Text

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)
	v • d • e

S-301 Administrative Topics Outline Form ES-301-1 Facility: SSES Date of Examination: 08111/03 Examination Level (circle one): Ro Operating Test Number:

Administrative Topic Describe activity to be performed (See Note)

Conduct of Operations 2.1.25 2.813.1 JPM Determine Estimated Time to Reach 200 OF and Required Technical Specification Actions.

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

Equipment Control 2.2.13 3.613.8 JPM Determine blocking points of a clearance order.

Radiation Control NIA Emergency Pian 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 b r SROs. RO applicants require only4 items unless they are retaking only the administrative topics, when 5 are required.

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

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 provaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

\--

10 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:

Eva1uator Name:

Signature Typed or Printed Comments:

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

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

REQUIRED TAS K I NFORMAT10N 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):

4 None IV. TASK CONDITIONS A. Unit 1 is in Mode 4.

B. The reactor has been shutdown for 3.5 days.

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

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

G. B loop of RHR is Out Of Service.

H. A RHR pump is operating and C RHR pump is in standby I. 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 1hour (+/- 5 minutes);

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

.u 2003 NRC Exam Rev. 2

PERFORMANCE CHECKLIST Page 3 of 4 Appl. To/JPM No.: S/RO 49.0N.003.201 Student Name:

Step Action Standard Eva1 Comments 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.

1 Obtains a controlled copy of ON-149-001 Controlled copy obtained.

2 Reviews symptoms and Observations section of Determines ON-149-001 is procedure appropriate procedure for the given conditions.

EVALUATOR NOTE Steps may be done in any order.

3 Selects correct procedure section Determines section 3.4 is applicable.

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

1 Hour (+/- 5 minutes)

Critical Step #Critical Sequence STCPPA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

PERFORMANCECHECKLIST Page 4 of 4 Appl. To/JPM No.: S/RO 49.0N.003.201 Student Name:

Step Action Standard Eva1 Comments 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.

4 Comply with Technical Specification 3.4.9 Refers to Technical Specification 3.4.9 and determines:

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

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

AND Must monitor Reactor coolant temperature once per hour EVALUATOR CUE This completes the JPM.

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

Page 1 of 1 2003 NRC Exam Rev. 2

TASK CONDITIONS

.--- , A. Unit 1 is in Mode 4.

B. The reactor has been shutdown for 3.5 days.

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

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

G. B loop of RHR is Out Of Service.

H. ARHR pump is operating and C RHR pump is in standby I. 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.

Page Iof 2 2003 NRC Exam Rev. 2

TASK CONDITIONS A. Unit 1 is in Mode 4.

B. The reactor has been shutdown for 3.5 days.

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

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

G. B loop of RHR is Out Of Service.

H. A RHR pump is operating and C RHR pump is in standby I. 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.

Page 2 of 2 2003 NRC Exam Rev. 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:

Document a Failed LPRM Detector Completed By: Reviews:

Russ Halm 06/14/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

..?.--

15 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Eva1uat ion:

Eva1uator Name:

Signature Typed or Printed Comments:

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

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 78.AD.001 .I01 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 MAN1PULATIONS This JPM satisfies the requirements of Operational Activity@):

None

-_v<_

IV. TASK CONDITIONS A. Unit 1 is in MODE 1.

B. Reactor Engineering has completed evaluation of a downscale alarm condition for LPRM detector 48-178.

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 48-17B.

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

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM No.: S/RO 78.AD.001.101 Student Name:

Step Action Standard Eva1 Comments 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.

1 Obtains a controlled copy of procedure. Controlled copy obtained.

2 Refers to correct section. Refers to section 4.

3 Determines current LPRM status. Obtains the Operations Special Log Book in the Unit 1 control EVALUATOR CUE: room and locates the previously When the candidate identifies where the current LPRM completed copy of Attachment A &

Upscale Alarm Status Control Log is retained provide the B.

candidate with the JPM copy of Attachment A & B.

4 Obtains a blank copy of Attachment A & B. Blank copy obtained.

EVALUATOR CUE:

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

& B.

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

Page 1 of 1 2003 NRC Exam Rev. 2

i' i/

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

Step Action Standard Eva1 Cornments 5 Completes new Attachment A. Enters 1 for Unit.

EVALUATOR CUE: Transfers the previous LPRM data If candidate elects to verify position of switches in lower to the new Attachment A.

relay room, provide the cue that the switches are in the positions indicated on Attachment A (Special log book OR Candidate may desire to verify switches in lower relay room.

Place a checkmark in column 2 adjacent to LPRM detector 48-17B in Zone 4.

6 Determine if 250% of LPRM Upscale alarms in each zone Circles YES for zone 1, 2, 3, 5, 6, are operable. 7, 8, and 9.

Circles NO for zone 4.

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

8 Make notifications. Notifies the Unit Supervisor and Unit IPCOs about the operating restriction based upon the LPRM alarm condition.

Critical Step #Critical Sequence 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 Action Standard Eva1 Comments

9 Posts placard. Attaches placard to operating panel 1C651.

EVALUATOR NOTE:

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

10 Complete Attachment 6. Enters 1 for Unit.

Transfers the previous LPRM data to the new Attachment 6.

Circles LPRM detector 48-17 for APRM E, under the column B Level.

11 Notify Reactor Engineering. Contacts reactor engineering and provides the current LPRM status.

12 Obtains review. Submit the completed Attachment A and B to the Unit Supervisor.

EVALUATOR CUE:

This completes the JPM.

Critical Step #Critical Sequence 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 48-17B.

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

INITIATING CUE Complete all required documentation in accordance with the appropriate instruction for LPRM detector 48-17B.

.v-.

Page 1 of 2 2003 NRC Exam Rev. 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 48-17B.

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

INITIATING CUE Complete all required documentation in accordance with the appropriate instruction for LPRM detector 48-17B.

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 06113/03 Writer Date InstructorNVriter 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 ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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 1B (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 1P501B 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/electricaIdrawing@),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 Action Standard Eva1 Comments EVALUATOR NOTE 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:

Blank table labeled for tagout points 0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LEITERS.

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.

1 Obtains NDAP-QA-0322, ENERGY CONTROL PROCESS References NDAPs to determine overall process and prescribed and NDAP-QA-0323, STANDARD BLOCKING sequence.

PRACTICES 2 Reviews the scope of work planned for 1P501B. Determines the pump discharge vent valve 115137B will be replaced.

3 Use electrical print to identify 1P501B motor breaker 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

Critical Step #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 Action Standard Eva1 Comments

4 Use electrical print to identify HV-I 1511B MOV breaker. Using -I 38 Sht.1, determines breaker lB501024 will need to be:

Second in the sequence Opened Red tagged Then fills out table "5 Use electrical print to identify HV-I 151IB MOV breaker. Using E-I 38 Sht.19, determines breaker 18501034 will need to be:

Second in the sequence Opened Red tagged Then fills out table

6 Use mechanical drawing to identify HV-I 15136, CWP 6 Using M-I15 Sht.1, determines Suction valve. HV-11513B will need to be:

Third in the sequence Closed Red tagged Then fills out table

Critical Step #C riticaI Sequence 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 Action Standard Eva1 Comments

7 Use mechanical drawing to identify HV-11511B, CWP B Using M-I 15 Sht.1, determines Discharge valve. HV-11511B will need to be:

Third in the sequence Closed Red tagged Then fills out table

8 U mechanical drawing to identif! 115153, CWP B I6 Using M-I 15 Sht.1, determines Bearing Seal Water Supply valve. 115153 will need to be:

EVALUATOR NOTE: Third in the sequence Drawing grid location is D-I (Detail A). Closed Red tagged Then fills out table

9 Use mechanical drawing to identify 115154, CWP B OB Using M-I 15 Sht.1, determines Bearing Seal Water Supply valve. I15154 will need to be:

EVALUATOR NOTE: Third in the sequence Drawing grid location is C-I (Detail A). Closed Red tagged Then fills out table 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 #Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i:'

PERFORMANCECHECKLIST Page 6 of 7 Appl. ToIJPM No.: New Admin ID Blocking Points Student Name:

Step Action Standard Eva1 Comments

I0 Use mechanical drawing to identify 1151398, CWP B Using M-I 15 Sht.1, determines Suctioh Vent valve. 115139B will need to be:

EVALUATOR NOTE: Fourth in the sequence Drawing grid location is 1-1. Opened No Tag Required Then fills out table

I1 Use mechanical drawing to identify I15141B, CWP B Using M-I 15 Sht.1, determines Suction Vent valve. 115141B will need to be:

EVALUATOR NOTE: Fourth in the sequence Drawing grid location is 1-1. Opened No Tag Required Then fills out table

I2 Use mechanical drawing to identify 115142B, CWP B Using M-I 15 Sht.1, determines Discharge Drain valve. 115142B will need to be:

EVALUATOR NOTE: Fourth in the sequence Drawing grid location is 1-1 Opened No Tag Required Then fills out table

Critical Step #Critical Sequence STCP-PA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i:'

i:

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

~

Step Action Standard Eva1 Comments

I3 Use mechanical drawing to identify 115143B, CWP B Using M-I 15 Sht.1, determines Suction Drain valve. 115123B will need to be:

EVALUATOR NOTE: Fourth in the sequence Drawing grid location is 1-1 Opened No Tag Required Then fills out table

I4 Reports the results. Informs the Unit Supervisor of the results by handing the supervisor EVALUATOR CUE the completed table.

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.

Critical Step #Critical Sequence STCP-QA-1ZSB Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 2

i ANSWER KEY (DO NOT GIVE TO STUDENTS) c,Sequence 2

Component ID I A I0203 Component Description ClRC WATER PUMP B IP501B 13.8 KV BKR IB501024 CWP 1B DSCH MOV HV-I 1511B BKR 52-024 1B501034 ClRC WATER PUMP B SUCTION VLV HV-I 1513B Position Racked out Open Open Tag Color Red Red Red BKR 3 HV-I 1513B ClRC WATER PUMP B SUCTION VLV Close Red I-+-

HV-I 151I B ClRC WATER PUMP B DISCHARGE VLV Close Red

=

115153 CWP B IB BEARING SEAL WATER SUPPLY IS0 Close Red VLV 115154 CWP B OB BEARING SEAL WATER SUPPLY IS0 VLV Close Red 1 I

115139B CW PUMP B SUCTION VENT VLV Open No Tag 115141B CW PUMP B SUCTION VENT VLV Open No Tag 115142B ClRC WATER PUMP B SUCTION DRAIN VLV Open No Tag 4 115143B ClRC WATER PUMP B SUCTION DRAIN VLV Open No Tag I Page 1 of 2 I 2003 NRC Exam Rev. 2

TASK CONDITIONS i- A. NlMS is not available.

B. Unit 1 Circ Water Pump 1P501B 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.

Page 1 of 2 2003 NRC Exam Rev. 2

TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1P501B 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 INITIATING CUE Using the appropriate NDAP(s) and mechanicaVelectrica1drawing(s), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

Page 2 of 2 2003 NRC Exam Rev. 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:

Activate the Fire Brigade.

Completed By: Reviews:

Russ Halm 06114/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

.~

c.-

20 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, (05100)

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

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. ON-013-001 RESPONSE TO FIRE, REV. 14 B. FP-013-189 DIESEL GENERATOR BAY A, REV. 3 C. AR-SP-001 PAGE 118, REV. 7 D. AR-SP-002 PAGE 72, REV. 9

--- E. AR-SP-002 PAGE 76, REV. 9 III. REACTIVITY MAN1PULATlONS 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 11-AUG-03 44-660 A DIESEL GEN FIRE DET X I 16-21 ALM 17:16 MON 11-AUG-03 44-677/710 A DG FIRE SUP X25O-Zl ALM 17:20 MON 11-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 PERFORMANCE CHECKLIST Page 4 of 7 Appl. To/JPM No.: SIR0 13.ON.003.001 Student Name:

Step Action Standard Eva1 Comments 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:

A COPY of ON-013-001.

0 Pre-Fire Plans.

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

Locates alarm procedure for X250 Z1. Selects AR-SP-001 page 118.

EVALUATOR NOTE:

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

Locates alarm procedure for X I 16- Z1. Selects AR-SP-002 page 72.

EVALUATOR NOTE:

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

Critical Step #Critical Sequence 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 Action Standard Eva1 Comments 4 Locates alarm procedure for X I 16- 25. Selects AR-SP-002 page 76.

EVALUATOR NOTE:

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

5 3btains a controlled copy of Off-Normal procedure ON- Controlled copy obtained.

313-001.

6 Refers to correct section. Refers to section 3.

7 Activates fire brigade. Refers to Attachment Q or the Activity Hard Card.

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

AND EVALUATOR CUE: Informs the Fire Brigade Leader a As fire brigade leader inform th- candidate you will be fire is confirmed in Diesel setting up the command post at control structure central Generator A building.

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.

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

=

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

Page 1 of 1 2003 NRC Exam Rev. 2

i:

PERFORMANCE CHECKLIST Page 6 of 7 Appl. TolJPM No.: S/RO 13.ON.003.001 Student Name:

Step Action Standard Eva1 Comments

9 Contacts Fire brigade members from Operations. 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.

I 0 Send Pre-Fire Plan FP-013-189 to command post. Designates one fire brigade member to take Pre-Fire Plan FP-013-189 to the command post.

11 Contacts Fire brigade members from Security. Dials extension 3114 or 3115 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.

12 Sound fire alarm. At panel OC695:

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

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

Critical Step #Critical Sequence STCP-QA-1255 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i:

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

Step Action Standard Eva1 Comments 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.

13 Make plant page announcement. Keys the plant page and announces:

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

Repeat the above announcement.

I4 Selects the appropriate Pre-Fire Plan. Obtains a copy of FP-013-189.

EVALUATOR CUE:

This completes the JPM.

Critical Step #Critical Sequence 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 1I-AUG-03 44-660 A DIESEL GEN FIRE DET X I 16-21 ALM 17:16 MON 11-AUG-03 44-677/710 A DG FIRE SUP X25O-Zl ALM 17:20 MON 11-AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

Page Iof 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 44-6771710 A DG FIRE SUP X25O-Zl ALM 1720 MON 11-AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

Page 2 of 2 2003 NRC Exam Rev. 2

ES-301 Administrative Topics Outline Form ES-301-1 I

1 Facility: SSES Date of Examination: 08/11/03 I Examination Level (circle one): SRO Operating Test Number:

Administrative Topic Describe activity to be performed (See Note)

Conduct of Operations 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

~ ~~

Equipment Control 2.2.13 3.613.8 JPM Determine accuracy and adequacy of a clearance order.

Radiation Control 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 b r SROs. RO applicants require only4 items unless they are retaking only the administrative topics, when 5 are required.

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

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:

Authorize Bypassing Rod Worth Minimizer In Accordance With NDAP-QA-0338 Completed By: Reviews:

Russ Halm 06114/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 15 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, (0300)

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

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

i i r

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

Step Action Standard Eva1 Comments EVALUATOR NOTE:

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

A COPY of NDAP-QA-0338.

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

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

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. Controlled copy obtained.

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

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

Enters initiating condition data. Enters the following data for Initiating Condition:

0 Rod ID is 22-59 0 Notch is 00 0 Unit is 1 0 RBM Channel A or B is NA 0 Power Level is 1%

0 Date/Time Determine if power is above the LPSP. Places a checkmark in NO box.

Critical Step #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 Action Standard Eva1 Comments 6 Determine if a special test is being performed. Places a checkmark in the No box.

7 Determine if both RSCS and RWM are problems. Places a checkmark in the No box.

8 Determine if a computer problem exists. Places a checkmark in the No box.

9 Determine if RPlS problems exist. Places a checkmark in the No box.

10 Contact Reactor Engineering. Contacts Rx Engineer to :

investigate the RWM pointer EVALUATOR CUE: 0 Sequence in RWM As Rx Engineer, inform the candidate the RWM pointer Investigate sequence error and sequence has been verified correct.

Places a checkmark in the No Fix box.

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

I2 Determines Tech Spec impact. 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 510% RTP.

Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

i PERFORMANCE CHECKLIST Page 6 of 7 Appl. To/JPM No.: S/RO 00.AD.047.001 Student Name:

Step Action Standard Eva1 Comments Identifies Condition C must be entered and the following Required Actions are applicable:

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

EVALUATOR CUE: -

OR C.2.1.I, Immediately verify 2 Give the candidate the Start-up control rod sequence A2.

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.

13 Identifies a LCO/TRO Log Sheet must be completed. States 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 #Critical Sequence STCP-QA-1258 Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 2

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

Step Action Standard Eva1 Comments

I4 Determine that it is allowable to bypass RWM. Determines that RWM can be bypassed.

15 Authorize bypassing RWM. Places a checkmark in box for RWM.

Signs form and enter current time/date.

EVALUATOR CUE:

This completes the JPM.

Critical Step #Critical Sequence 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 38-59from 00 to 04 as specified by Rod Step A2-66 in the pull sheet.

C. When the PCO attempted Step A2-67(Rod 22-59from 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 Page 1 of 2 2003 NRC Exam Rev. 2

TASK CONDITIONS

I, A. A plant startup is in progress on Unit Iwith 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.