Text

Draft - Section a Operating
	ML032591125
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: ML032591125 (96)
	v • d • e

'S-301 Administrative Topics Outline Form ES-301-1 Facility: SSES Date of Examination: 08/11/03 Examination Level (circle one): RO Operating Test Number:

L-'

Administrative Topic Describe activity to be performed (See Note)

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Conduct of Operations 2.1.25 2.813.1 JPM Determine Primary Containment Water Level During Anomaly.

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

Equipment Control 2.2.13 3.6/3.8 JPM Determine blocking poinfs of a clearance order. (8)

-e Radiation Control N/A Emergency Plan 2.4.27 3.013.5 JPM Activate the Fire Brigade and select the appropriate Pre-Fire Plan N0TE:All items (5 total) are required 6r 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. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 59.0N.007.201 0 06114/03 2.1.25 2.813.1 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Perform Primary Containment Water Level Anomaly Completed By: Reviews:

Russ Halm 06114103 Writer Date InstructorNVriter Date Approval:

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 Eva1uation :

Evaluator Name:

Signature Typed or Printed Comments:

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

Page 1 of1 File No. A14-5B 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 59.0N.007.201

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. EP-DS-002 RPV AND PRIMARY CONTAINMENT FLOODING, REV. 1 B. ON-259-003 PRIMARY CONTAINMENT WATER LEVEL ANOMALY, REV. 3 III. REACTIVITY MANIPULATlONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. An accident occurred on Unit 2.

B. Control of the emergency was transferred to the TSC.

C. EP-DS-002, RPV and Primary Containment Flooding is being implemented.

D. Suppression pool water level is above 49 feet.

V. INITIATING CUE Calculate primary containment water level and inform the Unit Supervisor of your results.

VI. TASK STANDARD Primary containment water level is calculated to be 58.5 feet (+/- 0.5 foot).

2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 3 of 4 Appl. To/JPM No.: S/RO 59.0N.007.201 Student Name:

Step Action Standard Eva1 Comments EVALUAT0 R Ensure a copy of ON-259-003 is available.

EVALUAT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains a controlled copy of ON-259-003. Controlled copy obtained.

Checks approval to perform procedure. Verifies signature approval by Shift Supervision.

Selects correct procedure section. Selects section 3.2.

CAUTION HIGH PRIMARY CONTAINMENT WATER LEVEL MAY CAUSE HPCl AND RClC PUMP SUCTION RELIEF VALVES TO LIFT IF NOT ISOLATED FROM SUPPRESSION POOL.

Record suppression chamber pressure. Records suppression chamber pressure on panel 2C601 using EVALUATOR CUE the green pen on PR-2751OA(B).

After the correct instrument is identified, inform the candidate the value is 16 psig.

Record drywell pressure. Records drywell pressure on panel 2C601 using the red pen on PR-EVALUATOR CUE 2751OA(B).

After the correct instrument is identified, inform the candidate the value is 12 psig.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 4 of 4 Appl. To/JPM No.: S/RO 59.0N.007.201 Student Name:

Step Action Standard Eva1 Comments 6 Calculate differential pressure. Enters 16 psig for suppression chamber pressure.

Enter 12 psig for drywell pressure.

Subtracts 12 psig from 16 psig and enters 4 psid.

7 Plots data on curve. Refers to Attachment A.

Locates 4 psid on the X-axis of the curve and moves,vertically up until it intersects the line on the curve.

From the point of intersection moves horizontally to the Y-axis on the curve.

8 Determines containment water level. Determines primary containment water level is -58.5 feet.

9 Reports containment water level data. Notifies Unit Supervisor primary containment water level is -58.5 EVALUATOR CUE feet.

Act as Unit Supervisor and acknowledge value of containment water level.

EVALUATOR This completes the JPM.

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

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L--

A. An accident occurred on Unit 2.

B. Control of the emergency was transferred to the TSC.

C. EP-DS-002, RPV and Primary Containment Flooding is being implemented.

D. Suppression pool water level is above 49 feet.

INITIATING CUE Calculate primary containment water level and inform the Unit Supervisor of your results.

Page 1 of 2 2003 NRC Exam Rev. 1

TASK CONDITIONS i-'

A. An accident occurred on Unit 2.

B. Control of the emergency was transferred to the TSC.

C. EP-DS-002, RPV and Primary Containment Flooding is being implemented.

D. Suppression pool water level is above 49 feet.

INITIATING CUE Calculate primary containment water level and inform the Unit Supervisor of your results.

Page 2 of 2 2003 NRC Exam Rev. 1

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 L

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 EvaIuation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIR0 78.AD.001.101 L--

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.

6. 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 andlor 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 MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None u

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

B. Reactor Engineering has completed evaluation of a downscale alarm condition for LPRM detector 48-17B.

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 II of the power to flow map occurs.

2003 NRC Exam Rev. 1

i/

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM No.: S/RO 78.AD.001 .IO1 Student Name:

Step Action Standard Eva1 Comments EVALUATOR 0 This JPM should be performed in the simulator or plant control room.

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

Obtains a controlled copy of procedure. Controlled copy obtained.

Refers to correct section. Refers to section 4.

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.

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-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step Action Standard Eva1 Comments 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 1 PCOs about the operating restriction based upon the LPRM alarm condition.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step Action Standard Eva1 Comments

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

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

10 Complete Attachment B. Enters 1 for Unit.

Transfers the previous LPRM data to the new Attachment B.

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 This completes the JPM.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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.

Page 1 of 2 2003 NRC Exam Rev. 1

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 48-1 7B.

Page 2 of 2 2003 NRC Exam Rev. I

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Attachment A 01-078-001 LPRM UPSCALE ALARM STATUS CONTROL LOG Revision 7 Page 5 of 6 UNIT 1 As least 50%

LPRMs Operable per

'Zone (Circle

!YES or NO)

(1) (2) (1) (2) (1) (2) (1) (2) (1) (2)

Zone 1 16-49A - 16-41A - - 24-49A - 24-41A - - 16-498 - 16-416 - - 24-498 - 24-416 - - 16-49C - - 16-41C - - 24-49C - 24-41C - -

Zone2 40-49A ___ - 40-41A - - 48-49A - 48-41A - - 40-498 - ___ 40-418 - ___ 48-496 - ___ 48-416 - - @NO 40-49C - - 40-41C - __ 48-49C - 48-416 __ -

Zone3 16-17A - - 16-25A - - 24-17A - __ 24-25A - - 16-170 - - 16-256 - - 24-170 - __ 24-256 - - @No 16-17C - - 16-25C - __ 24-17C - 24-25C - -

Zone4 40-17A - L 40-25A 40-17A - 48-25A - -

- - - J -

_ I 40-178 40-256 48-176 ___ 48-258 @NO 40-17C - - 40-25C - - 48-17C - 48-25C - J

- - - __ - J Zone5 24-33A 24-336 24-33C 32-25A 32-256 32-25C 32-33A 32-338 32-33C 32-41A 32-416 32-41C 40-33A 40-330 40-33C 5

@NO Zone6 16-09A - __ 24-09A - - 32-09A - __ 40-09A - __ 32-17A - 16-098 - - 24-096 - - 32-096 - - 40-098 - __ 32-170

~

16-09C - - 24-09C .- 32-09C 40-09C - 32-17C __ -

Zone7 08-17A - - 08-25A - - 08-33A - __ 08-41A - __ 16-33A __

08-178 08-17C

__ 08-258 08-25C - __

08-336 08-33C 08-416 08-41C 16-338 16-33C __ -

Zone8 24-57A - - 32-57A - -,40-57A - - 32-49A - - 24-578 - - 32-578 - - 40-578 - - 32-496 - @o 24.576 - - 32-57C - - 40-57C - - 32-49C - ~

Zone9 48-33A - __ 56-25A - - 56-33A - - 56-41A ___ - 48-330 - - 56-256 - - 56-336 - 56-416 - - 48-33c - - 56-25C - - 56-33C _r/ - 56-41C - - LPRM Upscale Alarm Status Assessment Complete Shift Supervision Date Time FORM 01-078-001-1, Rev. 4, Page 1 of 1

L-- APRM CHANNEL LPRM LOCATIONS APRM B 32-57 08-49 16-57 24-49 16-41 40-49 32-41 08-33 48-41 24-33 16-25 40-33 32-25 56-33 ( 48-25 1 24-17 16-09 08-17 52-09 - 56-17 48-09 40-17 I

LPRM Operability Assessment Complete Shift Supervision Date Time FORM 01-078-001-2, Rev. 0, Page 1 of 1

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Attachment A 01-078-001 LPRM UPSCALE ALARM STATUS CONTROL LOG Revision 7 Page 5 of 6 UNIT As least 50%

LPRMs Operable per

'Zone (Circle IYES or NO)

(1) (2) (1) (2) (1) (2) (1) (2) (1) (2)

Zone 1 16-4919 ___ - 16-41A - - 24-49A - - 24-41A - - 16-498 __ __ 16-418 - - 24-498 - - 24-418 - - YES/NO 16-49C - - 16-41C __ - 24-49C - - 2441C - -

Zone 2 40-49A ___ __ 40-41A - 48-49A - - 48-41A - __

40-498 __ - 40-418 - 48-498 - __ 48-418 - YESINO 40-49C - - 4041C - __ 48-49c - - 48-41C __ ___

Zone3 16-17A - - 16-25A __ - 24-17A - - 24-25A - - 16-170 - - 16-258 __ - 24-178 __ - 24-258 - - YES/NO 16-17C __ ___ 16-25C - - 24-17C __ ___ 24-25C __ -

Zone4 40-17A - __ 40-25A - - 48-17A - - 48-25A ___ - 40-178 - __ 40-258 - - 48-178 - __ 48-258 - - YESINO 40-17C - - 40-25C - - 48-17C __ - 48-25C - -

Zone5 24-33A - __ 32-25A - - 32-33A ___ - 32-41A - - 40-33A __ - 24-338 - - 32-258 - __.32-338 - __ 32-418 - __ 40-338 - - YES/NO 24-33C __ - 32-233 __ - 32-33C ___ - 32-41C ___ - 40-336 __ -

Zone6 16-09A - __ 24-09A __ - 32-09A - - 40-09A - - 32-17A - - 16-098 - - 24-098 - - 32-098 __ - 40-098 ___ - 32-176 __ _- YESlNO 16-09C __ - 24-09C - - 32-09C - - 40-09C - - 32-17C - -

Zone7 08-17A - __ 08-25A __ - 08-33A - - 0841A __ 16-33A __ ___

08-178 08-17C

- 08-258 08-25C 08-338 08-33C 08-418 08-41C - 16-338 16-33C YESlNO Zone8 24-57A - - 32-57A - -,40-57A - - 32-49A - - 24-578 - - 32-578 - - 40-578 - - 32-498 ___ - Y ESINO 24-57C - - 32-576 - ___ 40-57C - - 32-49C - -

Zone9 48-33A - __ 56-25A - - 56-33A - - 56-41A - - 48-338 - - 56-258 ___ - 56-338 - - 56.418 - - YEWNO 48-33c - - 56-25C - - 56-336 .__ - 56-41C __ -

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LPRM Upscale Alarm Status Assessment Complete I I Shift Supervision Date Time FORM 01-078-001-1, Rev. 4, Page 1 of 1

UNIT Attachment 8 01-078-001 LPRM vs. APRWLPRM Group Status Control Log - Revision 7 (Inoperable LPRM's are circled) Page 6 of 6 APRM B 32-57 08-49 16-57 24-49 16-41 40-49 32-41 08-33 48-41 24-33 16-25 40-33 32-25 56-33 48-25 24-17 16-09 08-17 32-09 56-17 I

48-09 40-17 APRM F 16-57 24-49 32-57 I 08-49 32-41 08-33 16-41 . 40-49 16-25 40-33 48-41 24-33 48-25 24-17 32-25 ' 56-33 32-09 56-17 16-09 08-17 48-09 40-17 LPRM GROUP A 32-49 40-57 16-49 24-57 1 6-33 24-41 4a-49 08-41 48-33 56-41 32-33 . 40-41 32-17 08-25 16-17 24-25 40-25 48-17 56-25 LPRM GROUP B 08-49 16-57 24-49 32-57 40-49 32-41 08-33 16-41 24-33 16-25 40-33 48-41 56-33 48-25 24-17 32-25 08-17 33-09 56-17 LPRM Operability Assessment Complete J I Shift Supervision Date Time FORM 01-078-001-2, Rev. 0, Page 1 of 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET RO New ID 0 06/13/03 2.2.13 3.6/3.8 Blocking Points Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Identify Blocking Points Completed By: Reviews:

Russ Halm 06/13/03 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:

F o STCP-QA-IZ5A

~

Rev. 4. (05100)

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

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

1. SAFETY CONSIDERATIONS U

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:

I.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. 1I)

E. E-I38 Sheet 1 ClRC WATER PUMP DISCHARGE VALVE (Rev. 13) v F. E-I38 Sheet 19 ClRC WATER PUMP SUCTION VALVE (Rev. 6)

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

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

B. Unit 1 Circ Water Pump IP501B discharge vent valve 1151 7B neeGs to be replaced (scope of work).

C. When NIMS 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 rnechanicaVelectricaIdrawing@), 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. I

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

Step Action Standard Eva1 Comments EVALUATOR 0 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:

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

EVALUATOR 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-I37 Sht.3, determines breaker IA10203 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. (9193)

Page 1 of1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 4 of 7 Appl. TolJPM No.: New Admin ID Blockinq Points Student Name:

~

Step Action Standard Eva1 Comments

4 Use electrical print to identify HV-11511B MOV breaker. Usina E-I 38 Sht.1, determines breavker 1B501024 will need to be:

Second in the sequence Opened Red tagged Then fills out table

5 Use electrical print to identify HV-I 1511B MOV breaker. Using E-I 38 Sht.19, determines breaker 1B501034 will need to be:

Second in the sequence Opened Red tagged Then fills out table

6 Use mechanical drawing to identify HV-l1513B, CWP B Using M-I 15 Sht.1, determines Suction valve. HV-11513B will need to be:

Third in the sequence Closed Red tagged Then fills out table

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

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 5 of 7 Appl. TolJPM 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 Use mechanical drawing to identify 115153, CWP B IB Using M-I 15 Sht.1, determines Bearing Seal Water Supply valve. I15153 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. 115154 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-125B Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

'i i

PERFORMANCE CHECKLIST Page 6 of 7 Appl. To/JPM No.: New Admin ID Blocking Points Student Name:

Step Action Standard Eva1 Comments

I0 Use mechanical drawing to identify I 15139B, CWP B Using M-I 15 Sht.I , determines Suction Vent valve. 1151398 will need to be:

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

I 1 Use mechanical drawing to identify 115141B, 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

I 2 Use mechanical drawing to identify 115142B, CWP B Using M-I 15 Sht.1, determines Discharge Drain valve. 1151428 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-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step Action Standard Eva1 Comments

I3 Use mechanical drawing to identify I151438, CWP B Using M-I 15 Sht.1, determines Suction Drain valve. 115143B 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 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 STCPQA-1256 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

ANSWER KEY (DO NOT GIVE TO STUDENTS)

Component Description Position Tag Color ClRC WATER PUMP B IP501B 13.8 KV BKR I Rackedout I Red I 2 I 1B501024 CWP IB DSCH MOV HV-1151IB BKR 52-024 I ODen I Red 2

I 3 I 1B501034 ClRC WATER PUMP B SUCTION VLV HV-11513B BKR HV-I 1513B ClRC WATER PUMP B SUCTION VLV HV-1151lB ClRC WATER PUMP B DISCHARGE VLV Open Close Close Red Red Red I 115153 CWP B IB BEARING SEAL WATER SUPPLY IS0 VLV Close Red 3 115154 115139B CWP B OB BEARING SEAL WATER SUPPLY IS0 VLV CW PUMP B SUCTION VENT VLV II Close ODen I Red NoTaa I 4 I 115141B CW PUMP B SUCTION VENT VLV Open No Tag

- 4 115142B ClRC WATER PUMP B SUCTION DRAIN VLV Open No Tag 4 115143B ClRC WATER PUMP B SUCTION DRAIN VLV Open No Tag Page 1 of 2 2003 NRC Exam Rev. 1

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 1 of 2 2003 NRC Exam Rev. I

TASK CONDITIONS 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 IP501B has been removed from service IAW OP-142-001 section 3.2 INITIATING CUE Using the appropriate NDAP(s) and mechanicaVelectrica1drawing@), 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. I

ai quauodluo3 amanbag j

PENNSYLVANIA POWER & LIGHT COMPANY L-JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 13.ON.003.001 0 06114/03 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 06/14/03 Writer Date InstructorNVriter Date Approval:

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

'4 on LU 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. A14-56 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 13.ON.003.001 i d

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.

11. 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 I11. REACTIVITY MANIPULATlONS This JPM satisfies the requirements of Operational Activity(s):

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 X I 16-Z5 ALM 17:14 MON 11-AUG-03 44-660 A DIESEL GEN FIRE DET XIl6-Zl ALM 17:16 MON 1I-AUG-03 44-677/710 A DG FIRE SUP X250-21 ALM 17:20 MON 11-AUG-03 44-676 PA011 ADIESL 2003 NRC Exam Rev. 1

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. A14-5B 2003 NRC Exam Rev. 1

PERFORMANCECHECKLIST Page 4 of 6 Appl. To/JPM No.: SlRO 13.ON.003.001 Student Name:

=

Step Action Standard Eva1 Comments EVALUATOR 0 This JPM must be done in the simulator or plant control room.

0 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 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- Z l . 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-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 5 of 6 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 Plan FP-013-189.

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

013-001.

6 Refers to correct section. Refers to section 3.

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

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

EVALUATOR CUE Informs the Fire Brigade Leader a As fire brigade leader inform the 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-1258 Rev. 2,(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

( (,

PERFORMANCE CHECKLIST Page 6 of 6 Appl. To/JPM 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-OA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(

PERFORMANCE CHECKLIST Page 7 of 6 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 This completes the JPM.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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?16-25 ALM 17:14 MON 11-AUG-03 44-660 A DIESEL GEN FIRE DET X116-21 ALM 17:16 MON 11-AUG-03 44-6771710 A DG FIRE SUP X250-Zl ALM 17:20 MON II-AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

L-'

Page 1 of 2 2003 NRC Exam Rev. 1

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

6. The following SIMPLEX data print out is available:

FIRE DET X I I6-25 ALM 17:14 MON 11-AUG-03 44-660 A DIESEL GEN FIRE DET XI16-21 ALM 17:16 MON II-AUG-03 44-6771710 A DG FIRE SUP X250-ZI 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 2 of 2 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET E-PLAN 06/14/03 SRO PCOl7-I02 0 2.4.41 4.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Perform Emergency Plan Classification and Identify Reportability Requirements.

Completed By: Reviews:

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

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 15 Time Critical 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:

L-'

Form STCP-CL4-125A Rev. 4, (05/00)

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO E-PLAN PCOl7-I 02 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. EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18

6. PCOl70-I 02, SIMULATOR EVALUATION SCENARIO C. NDAP-QA-0720 , STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9

-\--

III. 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reportability to the NRC identified.

2003 NRC Exam Rev. 1

(

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

Step Action Standard Eva1 Comments Eva1uator 0 .This JPM must be performed in the simulator following completion of the scenario as Unit Supervisor.

This is a time critical JPM.

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

EVALUAT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Eva1uator After the candidate reviews the Task Conditions / Initiating Cue Sheet:

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. Controlled copy obtained.

Evaluates information. Identifies loss of reactivity control as potential Emergency Plan EVALUATOR CUE entry.

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. Selects Tab 4.

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

Page 1 of 1 2003 NRC Exam Rev. 1

(:

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

Step Action Standard Eva1 Comments 4 Reviews the table of contents for events experienced Reviews all category 11.

during the scenario.

5 Choose appropriate emergency action level. Identifies entry into EAL II.3 based upon loss of functions needed to bring the reactor subcritical and loss of ability to bring reactor to cold shutdown.

6 Record Time of Site Area Classifies the event as a Site Area Emergency declaration Emergency.

EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements 7 Obtains a copy of NDAP-QA-0720 , STATION REPORT Controlled copy obtained.

MATRIX AND REPORTABILITY EVALUATION GUIDANCE 8 Reviews reporting requirements Reviews Attachments:

E, F, G, and H 9 Determines Reportability requirements Determines 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS notification due to activation of the emergency plan.

I0 Reports results Reports Ihour ENS notification to the evaluator.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step Action Standard Eva1 Comments EVALUATOR CUE:

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

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

Page 1 of 1 2003 NRC Exam Rev. 1

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.

Page 1 of 4 2003 NRC Exam Rev. 1

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.

L-.

Page 2 of 4 2003 NRC Exam Rev. 1

TASK CONDITIONS L=

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.

Page 3 of 4 2003 NRC Exam Rev. 1

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.

Page 4 of 4 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY L--

JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET E-PLAN 06/14/03 SRO PCOl7-I 03 0 2.4.41 4.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Perform Emergency Plan Classification and Identify Reportability Requirements.

Completed By: Reviews:

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

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

15 Time Critical 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. 1

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

11. REFERENCES A. EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 B. PCOI70-103, SIMULATOR EVALUATION SCENARIO C. 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 Site Area Emergency declared within 15 minutes and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reportability to the NRC identified.

'L-.

2003 NRC Exam Rev. 1

(

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM NO.:SRO E-PLAN PCO17-103 Student Name:

Step Action Standard Eva1 Comments Evaluator 0 This JPM must be performed in the simulator following completion of the scenario as Unit Supervisor.

0 This is a time critical JPM.

Ensure a copy of EP-PS-I 00 is available to support performance of this JPM.

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

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

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 1 Obtains a copy of EP-PS-100. Controlled copy obtained.

2 Evaluates information. Identifies the following events as potential Emergency Plan entry:

EVALUATOR CUE Unexpected in-plant high Assistance may be necessary for some specific scenario radiation levels data or sequence of events. Use your judgement on Loss of reactor vessel inventory acceptable levels of cueing based on candidates request.

Steam line break

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

Page 1 of 1 2003 NRC Exam Rev. 1

{

PERFORMANCE CHECKLIST Page 4 of 5 Appl. To/JPM NO.: SRO E-PLAN PCO17-1 Student Name:

Step Action Standard Comments 3 Refers to classification matrix. Selects Tab 4.

4 Reviews the table of contents for events experienced Reviews all category 6.

during the scenario.

Reviews all category 12.

Reviews all category 18.

5 Choose appropriate emergency action level. Identifies entry into EAL 18.3 based upon any other un-isolatable steam line break (RWCU Break).

6 Record Time of Site Area Classifies the event as a Site Area Emergency declaration Emergency.

EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements 7 Obtains a copy of NDAP-QA-0720, STATION REPORT Controlled copy obtained.

MATRIX AND REPORTABILITY EVALUATION GUIDANCE 8 Reviews reporting requirements Reviews Attachments:

E, F, GIand H "Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(;

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

Step 9

Action Determines Reportability requirements Standard Determines 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS Eva1 I Comments notification due to activation of the emergency plan.

I0 Reports results Reports 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS notification to the evaluator.

EVALUATOR CUE:

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

Critical Step #Critical Sequence STCP-QA-I 256 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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.

u Page 1 of 4 2003 NRC Exam Rev. 1

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.

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

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.

.v.

Page 3 of 4 2003 NRC Exam Rev. 1

TASK CONDITIONS Iw-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.

Page 4 of 4 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET E-PLAN 06114/03 SRO PCOl7-I 04 0 2.4.41 4.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Perform Emergency Plan Classification and identify Reportability Requirements.

Completed By: Reviews:

Russ Halm 06114/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv.1C.A. Date Nuclear Trng. Supv. Date Head L-.

15 Time Critical 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. A14-5B 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO E-PLAN PCOl7-104

..-../-

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. EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 B. PCOI70-104, SIMULATOR EVALUATION SCENARIO C. 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reportability to the NRC identified.

I 2003 NRC Exam Rev. 1

(

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM NO.: SRO E-PLAN PCO17-104 Student Name:

Step Action Standard Eva1 Comments Evaluator 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.

EVALUAT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Eva1uator After the candidate reviews the Task Conditions / Initiating Cue Sheet:

0 Ask if the candidate is ready to begin the JPM.

0 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-I00. Controlled copy obtained.

Evaluates information. Identifies loss of reactor vessel inventory as potential Emergency EVALUATOR CUE Plan entry.

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. Selects Tab 4.

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

Page 1 of 1 2003 NRC Exam Rev. 1

I' {,

PERFORMANE CHECKLIST Page 4 of 5 Appl. ToIJPM NO.: SRO E-PLAN PCO17-104 Student Name:

Step Action Standard Eva1 Comments 4 Reviews the table of contents for events experienced Reviews all category 12.

during the scenario.

"5 Choose appropriate emergency action level. Identifies entry into EAL 12.2 based upon reactor coolant system leak rate greater than 50 gpm.

6 Record Time of Classifies the event as an Alert.

Alert declaration EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements 7 Obtains a copy of NDAP-QA-0720 , STATION REPORT Controlled copy obtained.

MATRIX AND REPORTABILITY EVALUATION GUIDANCE 8 Reviews reporting requirements Reviews Attachments:

E, F, G, and H 9 Determines Reportability requirements Determines 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS notification due to activation of the emergency plan.

I 0 Reports results Reports 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS notification to the evaluator.

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

Page 1 of 1 2003 NRC Exam Rev. I

PERFORMANCE CHECKLIST Page 5 of 5 Appl. To/JPM NO.:SRO E-PLAN PCO17-104 Student Name:

Step Action Standard Eva1 Comments EVALUATOR CUE:

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

Critical Step #Critical Sequence STCP-QA-1256 Rev. 2.(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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.

b Page Iof 4 2003 NRC Exam Rev. 1

TASK CONDITIONS L

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.

v Page 2 of 4 2003 NRC Exam Rev. 1

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.

Page 3 of 4 2003 NRC Exam Rev. 1

TASK CONDITIONS L-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.

Page 4 of 4 2003 NRC Exam Rev. 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SSES Date of Examination: 08/11/03 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 Primary Containment Water Level During Anomaly.

Conduct of Operations 2.1.23 3.9/4.0 JPM Authorize Bypassing Rod Worth Minimizer IAW NDAP-QA-0388

~~~

Equipment Control 2.2.13 3.6/3.8 JPM Determine accuracy and adequacy of a clearance order.

Radiation Control 2.3.9 2.5/3.4 JPM Authorize De-inerting and Purging the Dryvell and Suppression Chamber with Air.

Emergency Plan 2.4.41 2.314.1 JPM Determine Emergency Plan EAL Classification.

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

NUREG-1021, Draft Rev 9 Susquehanna Facsimile 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY

---i 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 BvDassina Rod Worth Minimizer In Accordance With NDAP-QA-0338 Completed By: Reviews:

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

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head L- '

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, (05COO)

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.AD.047.001

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-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 III. REACTIVITY MAN1PULATIONS 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. 1

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 just@ 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.

u Form STCP-QA-1PM Rev. 4, (05/00)

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

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

Step Action Standard Eva1 Comments EVALUATOR 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 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 9,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 I 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-QA-1256 Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

'\

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 :

0 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. 1

( (1 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:

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

EVALUATOR CUE -

OR C.2. I .1, 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 LCORRO 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-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(:

PERFORMANCE CHECKLIST 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 This completes the JPM.

Critical Step #Critical Sequence STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L--

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

6. 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.

Page 1 of 2 2003 NRC Exam Rev. 1

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

6. 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.

Page 2 of 2 2003 NRC Exam Rev. 1

Attachment A REACTIVITY CONTROL SYSTEM NDAP-QA-0338 BYPASS AUTHORIZATION FORM Revision 6 (RBM) Page 34 of 42

(- RBM Providing Rod Block ]

Initiating Condition Rod I.D. - Notch -Unit-RBM Channel A or B Power Level - %

Date I Time I I Shift Supervision Authorization Date Time 1 To bypass RBM Channel up to 30% power. Enter into

?CO log. Reanalyze at 30%.

4 30% Power O.K. to Bypass RBM Channel RBM restored to normal.

1

--I I Shift Supervision Authorization Date Time Dyes I Do not Bvoass RBM Channel I

1) Invalid APRM inputs 0 Yes No

~.. ___ _..... - adjust or bypass APRMs Yes+ -rake Appropriate J 2) Invalid Flow inputs 0 Yes 0 No Corrective Actions

- adjust or bypass flow units

3) Invalid LPRM inputs Yes No

- a) determine if LPRMs are valid via TIPS or other means

- b) bypass or adjust LPRMs as required 0 No L A r

Call I&C to repair RBM andlor --I I Shift Supervision Authorization Date Time To bypass RBM Channel. Enter into LCO Log.

I I

RBM restored to normal. LCO cleared.

OK to bypass RBM Channel I.A.W.

TS 3.3.2.1 Shift Supervision Authorization FORM NDAP-QA-0338-8, Rev. 2, Page 0 of 1 (File A-23)

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 New Clearance 0 06/13/03 2.2.13 3.613.8 Order Accuracy Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Review a Clearance Order for Accuracy Completed By: Reviews:

Russ Halm 06113/03 Writer Date InstructorNVriter Date Approval:

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

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-IZSA Rev. 4, (05/00)

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

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

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

I.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-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. 1I )

-c E. E-I38 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(s):

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

B. Unit 1 Circ Water Pump IP501B discharge vent valve 115137B needs to be replaced.

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

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

VI. TASK STANDARD Component 16511034 (tag number 4) is identified as the wrong device and the correct device is 1B501034.

L-2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 3 of 7 Appl. To/JPM No.: S/RO New Admin Student Name:

Step Action Standard Eva1 Comments Evaluator 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.

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

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

Provide the candidate with the Clearance Order 54015.

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

2 Reviews NOTE 1 for conditions necessary before applying Determines 1P501B will be blocking. removed from service IAW OP-142-001 Section 3.2.

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.

3 Use electrical print to verify 1P501B motor breaker. Using E-I 37 Sht.3, determines breaker 1AlO203 is correct.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step Action Standard Eva1 Comments 4 Reviews position of Red tagged device. Breaker IAlO203 should be RACKED OUT.

5 Use electrical print to verify HV-1151IB MOV breaker. Using E-I38 Sht.1, determines breaker 1850124 is correct.

6 Reviews position of Red tagged device. Breaker 1850124 should be OPEN.

FAULT STATEMENT THE NEXT DEVICE AND BREAKER NUMBER ARE INCORRECT.

7 Use electrical print to verify HV-11511A MOV breaker. Using E-138 Sht. 19, determines breaker 18511034 is NOT correct.

The correct breaker is 18501034 for HV-115118.

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.

8 Reviews position of Red tagged device. Breaker 1B501034 should be OPEN.

Verifies mechanical blocking required.

9 Use mechanical drawing to verify HV-l1513B, CWP B Using M-I 15 Sht.1, determines Suction valve. HV-11513B is correct.

Critical Step #Critical Sequence STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 5 of 7 Appl. To/JPM No.:S/RO New Admin Student Name:

Step Action Standard Eva1 Comments 10 Reviews position of Red tagged device. Valve HV-115138 should be CLOSE.

I1 Use mechanical drawing to verify HV-11511B, CWP B Using M-I 15 Sht.1, determines Discharge valve. HV-I 1511B is correct.

12 Reviews position of Red tagged device. Valve HV-11511B should be CLOSE.

13 Use mechanical drawing to verify 115153, CWP B IB Using M-I 15 Sht.1, determines Bearing Seal Water Supply valve. 115153 is correct.

EVALUATOR NOTE:

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

14 Reviews position of Red tagged device. Valve I15153 should be CLOSE.

15 Use mechanical drawing to verify 115154, CWP B OB Using M-I 15 Sht.1, determines Bearing Seal Water Supply valve. 115154 is correct.

EVALUATOR NOTE:

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

16 Reviews position of Red tagged device. Valve 115154 should be CLOSE.

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

Page 1 of 1 2003 NRC Exam Rev. 1

f I" PERFORMANCE CHECKLIST Page 6 of 7 Appl. To/JPM No.: SIR0 New Admin Student Name:

Step Action Standard Eva1 Comments 17 Use mechanical drawing to verify 115139B, CWP 8 Suction Using M-I15 Sht.1, determines Vent valve. 1151398 is correct.

EVALUATOR NOTE:

Drawing grid location is 1-1.

18 Reviews position of device. Valve 115139B should be OPEN.

19 Use mechanical drawing to verify 115141B, CWP B Suction Using M-I15 Sht.1, determines Vent valve. 1151418 is correct.

EVALUATOR NOTE:

Drawing grid location is 1-1.

20 Reviews position of device. Valve 115141B should be OPEN.

21 Use mechanical drawing to verify 115142B, CWP 8 Using M-I 15 Sht.1, determines Discharge Drain valve. 115142B is correct.

EVALUATOR NOTE:

Drawing grid location is 1-1.

22 Reviews position of device. Valve 1151428 should be OPEN.

23 Use mechanical drawing to verify 1151438, CWP B Suction Using M-I15 Sht.1, determines Drain valve, 115143B is correct.

EVALUATOR NOTE:

Drawing grid location is 1-1.

24 Reviews position of device. Valve 1151438 should be OPEN.

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

Page 1 of 1 2003 NRC Exam Rev. 1

( (

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

Step Action Standard Eva1 Comments

25 Reports the review results. Informs the Unit Supervisor:

0 Tag ##4for breaker 1B511034 EVALUATOR CUE is not correct.

Roleplay the Unit Supervisor and acknowledge the results 0 Breaker 18501034 is the when reported. correct breaker.

0 Breaker 1B501034 description is CIRC WATER PUMP B If candidate fails to volunteer the correct blocking point for DISCHARGE VLV HV-11511B JPM step 7, ask them to provide it. BKR.

EVALUATOR This completes the JPM.

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

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L-.

A. NlMS is not available.

B. Unit 1 Circ Water Pump 1P501B 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.

Page 1 of 2 2003 NRC Exam Rev. 1

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.

Page 2 of 2 2003 NRC Exam Rev. I

TATS TAG/ NG WMX ( dTAGHANG

(

CO: 54015 NAME: 1P501B CIRC WATER PUMP O O S Hang Authorized By:

Status: AUTHHANG lJnit: 1 Year: 2003 Change In Progress: N Component ID: 1 PSO 1D Work

Description:

Replace 1 P501 I3 Circ Water Pump Discharge Vent Valve, 1 15 I37J3 Seq Blocking Req N De-energized :N De-pressureized : N Continuously Vented :N Drained :N Purged : N Isolated : N Note :

~ _ _ _ __ . ... ____.~ _____

Seq TagNo Component ID Component Description Position Status Tag Color Plant Ln bel 01%Chmments/Noun Location J L 1 1 NOTE 1 SEE BLOCKING COMMENTS FOR DETAILS N/A INA NT Tag Comments: Remove 11501B UI Circ Water Pump B from service IAW OP-142-001 Section 3.2 prior to applying blocking.

Area-Elev 0 -0 Room ? Azimuth Parent 11) Grating 0 Actual 0 2 2 lA10203 CIRC WATER PUMP B 1P501B 13.8 KV BKR RACKED OUT INA RT IA10203 (RM)

Tag Comments:

Area-Elev 4 - 699 Room 1-220 Azimuth Parent ID lA102 Grating 0 Actual 699 3 3 1B501024 CWP I B DSCH MOV HV-1151 IB BKR 52-024 OPEN INA RT Tag Comments:

Area-Elev 52 - 670 Room CW-020Aziniiith Parent ID IBS01 Grating 0 Actual 676

~ _ _ _ ~

Page 1 of 4 Report Datc: 05/07/2003 1456

TATS

( WMX r TAGHANG CO: 54015 NAME: IPSOIB CIRC WATER PUMP 00s Hang Authorized By:

Status: AUTI-I1IANG IJnit: I Year: 2003 Change In Progress: N Component ID: 11501 13 Work

Description:

Replace 1 PSO1 R Circ Water Pump Dischnrge Vent Valve, I 15137B Seq Blocking Req N De-energized :N De-pressureized : N Continuously Vented :N Drained :N Purged : N Isolated : N Note :

, ... ._.. .. . -. . .. . ..~ ~. ~..~ ... ._. ~~ -

Seq Tag No Component 11) Componen t Description Position Status Tag Color Plant Label OPS Comments/Noun Location 4 4 1B511034 CIRC WATER PUMP A DISCHARGE VLV HV- OPEN 11511A13KR INA RT Tag Comments:

Area-Elev 5 I - 676 Room CW-020 Azimuth Parent ID 1BS11 Grating 0 Actual 676 5 5 HVl1513B CIKC WATER PUMP B SUCTION VLV CLOSE INA RT Noun Lot: CAUTION: DURING MANUAI, OPERATION, I)O N O T IOSITION PAST S(IZ1131S MARKS Tag Comments:

Area-Elev 50 - 66 1 Room cw-003 Azimuth Pa rent I I) Grating 0 Actual 665 6 6 HV1 151 1 R CIRC WATER PUMP B DISCHARGE VLV CLOSE INA RT Noun Loc: CAUTION: DURING MANUAL OPERATION, DO NOT POSITION PAST SCRIBE MARKS Tag Comments:

Area-Elev 50 - 60 I Room CW-003 Azimuth Parent ID Crating 0 Actual 667 Page 2 of 4 Report Date: 05/07/2003 1456

TATS TAG! NG TAGHANG i WMX i CO: 54015 NAME: 1 P501 B CIRC WATER PUMP 00s Hang Authorized By:

Status: AUTHHANG IJnit: 1 Year: 2003 Change In Progress: N Component 11): 1 150 I Ii Work

Description:

Replace 1P501B Circ Water Pump Discharge Vent Valve, 115137B Seq Blocking Req N De-energized :N De-pressureized : N Continuously Vented :N Drained :N Purged : N Isolated : N Note :

Seq TagNo Component In Component Description Position Stnius Iag Color 11;1111 I .iltWl OIS Coiiiniciits/Noun I,ociltioI1 7 7 115153 CWP B IB BEARING SEAL WATER SUPPLY I S 0 CLOSE VLV INA RT Tag Comments:

Area-Elev 50 - 676 Room CW-003 Azimuth Parent ID Grating 0 Actual 671 8 8 115154 CWP B OB BEARING SEAL WATER SUPPLY IS0 CLOSE VLV INA RT Tag Comments:

Area-Elev 50 - 676 Room CW-003 Azimuth Parent ID Grating 0 Actual 671

-~ -

9 9 I151393 CW PUMP B SUCTION VENT VLV OPEN INA NT Tag Comments:

Area-Elev 50 - 661 Room ? Azimuth Parent ID Grating 0 Actual 661 Page 3 of 4 Iteport 1)sle: 05/07/2003 1456

TATS TA GIIA NG wMx?

CO: 54015 NAME: I P501 B CIRC WATER PUMP 0 0 s Hang Authorized By: .

Status: AUTHI-IANG Unit: 1 Year: 2003 Change In Progress: N Component ID: 1 P50 I R Work

Description:

ltepliicc I P.501I3 Circ Water Puiiip Discliiirgc Vcnt Viilvc, 1 IS I3713 Seq Blocking Req N De-energized :N De-pressuieized : N Continuously Vented :N Drained :N Purged : N Isolated : N Note :

Seq TagNo Cornponen t ID Component Description Position Status Tag Color Plant Label OPS Comments/Noun Location 10 10 1151413 CW PUMP B SUCTION VENT VLV OPEN INA NT Tag Comments:

Area-Elev SO - 661 Room ? Azimuth Parent ID Grating 0 Actual 661 11 I1 1151421% C'117C WATER PUMP I3 DISCIIARGIX DRAIN VLV OPEN INA NT

'rag Comnients:

Area-Elev 50 -661 Room CW-003 Aziniuth Parent ID Grating 0 Actual 663 12 12 1151331% CIRC WATER PUMP B SUC'I'ION DRAIN VLV OPEN INA NT Tag Comments:

Area-Il:lev 50 - 601 Room ? Azimuth Parent 11) Grating 0 Actual 661 Page 4 of 4 Report Date: 05/07/2003 14:56

h PENNSYLVANIA POWER & LIGHT JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 00.AD.040.00 1 0 06/14/03 2.3.9 3.4 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

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

Completed By: Reviews:

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

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head L-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:

S ig nature Typed or Printed Comments:

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

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.AD.040.001 b--

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-0309 PRIMARY CONTAINMENT ACCESS AND CONTROL, REV. 13 B. OP-I 73-001 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 III. REACTIVITY MAN1PULATIONS

-Lu This JPM satisfies the requirements of Operational Activity(s):

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

ea IOW.

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. 1

(:

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

Step Action Standard Eva1 Comments EVALUATOR 0 Ensure the following reference material is available to support the JPM:

NDAP-QA-0309 OP-173-001 0 TRM 0 TECHNICAL SPECIFICATIONS 0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LElTERS.

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

Obtains a copy of NDAP-QA-0309. Controlled copy obtained.

Refers to section 6.2.3 EVALUATOR The exact order in which reauirements are identified mav vary based upon the sequence of procedure reference,

which is acceptable.

Identifies the verification requirements of TR 3.6.1. Identifies the requirements of TR 3.6.1 must be verified within 4 EVALUATOR CUE hours prior to the start of and Acknowledge surveillance requirements. every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during purging.

Identifies SGTS operability requirements. Identifies both SGTS trains shall be operable when purge system is EVALUATOR CUE in use.

Inform candidate both SGTS trains are operable.

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

Page 1 of 1 2003 NRC Exam Rev. 1

! (

PERFORMANCE CHECKLIST Page 4 of 5 Appl. To/JPM No.: S/RO 00.AD.040.001 Student Name:

~

Step Action Standard Eva1 Comments 4 Identifies SGTS exhaust sampling requirements per TR Identifies SGTS SPING must be 3.1 I.2.6. operable alternate sampling in progress during SGTS operation.

EVALUATOR CUE Inform candidate SPING is operable.

5 Chemistry sampling requirements of containment. Identifies chemistry samples and analyzes containment atmosphere EVALUATOR CUE IAW SC-173-101.

Acknowledge chemistry sampling requirement.

6 States release limits. Identifies release rates shall not exceed the allowable limits of TR EVALUATOR CUE 3.1 1.2.1.

Acknowledge release limit requirement.

7 Complete NDAP-QA-0309 Attachment 6. Completes Attachment 6.

Enter Ifor Unit.

Enter current date for start date.

Enters current time for start time.

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

=

Critical Step #Critical Sequence STCP-QA-1250 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step Action Standard Eva1 Comments 8 Install portable oxygen analyzer 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to de- Notifies

. _ _ .I&C

- to install portable inerting. oxygen analyzer IAW-IC-I73-002.

EVALUATOR CUE Acknowledge installation of portable analyzer.

9 Obtains a copy of OP-I 73-001. Controlled copy obtained.

10 Refers to correct procedure section. Selects Section 3.3 for the drywell or 3.4 for the suppression pool.

11 Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of purge and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Verify both SGTS systems are verifies the requirements of TRO 3.6.1 are met. operable per LCO 3.6.4.3. by administrative means.

EVALUATOR CUE Acknowledge all surveillance requirements are current and AND satisfactory.

12 FAULT STATEMENT: SGTS EXHAUST RADIATION Verify Function 2.e SGTS MONITOR A HAS JUST FAILED DOWNSCALE. (From Exhaust Radiation High is initiating cue) operable per LCO 3.3.6.1 by administrative means.

I3 Identifies de-inerting and air purge is not permitted until the Does not authorize de-inerting SGTS radiation monitor is operable. and air purge of the drywell and suppression chamber.

EVALUATOR This completes the JPM.

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

Page 1 of 1 2003 NRC Exam Rev. 1

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

B. ASBGT 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.

Page Iof 2 2003 NRC Exam Rev. I

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

B. ASBGT 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.

Page 2 of 2 2003 NRC Exam Rev. I

ML032591125

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