ML032650571

Final - Section a Operating

ML032650571
Person / Time
Site:	Susquehanna
Issue date:	08/01/2003
From:	Roush K Susquehanna
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-387/03-301, 50-388/03-301
Download: ML032650571 (87)

Text

S-301 Administrative Topics Outline Form ES-301-1 Facility:

SSES Date of Examination: 0811 1/03 Examination Level (circle one): Ro Operating Test Number:

Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Pian Describe activity to be performed 2.1.25 2.813.1 JPM Determine Estimated Time to Reach 200 OF and Required Technical Specification Actions.

2.1.7 3.714.4 JPM Document a failed LPRM and determine appropriate compensatory actions.

2.2.13 3.613.8 JPM Determine blocking points of a clearance order.

NIA 2.4.27 3.0/3.5 JPM Activate the Fire Brigade and select the appropriate Pre-Fire Plan NOTE: All items (5 total) are required br SROs. RO applicants require only4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 2 Susquehanna Facsimile

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 49.ON.003.201 0

07/15/03 2.1.25 2.8/3.1 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

K/A Task

Title:

Determine Estimated Time to 200 O F

and Required T.S. Actions.

Completed By:

Reviews:

Russ Halm 07/15/03 Writer Date InstructorNVriter Date Ap prova I:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head

\\--

Date of Performance:

10 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Eva1 uato r Name :

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (05100)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-56

REQUIRED TAS K I N FORM AT1 0 N JOB PERFORMANCE MEASURE SlRO 49.0N.003.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. TECHNICAL SPECIFICATIONS SECTION 3.4.9, Amendment 178 B. ON-149-001 LOSS OF SHUTDOWN COOLING MODE, REV. 18 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None 4

IV. TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is in Mode 4.

The reactor has been shutdown for 3.5 days.

RPV pressure is 25 psig and stable Reactor coolant temperature is 150 O F and stable A and B Recirculation MG sets are out of service for maintenance.

RPV level is being maintained at 90 inches by the CRD and RWCU systems.

B loop of RHR is Out Of Service.

A RHR pump is operating and C RHR pump is in standby A RHR pump TRIPS and the C RHR pump cannot be started V. INITIATING CUE Using the appropriate procedure, determine the estimated time for the Reactor coolant temperature to reach 200 O F and identify the Technical Specification required action(s) for this event.

VI. TASK STANDARD Estimated time for the Reactor coolant temperature to reach 200 O F is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (+/- 5 minutes);

Technical Specification required action(s) determined as: Verify 2 alternate methods of decay heat removal within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Verify an alternate circulation method (245 inches and re-verify every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) and monitor Reactor coolant temperature once per hour

.u 2003 NRC Exam Rev. 2

Appl. To/JPM No.: S/RO 49.0N.003.201 Step 1

2

• 3 PERFORMANCE CHECKLIST Action EVALUATOR NOTE Ensure a copy of ON-149-001 is available.

EVALUATOR NOTE To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains a controlled copy of ON-149-001 Reviews symptoms and Observations section of procedure EVALUATOR NOTE Steps may be done in any order.

Selects correct procedure section AND Determines the estimated Time to 200 O F

• Critical Step

1. Critical Sequence Student Name:

Standard Controlled copy obtained.

Determines ON-149-001 is appropriate procedure for the given conditions.

Determines section 3.4 is applicable.

Refers to attachment C Determines the estimated Time to 200 O F to be:

1 Hour (+/- 5 minutes)

Eva1 Page 3 of 4 Comments STCPPA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

Appl. To/JPM No.: S/RO 49.0N.003.201 Step

• 4 PERFORMANCE CHECKLIST Page 4 of 4 Action EVALUATOR NOTE The Technical Specification determination in the next step will require the verification of an alternate decay heat removal method for EACH inoperable RHR shutdown cooling subsystem. Therefore the candidates should identify the need for 2 alternate decay heat removal methods since 2 subsystems are now inoperable.

Comply with Technical Specification 3.4.9 EVALUATOR CUE This completes the JPM.

Student Name:

Standard Refers to Technical Specification 3.4.9 and determines:

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> must verify 2 alternate methods of decay heat removal are available.

AND Verify an alternate circulation method e45 inches and re-verify every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

AND Must monitor Reactor coolant temperature once per hour Eva1 Comments

• Critical Step STCP-CIA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

1. Critical Sequence

TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is in Mode 4.

The reactor has been shutdown for 3.5 days.

RPV pressure is 25 psig and stable Reactor coolant temperature is 150 O F and stable A and B Recirculation MG sets are out of service for maintenance.

RPV level is being maintained at 90 inches by the CRD and RWCU systems.

B loop of RHR is Out Of Service.

A RHR pump is operating and C RHR pump is in standby A

RHR pump TRIPS and the C RHR pump cannot be started INITIATING CUE Using the appropriate procedure, determine the estimated time for the Reactor coolant temperature to reach 200 O F and identify the Technical Specification required action(s) for this event.

2003 NRC Exam Rev. 2 Page I of 2

TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is in Mode 4.

The reactor has been shutdown for 3.5 days.

RPV pressure is 25 psig and stable Reactor coolant temperature is 150 O F and stable A and B Recirculation MG sets are out of service for maintenance.

RPV level is being maintained at 90 inches by the CRD and RWCU systems.

B loop of RHR is Out Of Service.

A RHR pump is operating and C RHR pump is in standby A

RHR pump TRIPS and the C RHR pump cannot be started INITIATING CUE Using the appropriate procedure, determine the estimated time for the Reactor coolant temperature to reach 200 O F and identify the Technical Specification required action(s) for this event.

2003 NRC Exam Rev. 2 Page 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 78.AD.001.IO1 0

06/14/03 2.1.7 2.8/3.1 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews:

Document a Failed LPRM Detector Russ Halm 06/14/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head

?.--

Date of Performance:

15 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Perform an ce Eva1 u a t ion:

(

)

Satisfactory

(

)

Unsatisfactory Eva1 u a tor Name:

Signature Typed or Printed Comments:

Form STCP-QA-IZ5A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-58

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 78.AD.001.I 01 L-

1.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. 01-078-001 LPRM STATUS CONTROL, REV. 7 111. REACTIVITY MAN1 PU LATIONS This JPM satisfies the requirements of Operational Activity@):

None IV. TASK CONDITIONS v

A. Unit 1 is in MODE 1.

B. Reactor Engineering has completed evaluation of a downscale alarm condition for LPRM detector 48-1 78.

C. LPRM detector 48-17B is failed and bypassed.

V. INITIATING CUE Complete all required documentation in accordance with the appropriate instruction for LPRM detector 48-1 7B.

VI. TASK STANDARD Zone 4 is identified as not having more than 50% upscale alarms operable and the operational restriction to place the reactor mode switch to shutdown if entry to region I1 of the power to flow map occurs.

2003 NRC Exam Rev. 2

Appl. To/JPM No.: S/RO 78.AD.001.101 Step 1

2 3

4 PERFORMANCE CHECKLIST Page 3 of 5 Action EVALUATOR NOTE:

0 This JPM should be performed in the simulator or plant control room.

0 Ensure the following material is available to support performance of this JPM:

A COPY of 01-078-001.

Prepare attachments A & B with zone 4 having exactly 50% operable LPRM upscale alarms.

Blank copy of attachment A & B.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains a controlled copy of procedure.

Refers to correct section.

Determines current LPRM status.

EVALUATOR CUE:

When the candidate identifies where the current LPRM Upscale Alarm Status Control Log is retained provide the candidate with the JPM copy of Attachment A & B.

Obtains a blank copy of Attachment A & B.

EVALUATOR CUE:

When the candidate identifies a new form is required provide the candidate with a blank copy of Attachment A

& B.

Student Name:

Standard Controlled copy obtained.

Refers to section 4.

Obtains the Operations Special Log Book in the Unit 1 control room and locates the previously completed copy of Attachment A &

B.

Blank copy obtained.

Eva1 Comments

• Critical Step

1. Critical Sequence STCP-QA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i' PERFORMANCE CHECKLIST i/

Page 4 of 5 Appl. To/JPM No.: S/RO 78.AD.001.I 01 Student Name:

Step 5

• 6 7

8 Action Completes new Attachment A.

EVALUATOR CUE:

If candidate elects to verify position of switches in lower relay room, provide the cue that the switches are in the positions indicated on Attachment A (Special log book Determine if 250% of LPRM Upscale alarms in each zone are operable.

Identifies operating restriction.

Make notifications.

• Critical Step

1. Critical Sequence Standard Enters 1 for Unit.

Transfers the previous LPRM data to the new Attachment A.

OR Candidate may desire to verify switches in lower relay room.

Place a checkmark in column 2 adjacent to LPRM detector 48-1 7B in Zone 4.

Circles YES for zone 1, 2, 3, 5, 6, 7, 8, and 9.

Circles NO for zone 4.

Identifies an immediate reactor scram is required if entry into region II of the power to flow map occurs.

Notifies the Unit Supervisor and Unit I PCOs about the operating restriction based upon the LPRM alarm condition.

Eva1 Corn men ts STCP-QA-125B Rev. 2, (9/93)

Page 1 of I 2003 NRC Exam Rev. 2

i PERFORMANCE CHECKLIST Page 5 of 5 Appl. To/JPM No.: S/RO 78.AD.001.101 Student Name:

Step

• 9 10 11 12 Action Posts placard.

EVALUATOR NOTE:

The placard is required to remain posted until all zones have >50% upscale alarms operable.

Complete Attachment 6.

Notify Reactor Engineering.

Obtains review.

EVALUATOR CUE:

This completes the JPM.

• Critical Step

1. Critical Sequence Standard Attaches placard to operating panel 1 C651.

Enters 1 for Unit.

Transfers the previous LPRM data to the new Attachment 6.

Circles LPRM detector 48-1 7 for APRM E, under the column B Level.

Contacts reactor engineering and provides the current LPRM status.

Submit the completed Attachment A and B to the Unit Supervisor.

Eva1 Comments STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS A. Unit 1 is in MODE 1.

B. Reactor Engineering has completed evaluation of a downscale alarm condition for LPRM detector 48-1 7B.

C. LPRM detector 48-17B is failed and bypassed.

INITIATING CUE Complete all required documentation in accordance with the appropriate instruction for LPRM detector 48-1 7B.

v-2003 NRC Exam Rev. 2 Page 1 of 2

TASK CONDITIONS

-i-A. Unit 1 is in MODE 1.

B. Reactor Engineering has completed evaluation of a downscale alarm condition for LPRM detector 48-1 7B.

C. LPRM detector 48-17B is failed and bypassed.

INITIATING CUE Complete all required documentation in accordance with the appropriate instruction for LPRM detector 48-1 7B.

Page 2 of 2 2003 NRC Exam Rev. 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET RO New ID 0

06/13/03 2.2.13 3.613.8 Blocking Points Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Identify Blocking Points Completed By:

Reviews:

Russ Halm 0611 3/03 Writer Date I nstructorNV riter Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head

~-..-i 20 Date of Performance:

Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-58

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE RO New Admin ID Blocking Points

1.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. NDAP-QA-0322, ENERGY CONTROL PROCESS (Rev. 13)

B. NDAP-QA-0323, STANDARD BLOCKING PRACTICES (Rev. 17)

C. M-I 15 Sheet 1 CIRCULATING WATER (Rev. 43)

D. E-I 37 Sheet 3 ClRC WATER PUMP 1 B (Rev. 11)

E. E-I 38 Sheet 1 ClRC WATER PUMP DISCHARGE VALVE (Rev. 13)

F. E-I38 Sheet 19 ClRC WATER PUMP SUCTION VALVE (Rev. 6)

IV. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity@):

None IV. TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1 P501 B discharge vent valve 115137B needs to be replaced (scope of work).

C. When NlMS is returned to service, a tagout will be prepared to perform this valve replacement.

D. While NlMS is out of service, your supervisor wants to begin preparations for this tagout E. Unit 1 Circ Water Pump 1P501B has been removed from service IAW OP-142-001 section 3.2 V. INITIATING CUE Using the appropriate NDAP(s) and mechanical/electricaI drawing@), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

VI. TASK STANDARD Components identified in the attached answer key are placed sequentially in the specified position.

2003 NRC Exam Rev. 2

i' PERFORMANCE CHECKLIST Page 3 of 7 Appl. To/JPM No.: New Admin ID Blocking Points Student Name:

Step 1

2

• 3 Action This JPM must be performed in the simblator or the plant control room.

Ensure the following material is available to support performance of this JPM:

The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LEITERS.

EVALUATOR NOTE Blank table labeled for tagout points 0

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet, and attached student copy of the blank table.

Obtains NDAP-QA-0322, ENERGY CONTROL PROCESS and NDAP-QA-0323, STANDARD BLOCKING PRACTICES Reviews the scope of work planned for 1 P501 B.

Use electrical print to identify 1 P501 B motor breaker Standard References NDAPs to determine overall process and prescribed sequence.

Determines the pump discharge vent valve 1 151 37B will be replaced.

Using E-I 37 Sht.3, determines breaker lA10203 will need to be:

First in the sequence Racked out Red tagged Then fills out table Eva1 Comments

• Critical Step

1. Critical Sequence STCP-QA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 4 of 7 Appl. To/JPM No.: New Admin ID Blockina Points Student Name:

Step

• 4 "5

• 6

• Critical Step Action Use electrical print to identify HV-I 151 1 B MOV breaker.

Use electrical print to identify HV-I 151 I B MOV breaker.

Use mechanical drawing to identify HV-I 151 36, CWP 6 Suction valve.

1. C ri tica I Seq uen ce Standard Using -I 38 Sht.1, determines breaker lB501024 will need to be:

Second in the sequence Opened Red tagged Then fills out table Using E-I 38 Sht.19, determines breaker 18501 034 will need to be:

Second in the sequence Opened Red tagged Then fills out table Using M-I15 Sht.1, determines HV-11513B will need to be:

Third in the sequence Closed Red tagged Then fills out table Eva1 Comments STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

i PERFORMANCE CHECKLIST

(

Page 5 of 7 Appl. To/JPM No.: New Admin ID Blockinq Points Student Name:

Step

• 7

• 8

• 9 Action Use mechanical drawing to identify HV-11511 B, CWP B Discharge valve.

U mechanical drawing to identif!

Bearing Seal Water Supply valve.

115153, CWP B I6 EVALUATOR NOTE:

Drawing grid location is D-I (Detail A).

Use mechanical drawing to identify 115154, CWP B OB Bearing Seal Water Supply valve.

EVALUATOR NOTE:

Drawing grid location is C-I (Detail A).

EVALUATOR NOTE:

Multiple pump vent and drain valves are available. Any pair of valves is acceptable so long as one set of vents and one set of drain valves are opened.

• Critical Step

1. Critical Sequence Standard Using M-I 15 Sht.1, determines HV-11511 B will need to be:

Third in the sequence Closed Red tagged Then fills out table Using M-I 15 Sht.1, determines 1 151 53 will need to be:

Third in the sequence Closed Red tagged Then fills out table Using M-I 15 Sht.1, determines I

151 54 will need to be:

Third in the sequence Closed Red tagged Then fills out table Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Appl. ToIJPM No.: New Admin ID Blocking Points Student Name:

Step

• I 0

• I 1

• I 2 Action Use mechanical drawing to identify 1151398, CWP B Suctioh Vent valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Use mechanical drawing to identify I 15141 B, CWP B Suction Vent valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Use mechanical drawing to identify 115142B, CWP B Discharge Drain valve.

EVALUATOR NOTE:

Drawing grid location is 1-1

• Critical Step

1. Critical Sequence Stand a rd Using M-I 15 Sht.1, determines 115139B will need to be:

Fourth in the sequence Opened No Tag Required Then fills out table Using M-I 15 Sht.1, determines 115141 B will need to be:

Fourth in the sequence Opened No Tag Required Then fills out table Using M-I 15 Sht.1, determines 115142B will need to be:

Fourth in the sequence Opened No Tag Required Then fills out table Eva1 i:'

Page 6 of 7 Comments STCP-PA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i:'

PERFORMANCE CHECKLIST Page 7 of 7 i:

Appl. To/JPM No.: New Admin ID Blocking Points Student Name:

~

Step

• I 3

• I 4

• Critical Step Action Use mechanical drawing to identify 11 5143B, CWP B Suction Drain valve.

EVALUATOR NOTE:

Drawing grid location is 1-1 Reports the results.

EVALUATOR CUE Roleplay the Unit Supervisor and acknowledge the results when reported.

EVALUATOR CUE:

This completes the JPM.

DUE TO THE NATURE OF THIS JPM OTHER BLOCKING POINTS MAY BE ACCEPTABLE. CONSULT WITH ADDITIONAL SMEs AS NECESSARY TO DETERMINE ACCEPTABILITY OF ALTERNATE BLOCKING POINTS.

1. Critical Sequence Standard Using M-I 15 Sht.1, determines 11 5123B will need to be:

Fourth in the sequence Opened No Tag Required Then fills out table Informs the Unit Supervisor of the results by handing the supervisor the completed table.

Eva1 Comments STCP-QA-1ZSB Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

i Component ID ANSWER KEY (DO NOT Component Description Position Tag Color GIVE TO STU DENTS)

I A I 0203 I

B501024 1 B501034 HV-I 1513B HV-I 151 I B 115153 115154 1 151 39B 115141B 115142B 115143B Sequence c,

ClRC WATER PUMP B I P501 B 13.8 KV BKR Racked out Red CWP 1 B DSCH MOV HV-I 151 1 B BKR 52-024 Open Red ClRC WATER PUMP B SUCTION VLV HV-I 151 3B Open Red BKR ClRC WATER PUMP B SUCTION VLV Close Red ClRC WATER PUMP B DISCHARGE VLV Close Red CWP B IB BEARING SEAL WATER SUPPLY IS0 Close Red VLV CWP B OB BEARING SEAL WATER SUPPLY IS0 Close Red VLV CW PUMP B SUCTION VENT VLV Open No Tag CW PUMP B SUCTION VENT VLV Open No Tag ClRC WATER PUMP B SUCTION DRAIN VLV Open No Tag No Tag ClRC WATER PUMP B SUCTION DRAIN VLV 1 I I

Open 2

3 I-+- =

4 Page 1 of 2 I

2003 NRC Exam Rev. 2

i-TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1 P501B discharge vent valve 1151378 needs to be replaced (scope of work).

C. When NlMS is returned to service, a tagout will be prepared to perform this valve replacement.

D. While NlMS is out of service, your supervisor wants to begin preparations for this tagout E. Unit 1 Circ Water Pump 1P501B has been removed from service IAW OP-142-001 section 3.2 INITIATING CUE Using the appropriate NDAP(s) and mechanicallelectrical drawing@), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

2003 NRC Exam Rev. 2 Page 1 of 2

TASK CONDITIONS A.

B.

C.

D.

E.

NlMS is not available.

Unit 1 Circ Water Pump 1 P501 B discharge vent valve 11 51 37B needs to be replaced (scope of work).

When NlMS is returned to service, a tagout will be prepared to perform this valve replacement.

While NlMS is out of service, your supervisor wants to begin preparations for this tagout Unit 1 Circ Water Pump 1 P501 B has been removed from service IAW OP-142-001 section 3.2 INITIATING CUE Using the appropriate NDAP(s) and mechanicaVelectrica1 drawing(s), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

2003 NRC Exam Rev. 2 Page 2 of 2

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PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 13.ON.003.001 0

06/ 14/03 2.4.27 3.013.5 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Completed By:

Reviews:

Activate the Fire Brigade.

Russ Halm 0611 4/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head

.~

c.-

Date of Performance:

20 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (05100)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-58

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 13.ON.003.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A.

B.

C.

D.

ON-013-001 RESPONSE TO FIRE, REV. 14 FP-013-189 DIESEL GENERATOR BAY A, REV. 3 AR-SP-001 PAGE 118, REV. 7 AR-SP-002 PAGE 72, REV. 9 E. AR-SP-002 PAGE 76, REV. 9 I II. REACTIVITY MAN1 PU LATlO NS This JPM satisfies the requirements of Operational Activity@):

None IV. TASK CONDITIONS A. A fire is confirmed to exist in Diesel Generator A building.

B. The following SIMPLEX data print out is available:

FIRE DET X116-25 ALM 17:14 MON 1 1 -AUG-03 44-660 A DIESEL GEN FIRE DET X I 16-21 ALM 17:16 MON 1 1 -AUG-03 44-677/710 A DG FIRE SUP X25O-Zl ALM 17:20 MON 1 1 -AUG-03 44-676 PA011 ADIESL 2003 NRC Exam Rev. 2

V. INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

VI. TASK STANDARD Fire brigade activated and Pre-Fire Plan FP-013-189 selected.

Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 File No. A14-58 2003 NRC Exam Rev. 2

i Appl. To/JPM No.: SIR0 13.ON.003.001 Step

• Critical Step PERFORMANCE CHECKLIST Page 4 of 7 Action EVALUATOR NOTE:

0 This JPM must be done in the simulator or plant control room.

Ensure the following material is available to support performance of this JPM:

0 Pre-Fire Plans.

A COPY of ON-01 3-001.

AR-SP-001.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains SIMPLEX fire alarm panel alarm response.

Locates alarm procedure for X250 Z1.

EVALUATOR NOTE:

The alarm response procedure identifies the Pre-Fire Plan FP-013-189.

Locates alarm procedure for X I 16-Z1.

EVALUATOR NOTE:

The alarm response procedure identifies the Pre-Fire Plan FP-013-189.

1. Critical Sequence Student Name:

Standard Obtains controlled copy of AR-SP-001 and AR-SP-002.

Selects AR-SP-001 page 1 18.

Selects AR-SP-002 page 72.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i PERFORMANCE CHECKLIST Page 5 of 7 Appl. To/JPM No.: S/RO 13.ON.003.001 Student Name:

Step 4

5 6

7

• 8 Action Locates alarm procedure for X I 16-25.

EVALUATOR NOTE:

The alarm response procedure identifies the Pre-Fire Pian FP-013-189.

3btains a controlled copy of Off-Normal procedure ON-Refers to correct section.

Activates fire brigade.

Zontacts Fire Brigade Leader.

313-001.

EVALUATOR CUE:

As fire brigade leader inform th-candidate you will be setting up the command post at control structure central area access on the east side and radio channel 4 will be used. Contact security and have them bring the fire brigade van to the command post.

Standard Selects AR-SP-002 page 76.

Controlled copy obtained.

Refers to section 3.

Refers to Attachment Q or the Activity Hard Card.

Contacts the Field Unit Supervisor as Fire Brigade Leader using the plant page or radio.

AND Informs the Fire Brigade Leader a fire is confirmed in Diesel Generator A building.

Acknowledges the command post location and radio channel 4 will be used.

Eva1

=

Comments

• Critical Step

1. Critical Sequence STCP-QA-125B Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

i:

Appl. TolJPM No.: S/RO 13.ON.003.001 Step

• 9

• I 0

11 12 PERFORMANCE CHECKLIST Action Contacts Fire brigade members from Operations.

Send Pre-Fire Plan FP-013-189 to command post.

Contacts Fire brigade members from Security.

Sound fire alarm.

• Critical Step

1. Critical Sequence Student Name:

Standard Contacts a minimum of 2 operators designated for fire brigade on the shift schedule.

Informs them to dress at the fire brigade van which will be brought to the central area access. Select the radio to channel 4, and report to the command post.

Designates one fire brigade member to take Pre-Fire Plan FP-013-189 to the command post.

Dials extension 31 14 or 31 15 for fire brigade support.

Informs them to bring the fire brigade van to the central access area, select the radio to channel 4, and report to the command post.

At panel OC695:

Turn the siren tone generator switch to Siren / Fire position.

Pull out evacuation alarm switch, turn to PLANT ALARM position.

Eva1 Page 6 of 7 Comments STCP-QA-1255 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i:

Appl. To/JPM No.: S/RO 13.ON.003.001 Step 13

• I4 PERFORMANCE CHECKLIST Page 7 of 7 Action Make plant page announcement.

Selects the appropriate Pre-Fire Plan.

EVALUATOR CUE:

This completes the JPM.

• Critical Step

1. Critical Sequence Student Name:

Standard Push in the evacuation alarm switch.

After -1 0 seconds, pull out the evacuation alarm switch.

Rotate the evacuation alarm switch to OFF position and push in the evacuation alarm switch.

Keys the plant page and announces:

Attention all personnel, there is a fire in the A Diesel Generator Building. Station fire brigade has been activated, stay clear of affected areas.

Repeat the above announcement.

Obtains a copy of FP-013-189.

Eva1 Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS v

A. A fire is confirmed to exist in Diesel Generator A building.

B. The following SIMPLEX data print out is available:

FIRE DET X1IG-25 ALM 17:14 MON 1 I

-AUG-03 44-660 A DIESEL GEN FIRE DET X I 16-21 ALM 17:16 MON 1 1 -AUG-03 44-677/710 A DG FIRE SUP X25O-Zl ALM 17:20 MON 1 1 -AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

Page I of 2 2003 NRC Exam Rev. 2

TASK CONDITIONS A. A fire is confirmed to exist in Diesel Generator A building.

B. The following SIMPLEX data print out is available:

FIRE DET X I 16-Z5 ALM 17:14 MON 11-AUG-03 44-660 A DIESEL GEN FIRE DET X I 16-ZI ALM 17:16 MON 11-AUG-03 44-677171 0 A DG FIRE SUP X25O-Zl ALM 1720 MON 1 1 -AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

2003 NRC Exam Rev. 2 Page 2 of 2

ES-301 Administrative Topics Outline Form ES-301-1 II 11 Facility:

SSES Date of Examination:

08/11/03 Examination Level (circle one): SRO I

Operating Test Number:

Administrative Topic (See Note)

Conduct of Operations Equipment Control Radiation Control Describe activity to be performed 2.1.25 2.813.1 JPM Determine Estimated Time to Reach 200 OF and Required Technical Specification Actions.

2.1.23 3.914.0 JPM Authorize Bypassing Rod Worth Minimizer IAW NDAP-QA-0388

~

~~

2.2.1 3 3.613.8 JPM Determine accuracy and adequacy of a clearance order.

2.3.9 2.513.4 JPM Authorize De-inerting and Purging the D w e l l and Suppression Chamber with Air.

2.4.41 2.314.1 JPM Determine Emergency Plan EAL Classification.

NOTE: All items (5 total) are required br SROs. RO applicants require only4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 2 Susquehanna Facsimile

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 00.AD.047.001 2

06/14/03 2.1.23 4.0 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews:

Authorize Bypassing Rod Worth Minimizer In Accordance With NDAP-QA-0338 Russ Halm 0611 4/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

15 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S.

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (0300)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-55

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.AD. 047.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

11. REFERENCES A. NDAP-QA-0338, Reactivity Management and Controls Program, Rev. 6 B. Start-up control rod sequence A2, 04/02/02.

C. TS 3.3.2.1, Control Rod Block Instrumentation, Amendment 178 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. A plant startup is in progress on Unit 1 with reactor power at one percent.

B. The PCOM has successfully completed withdrawing Rod 38-59 from 00 to 04 as specified by Rod Step A2-66 in the pull sheet.

C. When the PCOM attempted Step A2-67 (Rod 22-59 from 00 to 04), the ROD BLOCK annunciator alarmed.

D. There are no indications that the Rod Sequence Control System (RSCS) is generating the rod block.

E. The WITHDRAW BLOCK status light on the Rod Worth Minimizer (RWM) is illuminated.

F. The PCOM and the Reactor Engineer verified that all rods were in the positions specified by the pull sheet.

G. The Reactor Engineer verified that there are no problems with the pull sheet.

H. I&C performed an initial investigation of the event. It appears that the RWM has failed.

I. The RSCS and Rod Position Indication System (RPIS) both appear to be operable.

J. The PCOM has suggested bypassing the RWM and continuing with the rod withdrawals and reactor startup.

2003 NRC Exam Rev. 2

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.AD.047.001 V. INITIATING CUE Determine if it is allowable to bypass the RWM under these circumstances and complete all necessary documentation to justify your decision.

VI. TASK STANDARD Completes the reactivity control system bypass authorization form, implements the required action of LCO 3. 3.2.2, and authorizes bypassing the rod worth minimizer.

Form STCP-QA-125A Rev. 4, (05100)

Page 1 of 1 File No. A14-58 2003 NRC Exam Rev. 2

r i

i PERFORMANCE CHECKLIST Page 4 of 7 Appl. To/JPM No.: S/RO 00.AD.047.001 Student Name:

Step Action EVALUATOR NOTE:

Ensure the following material is available to support performance of this JPM:

0 A blank copy of NDAP-QA-0338, Attachment B.

0 A copy of start-up control rod sequence A2.

A COPY of NDAP-QA-0338.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains a controlled copy of NDAP-QA-0338.

EVALUATOR CUE:

When the candidate indicates NDAP-QA-0338, Attachment B, must be completed give him/her the blank form.

Completes NDAP-QA-0338, Attachment B.

Determines entry condition.

Enters initiating condition data.

Determine if power is above the LPSP.

Standard Controlled copy obtained.

Reviews NDAP-QA-0338, Section 6.4 and/or Attachment B.

Places a checkmark in Yes box for RWM INOP or blocking motion.

Enters the following data for Initiating Condition:

0 Rod ID is 22-59 0

Notch is 00 0

Unit is 1 0

0 Power Level is 1%

0 Date/Time RBM Channel A or B is NA Places a checkmark in NO box.

Eva1 Comments

• Critical Step

1. Critical Sequence STCP-PA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 5 of 7 Appl. To/JPM No.: S/RO 00.AD.047.001 Student Name:

Step 6

7 8

9 10 11

• I 2 Action Determine if a special test is being performed.

Determine if both RSCS and RWM are problems.

Determine if a computer problem exists.

Determine if RPlS problems exist.

Contact Reactor Engineering.

EVALUATOR CUE:

As Rx Engineer, inform the candidate the RWM pointer and sequence has been verified correct.

Contact I&C.

Determines Tech Spec impact.

• Critical Step

1. Critical Sequence Standard Places a checkmark in the No box.

Places a checkmark in the No box.

Places a checkmark in the No box.

Places a checkmark in the No box.

Contacts Rx Engineer to :

investigate the RWM pointer 0

Sequence in RWM Investigate sequence error Places a checkmark in the No Fix box.

Determines I &C has investigated for hardware problems from the task conditions.

Refers to TS LCO 3.3.2.1 Refers to Table 3.3.2.1-1 for Function 2 and determines the RWM is required in MODE 2 with Thermal Power 51 0% RTP.

Eva1 Comments STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i Appl. To/JPM No.: S/RO 00.AD.047.001 Step 13 PERFORMANCE CHECKLIST Page 6 of 7 Action EVALUATOR CUE:

Give the candidate the Start-up control rod sequence A2.

Identifies a LCO/TRO Log Sheet must be completed.

EVALUATOR CUE:

Inform the candidate it is not necessary to complete the LCO/TRO Log Sheet at this time.

• Critical Step

1. Critical Sequence Student Name:

Standard Identifies Condition C must be entered and the following Required Actions are applicable:

C.l, Immediately suspend control rod movement except by scram.

OR C.2.1.I, Immediately verify 2 12 rods withdrawn C.2.1.2, Immediately verify by administrative methods that startup with RWM inoperable has not been performed in the last calendar year C.2.2, During control rod movement verify movement of control rods is in compliance with BPWS by a second licensed operator or other qualified member of the technical staff.

States LCO/TRO Log Sheet must be completed.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i Appl. To/JPM No.: S/RO 00.AD.047.001 Step

• I 4 15 PERFORMANCE CHECKLIST Page 7 of 7

• Critical Step Action Determine that it is allowable to bypass RWM.

Authorize bypassing RWM.

EVALUATOR CUE:

This completes the JPM.

Student Name:

1. Critical Sequence Standard Determines that RWM can be bypassed.

Places a checkmark in box for RW M.

Signs form and enter current time/date.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRG Exam Rev. 2

TASK CONDITIONS A. A plant startup is in progress on Unit 1 with reactor power at one percent.

B. The PCO has successfully completed withdrawing Rod 38-59 from 00 to 04 as specified by Rod Step A2-66 in the pull sheet.

C. When the PCO attempted Step A2-67 (Rod 22-59 from 00 to 04), the ROD BLOCK annunciator alarmed.

D. There are no indications that the Rod Sequence Control System (RSCS) is generating the rod block.

E. The WITHDRAW BLOCK status light on the Rod Worth Minimizer (RWM) is illuminated.

F. The PCO and the Reactor Engineer verified that all rods were in the positions specified by the pull sheet.

G. The Reactor Engineer verified that there are no problems with the pull sheet.

H. I&C performed an initial investigation of the event. It appears that the RWM has failed.

I. The RSCS and Rod Position Indication System (RPIS) both appear to be operable.

J. The PCO has suggested bypassing the RWM and continuing with the rod withdrawals and reactor startup.

INITIATING CUE Determine if it is allowable to bypass the RWM under these circumstances and complete all necessary documentation to justify your decision.

x 2003 NRC Exam Rev. 2 Page 1 of 2

---

I TASK CONDITIONS A. A plant startup is in progress on Unit I with reactor power at one percent.

B. The PCO has successfully completed withdrawing Rod 38-59 from 00 to 04 as specified by Rod Step A2-66 in the pull sheet.

C. When the PCO attempted Step A2-67 (Rod 22-59 from 00 to 04), the ROD BLOCK annunciator alarmed.

D. There are no indications that the Rod Sequence Control System (RSCS) is generating the rod block.

E. The WITHDRAW BLOCK status light on the Rod Worth Minimizer (RWM) is illuminated.

F. The PCO and the Reactor Engineer verified that all rods were in the positions specified by the pull sheet.

G. The Reactor Engineer verified that there are no problems with the pull sheet.

H. I&C performed an initial investigation of the event. It appears that the RWM has failed.

I.

The RSCS and Rod Position Indication System (RPIS) both appear to be operable.

J. The PCO has suggested bypassing the RWM and continuing with the rod withdrawals and reactor startup.

INITIATING CUE Determine if it is allowable to bypass the RWM under these circumstances and complete all necessary documentation to justify your decision.

2003 NRC Exam Rev. 2 Page 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO New Clearance 0

06/13/03 2.2.13 3.6/3.8 0 rde r Accuracy Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews:

Review a Clearance Order for Accuracy Russ Halm 06/13/03 Writer Date InstructorNVriter Date App rova I:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head

_/

20 Date of Performance:

Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO New Admin I.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. NDAP-QA-0322, ENERGY CONTROL PROCESS (Rev. 13)

B. NDAP-QA-0323, STANDARD BLOCKING PRACTICES (Rev. 17)

C. M-I 15 Sheet 1, CIRCULATING WATER (Rev. 43)

D. E-I37 Sheet 3 ClRC WATER PUMP 1B (Rev. 1 I )

E. E-138 Sheet 1 ClRC WATER PUMP DISCHARGE VALVE (Rev. 13)

F. E-I 38 Sheet I 9 ClRC WATER PUMP SUCTION VALVE (Rev. 6)

IV. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity@):

None IV. TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1 P501 B discharge vent valve 115137B needs to be replaced.

C. Clearance Order 5401 5 has been prepared to support this repair work.

V. INITIATING CUE Review Clearance Order 5401 5 for adequacy and accuracy and report your results to the Unit Supervisor.

VI. TASK STANDARD Component 1851 1034 (tag number 4) is identified as the wrong device and the correct device is 1 B501034.

2003 NRC Exam Rev. 2

i'

(,"

~ p l.

To/JPM No.: S/RO New Admin Step 1

2 3

PERFORMANCE CHECKLIST Page 3 of 7 Action EVALUATOR NOTE:

This JPM must be performed in the simulator or the plant control room.

Ensure the following material is available to support performance of this JPM:

A copy of Clearance Order.

The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Provide the candidate with the Clearance Order 54015.

Reviews the scope of work planned for I P501 B.

Reviews NOTE 1 for conditions necessary before applying blocking.

EVALUATOR NOTE:

Candidate may review the suggested mechanical blocking starting on JPM step 9 prior to reviewing the electrical blocking, this is acceptable.

Verifies electrical blocking required.

Use electrical print to verify 1 P501 B motor breaker.

• Critical Step

1. Critical Sequence Student Name:

Standard Determines the pump discharge dent valve 1 151 376 will be

-e p I aced.

Determines I P501 B will be

-emoved from service IAW OP-142-001 Section 3.2.

Using E-I37 Sht.3, determines breaker 1 AI 0203 is correct.

Eva1 Comments STCP-QA-125B Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

i" \\

PERFORMANCE CHECKLIST Page 4 of 7 Appl. To/JPM No.: S/RO New Admin Student Name:

Step 4

5 6

• 7 8

9

~

Action Reviews position of R.ed tagged device.

Use electrical print to verify HV-11511 B MOV breaker.

Reviews position of Red tagged device.

FAULT STATEMENT THE NEXT DEVICE AND BREAKER NUMBER ARE INCORRECT.

Use electrical print to verify HV-I 151 I A MOV breaker.

EVALUATOR NOTE:

Candidate may also determine the wrong breaker number has been listed by comparing the power supply list to the component description list. If this is observed, ask the candidate to use the e-prints to verify this conclusion.

Reviews position of Red tagged device.

Verifies mechanical blocking required.

Use mechanical drawing to verify HV-115138, CWP B Suction valve.

• Critical Step

1. Critical Sequence Standard Breaker lA10203 should be RACKED OUT.

Using E-I 38 Sht.1, determines breaker 1 B50124 is correct.

Breaker 1 B50124 should be OPEN.

Using E-I38 Sht.19, determines breaker 1 B511034 is NOT correct.

The correct breaker is 1 B501034 for HV-I 151 1 B.

Breaker 1 B501034 should be OPEN.

Using M-I 15 Sht. 1, determines HV-11513B is correct.

Eva1 Comments STCP-QA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i' Appl. To/JPM No.: S/RO New Admin Step 10 11 12 13 14 15 16 PERFORMANCE CHECKLIST Page 5 of 7 Action Reviews position of Red tagged device.

Use mechanical drawing to verify HV-11511 B, CWP B Discharge valve.

Reviews position of Red tagged device.

Use mechanical drawing to verify 115153, CWP B IB Bearing Seal Water Supply valve.

EVALUATOR NOTE:

Drawing grid location is D-I (Detail A).

Reviews position of Red tagged device.

Use mechanical drawing to verify 115154, CWP B OB Bearing Seal Water Supply valve.

EVALUATOR NOTE:

Drawing grid location is C-I (Detail A).

Reviews position of Red tagged device.

EVALUATOR NOTE:

Multiple pump vent and drain valves are available. Any pair of valves is acceptable as an alternative to JPM steps 17, 19,21, and 23 so long as one set of vents and one set of drain valves are opened.

• Critical Step

1. Critical Sequence Student Name:

Standard Valve HV-115138 should be CLOSE.

Using M-I 15 Sht.1, determines HV-11511 B is correct.

Valve HV-11511 B should be CLOSE.

Using M-I 15 Sht.1, determines 1 151 53 is correct.

Valve 115153 should be CLOSE.

Using M-I 15 Sht. 1, determines 1 151 54 is correct.

Valve 1 151 54 should be CLOSE.

Eva1 Comments STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 6 of 7 Appl. To/JPM No.: S/RO New Admin Student Name:

Step 17 18 I 9 20 21 22 23 24 Action Use mechanical drawing to verify 115139B, CWP B Suction Vent valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

Use mechanical drawing to verify 115141 B, CWP B Suction Vent valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

Use mechanical drawing to verify 115142B, CWP B Discharge Drain valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

Use mechanical drawing to verify 11 5143B, CWP B Suction Drain valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

• Critical Step

1. Critical Sequence Standard Using M-I 15 Sht. 1, determines 11 51 398 is correct.

Valve 115139B should be OPEN.

Using M-I 15 Sht. 1, determines 1 15141 B is correct.

Valve 115141 B should be OPEN.

Using M-I 15 Sht.1, determines 11 5142B is correct.

Valve 1 15142B should be OPEN.

Using M-I 15 Sht.1, determines I 1 5143B is correct.

Valve 1 151438 should be OPEN.

Eva1 Comments STCP-QA-I 25B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

Appl. To/JPM No.: S/RO New Admin Step

• 25 PERFORMANCE CHECKLIST Page 7 of 7 Action

• Critical Step Reports the review results.

EVALUATOR CUE Roleplay the Unit Supervisor and acknowledge the results when reported.

If candidate fails to volunteer the correct blocking point for JPM step 7, ask them to provide it.

EVALUATOR CUE This completes the JPM.

1. Critical Sequence Student Name:

Standard Informs the Unit Supervisor:

Tag #4 for breaker 1 B511034 is not correct.

Breaker 1B501034 is the correct breaker.

Breaker I B501034 description is CIRC WATER PUMP B BKR.

DISCHARGE VLV HV-11511 B Eva1 Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS

.~ -

A. NlMS is not available.

B. Unit 1 Circ Water Pump 1P501 B discharge vent valve 115137B needs to be replaced.

C. Clearance Order 54015 has been prepared to support this repair work.

INITIATING CUE Review Clearance Order 54015 for adequacy and accuracy and report your results to the Unit Supervisor.

-4 2003 NRC Exam Rev. 2 Page 1 of 2

TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1P501B discharge vent valve 115137B needs to be replaced.

C. Clearance Order 5401 5 has been prepared to support this repair work.

INITIATING CUE Review Clearance Order 5401 5 for adequacy and accuracy and report your results to the Unit Supervisor.

2003 NRC Exam Rev. 2 Page 2 of 2

\\..-

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 00.AD.040.001 0

0611 4/03 2.3.9 3.4 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews :

Authorize De-inerting and Purging the Drywell and Suppression Chamber with Air.

Russ Halm 06/14/03 Writer Date InstructorNVriter Date Ap prova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head 20

-v-Date of Performance:

Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance

(

)

Satisfactory

(

)

Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.AD.040.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A.

B.

NDAP-QA-0309 PRIMARY CONTAINMENT ACCESS AND CONTROL, REV. 13 OP-173-001 CONTAINMENT ATMOSPHERE CONTROL SYSTEM, REV. 24 C. TR 3.6.1 VENTING OR PURGING, 8/31/98 D. TS 3.3.6.1 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION, AMENDMENT 178

- m I I I. REACTIVITY MAN I PU LATl ONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. A scheduled shutdown is in progress on Unit 1.

B. A SBGT Radiation Monitor RISHH-DI2-OK617A has just failed low.

C. Unit 1 is currently in Mode 3.

D. You are preparing for initial containment entry.

V. INITIATING CUE Identify the requirements necessary for your authorization to de-inert and purge the drywell and suppression chamber with air.

VI. TASK STANDARD Denies authorization to de-inert and air purge the containment due to inoperable SGTS exhaust radiation monitor.

2003 NRC Exam Rev. 2

i'

(,

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM No.: S/RO 00.AD.040.001 Student Name:

Step Action EVALUATOR NOTE:

Ensure the following reference material is available to support the JPM:

NDAP-QA-0309 OP-173-001 TRM 0

TECHNICAL SPECIFICATIONS The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

0 EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains a copy of NDAP-QA-0309.

EVALUATOR NOTE:

The exact order in which requirements are identified may vary based upon the sequence of procedure reference, which is acceptable.

Identifies the verification requirements of TR 3.6.1.

EVALUATOR CUE:

Acknowledge surveillance requirements.

Identifies SGTS operability requirements.

EVALUATOR CUE:

Inform candidate both SGTS trains are operable.

• Critical Step

1. Critical Sequence Standard Controlled copy obtained.

Refers to section 6.2.3 Identifies the requirements of TR 3.6.1 must be verified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the start of and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during purging.

Identifies both SGTS trains shall be operable when purge system is in use.

Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i' PERFORMANCE CHECKLIST Page 4 of 5 Appl. ToIJPM No.: S/RO 00.AD.040.001 Student Name:

Step 4

5 6

7

• Critical Step Action Identifies SGTS exhaust sampling requirements per TR 3.1 1.2.6.

EVALUATOR CUE:

Inform candidate SPING is operable.

Chemistry sampling requirements of containment.

EVALUATOR CUE:

Acknowledge chemistry sampling requirement.

States release limits.

EVALUATOR CUE:

Acknowledge release limit requirement.

Complete NDAP-QA-0309 Attachment 6.

CAUTION PRIMARY CONTAINMENT SHALL NOT BE ENTERED WHILE EITHER DRYWELL OR SUPPRESSION CHAMBER INERTED.

1. Critical Sequence Standard Identifies SGTS SPING must be operable alternate sampling in progress during SGTS operation.

Identifies chemistry samples and analyzes containment atmosphere IAW SC-173-101.

Identifies release rates shall not exceed the allowable limits of TR 3.1 1.2.1.

Completes Attachment B.

Enter 1 for Unit.

Enter current date for start date.

Enters current time for start time.

Eva1 Comments STCP-QA-I 258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 5 of 5 Appl. To/JPM No.: S/RO 00.AD.040.001 Student Name:

Step 8

9 I O 11 12

• I 3

Action Install portable oxygen analyzer 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to de-inerting.

EVALUATOR CUE:

Acknowledge installation of portable analyzer.

Obtains a copy of OP-173-001.

Refers to correct procedure section.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of purge and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verifies the requirements of TRO 3.6.1 are met.

EVALUATOR CUE:

Acknowledge all surveillance requirements are current and satisfactory.

FAULT STATEMENT: SGTS EXHAUST RADIATION MONITOR A HAS JUST FAILED DOWNSCALE. (From initiating cue)

Identifies de-inerting and air purge is not permitted until the SGTS radiation monitor is operable.

EVALUATOR CUE:

This completes the JPM.

• Critical Step

1. Critical Sequence Standard Notifies I&C to install portable oxygen analyzer IAW IC-I 73-002.

Controlled copy obtained.

Selects Section 3.3 for the drywell or 3.4 for the suppression pool.

Verify both SGTS systems are operable per LCO 3.6.4.3. by administrative means.

AND Verify Function 2.e SGTS Exhaust Radiation High is operable per LCO 3.3.6.1 by administrative means.

Does not authorize de-inerting and air purge of the drywell and suppression chamber.

Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS u

A. A scheduled shutdown is in progress on Unit 1.

B. A SBGT Radiation Monitor RISHH-Dl2-0K617A has just failed low.

C. Unit 1 is currently in Mode 3.

D. You are preparing for initial containment entry.

INITIATING CUE Identify the requirements necessary for your authorization to de-inert and purge the drywell and suppression chamber with air.

2003 NRC Exam Rev. 2 Page 1 of 2

TASK CONDITIONS v-A. A scheduled shutdown is in progress on Unit 1.

B. A SBGT Radiation Monitor RISHH-Dl2-OK617A has just failed low.

C. Unit 1 is currently in Mode 3.

D. You are preparing for initial containment entry.

INITIATING CUE Identify the requirements necessary for your authorization to de-inert and purge the drywell and suppression chamber with air.

2003 NRC Exam Rev. 2 Page 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO PCOl7-I 02 0

2.4.41 4.0 06/14/03 E-PLAN Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Completed By:

Reviews:

Perform Emergency Plan Classification and Identify Reportability Requirements.

Russ Halm 0611 4/03 Writer Date InstructorNVriter Date Ap prova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

15 Time Critical/l 0 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

\\-

Form STCP-QA-125A Rev. 4, (05100)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-56

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO E-PLAN PCOl7-I02 v

1.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A.

B.

C.

EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 PCOl70-I 02, SIMULATOR EVALUATION SCENARIO NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9

-v-111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

V. INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

VI. TASK STANDARD Emergency classification of Site Area Emergency declared within 15 minutes and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reportability to the NRC identified.

• -I 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM NO.: SRO E-PLAN PCOl7-102 Student Name:

Step Action This JPM must be performed in the simulator following completion of the scenario as Unit Supervisor.

This is a time critical JPM.

Ensure a copy of EP-PS-100 is available to support performance of this JPM.

EVALUATOR NOTE:

0 0

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

EVALUATOR NOTE:

After the candidate reviews the Task Conditions / Initiating Cue Sheet:

0 0

Ask if the candidate is ready to begin the JPM.

When the candidate is ready to begin the JPM inform the candidate that this is a Time Critical JPM.

Record Start Time Obtains a copy of EP-PS-I 00.

Evaluates information.

EVALUATOR CUE:

Assistance may be necessary for some specific scenario data or sequence of events. Use your judgement on acceptable levels of cueing based on candidate's request.

Refers to classification matrix.

• Critical Step

1. Critical Sequence Standard Controlled copy obtained.

Identifies loss of reactivity control as potential Emergency Plan entry.

Selects Tab 4.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i PERFORMANCE CHECKLIST Page 4 of 5 Appl. To/JPM NO.: SRO E-PLAN PCOl7-102 Student Name:

Step 4

• 5

• 6 7

8 9

• I 0

• Critical Step Action Reviews the table of contents for events experienced during the scenario.

Choose appropriate emergency action level.

Record Time of Site Area Emergency declaration EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements Obtains a copy of NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE Reviews reporting requirements Determines Reportability requirements Reports results STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

1. Critical Sequence Standard Reviews all category I

1.

Identifies entry into EAL 11.3 based upon loss of functions needed to bring the reactor subcritical and loss of ability to bring reactor to cold shutdown.

Classifies the event as a Site Area Emergency.

Controlled copy obtained.

Reviews Attachments:

E, F, G, and H Determines 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification due to activation of the emergency plan.

Reports 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification to the evaluator.

Eva1

=

Com men ts

Appl. To/JPM NO.: SRO E-PLAN PCO17-102 Step PERFORMANCE CHECKLIST Page 5 of 5 Action Standard Eva1 Comments I

EVALUATOR CUE:

Student Name:

After the reportability requirements have been identified, inform the candidate the JPM is complete.

• Critical Step STCP-CIA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

1. Critical Sequence

TASK CONDITIONS A. The emergency plan has just been implemented for the classification you just made.

v-INITIATING CUE Based on this emergency classification ONLY, determine the NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE reporting requirements, and report your results to the evaluator.

2003 NRC Exam Rev. 2 Page 1 of 4

TASK CONDITIONS

'd A. The emergency plan has just been implemented for the classification you just made.

INITIATING CUE Based on this emergency classification ONLY, determine the NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE reporting requirements, and report your results to the evaluator.

'V 2003 NRC Exam Rev. 2 Page 2 of 4

TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

2003 NRC Exam Rev. 2 Page 3 of 4

TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

2003 NRC Exam Rev. 2 Page 4 of 4

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO PCOl7-I 03 0

2.4.41 4.0 06/14/03 E-PLAN Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

H A Task

Title:

Completed By:

Reviews:

Perform Emergency Plan Classification and Identify Reportability Requirements.

Russ Halm 0611 4/03 Writer Date InstructorNVriter Date App rova I:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

15 Time Critical/lO Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (05JOO)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A1 4-58

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO E-PLAN PCOl7-103 I.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A.

B.

C.

EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 PCOI 70-1 03, SIMULATOR EVALUATION SCENARIO NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9 I II. REACTIVITY MAN I PULATIONS This JPM satisfies the requirements of Operational Activity@):

.~

None IV. TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

V. INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

VI. TASK STANDARD Emergency classification of Site Area Emergency declared within 15 minutes and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reportability to the NRC identified.

2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM NO.: SRO E-PLAN PCOl7-103 Student Name:

Step 1

2 Action EVALUATOR NOTE:

0 This JPM must be performed in the simulator following completion of the scenario as Unit Supervisor.

0 This is a time critical JPM.

0 Ensure a copy of EP-PS-100 is available to support performance of this JPM.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

EVALUATOR NOTE:

After the candidate reviews the Task Conditions / Initiating Cue Sheet:

0 0

Ask if the candidate is ready to begin the JPM.

When the candidate is ready to begin the JPM inform the candidate that this is a Time Critical JPM.

Record Start Time Obtains a copy of EP-PS-100.

Evaluates information.

EVALUATOR CUE:

Assistance may be necessary for some specific scenario data or sequence of events. Use your judgement on acceptable levels of cueing based on candidates request.

• Critical Step

1. Critical Sequence Controlled copy obtained.

Identifies the following events as potential Emergency Plan entry:

Unexpected in-plant high Loss of reactor vessel Steam line break radiation levels inventory Eva1

=

~

~~

Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

I' PERFORMANCE CHECKLIST Page 4 of 5 Appl. To/JPM NO.: SRO E-PLAN PCOl7-103 Student Name:

Step 3

4

• 5

• 6 7

8 Action Refers to classification matrix.

Reviews the table of contents for events experienced during the scenario.

Choose appropriate emergency achn leve Record Time of Site Area Emergency declaration EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements Obtains a copy of NDAP-QA-0720, STATION REPORT MATRIX AND RE PO RTAB I Ll TY EVALU AT10 N GUIDANCE Reviews reporting requirements

• Critical Step

1. Critical Sequence Standard Selects Tab 4.

Reviews all category 6.

Reviews all category 12.

Reviews all category 18.

Identifies entry into EAL 8.3 based upon any other un-isolatable steam line break (RWCU Break).

Classifies the event as a Site Area Emergency.

Controlled copy obtained.

Reviews Attachments:

E, F, G, and H Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

Appl. To/JPM NO.: SRO E-PLAN PCO17-103 Step 9

• I 0 PERFORMANCE CHECKLIST Page 5 of 5 Action Determines Reportability requirements Reports results EVALUATOR CUE:

After the reportability requirements have been identified, inform the candidate the JPM is complete.

• Critical Step

1. Critical Sequence Student Name:

Standard Determines 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification due to activation of the emergency plan.

Reports 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification to the evaluator.

Eva1 Comments STCP-PA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS

-Y.

A. The emergency plan has just been implemented for the classification you just made.

INITIATING CUE Based on this emergency classification ONLY, determine the NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE reporting requirements, and report your results to the evaluator.

2003 NRC Exam Rev. 2 Page 1 of 4

TASK CONDITIONS A. The emergency plan has just been implemented for the classification you just made.

INITIATING CUE Based on this emergency classification ONLY, determine the NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE reporting requirements, and report your results to the evaluator.

2003 NRC Exam Rev. 2 Page 2 of 4

TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

I 2003 NRC Exam Rev. 2 Page 3 of 4

TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

2003 NRC Exam Rev. 2 Page 4 of 4

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET PCOl7-I 04 0

2.4.41 4.0 06/14/03 E-PLAN SRO Appl. To JPlvl Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews:

Perform Emergency Plan Classification and Identify Reportability Requirements.

Russ Halm 0611 4/03 Writer Date InstructorNVriter Date Ap p rova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

15 Time Criticalllo Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (0300)

Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO E-PLAN PCOI 7-1 04

\\--

I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A.

B.

C.

EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 PCOl70-I 04, SIMULATOR EVALUATION SCENARIO NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

V. INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

VI. TASK STANDARD Emergency classification of Alert declared within 15 minutes and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reportability to the NRC identified.

2003 NRC Exam Rev. 2

Appl. To/JPM NO.: SRO E-PLAN PCOl7-104 Step PERFORMANCE CHECKLIST Page 3 of 5 Student Name:

Action EVALUATOR NOTE:

0 0

0 This JPM rliust be performed in the simulator following completion of the scenario as Unit Supervisor.

This is a time critical JPM.

Ensure a copy of EP-PS-100 is available to support performance of this JPM.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

EVALUATOR NOTE:

After the candidate reviews the Task Conditions / Initiating Cue Sheet:

0 0

Ask if the candidate is ready to begin the JPM.

When the candidate is ready to begin the JPM inform the candidate that this is a Time Critical JPM.

Record Start Time Obtains a copy of EP-PS-100.

Evaluates information.

EVALUATOR CUE:

Assistance may be necessary for some specific scenario data or sequence of events. Use your judgement on acceptable levels of cueing based on candidates request.

Refers to classification matrix.

• Critical Step

1. Critical Sequence Standard Controlled copy obtained.

Identifies loss of reactor vessel inventory as potential Emergency Plan entry.

Selects Tab 4.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Appl. To/JPM NO.: SRO E-PLAN PCOl7-104 Student Name:

Step 4

• 5

• 6 7

8 9

• I 0 Action Reviews the table of contents for events experienced during the scenario.

Choose appropriate emergency action level.

Record Time of Alert declaration EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements Obtains a copy of NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE Reviews reporting requirements Determines Reportability requirements Reports results

• Critical Step

1. Critical Sequence STCP-QA-12%

Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2 Standard Reviews all category 12.

Identifies entry into EAL 12.2 based upon reactor coolant system leak rate greater than 50 gpm.

Classifies the event as an Alert.

Controlled copy obtained.

Reviews Attachments:

E, F, G, and H Determines 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification due to activation of the emergency plan.

Reports 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification to the evaluator.

Eva1 I

Page 4 of 5 Comments

i Standard Step Action EVALUATOR CUE:

Appl. To/JPM NO.: SRO E-PLm Eva1 Comments J PC017- 04 i'

PERFORMANCE CHECKLIST Student Name:

(:

Page 5 of 5 After the reportability requirements have been identified, inform the candidate the JPM is complete.

I I

I I

I1

• Critical Step

1. Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS v

A. The emergency plan has just been implemented for the classification you just made.

INITIATING CUE Based on this emergency classification ONLY, determine the NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE reporting requirements, and report your results to the evaluator.

I Y

Page 1 of 4 2003 NRC Exam Rev. 2

TASK CONDITIONS A. The emergency plan has just been implemented for the classification you just made.

INITIATING CUE Based on this emergency classification ONLY, determine the NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE reporting requirements, and report your results to the evaluator.

-Lr-2003 NRC Exam Rev. 2 Page 2 of 4

TASK CONDITIONS

.VI A. Consider the plant transient conditions and failures experienced in this scenario.

INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

2003 NRC Exam Rev. 2 Page 3 of 4

'J TASK CONDITIONS A. Consider the plant transient conditions and failures experienced in this scenario.

INITIATING CUE Provide the highest emergency classification level for the events in the scenario just completed.

e 2003 NRC Exam Rev. 2 Page 4 of 4