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

L-'

-e

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

SSES Examination Level (circle one): RO Date of Examination:

08/11/03 Operating Test Number:

Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed

~~

~

2.1.25 2.813.1 JPM Determine Primary Containment Water Level During Anomaly.

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

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

N/A 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 2003 NRC Exam Rev. 1 Susquehanna Facsimile

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 59.0N.007.201 0

0611 4/03 2.1.25 2.813.1 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews:

Perform Primary Containment Water Level Anomaly Russ Halm 0611 4103 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

10 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Eva1 u a ti on :

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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.

B.

EP-DS-002 RPV AND PRIMARY CONTAINMENT FLOODING, REV. 1 ON-259-003 PRIMARY CONTAINMENT WATER LEVEL ANOMALY, REV. 3 I II. REACTIVITY MAN I P U LATlO NS 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 EVALU AT0 R Ensure a copy of ON-259-003 is available.

EVALU AT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Obtains a controlled copy of ON-259-003.

Checks approval to perform procedure.

Selects correct procedure section.

CAUTIO N 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.

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

Record drywell pressure.

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

Critical Step

Critical Sequence Standard Controlled copy obtained.

Verifies signature approval by Shift Supervision.

Selects section 3.2.

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

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

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

Page 1 of 1 2003 NRC Exam Rev. 1

(\\

Appl. To/JPM No.: S/RO 59.0N.007.201 Step 6

7

8 9

PERFORMANCE CHECKLIST Page 4 of 4 Student Name:

Action Calculate differential pressure.

Plots data on curve.

Determines containment water level.

Reports containment water level data.

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

EVALUATOR This completes the JPM.

"Critical Step

Critical Sequence Standard Enters 16 psig for suppression chamber pressure.

Enter 12 psig for drywell pressure.

Subtracts 12 psig from 16 psig and enters 4 psid.

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.

Determines primary containment water level is -58.5 feet.

Notifies Unit Supervisor primary containment water level is -58.5 feet.

Eva1 Comments 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.

2003 NRC Exam Rev. 1 Page 1 of 2

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 15 L

Date of Performance:

Allowed Time (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Performance Eva I uat i o n :

(

)

Satisfactory Time Taken (Min.)

Employee #/S.S. #

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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 IV. TASK CONDITIONS u

A. Unit 1 is in MODE 1.

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

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

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

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

2003 NRC Exam Rev. 1

i/

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

Refers to correct section.

Determines current LPRM status.

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

Obtains a blank copy of Attachment A & B.

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

& B.

Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Refers to section 4.

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

B.

Blank copy obtained.

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. ToIJPM No.: S/RO 78.AD.001.I 01 Step 5

6 7

8 i\\

PERFORMANCE CHECKLIST Action Completes new Attachment A.

EVALUATOR CUE:

If candidate elects to verify position of switches in lower relay room, provide the cue that the switches are in the positions indicated on Attachment A (Special log book)

Determine if 250% of LPRM Upscale alarms in each zone are operable.

Identifies operating restriction.

Make notifications.

Critical Step

Critical Sequence Student Name:

Standard Enters 1 for Unit.

Transfers the previous LPRM data to the new Attachment A.

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

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

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

Circles NO for zone 4.

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

Notifies the Unit Supervisor and Unit 1 PCOs about the operating restriction based upon the LPRM alarm condition.

Eva1

(,

Page 4 of 5 Comments STCP-CIA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 78.AD.001.I 01 Step

9 10 11 12 PERFORMANCE CHECKLIST Action Posts placard.

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

Complete Attachment B.

Notify Reactor Engineering.

Obtains review.

EVALUATOR This completes the JPM.

Critical Step

Critical Sequence Student Name:

(

Page 5 of 5 Standard Attaches placard to operating panel 1 C651.

Enters 1 for Unit.

Transfers the previous LPRM data to the new Attachment B.

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

Contacts reactor engineering and provides the current LPRM status.

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

Eva1 Comments STCP-QA-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 48-1 7B.

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

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

2003 NRC Exam Rev. 1 Page 1 of 2

TASK CONDITIONS A. Unit 1 is in MODE 1.

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

C. LPRM detector 48-1 7B is failed and bypassed.

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

2003 NRC Exam Rev. I Page 2 of 2

i' LPRM UPSCALE ALARM STATUS CONTROL LOG UNIT 1

Attachment A Revision 7 Page 5 of 6 01-078-001 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 - -

@NO

@No

@NO Zone2 40-49A 40-41A - -

48-49A -

48-41A -

40-498 - ___

40-418 -

48-496 - ___

48-416 -

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 -

16-17C - -

16-25C - __

24-17C -

24-25C -

Zone4 40-17A - L 40-25A

_I 40-17A -

48-25A -

40-178 - -

40-256 - J 48-176 48-258 - -

40-17C - -

40-25C - -

48-17C -

48-25C - J 5

@NO Zone5 24-33A - __

32-25A - -

32-33A - __

32-41A - J 40-33A -

24-336 - -

32-256 -

32-338 32-416 - __

40-330 -

24-33C - -

32-25C - -

32-33C - __

32-41C 40-33C 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 08-41A - __

16-33A Zone7 08-17A - -

08-25A - -

08-33A -

08-178 - __

08-258 08-336 - -

08-416 - __ 16-338 08-17C - -

08-25C - -

08-33C - __

08-41C - -

16-33C

~

@o Zone8 24-57A - -

32-57A - -

,40-57A - -

32-49A -

24-578 - -

32-578 - -

40-578 - -

32-496 -

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 32-4 1 08-33 48-41 24-33 16-25 40-33 32-25 56-33

( 48-25 1 24-1 7 16-09 08-1 7 52 56-1 7 48-09 40-17 I

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

i I(

LPRM UPSCALE ALARM STATUS CONTROL LOG Attachment A Revision 7 Page 5 of 6 01-078-001 UNIT (1)

(2)

(1)

(2)

(1)

(2)

(1)

(2)

(1)

(2)

Zone 1 16-4919 16-41A - -

24-49A - -

24-41A - -

16-498 16-418 -

2441C -

16-49C - -

16-41C 24-49C - -

24-498 - -

24-418 -

YES/NO As least 50%

LPRMs Operable per

'Zone (Circle IYES or NO)

Zone 2 40-49A 40-41A -

48-49A - -

48-41A - __

40-498 40-49C - -

4041C - __

48-49c - -

48-41C Zone3 16-17A - -

16-25A 24-17A - -

24-25A - -

16-258 24-178 24-258 -

YES/NO 16-170 -

16-17C 16-25C - -

24-17C 24-25C 40-25A - -

48-17A - -

48-25A Zone4 40-17A -

48-178 - __

48-258 -

YESINO 40-178 - __

40-258 -

40-17C - -

40-25C - -

48-17C 48-25C - -

40-418 - -

48-498 - __

48-418 -

YESINO Zone5 24-33A - __

32-25A - -

32-33A 32-41A - -

40-33A 24-338 - -

32-258 -

24-33C 32-233 32-33C 32-41C 40-336 32-338 - __

32-418 - __

40-338 - -

YES/NO Zone6 16-09A - __

24-09A 32-09A - -

40-09A - -

32-17A - -

16-098 -

16-09C 24-09C - -

32-09C - -

40-09C - -

32-17C - -

0841A 16-33A 24-098 - -

32-098 40-098 32-176 YESlNO 08-25A 08-33A -

Zone7 08-17A -

YESlNO 16-338 -

08-178 - -

08-258 -

08-338 - -

08-418 - _-_

08-17C - -

08-25C - __

08-33C - -

08-41C - -

16-33C - -

Zone8 24-57A - -

32-57A - -

,40-57A - -

32-49A - -

24-578 - -

32-578 - -

40-578 - -

32-498 24-57C - -

32-576 - ___

40-57C - -

32-49C - -

Y ESINO Zone9 48-33A - __

56-25A - -

56-33A - -

56-41A - -

48-338 - -

56-258 56-338 - -

56.418 - -

56-41C 48-33c - -

56-25C - -

56-336 YEWNO

~

LPRM Upscale Alarm Status Assessment Complete I

I Shift Supervision Date Time FORM 01-078-001-1, Rev. 4, Page 1 of 1

UNIT 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 56-1 7 48-09 40-17 I

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 24-1 7 32-25 56-33 32-09 56-17 16-09 08-17 48-09 40-17 LPRM GROUP A 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 08-1 7

33-09 56-17 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 48-1 7 56-25 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 Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

F o

~

STCP-QA-IZ5A Rev. 4. (05100)

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

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. 1 I)

E. E-I38 Sheet 1 ClRC WATER PUMP DISCHARGE VALVE (Rev. 13)

F. E-I38 Sheet 19 ClRC WATER PUMP SUCTION VALVE (Rev. 6) v 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 I P501 B discharge vent valve 1151 work).

7B neeGs to be replaced (scope of 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 1 P501 B has been removed from service IAW OP-142-001 section 3.2 V. INITIATING CUE Using the appropriate NDAP(s) and rnechanicaVelectricaI drawing@), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

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

2003 NRC Exam Rev. I

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

Step 1

2

3 Action 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:

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

Blank table labeled for tagout points EVALUATOR To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet, and attached student copy of the blank table.

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

Use electrical print to identify 1 P501 B motor breaker.

Critical Step

Critical Sequence Standard References NDAPs to determine overall process and prescribed sequence.

Determines the pump discharge vent valve 115137B will be replaced.

Using E-I 37 Sht.3, determines breaker IA10203 will need to be:

First in the sequence Racked out Red tagged Then fills out table Eva1 Comments STCP-QA-1258 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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

~

Step

4

5

6 Action Use electrical print to identify HV-11511 B MOV breaker.

Use electrical print to identify HV-I 151 1 B MOV breaker.

Use mechanical drawing to identify HV-l1513B, CWP B Suction valve.

Critical Step

Critical Seq uence Standard Usina E-I 38 Sht.1, determines breavker 1 B501024 will need to be:

Second in the sequence Opened Red tagged Then fills out table Using E-I 38 Sht.19, determines breaker 1 B501034 will need to be:

Second in the sequence Opened Red tagged Then fills out table Using M-I 15 Sht.1, determines HV-11513B will need to be:

Third in the sequence Closed Red tagged Then fills out table Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. TolJPM No.: New Admin ID Blockinq Points Student Name:

Page 5 of 7 Step

7

8

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

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

EVALUATOR NOTE:

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

Use mechanical drawing to identify 11 5154, CWP B OB Bearing Seal Water Supply valve.

EVALUATOR NOTE:

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

EVALUATOR NOTE:

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

Critical Step

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

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

151 53 will need to be:

Third in the sequence Closed Red tagged Then fills out table Using M-I 15 Sht.1, determines 115154 will need to be:

Third in the sequence Closed Red tagged Then fills out table Eva1 Comments STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i Page 6 of 7 i'

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

Step

I 0

I 1

I 2

Action Use mechanical drawing to identify I 1 51 39B, CWP B Suction Vent valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

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

EVALUATOR NOTE:

Drawing grid location is 1-1.

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

EVALUATOR NOTE:

Drawing grid location is 1-1.

Standard Using M-I 15 Sht. I, determines 11 51 398 will need to be:

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

Fourth in the sequence Opened No Tag Required Then fills out table Using M-I 15 Sht.1, determines 1 151428 will need to be:

Fourth in the sequence Opened No Tag Required Then fills out table Eva1 Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. 1

i' Appl. To/JPM No.: New Admin ID Blockinq Points Step

I 3

I 4

Critical Step

(

PERFORMANCE CHECKLIST

(

Page 7 of 7 Action Use mechanical drawing to identify I 151438, CWP B Suction Drain valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reports the results.

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

EVALUATOR 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 Seq uence Student Name:

Standard Using M-I 15 Sht.1, determines 115143B will need to be:

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

Eva1 Comments STCPQA-1256 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

ANSWER KEY (DO NOT GIVE TO STUDENTS)

Component Description I

2 I

1B501024 Position Tag Color 1 B501034 2

HV-I 151 3B ClRC WATER PUMP B SUCTION VLV HV-11513B BKR ClRC WATER PUMP B SUCTION VLV I

3 I HV-1151lB Open Red Close Red I

115153 ClRC WATER PUMP B DISCHARGE VLV CWP B IB BEARING SEAL WATER SUPPLY IS0 VLV 115154 3

115139B Close Red Close Red I

4 I

115141B CW PUMP B SUCTION VENT VLV ClRC WATER PUMP B SUCTION DRAIN VLV ClRC WATER PUMP B SUCTION DRAIN VLV Open No Tag Open No Tag Open No Tag 4

4 ClRC WATER PUMP B I P501 B 13.8 KV BKR I Rackedout I Red 115142B 115143B CWP I B DSCH MOV HV-1151 I B BKR 52-024 I

ODen I

Red Red I

Close CWP B OB BEARING SEAL WATER SUPPLY IS0 VLV CW PUMP B SUCTION VENT VLV I

ODen I

NoTaa 2003 NRC Exam Rev. 1 Page 1 of 2

TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1 P501 B discharge vent valve 1 151 37B 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 mechanicaVelectrica1 drawing(s), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

2003 NRC Exam Rev. I Page 1 of 2

TASK CONDITIONS A. NlMS is not available.

B. Unit 1 Circ Water Pump 1 P501 B discharge vent valve 1151 378 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 I P501 B has been removed from service IAW OP-142-001 section 3.2 INITIATING CUE Using the appropriate NDAP(s) and mechanicaVelectrica1 drawing@), complete the attached table to identify the blocking required for the job and the order in which the blocking should be applied.

2003 NRC Exam Rev. I Page 2 of 2

ai quauodluo3 j

amanbag

L-S/RO Appl. To Task

Title:

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

0611 4/03 2.4.27 3.013.5 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA 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 Date of Performance:

LU Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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.

B.

C.

D.

ON-013-001 RESPONSE TO FIRE, REV. 14 FP-013-189 DIESEL GENERATOR BAY A, REV. 3 AR-SP-001 PAGE 11 8, REV. 7 AR-SP-002 PAGE 72, REV. 9 E. AR-SP-002 PAGE 76, REV. 9 I 11. REACTIVITY MAN I PU LATl ONS 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 1 1 -AUG-03 44-660 A DIESEL GEN FIRE DET XIl6-Zl ALM 17:16 MON 1 I-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

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

Step Action 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:

0 Pre-Fire Plans.

A COPY of ON-01 3-001.

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.

Locates alarm procedure for X250 Z1.

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

Locates alarm procedure for X I 16-Z l.

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

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

Selects AR-SP-001 page 1 18.

Selects AR-SP-002 page 72.

=

Eva1 Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 13.ON.003.001 Step 4

5 6

7

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

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

Obtains a controlled copy of Off-Normal procedure ON-01 3-001.

Refers to correct section.

Activates fire brigade.

Contacts Fire Brigade Leader.

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

Critical Step

Critical Sequence Student Name:

Standard Selects AR-SP-002 page 76.

Controlled copy obtained.

Refers to section 3.

Refers to Attachment Q or the Activity Hard Card.

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

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

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

Eva1 Page 5 of 6 Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(:

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

9

I 0

11 12

(,

PERFORMANCE CHECKLIST Page 6 of 6 Student Name:

Action Contacts Fire brigade members from Operations.

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

Contacts Fire brigade members from Security.

Sound fire alarm.

Critical Step

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

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

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

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

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

At panel OC695:

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

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

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

Page 1 of 1 2003 NRC Exam Rev. 1

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

I 4 PERFORMANCE CHECKLIST

Critical Step Action Make plant page announcement.

Selects the appropriate Pre-Fire Plan.

EVALUATOR This completes the JPM.

Student Name:

Stand a rd Push in the evacuation alarm switch.

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

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

Keys the plant page and announces:

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

Repeat the above announcement.

Obtains a copy of FP-013-189.

Critical Seq uence Eva1

(

Page 7 of 6 Comments 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 1 1 -AUG-03 44-660 A DIESEL GEN FIRE DET X116-21 ALM 17:16 MON 1 1 -AUG-03 44-6771710 A DG FIRE SUP X250-Zl ALM 17:20 MON I I

-AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

L-'

2003 NRC Exam Rev. 1 Page 1 of 2

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 I I

-AUG-03 44-677171 0 A DG FIRE SUP X250-ZI ALM 17:20 MON 1 1 -AUG-03 44-676 PA011 ADIESL INITIATING CUE Activate the fire brigade and select the appropriate Pre-Fire Plan.

2003 NRC Exam Rev. 1 Page 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO PCOl7-I02 0

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

Date NUREG 1123 Sys. No.

WA Task

Title:

Completed By:

Reviews:

Perform Emergency Plan Classification and Identify Reportability Requirements.

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

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

JPM Performed By:

15 Time Critical Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

L-'

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

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

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.

6.

C.

EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 PCOl70-I 02, SIMULATOR EVALUATION SCENARIO NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9 I I I. REACTIVITY MAN I PU LATIONS 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 Appl. To/JPM NO.: SRO E-PLAN PCOl7-102 Student Name:

(

Page 3 of 5 Step Action Eva1 uato r 0

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

This is a time critical JPM.

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

0 EVALU AT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Eva1 uato r 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.

Evaluates information.

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

Refers to classification matrix.

Critical Step

Critical Sequence Standard Controlled copy obtained.

Identifies loss of reactivity control as potential Emergency Plan entry.

Selects Tab 4.

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM NO.: SRO E-PLAN PCOl7-102 Step 4

5

6 7

8 9

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

Choose appropriate emergency action level.

Record Time of Site Area Emergency declaration EVALUATOR CUE:

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

Critical Step

Critical Sequence Student Name:

Standard Reviews all category 11.

Identifies entry into EAL I I

.3 based upon loss of functions needed to bring the reactor subcritical and loss of ability to bring reactor to cold shutdown.

Classifies the event as a Site Area Emergency.

Controlled copy obtained.

Reviews Attachments:

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

Reports I hour ENS notification to the evaluator.

Eva1

(:

Page 4 of 5 Comments STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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

Action Standard Eva1 Comments EVALUATOR CUE:

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

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

Page 1 of 1 2003 NRC Exam Rev. 1

Critical Sequence

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

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

2003 NRC Exam Rev. 1 Page 1 of 4

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

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

L-.

2003 NRC Exam Rev. 1 Page 2 of 4

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

L=

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

2003 NRC Exam Rev. 1 Page 3 of 4

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

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

2003 NRC Exam Rev. 1 Page 4 of 4

PENNSYLVANIA POWER & LIGHT COMPANY L--

JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO Appl. To PCOl7-I 03 0

2.4.41 4.0 06/14/03 E-PLAN 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--

Date of Performance:

JPM Performed By:

15 Time Critical Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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.

B.

C.

EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 PCOI 70-1 03, SIMULATOR EVALUATION SCENARIO NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9

- 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

Appl. To/JPM NO.: SRO E-PLAN PCO17-103 Step 1

2 PERFORMANCE CHECKLIST Action Evaluator 0

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

This is a time critical JPM.

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

0 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 Obtains a copy of EP-PS-100.

Evaluates information.

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

Student Name:

Standard Controlled copy obtained.

Identifies the following events as potential Emergency Plan entry:

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

(

Page 3 of 5 Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM NO.: SRO E-PLAN PCO17-1 Step 3

4

5

6 7

8 PERFORMANCE CHECKLIST

{

Page 4 of 5 Student Name:

Action Refers to classification matrix.

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

Choose appropriate emergency action level.

Record Time of Site Area Emergency declaration EVALUATOR CUE:

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

Critical Sequence Standard Selects Tab 4.

Reviews all category 6.

Reviews all category 12.

Reviews all category 18.

Identifies entry into EAL 18.3 based upon any other un-isolatable steam line break (RWCU Break).

Classifies the event as a Site Area Emergency.

Controlled copy obtained.

Reviews Attachments:

E, F, GI and H Comments 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

I 0 Action Determines Reportability requirements Reports results EVALUATOR CUE:

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

Critical Step

Critical Sequence Standard 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.

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

Eva1 I Comments 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 2003 NRC Exam Rev. 1 Page 1 of 4

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

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

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

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

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

.v.

2003 NRC Exam Rev. 1 Page 3 of 4

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.

2003 NRC Exam Rev. 1 Page 4 of 4

SRO Appl. To Task

Title:

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

2.4.41 4.0 0611 4/03 E-PLAN JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Perform Emergency Plan Classification and identify Reportability Requirements.

Completed By:

Reviews:

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

Requesting Supv.1C.A.

Date Nuclear Trng. Supv.

Date Head L-.

Date of Performance:

15 Time Critical Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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.

B.

C.

EP-PS-100, EMERGENCY DIRECTOR CONTROL ROOM, REV. 18 PCOI 70-1 04, SIMULATOR EVALUATION SCENARIO NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE, REV. 9 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

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

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

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

I-'

2003 NRC Exam Rev. 1

Appl. To/JPM NO.: SRO E-PLAN PCO17-104 Step PERFORMANCE CHECKLIST Action Evaluator 0

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

This is a time critical JPM.

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

0 0

EVALU AT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Eva1 u ator After the candidate reviews the Task Conditions / Initiating Cue Sheet:

0 0

Ask if the candidate is ready to begin the JPM.

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

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

Evaluates information.

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

Refers to classification matrix.

Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

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

Selects Tab 4.

Eva1

(

Page 3 of 5 Comments 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 4

"5

6 7

8 9

I 0

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

Choose appropriate emergency action level.

Record Time of Alert declaration EVALUATOR CUE:

After the emergency declaration is made, Hand the candidate the second cue sheet for reportability requirements Obtains a copy of NDAP-QA-0720, STATION REPORT MATRIX AND REPORTABILITY EVALUATION GUIDANCE Reviews reporting requirements Determines Reportability requirements Reports results Standard Reviews all category 12.

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

Classifies the event as an Alert.

Controlled copy obtained.

Reviews Attachments:

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

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

Eva1 Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. I

PERFORMANCE CHECKLIST Step Page 5 of 5 Action Standard Eva1 Comments EVALUATOR CUE:

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

Appl. To/JPM NO.: SRO E-PLAN PCO17-104 Student Name:

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 2003 NRC Exam Rev. 1 Page I of 4

L 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.

v 2003 NRC Exam Rev. 1 Page 2 of 4

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

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

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.

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

2003 NRC Exam Rev. 1 Page 4 of 4

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 (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed 2.1.25 2.813.1 JPM Determine Primary Containment Water Level During Anomaly.

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

~~~

2.2.1 3 3.6/3.8 JPM Determine accuracy and adequacy of a clearance order.

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

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 2003 NRC Exam Rev. 1 Susquehanna Facsimile

---i L-PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO

00. AD. 047.00 1 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 Date of Performance:

15 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 I of 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 I II. REACTIVITY MAN1 PULATIONS 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

Appl. To/JPM No.: S/RO 00.AD.047.001 Step PERFORMANCE CHECKLIST Page 4 of 7 Action EVALUATOR Ensure the following material is available to support performance of this JPM:

0 0

A COPY Of NDAP-QA-0338.

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

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.

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.

Determines entry condition.

Enters initiating condition data.

Determine if power is above the LPSP.

Critical Step

Critical Sequence Student Name:

Stand a rd Controlled copy obtained.

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

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

Enters the following data for Initiating Condition:

0 Rod ID is 22-59 0

Notch is 00 0

Unit is I 0

0 Power Level is 1%

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

Eva1 Comments 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 6

7 8

9 10 11

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

Determine if both RSCS and RWM are problems.

Determine if a computer problem exists.

Determine if RPlS problems exist.

Contact Reactor Engineering.

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

Contact I&C.

Determines Tech Spec impact.

Critical Step

Critical Sequence Standard Places a checkmark in the No box.

Places a checkmark in the No box.

Contacts Rx Engineer to :

0 Investigate the RWM pointer 0

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

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

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

Eva1

~~~

~

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 00.AD.047.001 Step 13

(;

(1 PERFORMANCE CHECKLIST Page 6 of 7 Action EVALUATOR CUE Give the candidate the Start-up control rod sequence A2.

Identifies a LCORRO 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 Student Name:

~~

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

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

C.2. I. 1, Immediately verify 2 OR 12 rods withdrawn C.2.1.2, Immediately verify by administrative methods that startup with RWM inoperable has not been performed in the last calendar year C.2.2, During control rod movement verify movement of control rods is in compliance with BPWS by a second licensed operator or other qualified member of the technical staff.

States LCO/TRO Log Sheet must be completed.

Eva1 Comments STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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

I4 15

(:

PERFORMANCE CHECKLIST Student Name:

Action Determine that it is allowable to bypass RWM.

Authorize bypassing RWM.

EVALUATOR This completes the JPM.

Critical Step

Critical Sequence Standard Determines that RWM can be bypassed.

Places a checkmark in box for RW M.

Signs form and enter current time/date.

Eva1 Page 7 of 7 Comments 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.

2003 NRC Exam Rev. 1 Page 1 of 2

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.

2003 NRC Exam Rev. 1 Page 2 of 2

REACTIVITY CONTROL SYSTEM BYPASS AUTHORIZATION FORM (RBM)

~..

Yes+

-rake Appropriate J

Corrective Actions 0

No L

A r

(-

RBM Providing Rod Block ]

1) Invalid APRM inputs 0 Yes No

- adjust or bypass APRMs

2) Invalid Flow inputs 0 Yes 0 No

3) Invalid LPRM inputs Yes No

- adjust or bypass flow units

- a) determine if LPRMs are valid via

- b) bypass or adjust LPRMs as required TIPS or other means Initiating Condition Rod I.D.

Notch -

Unit-RBM Channel A or B Power Level -

Date I Time I

1 O.K. to Bypass RBM Channel 4 30% Power D y e s I Do not Bvoass RBM Channel I

Attachment A Revision 6 Page 34 of 42 N DAP-QA-0338 I

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

?CO log. Reanalyze at 30%.

1 RBM restored to normal.

I--

I Shift Supervision Authorization Date Time Call I&C to repair RBM andlor I--

I Shift Supervision Authorization Date Time To bypass RBM Channel. Enter into LCO Log.

OK to bypass RBM Channel I.A.W.

TS 3.3.2.1 I

I RBM restored to normal. LCO cleared.

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:

Completed By:

Reviews:

Review a Clearance Order for Accuracy Russ Halm 0611 3/03 Writer Date I nstructorNV riter 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. #

Perform an ce Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signatu re Typed or Printed Comments:

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

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

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. 1 I )

E. E-I38 Sheet 1 ClRC WATER PUMP DISCHARGE VALVE (Rev. 13)

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

-c IV. REACTIVITY MAN I P U LATIONS This JPM satisfies the requirements of Operational Activity(s):

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

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

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

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

VI. TASK STANDARD Component 1651 1034 (tag number 4) is identified as the wrong device and the correct device is 1B501034.

L-2003 NRC Exam Rev. 1

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

2 3

PERFORMANCE CHECKLIST Page 3 of 7 Action This JPM must be performed in the simulator or the plant control room.

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

A copy of Clearance Order.

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

Evaluator 0

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

Provide the candidate with the Clearance Order 5401 5.

Reviews the scope of work planned for 1 P501 B.

Reviews NOTE 1 for conditions necessary before applying blocking.

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

Verifies electrical blocking required.

Use electrical print to verify 1 P501 B motor breaker.

Student Name:

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

Determines 1 P501 B will be removed from service IAW OP-142-001 Section 3.2.

Using E-I 37 Sht.3, determines breaker 1AlO203 is correct.

Eva1 Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. 1

/,

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

PERFORMANCE CHECKLIST Page 4 of 7 Student Name:

Step 4

5 6

7 8

9 Action Reviews position of Red tagged device.

Use electrical print to verify HV-1151 I B MOV breaker.

Reviews position of Red tagged device.

FAULT STATEMENT THE NEXT DEVICE AND BREAKER NUMBER ARE INCORRECT.

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

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

Reviews position of Red tagged device.

Verifies mechanical blocking required.

Use mechanical drawing to verify HV-l1513B, CWP B Suction valve.

Critical Step

Critical Sequence Standard Breaker IAlO203 should be RACKED OUT.

Using E-I38 Sht.1, determines breaker 1850124 is correct.

Breaker 1 850124 should be OPEN.

Using E-1 38 Sht. 19, determines breaker 1851 1034 is NOT correct.

The correct breaker is 18501034 for HV-11511 8.

Breaker 1 B501034 should be OPEN.

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

Eva1 Comments STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO New Admin Step 10 I 1 12 13 14 15 16 PERFORMANCE CHECKLIST Page 5 of 7 Student Name:

Action Reviews position of Red tagged device.

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

Reviews position of Red tagged device.

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

EVALUATOR NOTE:

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

Reviews position of Red tagged device.

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

EVALUATOR NOTE:

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

Reviews position of Red tagged device.

EVALUATOR NOTE:

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

Standard Valve HV-115138 should be CLOSE.

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

Valve HV-11511 B should be CLOSE.

Using M-I 15 Sht.1, determines 115153 is correct.

Valve I 151 53 should be CLOSE.

Using M-I 15 Sht.1, determines 115154 is correct.

Valve 11 51 54 should be CLOSE.

Eva1 Comments

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 17 18 19 20 21 22 23 24 Action Use mechanical drawing to verify 115139B, CWP 8 Suction Vent valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

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

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

Use mechanical drawing to verify 115142B, CWP 8 Discharge Drain valve.

EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

Use mechanical drawing to verify 1151438, CWP B Suction Drain valve, EVALUATOR NOTE:

Drawing grid location is 1-1.

Reviews position of device.

Critical Step

Critical Sequence Standard Using M-I15 Sht.1, determines 1 151398 is correct.

Valve 1 151 39B should be OPEN.

Using M-I15 Sht.1, determines 11 5141 8 is correct.

Valve 115141B should be OPEN.

Using M-I 15 Sht.1, determines 1 151 42B is correct.

Valve 1151428 should be OPEN.

Using M-I15 Sht.1, determines 115143B is correct.

Valve 11 51438 should be OPEN.

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

Page 1 of 1 2003 NRC Exam Rev. 1

(

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

25

(

PERFORMANCE CHECKLIST Page 7 of 7 Student Name:

Action Reports the review results.

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

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

EVALUATOR This completes the JPM.

Critical Step

Critical Sequence Standard Informs the Unit Supervisor:

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

0 Breaker 18501 034 is the correct breaker.

0 Breaker 1 B501034 description is CIRC WATER PUMP B BKR.

DISCHARGE VLV HV-11511 B Eva1 Comments 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 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.

2003 NRC Exam Rev. 1 Page 1 of 2

TASK CONDITIONS A. NlMS is not available.

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

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

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

2003 NRC Exam Rev. I Page 2 of 2

(

TATS Seq TagNo Component ID Component Description Position Status Tag Color Plant Ln bel 01% Chmments/Noun Location J

L TAG/

NG WMX ( dTAGHANG CO: 54015 NAME: 1P501B CIRC WATER PUMP OOS Hang Authorized By:

Status:

AUTHHANG lJnit: 1 Year:

2003 Change In Progress: N Component ID:

Work

Description:

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

~

____.~

1 INA 2

INA 3

INA 1

NOTE 1 SEE BLOCKING COMMENTS FOR DETAILS N/A 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 lA10203 CIRC WATER PUMP B 1P501B 13.8 KV BKR RACKED OUT RT IA10203 (RM)

Tag Comments:

Area-Elev 4 - 699 Room 1-220 Azimuth Parent ID lA102 Grating 0

Actual 699 3

1B501024 CWP IB DSCH MOV HV-1151 IB BKR 52-024 OPEN 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 Position Seq Tag No Component 11)

Componen t Description Status Tag Color Plant Label OPS Comments/Noun Location TAGHANG WMX r CO: 54015 NAME: IPSOIB CIRC WATER PUMP 00s Hang Authorized By:

Status:

AUTI-I1 IANG 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 15 137B Seq Blocking Req N De-energized :N De-pressureized : N Continuously Vented :N Drained :N Purged : N Isolated : N Note :

....~

~. ~..~

~~

4 INA 5

INA 6

INA 4

1B511034 RT Tag Comments:

Area-Elev 5 I - 676 Room CW-020 Azimuth 5

HVl1513B RT Tag Comments:

Area-Elev 50 - 66 1 Room cw-003 Azimuth 6

HV1 151 1R RT Tag Comments:

Area-Elev 50 - 60 I Room CW-003 Azimuth CIRC WATER PUMP A DISCHARGE VLV HV-11511A13KR Parent ID 1BS11 Grating 0

Actual 676 CIKC WATER PUMP B SUCTION VLV Noun Lot: CAUTION: DURING MANUAI, OPERATION, I)O N O T IOSITION PAST S(IZ1131S MARKS Pa rent I I)

Grating 0

Actual 665 CIRC WATER PUMP B DISCHARGE VLV Noun Loc: CAUTION: DURING MANUAL OPERATION, DO NOT POSITION PAST SCRIBE MARKS Parent ID Crating 0

Actual 667 OPEN CLOSE CLOSE Page 2 of 4 Report Date:

05/07/2003 1456

TAGHANG WMX i TAG!

NG i

TATS 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):

Work

Description:

Replace 1P501B Circ Water Pump Discharge Vent Valve, 115137B 1 150 I Ii Continuously Vented :N Drained :N Purged : N Isolated : N Seq Blocking Req N De-energized :N De-pressureized : N Note :

Seq TagNo Component In Component Description Position Stnius Iag Color 11;1111 I.iltWl OIS Coiiiniciits/Noun I,ociltioI1 7

7 115153 INA RT CLOSE CWP B IB BEARING SEAL WATER SUPPLY IS0 VLV Tag Comments:

Grating 0

Actual 671 Area-Elev 50 - 676 Room CW-003 Azimuth Parent ID 8

8 115154 INA RT Tag Comments:

Area-Elev 50 - 676 Room CW-003 Azimuth 9

9 I151393 INA NT Tag Comments:

CWP B OB BEARING SEAL WATER SUPPLY IS0 VLV CLOSE Parent ID Grating 0

Actual 671 CW PUMP B SUCTION VENT VLV

-~

OPEN 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 00s Hang Authorized By:.

Status:

AUTHI-IANG Unit: 1 Year:

2003 Change In Progress: N Component ID:

Work

Description:

ltepliicc I P.501 I3 Circ Water Puiiip Discliiirgc Vcnt Viilvc, 1 IS I3713 1 P50 I R 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 INA 11 INA 12 INA 10 115141 3 NT Tag Comments:

Area-Elev SO - 661 I 1 1151421%

NT

'rag Comnients:

Area-Elev 50 -661 12 1151331%

NT Tag Comments:

Area-Il:lev 50 - 601 Room

?

Azimuth Room CW-003 Aziniuth Room

?

Azimuth CW PUMP B SUCTION VENT VLV Parent ID Grating 0

Actual 661 C'117C WATER PUMP I3 DISCIIARGIX DRAIN VLV Parent ID Grating 0

Actual 663 CIRC WATER PUMP B SUC'I'ION DRAIN VLV Parent 11)

Grating 0

Actual 661 OPEN OPEN OPEN 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-Date of Performance:

20 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

S ig nature Typed or Printed Comments:

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

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

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.

B.

NDAP-QA-0309 PRIMARY CONTAINMENT ACCESS AND CONTROL, REV. 13 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 I II. REACTIVITY MAN1 PULATIONS This JPM satisfies the requirements of Operational Activity(s):

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

C. Unit 1 is currently in Mode 3.

D. You are preparing for initial containment entry.

ea IOW.

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 EVALUATOR 0

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

NDAP-QA-0309 OP-173-001 0

TRM 0

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

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

Obtains a copy of NDAP-QA-0309.

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.

EVALUATOR CUE Acknowledge surveillance requirements.

Identifies SGTS operability requirements.

EVALUATOR CUE Inform candidate both SGTS trains are operable.

Standard Controlled copy obtained.

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

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

Eva1 Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. 1

(

Appl. To/JPM No.: S/RO 00.AD.040.001 Step 4

5 6

7 PERFORMANCE CHECKLIST Page 4 of 5 Action Identifies SGTS exhaust sampling requirements per TR 3.1 I

.2.6.

EVALUATOR CUE Inform candidate SPING is operable.

Chemistry sampling requirements of containment.

EVALUATOR CUE Acknowledge chemistry sampling requirement.

States release limits.

EVALUATOR CUE Acknowledge release limit requirement.

Complete NDAP-QA-0309 Attachment 6.

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

Student Name:

~

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

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

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

Completes Attachment 6.

Enter I for Unit.

Enter current date for start date.

Enters current time for start time.

Eva1

=

Comments

Critical Step

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

Page 1 of 1 2003 NRC Exam Rev. 1

Page 5 of 5 PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 00.AD.040.001 Step 8

9 10 11 12

I 3 Action Install portable oxygen analyzer 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to de-inerting.

EVALUATOR CUE Acknowledge installation of portable analyzer.

Obtains a copy of OP-I 73-001.

Refers to correct procedure section.

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 verifies the requirements of TRO 3.6.1 are met.

EVALUATOR CUE Acknowledge all surveillance requirements are current and satisfactory.

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

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

EVALUATOR This completes the JPM.

Critical Step

Critical Sequence Student Name:

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

Controlled copy obtained.

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

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

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

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

Eva1 Comments 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. A SBGT Radiation Monitor RISHH-Dl2-0K617A has just failed low.

C. Unit 1 is currently in Mode 3.

D. You are preparing for initial containment entry.

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

2003 NRC Exam Rev. I Page I of 2

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

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

C. Unit 1 is currently in Mode 3.

D. You are preparing for initial containment entry.

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

2003 NRC Exam Rev. I Page 2 of 2

ML032591125

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