 30-35 34-35 38-35 14-43 18-43 22-43 26-39 30-39 34-39 38-39 14-47 18-47 22-47 26-43 30-43 34-43 38-43 26-47 30-47 1

INITIATING CUE:

Complete HC.OP-DL.ZZ-0026 Attachment 2, ITEMs 12, 13 and 14 for the midnight shift.

Nuclear Common Page 7

C~opy.

CORE MAP 60 Be 56 54 52 50 4H 46

-44 I 42 1 40 E 38 1 36 1 34 N

32 30E 26E 24 1 26 204 i E 16 14 12 10oa 06 04 02 ol 0 Deg 0103 050 7 09 11 13 15 1719 21 2325272931 33353739 4143 454749 5j 535557 59 E3olus 60 M

58 on I

2@ELE 3EiE31EE 56 FaOHM 54 0 ELM 48 E3 i

50 Ad11 13 S.

L3~~ I3 MIM E13 46 EEElm MMM 44 E 0 0 0 9 1 3 1 1 2 2 2 7 2 1 3 3 7 4 4 3 4O il347 g~~~~

M 3E382W3 B3 EE3E mugSgL~s 20 to13~g E3§3Mf3g3 E33E 3mlEE1m~E 16 Po ME~l~s31E31

,1TBDBEBE

~

lmt~r 14 MUR IML E@ EY 3EIE.d 3E 3E 04 a3035s070s91113151 7 9 a12325272s~ 3335s37 39 41 43 ei 47 49 51 5355 57 59

LPRM H IRM n

SRM

b~IlX

Qsbs,

I PSEG Internal Use Only

(,

KEY HC.OP-DL.ZZ-uO26(Q)

PaSe 2 of 5 ATTACHMENT 2 Refuel/Core Alterations HCGS Date OPER ACCETABLE LIMITS ITEM SURVEILLANCE COND MEN NORM MAX INSTRUMENT (PANEL)

DAY EVE MID COMMENTS IF CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER TIS 3.9.10.1 OR 3.9.10.2THEN COMPLETE ITEMS 10 AND 1I I1 EWISE MARK i I Me - NIA 10 REACTORMODESWITCH 4,5 LOCKED (10C651)

POSI_1ON IN SID OR FREFUEL I }.

FUEL LOADING OPERATIONS 4,5 YES N/A SUSPENDEDE_

(NOTE 1)

D-017 0Ir 0 >

m 0

z I

-A m

I 0U

-Hi z

G-)

m c

I-CD C')

P rn IF CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER TS 3.9.10.1, THEN COMPLETE ITEMS 12 THRU14, OTHERWISEMARK11hMb N1A

12.

4 FUEL ASSEMBLIES 4,5 YES N/A SURROUNDING EACH REMOVED CONTROL ROD OR MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL OR ALL OTHER CONTROL RODS IN A 5X5 ARRAY HAVE BEEN INSERTED AND DISARMED.

13.

VERIFYHC.OP-ST.SF-000I(Q) 4,5 ISMO N/A IS CURRENT.

14.

ALL OTHlER CONTROL RODS 4,5 YES ARE INSERTED I

I S, ---

A

-F V11

r.

9N A IF CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER T/S 3.9.10.2,THEN COMPLETE ITEMS 15 ANI 16, OTrRWISE MvuArK Ii r

-N/

15.

THE 4 FUEL ASSEMBLIES l

5 YES l

N/A SURROUNDING EACH REMOVED CONTROL ROD OR MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL.

16.

ALLOTHER CONTROL RODS 4.5 YES lAREINSERTED ni-v,

.5' 6

ITIXIT Ac~~JATQ

'TCH JSi'rwr BN AINATND "LeCK F

(.NO 3)

(NOTE 3)

NOTibb:

3. THE ONE-ROD-OUT INTERLOCK MAY BE BYPASSED FOR THE AFFECTED CONTROL CELLS AFTER THE FUEL IS REMOVED FROM THE CELLS (r/S 3.9.10.2.A)

Hope Creek Page 54 of 102 Rev. 86

KEY CORE MAP 6'

51 5'

5' 5'

.44 42 38 36 34 32 30 26 26 24 22 20 19 16 14 12 10 GB 06 04 02 01 03 05 07 09 12 13 a

a PINE 01 0 in S4 m a*10 S2 E ilks§ so E ES 4 131110l 910 5 70 1S 1 31 15 17 1S 21 2325272 3133353739 41 4345 47 49 51 535557 59 BERMSg ag 60 E

SS31E E~~tllEI

-LEINm B3S j

r e

56 54 152 l1R iSB EMIRa 4e 203 446 W~JOE lMTJ 44 342 J L 3 40 0EUSEl EEILI113 WIl~N 30 QI@@Xl gllS l~lS24 Miami 16 31 3 5 7 9 14345 743 153517 MUgE W

g a

E 12 2l~l~l2E@E2l$E~@E§lE 206 aSim EIEl 3

3 t

T 02

.S 17 19 21232527 29 333 35 3739 41 43 454t7 4'i) 51 53 55 57 59

LPRM H IRM U SRM I

a&E6T (ZcW5 -Pl,"M0d 0D15ftr De MiS~ff) (t06

I'SliFG Internal Usc Only TRAINING ONLY Page I of 2 PSEG NUCLEAR L.L.C.

HOPE CREEK GENERATING STATION HC.OP-ST.SF-0001(Q) - Rev. 5 REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS I S CATEGORY: I RI'VISION SUMIMJARY Biennial Review performed Yes No N A a/

I.

Notificatioln 20074864 - the following procedure changes allows partial performance of this procedure while performing Reactor shutdown:

Former Step ).1.4 "Plant is in Condition 3. 4 or 5" has been deleted.

Former Step 5.1.4 "ENSURE the Reactor Mode Switch is in the REFUEL position" has been deleted. Step 2.5 already states "The Reactor Mode Switch can be placed ill RUN. REFUEL, OR START UP & HOT STDY."

Tie followingJ changes were made in this revision to bring the procedure in line wxvith the rules uo\\ erning" procedure format, content. and writer/reviewer guidelines, as contained in NC.NA-

\\\\ (J.7Z/-O00I(Q). lProcedure Writers Guide and reflect an identical change approved in an equal or hi7llhcr tier procedurl-.

These changes can be considered Editorial in nature.

'-This procedure has been revised to add Document Security classification statement PSI(

Internal Use Onlvy to procedure header.

All procedure references to WCCS have been deleted. Generic change.

Throughout this procedure. the word Initials has been removed from the place keeping column. Due to the extensive changes, revision bars were omitted.

This entire procedure has been re-formatted to conform to NC.NA-WG.ZZ-000 I (Q)

[Step 4. 1 0.3 of the Writers Guide states "When formatting instructions in steps. substeps or details. include at least two items at that level (no A without a B. no I without a 2. etc.).

Rewrite steps, substeps or details to prevent single items."] This statement is applicable to Sections 2.0 & 5.0.

CAUTION 5.0 has been deleted, redundant information.

The information previously contented in CAUTION 5.1.4 has been placed into Step 5.4 and the caution has been deleted. This change has been incorporated to conform to NC.NA-WG.ZZ-000 l (Q); Writers Guide ["never use a Note or Caution to convey a required action"]

IFIPLEMIENTATION REQUIREMENTS Effective date APRltOVED:

TRAINING ONLY Manager - Hope Creek Operations Date

PSEG Internal Use Only TRAINING ONL Y Page 2 of 2 PSEG NUCLEAR L.L.C.

HOPE CREEK GENERATING STATION HC.OP-ST.SF-0001(Q) - Rev. 5 REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS USE CATEGORY: I CONTINUATION SHEET REVISION

SUMMARY

2.

Continued (Editorial changes)

The information previously contented in CAUTION 5.13.5 regarding compliance with Tech Specs has been placed into Step 5.13.4 and the caution has been deleted. This change has been incorporated to conform to NC.NA-WG.ZZ-000I(Q); Writers Guide ["never use a Note or Caution to convey a required action']

The information previously contented in former CAUTION 5.1.12.J has been placed into Step 5.12.11 and the caution has been deleted. This change has been incorporated to conform to NC.NA-WG.ZZ-000I(Q); Writers Guide ["never use a Note or Caution to convey a required action"]

The information previously contented in former CAUTION 5.1.12.Q has been placed into Step 5.12.19 and the caution has been deleted. This change has been incorporated to conform to NC.NA-WG.ZZ-0001(Q); Writers Guide ["never use a Note or Caution to convey a required action"]

Revised Step 6.1 by changing NC.NA-AP.ZZ-0003(Q), Document Management Progran to NC.NA-AP.ZZ-00 1 (Q), Records Management Program.

Attachment has been revised to conform to SAP

3.

Step 2.3 [indications] has been re-worded. This step previously stated, "Full Core Display lights indicate a full RPS Trip". The step has been re-worded to state, "Scram lights on Full Core Display indicate a full RPS scram." [Department reviewer's comments]

TRAINING ONL Y HC.OP-ST.SF-OOO 1(Q)

ATTACHMENT 1 OS/CRS DATA AND SIGNATURE SHEET REACTOR MODE SWITCH FUNCTIONAL TEST -18 MONTHS (Page 1 of 3)

1.

P RETEST INFORMATION I.1 Reason for the Test 1.1.1 I.1.2 RCeOl.Iar Surveillance IS INITIALS Retest INITIALS 1.1l3 IF not performing the complete test.

THEN LIST subsections to be performed.

SUBSECTION(S)

I.2 Plant Conditions 1.2.1 I. _2. _

Operational Condition Reactor Powver Level 4

O 0

1.2.3 GMWe 1.3 Permission to Perform the Test 1.,.1 Permission granted to perform this test.

John Smith OS/CRS

/ 08/10/01-0700 DATE-TIME 16146504897 1.3.2 Order No.

Hopse Creek Page 17 of 26 Rev. 5

TRAINING ONLY HC.OP-ST.SF-OOO1(Q)

ATTACHMENT 1 OS/CRS DATA AND SIGNATURE SHEET REACTOR MODE SWITCH FUNCTIONAL TEST -18 MONTHS (Page 2 of 3)

I. A OST TEST INFORMATION 1l data acquired dLrlhin! the performance of this test has been reviewed for completeness and compliance with Technical Specification 4.3.1. I Table 4.3. l. I -

Item I I anid 4.3.6 Table 4.3.0-1 Ite m 7 and 4.3.1.2 and the test is considered:

.1. I SATISFACTORY (All acceptance criteria is marked SAT)

Joohn Smith

/

OS/CRS

.1.2 UNSATISFACTORY and IF necessarv the T/S ACTION statement has 08/10101-1 753 DATE-TIME been implemented.

/

OS/CRS DATE-TIME

. 1.

Order No.

21.1.4 Remarks:

I lopre Crecek Page 18 of 26 t7 Rcv. 5

TRAINING ONLY HC.OP-ST.SF-0001(Q)

ATTACHMENT 1 OS/CRS DATA AND SIGNATURE SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page 3 of 3) 3.0 PROCEDURE PERFORMER(S) AND VERIFIER(S) 3.1 I have read and understand the steps of this procedure that I am required to perform.

(All Departments)

PRINT NAME SIGNATURE INITIALS DATE/TIME Russet Crowe

/ RSussefCrowe /____

Q1 8i+/-/10/010800 I_____

/I____

/_____

/___

/_____

/___

/_____

/___

/_

/______

/

_________/___________

/____

/______

/____/____

,1____

/1____

/_____

/________

/_______

/______

/___

/_____

Hope Creek Page 19 of 26 Rev. 5

TRAINING ONLY HC.OP-ST.SF-OOO 1(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page I of 7) 1.(

Reactor Mode Switch Functional Test 1

NOMENCLATURE REQUIRED ACTUAL SAT!

l PERF

__ I_

UNSAT RD OUT MOTlON BLOCK lANNIUN NOT ANNUN.\\OT S.IT ENERGIZED ENERGIZED____

i D3455-RPS MODE SWITCH A I SHUTDOWN SCRAM BYPASS NOT IN ALARM NOT/.

SAT 1)3456-RPS MODE SWITCHI C SH 1UTDOWN SCRAM BYPASS NOT IN ALARM 7OT/N S-7 ALARA!

1)3457-RPS MODE SWITCH B SSHUTDOWN SCRAM BYPASS NOTINALARM NOTI SA T7 ALARM-D3458-RPS MODE SWITCH D SHUTDOWN SCRAM BYPASS NOT IN ALARM NO T i Sl T T

I_____ALARAMWI MOFN1DE SWITCH SHUTDOWN ANNUN ANN VN SCRAM BYP ENERGIZED ENERGIZED S.A1T I)345 - RPS MODE SWITCH A SHUTDOWN SCRAM BYPASS IN ALARM INALOTRI SA T W

D3456-Rl'S MODE SWITCHI C SIIUT-EDOWN SCRAM BYPASS IN ALARM INALARMJ SAT D3457-RPS MODE SWITCHI B -

SHUTDOWN SCRAM BYPASS IN ALARM INEALARMI SAT 1)3458-RPS MODE SWITCH D SHUTDOWN SCRAM BYPASS IN ALARM INALARA!

SAT STE.I' NOMENCLATURE REQUIRED ACTUAL SAT!

PERF UNSAT I

SUI REACTOR SCRAM TRIP LOGIC Al ILLUMINATED ILLUtA.TED SAT 5.8.2 REACTOR SCRAM TRIP LOGIC A2 ILLUMINATED ILLUAIATED SAT 5 S..

REACTOR SCRAM TRIP LOGIC BI ILLUMINATED ILLUMIN4ATED SAT 5.8.4 REACTOR SCRAM TRIP LOGIC B2 ILLUMINATED ILLUMINATED SAT W

Acceptance Criterion - the SAT/UNSAT block must be marked SAT.

[lop~e Creek pCPage 20 of 26 Rev. 5

TRAINING ONLY HC.OP-ST.SF-OOO1(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page 2 of 7)

S I'TE NOMENCLATURE REQUIRED ACTUAL SAT/

PERF UNSAT NORMAL/RESET - LOGIC AI DE-ENERGIZED DE-EVERGIZED A T

,S. (

NORMAL'RESET -LOGIC A2 DE-ENERGIZED DE-LEX-E:RGIZED S1i7i 7 -.

N)RMiAL;RESET-LOGIC Bl DE-ENERGIZED DE-VEXRGIZED LiT

8. 8s NNORMIAL/RESET -LOGIC B2 DE-ENERGIZED DE-E.\\ERGIZED SL4 T

.'. I ROD OUT MOTION BLOCK ILLUMINATED ILLL'AIIA-11 TEL)

LT I

CAN NOT BE CAN\\' NOT BE CONTROL ROD WIHDAW4J'THRTI I I REACTOR SCRAM TRIP LOGIC Al DE-ENERGIZED DE-E.\\ERGIZED SA 7' I

REACTOR SCRAM TRIP LOGIC A2 DE-ENERGIZED DE-E.\\ERGIZED SL47IT I.1.3 REACTOR SCRAM TRIP LOGIC BI DE-ENERGIZED DE-E.\\ERGIZED LS4 T I.4 REACTOR SCRAM TRIP LOGIC B2 DE-ENERGIZED DF=E-ERGIZED LSI-lT

.1 1.5I NORMAL/RESET LOGIC Al ILLUMINATED ILLUMIINA TED SAT

1. 1.6 NORMAL/RESET LOGIC A2 ILLUMINATED ILLUMINA TED SA T 5.1 1.7 NORMAL/RESET LOGIC B I ILLUMINATED ILLUAfIIATED SA T 1.8 NORMAL/RESET LOGIC B2 ILLUMINATED ILLUMVINATED SA l C5-C4 DISCH VOL HI WTR LVL ANNUN NOT ANNUN NOT SAT TRIP BYP ENERGIZED ENERGIZED D3463-RPS DISCH VOL HIGH.WTR NOT IN ALARM NOTINALARAl SAT LVL TRIP BYP CHAN A N______f

-L

5. 1 2.3 D3464-RPS DISCH VOL HIGH WTR NOT IN ALARM NOTIN ALARM SA T D

LVL TRIP BYP CHAN C N

ASR A

D3465-RPS DISCH VOL HIGH WTR NOT IN ALARM NOTIALARAI SAT LVL TRIP BYP CHANB b

mutb akdST D3466-RPS DISCH VOL HIGH WTR NOT IN ALARM NOTIN ALARMt SA T quj,_

LVL TRIP BYP CHAN D

Acceptance Criterion - the SAT/UNSAT block must be marked SAT.

I lope Creeko Page 21 of 26 Rev. 5

TRAINING ONLY HC.OP-ST.SF-OOO1(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page 3 of 7)

STEP NOMENCLATURE REQUIRED ACTUAL SAT!

PERF UNSAT___

C5-C4 DISCH VOL HI WTR LVL ANNUN NOT AAANUNNOT SAT TRIP BYP ENERGIZED ENERGIZED

(

C5-C3 MSIV CLOSURE TRIP ANNUN NOT ANNUN NOT SATT BYP ENERGIZED ENERGIZED D3463-RPS DISCH VOL HIGH NOT IN ALARM VOTJI ALARAJ SAT WTR LVL TRIP BYP CHAN A D3464-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT WTR LVL TRIP BYP CHAN C D3465-RPS DISCH VOL HIGH NOT IN ALARM VOTINALARM SAT WTR LVL TRIP BYP CHAN B D3466-RPS DISCH VOL HIGH NOT IN ALARM NVOTINALARM SAT R'D 5.12.6 WTR LVL TRIP BYP CHAN D NOTINALA__

D3451 - RPS MSL A CLOSURE NOT IN ALARM NOTiNALARU SAT TRIP BYP

\\

D3452 - RPS MSL C CLOSURE NOT IN ALARM lOTIN ALARM SAT TRIP BYP NOT IAAM___

D3453 - RPS MSL B CLOSURE NOT IN ALARM NOTINALARA!

SAT TRIP BYP D3454 - RPS MSL D CLOSURE NOT IN ALARM

,VOTINLALARM SAT TRIP BYP C5-C4 DISCH VOL HI WTR LVL ANNUN NOT ANNUNNOT SAT TRIP BYP ENERGIZED l_ENERGIZED WC D3463-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT U

WTR LVL TRIP BYP CHAN A 5.12.8 D3464-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT WTR LVL TRIP BYP CHAN C D3465-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT WTR LVL TRIP BYP CHAN B N

N M__

D3466-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT D

WTR LVL TRIP BYP CHAN D

Acceptance Criterion - the SAT/UNSAT block must be marked SAT.

Hope Creek H CPage 22 of 26 Rev. 5

TRAINING ONL Y HC.OP-ST.SF-0001(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST -18 MONTHS (Page 4 of 7)

STEP N

NOMENCLATURE REQUIRED ACTUAL SAT/

PERF UNSAT i C'-C4 DISCH \\VOL 1I{ WTR LVL ANNUN NOT NOT TRIP BYP ENERGIZED E.NERGIZED

, T W

Y1 6-RPS DISC'I VOL HIGH NOT IN ALARM

\\07 7\\

II ii?

/ '

E

\\N-I-R1

\\1

'IRII'BYIAC'H N A.A.

.AR

\\WTR LVL TRIP BYP CHAN A I 12. I()

D33464-RPIS DISCH VOL HIGH NTI LR

'T~iI~

A 1 \\VTR LVL TRIP BYP CHAN C NOT ILVt S

D3465-RPS DISCH VOL HIGH NTI LR ol\\LRI ST

~

f

\\\\'TR LVL TRIP BYP CHAN B NOT IN A M____

D3466-RPS DISC.

VOL HIGH NOT INAL........

SAT

\\WTR LVL TRIP BYP CHAN D WU__

C5-C4 DISCH VOL Hi W'I K LVL TRIP RYP ANNUN NE I ENERGIZED ENERGIZED SA T 7ID

. I. I.1 D3463-RPS DISCH VOL HIGH NOT IN ALARM NOTIN.ALARM SAT WTR LVL TRIP BYP CHAN A D3464-RPS DISCH VOL HIGH NOT IN ALARM NOTINAL4RAI SA

\\'TR LVL TRIP BYP CH{AN C NOTINALARM D3465-RPS DISCII VOL HIGH NOT IN ALARM NOT INLRA!

SAT

'-TR LVL TRIP BYP CHAN B D3466-RPS DISCH VOL HIGH

\\WVI-R LVL TRIP BYP CHAN D NOT IN ALARM NO T 1\\ AL-RAl SA T CSC3 MSIV CLOSURE TRIP ANNUN SAvTUN KD T

BYP ENERGIZED ENERGIZED S

D3451 - RPS MSL A CLOSURE IN ALARM INALARAI SAT TRIP BYP D.1-.

D3452 - RPS MSL C CLOSURE IN ALARM INALARM SAT TRIP BYP D3453) - RPS MSL B CLOSURE IN ALARM INAAMSA T

TRIP BYP IN ALARM INALARMSAT D3454 - RPS MSL D CLOSURE IN ALARM INALARAI1 SAT TRIP BYP

. Acceptance Criterion - the SAT/UNSAT block must be marked SAT.

I-Jope Creek Page 23 of 26 Rev. 5

TRAINING ONLY HC.OP-ST.SF-0001(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page 5 of 7) r mT~k I CAI'l I

D 'Drw STEPl NOMENCLATURE REQUIRLb)

Al_ I UAL, UNSAT I 'L Li, 'L I

(Ž-C4 DISCH VOL HI WVTR LVL ANNUN NOT A;VVUA'AOT ST 7 TIP BYP ENERGIZED EAERG/ZED D3463-RPS DISCH VOL 1-uGH NOINARM

\\I\\IlR

£T D46-RPSVL DISI-VL CHIG A NOT IN ALARM

\\T7'4LlIsI SAT K

WTR LVL TRIP BYP CHAN C NOTIN AR.L.

R.I S

5 216 D3464-RPS DISCH4 VOL HIGH NTI LR OI LR A

WTR LVL TRIP BYP CHAN B D3466-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARAI SAT C5-C4 DISCH VOL HI WTR LVL ANNUN NOT AN,VUAA'OT SAT IPf TRIP BYP ENERGIZED E.ERGIZED D3463-RPS DISCH VOL HIGH NOT IN ALARM NOTIALARM SA T

\\\\:TR LVL TRIP BYP CHAN A I 3.1.1 t 1)64 RISV TRIPCHYVOLHHIGH NOT IN ALARM VOTIXNALAJAI SAT

\\VTR l VL TRIP BYP CHAN C O

NAAM

.OIVL4.I ST

§ D3,466-RPS DISCH VOL HIGH NOT IN ALARM A'OTlVIL.-IRtl SA T

§ f C5-C4 DISCH VOL HI WTR LVL ANNUN NOT ANNWUVANOT SA T TRIP BYP ENERGIZED ENERGIZED D3463-RPS DISCH VOL HIGH NOT IN ALARM NOTlNALARAl SAT R

WT,-IR LVL TRIP BYP CHAN A IS 5.12.21 D3464-RPS DISCH VOL HIGH NOT IN ALARM NOTINALAR SAT W\\TR LVL TRIP BYP CHAN C D3465-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT WTR LVL TRIP BYP CHAN B NTM OTINALAR D3466-RPS DISCH VOL HIGH NOINARM NNALM ST 7

WTR LVL TRIP BYP CHAN D VOT___

__4__

Acceptance Criterion - the SAT/UNSAT block must be marked SAT.

Hope Creek Page 24 of 26 Rev. 5

TRAINING ONLY HC.OP-ST.SF-0001(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page 6 of 7)

STEP NOMENCLATURE REQUIRED ACTUAL SAT/

PERF UNSAT C5-C3 MSIV CLOSURE TRIP ANNUN ANNUN SA T BYP ENERGIZED ENERGIZED SA D3451 - RPS MSL A CLOSURE IN ALARM INALARYU SAT TRIP BYP 5.12.22 D3452 - RPS MSL C CLOSURE IN ALARM INALARU SAT TRIP BYP NR D3453 - RPS MSL B CLOSURE IN ALARM INALARM SAT (D

TRIP BYP D3454 - RPS MSL D CLOSURE IN ALARM INALARM SAT TRIP BYP C5-C4 DISCH VOL HI WTR LVL ANNUN ANNUN TRIP BYP ENERGIZED ENERGIZED SA T D3463-RPS DISCH VOL HIGH N

WRLLTIBYCHNCIN ALARM INALARM SAT WTR LVL TRIP BYP CHAN AIARMNLA__

5.12.24 D3464-RPS DISCH VOL HIGH IN ALARM INALARM SAT T WTR LVL TRIP BYP CHAN C 1

D3465-RPS DISCH VOL HIGH IN ALARM INALARM-SAT WTR LVL TRIP BYP CHAN B K

D3466-RPS DISCH VOL HIGH IN ALARM INALARM SA T ID WTR LVL TRIP BYP CHAN D NNALARM SA__T C5-C4 DISCH VOL HI WTR LVL ANNUN NOT ANNUNNOT SAT T TRIP BYP ENERGIZED ENERGIZED W

D3463-RPS DISCH VOL HIGH NOT IN ALARM NOT IN ALARM SA T

~

WTR LVL TRIP BYP CHAN A 9

5.12.26 D3464-RPS DISCH VOL HIGH NOT IN ALARM NOTIN'ALARM SA T qu WTR LVL TRIP BYP CHAN C W

D3465-RPS DISCH VOL HIGH NOT IN ALARM NOTIN AARM SA WTR LVL TRIP BYP CHAN B NOTIA____

Tv D3466-RPS DISCH VOL HIGH NTI LR

____WTR LVL TRIP BYP CHAN D O

NAAM NOTIN ALARM SAWC(

Acceptance Criterion - the SAT/UNSAT block must be marked SAT.

Hope Creek Page 25 of 26 Rev. -5

TRAINING ONLY HC.OP-ST.SF-0001(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET REACTOR MODE SWITCH FUNCTIONAL TEST - 18 MONTHS (Page 7 of 7)

STEP NOMENCLATURE REQUIRED ACTUAL SAT/

PERF UNSAT C5-C4 DISCH VOL HI WTR LVL ANNUN NOT ANNUN NOT SA T TRIP BYP ENERGIZED ENERGIZED SA D3463-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT T WTR LVL TRIP BYP CHAN A

5. I'.8 D3464-RPS DISCH VOL HIGH NOT IN ALARM NOTINAL4RM SAT WTR LVL TRIP BYP CHAN C D3465-RPS DISCH VOL HIGH NOT IN ALARM NOTINAL4RM SAT T

WTR LVL TRIP BYP CHAN B W

D3466-RPS DISCH VOL HIGH NOT IN ALARM NOTINALARM SAT WTR LVL TRIP BYP CHAN D W

C5-C3 MSIV CLOSURE TRIP ANNUN ANNUN SAT BYP ENERGIZED ENERGIZED SAT D3451 - RPS MSL A CLOSURE IN ALARM INALAR&

SAT TRIP BYP

.D3454 - RPS MSL C CLOSURE IN ALARM

INALAR, SAT TRIP BYP D3454 - RPS MSL D CLOSURE IN ALARM INALARM SA T

_TRIP BYP 9

C5-C4 DISCH VOL HI WTR LVL ANNUN ANNUN SAT TRIP BYP ENERGIZED ENERGIZED SAT D3463-RPS DISCH VOL HIGH IN ALARM iNALA SAT WTR LVL TRIP BYP CHAN A INA____

5.12.30 D3464-RPS DISCH VOL HIGH IN ALARM INAL4RU SAT T

WTR LVL TRIP BYP CHAN C D3465-RPS DISCH VOL HIGH IN ALARM INALARM SAT WTR LVL TRIP BYP CHAN B D3466-RPS DISCH VOL HIGH IN ALARM INALARM SA T WTR LVL TRIP BYP CHAN D_

Acceptance Criterion - the SAT/UINSAT block must be marked SAT.

Hope Creek Page 26 of 26 Rev. 5

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION:

HOPE CREEK SYSTEM:

Equipment Control TASK:

Verification of Minor changes to the Fuel Movement Sheet IAW HC.RE-FR.ZZ-0001 (Q)

TASK NUMBER:

2.2.26 - Knowledge of refueling administrative requirements JPM NUMBER:

2003-NRC-LSRO-Admin A2 ALTERNATE PATH: m K/A NUMBER:

294000 G2.2.2 APPLICABILITY:

IMPORTANCE FACTOR:

2.5

.6 R7 iRO EO [

RO U SRO I LSF EVALUATION SETTING/METHOD:

CONTROL ROOM

REFERENCES:

HC.RE-FR.ZZ-0001 TOOLS AND EQUIPMENT:

NONE VALIDATED JPM COMPLETION TIME:

15 TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVED:

toIM T I I/SIMULATOR - PERFORM KU 0

min.

N/A min.

I NIA BARGAINING UNIT 0CD0=QDZI1TATIV/9 TRAINING SUPERVISOR SPIO*SMANAGER Ct Egnee FNra-U-m IA^

CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS Or Unit CRS;

2.

Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

JPM PERFORMED BY:

REASON, IF UNSATISFACTORY:

min.

N/A min.

GRADE:

a SAT El UNSAT EVALUATOR'S SIGNATURE:

DATE:

Nuclear Common 2003-NRC-LSRO-A2 Page 1 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROG JOB PERFORMANCE MEASL NAME:

DATE:

Equipment Control SYSTEM:

TASK:

TASK NUMBER:

2.2.26 - Verification of Minor changes to the Fuel Movement Sheet lAW HC.RE-FR.ZZ-0001 (Q) Attachment 4 INITIAL CONDITIONS:

Operational Condition 5, with the reactor core partially unloaded.

The Refueling Platform Operator found one of the move sheet pages missing.

The RE has a replacement page but needs an independent verification.

INITIATING CUE: Perform an Independent Verification of the Fuel Movement Sheet provided lAW HC. RE. FR-ZZ-000 1.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Nuclear Common 2003-NRC-LSRO-A2 Page 2 Rev. 0

(

NC.TL. B.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

TASK:

Equipment Control Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step) ll_l SIU UNSAT evaluation)

Operator obtains procedure HC.RE-Operator obtains the correct procedure.

FR.ZZ-0001 5.5.2 FORWARD the developed Fuel Movement Examiner Note: Provide Fuel Movement Sheet(s), Attachment 1, for Independent Sheet.

Verification.

5.5.2.A START TIME Using the Reactor Engineering Fuel Location Board, SIMULATE AND VERIFY the accuracy of all movements designated on the Fuel Movement Sheets, Attachment 1.

Examiner Note: Provide Core Quadrant Map, and Spent Fuel Pit Map.

Operator reviews Fuel Movement Sheet using criteria of HC.RE-FR.ZZ-0001.

Operator determines bundle WQ0447 CORE LOCATION 41-50 in the wrong orientation.

Correct orientation should be SE.

FOLLOWING the successful Independent Verification of the Fuel Movement Sheet(s),, SIGN AND DATE each sheet.

Operator withholds signature on Fuel Movement Sheet based on error found.

L _______________________________________________________________

Nuclear Common 2003-NRC-LSRO-A2 Page 3 REV.: 0

(I

(

NC.Tt.c-vVB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Equipment Control TASK:

Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NAME:

DATE:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for lll_(#Denotes a Sequential Step) ll_l S/U UNSAT evaluation)_

5.5.2.C IF fuel movement errors are found Examiner Cue: Make any necessary during the Independent Verification changes to the Fuel Movement Sheet for process, THEN RETURN the unverified the Refuel Floor.

Fuel Movement Sheet(s), Attachment 1, to the Preparer for disposition as necessary.

5.5.3 Identical copies of the Fuel Movement Operator reads step. Operator continues Sheet(s), Attachment 1, should be at step 5.6 produced for Refuel Floor, Control Room, and Reactor Engineering Department use. For new fuel receipt activities it is unnecessary for a copy of the Fuel Movement Sheet(s),, to be in the control room.

NOTE 5.6 NOTE 5.6 Operator reads note.

Errors found subsequent to the affected move being completed, must also be documented per the guidance in this Section.

Nuclear Common 2003-NRC-LSRO-A2 Page 4 REV-: 0

(

NC.TQ-vVB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Equipment Control Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NAME:

DATE:

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for l

(#Denotes a Sequential Step) ll_l SIU UNSAT evaluation) 5.6.1 IF it necessary to change the Fuel Examiner Cue: Perform as necessary to Movement Sheet(s), Attachment 1, to support fuel moves.

support unanticipated conditions on the fuel floor, THEN perform the following steps (Steps 5.6.1.A and 5.6.1.B should be performed in parallel with Step 5.6.1.C). (Ref. 7.13) 5.6.1.A CONTACT the on-shift Reactor Engineer.

Examiner Note: Role play as Reactor Engineer.

5.6.1.B DESCRIBE the reason for the change (the Operator requests the RE change the problem) and provide a proposed revision to move sheet for proper orientation of bundle the on-shift Reactor Engineer.

WQ0447 to SE orientation.

Examiner Cue: Repeat back request for change.

5.6.1.C IF the current step cannot be completed as Not applicable.

written, THEN place it in a temporary storage location in the SFP, which is approved by the Reactor Engineer.

Otherwise, suspend fuel movement sequence execution prior to execution of the Fuel Movement Sheet(s), Attachment 1, step-requiring change.

Nuclear Common 2003-NRC-LSRO-A2 Page 5 REV.: 0

(

NC.TQ-vnB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Equipment Control Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NAME:

DATE:

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

SIU UNSAT evaluation) 5.6.2 The Reactor Engineer contacted shall perform the following steps based on the information provided.

5.6.2.A EVALUATE the effect of the change on the Examiner Cue: Change does not effect remainder of the Fuel Movement Sheet(s),

the remainder of the Fuel Movement, AND make appropriate Sheet(s).

changes to maintain congruency of sequence.

5.6.2.B COMPLETE Attachment 4, Verification of Examiner Note: Provide completed Minor Changes to the Fuel Movement Sheet, change sheet HC.RE.FR-ZZ-0001 to determine if the change is considered for Refueling SRO review.

minor and will not affect Shutdown Margin.

Operator reviews the completed change sheet HC.RE.FR-ZZ-0001 Attachment 4 and signs the "Reviewed By" Refueling SRO signature space.

5.6.2.C IF any of the changes may adversely impact Examiner Cue: RE provided Attachment Shutdown Margin as determined by 4 to answer question., Verification of Minor Changes to the Fuel Movement Sheet, THEN evaluate Operator should go to step 5.6.2.E the impact of the change on calculated SDM.

Nuclear Common 2003-NRC-LSRO-A2 Page 6 REV.: 0

f NC.TQ-vVB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Equipment Control Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NAME:

DATE:

SYSTEM:

TASK:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for llll_(#Denotes a Sequential Step) l S/U UNSAT evaluation) 5.6.2.C. 1 Compare the K-infinity of the assembly in the Examiner Cue: RE says K Infinity is not approved sequence to the proposed change.

changed.

IF the K-infinity values are not available, THEN the performance of step 5.6.2.D is required.

5.6.2.C.2 IF the assembly K-infinity, for the proposed Examiner Cue: RE says K Infinity is not change, is equal to or less than the approved changed.

sequence assembly K-infinity, and it is being moved to the SAME location, THEN the change does not adversely affect SDM.

5.6.2.D IF the changes are believed to affect SDM, Operator determines SDM is not affected.

THEN ensure SDM is met in accordance with Precautions and Limitations 3.4 AND approval process in Step 5.5.1.

5.6.2.E IF completion of Attachment 4, Verification of Operator continues to step 5.6.2.E.1 Minor Changes to the Fuel Movement Sheet, determines that the changes are minor and do not affect SDM, THEN the Reactor Engineer AND the SRO shall perform the following:

Nuclear Common 2003-NRC-LSRO-A2 Page 7 REV.: 0

I(

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Equipment Control TASK:

Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NC.Tt.

VIB.ZZ-0310(Z)

NAME:

DATE:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation) 5.6.2.E. 1 The SRO shall perform pen & ink change on Examiner Cue:

Refuel Floor Fuel Movement Sheet(s),

This is the Refueling Floor copy, AND any Refuel Floor copies.

Operator pen and ink changes the original move sheet IAW 5.6.2.E.5 5.6.2.E.2 The Reactor Engineer shall perform pen &

Examiner Cue: The RE has performed ink change on the office copy(s) of the Fuel this step.

Movement Sheet(s), Attachment 1.

5.6.2.E.3 The Reactor Engineer, SRO OR RO shall Examiner Cue: The RE has performed perform the pen & ink change on the control this step.

room copy of the Fuel Movement Sheet(s),, (if applicable).

5.6.2.E.4 The Reactor Engineer shall ensure that the Examiner Cue: The RE has performed change to the sequence is saved in this step.

"SHUFFLEWORKS."

5.6.2.E.5 The pen and ink change should follow the following format.

5.6.2.E.5.a.

Single line through the item to be Operator single lines through NE changed.

orientation of CORE 41-50 Nuclear Common 2003-NRC-LSRO-A2 Page 8 REV.: 0

(.

NC.TL -&VB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Equipment Control TASK:

Verify HC.OP-DL.ZZ-0026 log requirements for resuming Core Alterations NAME:

DATE:

STEP NO.

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation) 5.6.2.E.5.b.

Corrections marked clearly Marks correction "SE" 5.6.2.E.5.c.

If additional steps are required...

Not applicable to this change 5.6.2.E.5.d.

Date AND initials of both SRO and Operator dates and initials next to change.

Reactor Engineer (per telecon is acceptable provided SRO concurs).

Examiner Cue: The RE has marked as you directed.

5.5.2.A Using the Reactor Engineering Fuel Location Operator determines the Fuel Movement Board, SIMULATE AND VERIFY the Sheet for bundle WQ0447 at TO Location accuracy of all movements designated on 41-50 now has the correct orientation of the Fuel Movement Sheets, Attachment 1.

SE.

Operator verifies the remainder of the move sheet.

5.5.2.B FOLLOWING the successful Independent Operator signs the "Independently Verified Verification of the Fuel Movement Sheet(s),

By:" line of the new move sheet., SIGN AND DATE each sheet.

STOP TIME Terminating Cue: This JPM is complete.

I REV.: 0 Nuclear Common 2003-NRC-LSRO-A2 Page 9

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Operational Condition 5, with the reactor core partially unloaded

The Refueling Platform Operator found one of the move sheet pages missing

The RE has a replacement page but needs an independent verification.

INITIATING CUE:

Perform an Independent Verification of the Fuel Movement Sheet provided lAW HC.RE.FR-ZZ-0001.

Nuclear Common Page 10

(

HC.RE-FR.ZZ-0001 (Q)

ATTACHMENT 1 FUEL MOVEMENT SHEET KEY REFUEL NO.

10 SHEET NO.

1 CONTINUED ON SHEET 2

Step I.D.

FROM Time TO Time Operator Verified By Number Number Location Orientation Date Location Orientation Date Initials Initials 01-01 WQ0540 SFP SE CORE NE AS-46 43-42 01-02 WQ0447 SFP NW CORE N

AS-47 41-50 01-03 WQ0019 SFP SE CORE SW AS-48 37-56 01-04 WQ0171 SFP NW CORE NW AS-49 35-36 t60""da699 Lucre Prepared By Independently Verified By

-1,?

berg Date Date Hope Creek Page 18 of 23 Rev. 20

.DAT:'

Firxl Hope Crook 12 01/08/03

?+/-nal (ntcycle)

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HC.RE-FR.ZZ-0001 (Q)

ATTACHMENT 4 VERIFICATION OF MINOR CHANGES TO THE FUEL MOVEMENT SHEET IF question 1) is answered NO, THEN the Shutdown Margin MAY be adversely impacted and any changes to the movement sheet must be verified per step 5.6.2.C OR 5.6.2.D:

YES NO

1)

All changes involve: Blade guides OR Orientation of item ONLY, AND/OR Changes do NOT involve movement of fuel into core during a shuffle OR to a temporary (i.e., non-final) in-core location (e.g., fuel in or being moved to the SFP OR fuel being moved into its FINAL core location during a complete offload/reload, is acceptable).

IF any of the following questions is answered NO, THEN any changes to the movement sheet must be verified per step 5.5.2:

2)

Has the proposed change been checked for complete support of control rods?

3)

Has the proposed change been checked for conflicts with later moves?

4)

If later moves are impacted, do the RE and SRO CONCUR that performance of Step 5.5.2 (simulating moves using Fuel Location Board), is NOT required?

Effected Steps and Description of Change:

Step 01-02 WQ0447 TO Location orientation changed from NE to SE.

'1 N/

.1, I

IF ALL questions are answered YES, THEN change(S) may be made. per Step 5.6.2.E.

Completed by:

Reactor Engineer Date Reviewed by:

Refueling SRO Date Hope Creek Page 21 of 23 Rev. 20

(

HC.RE-FR.ZZ-0001 (Q)

ATTACHMENT 1 FUEL MOVEMENT SHEET REFUEL NO.

10 SHEET NO.

1 CONTINUED ON SHEET 2

Step I.D.

FROM Time TO Time Operator Verified By Number Number Location Orientation Date Location Orientation Date Initials Initials 01-01 WQ0540 SFP SE CORE NE AS-46 43-42 01-02 WQ0447 SFP NW CORE NE AS-47 41-50 01-03 WQ0019 SFP SE CORE SW AS-48 37-56 01-04 WQ0171 SFP NW CORE NW AS-49 35-36 1&dda 199 'e Prepared By 6 9 o o t'd 9.a1

~ e Date Independently Verified By Date Hope Creek Page 18 of 23Rev. 20

I 866 888 617 159

.1 III

I I

Y Z MAAEA AC AD AE AFAG AH AJ AK AL AM AN AP AQ AR AS AT AU AV AWAX AY AZ BABEBESCD BEEBF SG BH BJ BK EL BMBN BP BO BR

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Operational Condition 5, with the reactor core partially unloaded

The Refueling Platform Operator found one of the move sheet pages missing

The RE has a replacement page but needs an independent verification.

INITIATING CUE:

Perform an Independent Verification of the Fuel Movement Sheet provided lAW HC.RE.FR-ZZ-0001 Steps 5.6.2.

Nuclear Common Page 9

Matrix#

SRO QUESTION #

KACataloglD KA Statement SRORating Question level COGNITIVE LEVEL Question Topic REFERENCE Material Provided LEARNING OBJECTIVE QSOURCE QUESTION 1

Admin A3-1 G 2.3.5 Knowledge of use of personnel monitoring equipment 2.5 S

Fundamental Response to personnel contamination Radiation Worker Training Handout Page 31 Closed Reference Peach Bottom LSRO 2002 modified for Hope Creek Given the following conditions:

- An operator has exited the Refueling Platform after handling poles in the Fuel Pool

- The operator removed PC's at the step-off-pad undress area

- The operator alarmed the Personal Contamination Monitor on the refuel floor one time What are the operator's required actions?

CORRECT ANSWER 1-May re-monitor one time.

EXAMINER CUE: After the the operator states he would re-monitor, Cue: "The monitor alarms again" 2-Minimize the spread of contamination (i.e. contact with personnel, tools, or equipment, etc.)

3-Contact Radiation Protection for assistance

Student Copy SRO QUESTION #

QUESTION Reference material is not available for this question Admin A3-1 Given the following conditions:

- An operator has exited the Refueling Platform after handling poles in the Fuel Pool

- The operator removed PC's at the step-off-pad undress area

- The operator alarmed the Personal Contamination Monitor on the refuel floor one time What are the operator's required actions?

CONTAMINA TION SECTION If your hands are clean, pick up the probe, and move it over the body (or surface) at about two inches per second. DO NOT allow probe to touch the surface being monitored.

If you see an increase in indicated counts hold the probe still and if there is an increase of 100 cpm or more, there may be contamination present. If this occurs, stay where you are and contact RP.

The second type of frisking device is the personnel contamination monitor.

Three types of personnel contamination monitors are used at this site:

IPM8/IPM9 Portal monitors Hand and foot monitors Use caution when utilizing any of these devices to ensure that the detectors are not damaged. Ask for help from Radiation Protection or a demonstration if you need it. If the monitor alarms on any of these devices, stay where you are, minimize touching anything, and contact RP. NOTE: If you alarm an IPM, you may proceed to another monitor and check again. If you alarm it the second time, stay Where you are and contact RP. Radiation Protection personnel will direct you in the proper decontamination procedures if necessary.*

Control of When working on contaminated systems, it is possible to contaminate tools, Contaminated equipment, or materials. Company policy is to minimize the contaminatipn of Materials these articles. Some of the things that you can co to help in this effort are:

Minimize the amount of material contaminated while on the job. Use only those tools that are necessary, keep the amount of packing material taken into the RCA at a minimum, and minimize the amount of trash generated.

When getting tools for use in the RCA, get the tools needed from the hot tool issue point.

If a contaminated article needs to be taken out of a contaminated area, it may either be deconned (wiped down) before coming across the step-off pad or it should be bagged in a poly bag designated for radioactive material. Contact Radiation Protection personnel for direction.

Contaminated Signs warn you of plant areas that are known to be contaminated. These signs are Area Postings as follows:

31 of 54 April 2002

CONTAMINA TION SECTION

Contamination Area-This is an area that has > 1,000 dpm/I00 cm 2 of beta-gamma or 2 20 dpm/100 cm2 of alpha contamination. Entry requires RWP authorization and meeting the RWP entry requirements.

High Contamination Area-This is an area that has 2 100,000 dpm/ 100 cm2 of beta-gamma or > 1,000 dpm/100 cm2 alpha. Entry requires RWP authorization and meeting the RWP entry requirements.

Any area designated as a Contamination or High Contamination area will be posted. This area is typically roped off with yellow and magenta rope with signs hanging from the rope with the area designation. There is an entrance and exit to the area marked with a step-off pad. The step-off pads are the only authorized ways in or out of the area.

Failure to adhere to these requirements can result in the spread of contamination, personnel contaminations, and potential disciplinary action.

Prior to the start of work, prior to entering overhead areas or systems breaches, notify a knowledgeable Rad Pro technician to discuss the scope of the work, and any changes to the work plan and work methodology.

Entry and Exit iithrough the Control Point When entering or exiting the Control Point, care must be taken to complete all of the required steps. Self-checking using the STAR method is essential during this process.

Discrete Particles Discrete particles were discussed earlier and are a concern because an individual may receive a large dose due to the high levels of radioactivity these particles are capable of. Radiation Protection will provide special instructions when working in a discrete particle area. Several methods are employed by Radiation Protection to warn you of discrete particle hazards and keep dose ALARA. Ropes, signs, barrier tape, bull pens, or a combination may be used.

Awareness of discrete particles, changing radiological conditions, and radiological hazard postings are helpful in alerting you to radiological hazards.

There are several ways to identify a discrete particle:

When frisking, a discrete particle can cause the meter to rapidly rise to a much higher count rate. Remember that the frisker will respond only if you have it close enough to the discrete particle and are moving it slowly enough for the detector to respond.

32 of 54 April 2002

Matrix#

SRO QUESTION #

KACatalogi D KA Statement SRORating Question level COGNITIVE LEVEL Question Topic REFERENCE Material Provided LEARNING OBJECTIVE QSOURCE QUESTION 2

Admin A3-2 G 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure 3.3 S

Fundamental Requirements for removal of tools or equipment from the Spent Fuel Pool NC.RE-AP.ZZ-0049 Rev. 0 Step 3.3.1.G Closed Reference New While performing fuel bundle movements in the Fuel Pool, the Main Fuel Grapple must be stored to repair a submerged air line.

What radiological requirements must be met to remove the grapple from the water?

CORRECT ANSWER The Grapple must be surveyed when removed from the Spent Fuel Pool.*

Minimum answer required for full credit underlined

Student Copy SRO QUESTION #

QUESTION Reference material is not available for this question Admin A3-2 While performing fuel bundle movements in the Fuel Pool, the Main Fuel Grapple must be stored to repair a submerged air line.

What radiological requirements must be met to remove the grapple from the water?

Matrix#

SRO QUESTION #

KACataloglD KA Statement SRORating Question level COGNITIVE LEVEL Question Topic REFERENCE Material Provided LEARNING OBJECTIVE QSOURCE QUESTION 3

Admin A4-1 G 2.4.40 Knowledge of SRO's responiblities in emergency plan implementation 4.0 S

Comprehension EP Event requiring Accountability of plant personnel Emergency Preparedness Overview page 12&13 Open Reference New You are supervising operators loading new fuel bundles into the Fuel Pool when ACCOUNTABILITY is called.

What location(s) do they have to report to and what action(s) must they take at these location(s)?

CORRECT ANSWER

- The Control Point 137' elevation to frisk out. There is an ACCOUNTABILITY BADGE READER located at the Control Point but this is for RP and Security personnel inside the RCA.

- The operators then report to the Operations Support Center (OSC) to use the ACCOUNTABILITY BADGE READER located there.

Student Copy SRO QUESTION #

QUESTION Admin A4-1 You are supervising operators loading new fuel bundles into the Fuel Pool when ACCOUNTABILITY is called.

What location(s) do they have to report to and what action(s) must they take at these location(s)?

Matrix#

SRO QUESTION #

KACatalogID KA Statement SRORating Question level COGNITIVE LEVEL Question Topic REFERENCE Material Provided LEARNING OBJECTIVE QSOURCE QUESTION 4

Admin A4-2 G 2.4.41 Knowledge of emergency action level thresholds and classifications 4.1 S

Application EP Event classification for fuel handling event Hope Creek ECG Open Reference New During movement of spent fuel within the Fuel Pool, a 3 times burned bundle is full-up on the fuel grapple.

The Refueling Platform crew leaves the bridge to reposition lights.

Subsequently, Fuel Pool level begins lowering rapidly.

Given:

- The Control Room receives a low Fuel Pool level alarm.

- The Rad Pro technician notices radiation levels increasing and notifies the crew.

- All personnel leave the Refueling Floor.

- Operations personnel stop the inventory loss.

- Rad Pro survey indicates the general area dose rate to be 800 mRem/hour on the Refueling Floor.

- The fuel bundle on the fuel grapple is 3 inches exposed above the water line as viewed by camera.

CORRECT ANSWER ALERT* lAW ECG Emergency Action Level 6.4.2.c*

"Visual observation of Irradiated Fuel uncovered"

Minimum answer required for full credit underlined

Student Copy SRO QUESTION # Admin A4-2 QUESTION During movement of spent fuel within the Fuel Pool, a 3 times burned bundle is full-up on the fuel grapple.

The Refueling Platform crew leaves the bridge to reposition lights.

Subsequently, Fuel Pool level begins lowering rapidly.

Given:

- The Control Room receives a low Fuel Pool level alarm.

- The Rad Pro technician notices radiation levels increasing and notifies the crew.

- All personnel leave the Refueling Floor.

- Operations personnel stop the inventory loss.

- Rad Pro survey indicates the general area dose rate to be 800 mRem/hour on the Refueling Floor.

- The fuel bundle on the fuel grapple is 3 inches exposed above the water line as viewed by camera.

Determine the required Event classification and Emergency Action Level

ML031130629

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