Text

Final Section a Operating (RO & SRO) (Folder 3)
	ML042750524
Person / Time
Site:	Susquehanna
Issue date:	08/09/2004
From:	Roush K; PPL Generation
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-387/04-302, 50-388/04-302
	Download: ML042750524 (103)
	v • d • e

v S/RO Appl. To Task

Title:

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 00.AD.038.001 0

0 1 128104 2.1.20 4,314.2 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

K/A Complete Aborted Evolution Log Completed By:

Reviews:

Russ Halm Writer Date InstructorMlriter Ap p rova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Head Date of Performance:

Date Date 10 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:

srw-w-1 2 5 ~

Rev. 2, (9/93)

Page 1 of 1 2004 NRC Exam As Given File No. A14-58

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 00.AD.038.001

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. OP-133-001 CHEMICAL ADDITION TO TURBINE BUILDING CHILLED WATER SYSTEM (Rev.

21) filled out up to step 2.4.10.

B. OP-AD-002 STANDARDS FOR SHIFT OPERATIONS (Rev. 10)

C. Blank Aborted Evolution Control Log (AECL) Form OP-AD-002-1 (Attachment H)

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

NONE IV. TASK CONDITIONS A.

B.

C.

D.

E.

F.

Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System In Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-I 33-001 Section 2.4.

During step 2.4.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened.

Maintenance will not be available until dayshift tomorrow to support opening 188003 valve.

You are the Unit 1 PCOM V. INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.

VI. TASK STANDARD Aborted Evolution Control Log identifies TB Chilled Wtr Chem Add Tank Out In valve 188003 could not be opened. Unit 1 turbine bldg. NPO, and Control Room Supervisor notified to make turnover sheet entries referencing the Aborted evolution. Plant operator turnover sheet entry referencing the Aborted evolution is made.

2004 NRC Exam As Given

(,

Page 3 of 7 PERFORMANCt CHECKLIST Appl. To/JPM No.: 00.AD.038.001 Step Action EVALUATOR NOTE:

Ensure a copy of OP-AD-002 Section 8.4 and OP-AD-002 Attachment H is available.

EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet AND OP-BUILDING CHILLED WATER SYSTEM (Rev. 21) filled out up to step 2.4.10.

133-001 CHEMICAL ADDITION TO TURBINE Obtain a controlled copy of OP-AD-002 Selects the correct section to perform. OP-AD-002 Section 8.4 Aborted Evolution Control Log (AECL) Form OP-AD-002-1 (Attachment H) shall be completed when:

An evolution is aborted prior to completion and will not be resumed prior to shift turnover.

Equipment is left in an abnormal lineup and additional information is essential to the on-coming shift.

Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Determines OP-AD-002 Section 8.4 is appropriate.

Determines:

Attachment H will need to be completed.

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.038.001 4

5 3k6 37 PERFORMANCt CHECKLIST Action Completes Attachment H of OP-AD-002 by performing the following:

Completing Line 1 Completing Line 2 Completing Line 3 Completing Line 4

Critical Step

Critical Sequence Student Name:

i.

Page 4 of 7

~~

Standard Places:

Date, Time, and name in the spaces provide in line I.

Places:

System number 133 and system name Turbine Building Chilled Water System in the spaces provide in line 2.

Places:

Procedure number OP-I 33-001, Revision 21, step 2.4.10 in the spaces provide in line 3 Places:

TB Chilled Wtr Chem Add Tank In valve I88003 could not be opened in the space provide in line 4 Eva1 Comments STCP-QA-125B Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.038.001 Step 8

9 10 i,

PERFORMANCE CHECKLIST Page 5 of 7 Action EVALUATOR NOTE:

Due to the nature of this JPM, the information provided by the candidate in the next 2 steps may vary from the information scripted in the STANDARD column. Evaluator judgement may need to be applied to information provided by the candidate.

Completing Line 5 Completing Line 6 Each AECL activity shall be referenced on the Turnover Sheet of the Operator performing the evolution and be reviewed as part of the Turnover process until such time as the AECL is no longer required, or in control.

%Critical Step

Critical Sequence Student Name:

Standard Places:

NONE in the space provide in line 5 Places:

Restart procedure beginning at step 2.4.10 in the space provide in line 6 Identifies:

Turbine Building NPO turnover sheet must have a reference to the aborted evolution, and be reviewed as part of the Turbine building NPO turnover process until such time as the AECL is no longer required.

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Appl. To/JPM No.: 00.AD.038.001 Step

I 1

12 Action Informs Turbine building NPO of Administrative requirements for the aborted evolution.

EVALUATOR CUE:

Role-play Turbine building NPO acknowledge the report.

Each AECL activity shall be referenced on the Unit Supervisor Turnover Sheet and the affected Plant Operator Turnover Sheet. The AECL Form shall be maintained by Unit Supervisor in the Control Room with a copy on the Plant Operator Turnover.

Critical Step

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

Page 1 of I 2004 NRC Exam As Given Student Name:

i Page 6 of 7 Standard Informs Turbine building NPO to:

Reference the aborted evolution IAW the AECL form AND Review the AECL as part of the turnover to the oncoming shift Identifies:

Unit 1 Control room Supervisors turnover sheet and the Unit 1 Plant operators turnover sheet must have a reference to the aborted evolution.

0 Original of the AECL is to be maintained by the Unit 1 Control room Supervisor Copy of the AECL is to be maintained with the Plant Operator Turnover sheet.

Eva1 Comments

Appl. To/JPM No.: 00.AD.038.001 Step

I 3 PERFORMANCt CHECKLIST Action Informs Unit I Control room Supervisor of Administrative requirements for the aborted evolution.

EVALUATOR CUE:

Role-play Unit 1 Control room Supervisor acknowledge the report.

EVALUATOR CUE:

This completes the JPM

%Critical Step

Critical Sequence Student Name:

Standard Informs Unit 1 Control room Supervisor to:

Reference the aborted evolution IAW the AECL form AND Review the AECL as part of the turnover to the oncoming shift Eva1 i

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

Page 1 of 1 2004 NRC Exam As Given

TASK CONDITIONS A.

Unit I is in Mode I

6. All Plant Equipment required for Mode I is in operation C. Turbine Building Chilled Water System In Service D. The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.4.

E.

During step 2.4.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened.

Maintenance will not be available until dayshift tomorrow to support opening 188003 valve.

F.

You are the Unit I PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.

2004 NRC Exam As Given 1 of2

TASK CONDITIONS

-7' A.

Unit 1 is in Mode 1 B. All Plant Equipment required for Mode 1 is in operation C. Turbine Building Chilled Water System In Service D. The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.4.

E.

During step 2.4.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened.

Maintenance will not be available until dayshift tomorrow to support opening 188003 valve.

F. You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.

2004 NRC Exam As Given 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 00.AD.037.051 0

0 1 129104 2.1.33 3.414.0 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Calculate RCS leakage and determine if leakage is less than Tech. Spec LCO.

Completed By:

Russ Halm Writer Approval:

Requesting Supv.1C.A.

Head Date of Performance:

JPM Performed By:

Reviews:

Date InstructorMlriter Date Date Nuclear Trng. Supv.

Date 15/25 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Eva I uation :

(

)

Satisfactory

(

) Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

1 STCP-QA-125A Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam As Given File No. A14-5B

V' REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 00.AD.037.051

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 SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG (Revision 44)

SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG Attachments F and M filled out for the 21 00 hour0 days 0 hours 0 weeks 0 months surveillance I II. REACTIVITY MAN1 PULATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A.

Unit 1 is at 100% power. Sometime during the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Drywell sump inleakage began increasing.

B.

It is 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months and time to perform SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOGS C. Total level increases on LWFR-16103 for Sump A are 109 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Total level increases on LWFR-16103 for Sump B are 99 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E.

Total percent rise in LRIFR-16103 forwarded over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is 268%

V. INITIATING CUE Your supervisor directs you to Determine RCS leakage by performing the Drywell Floor Drain inleakage calculation IAW with SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG and determine if any Tech Spec limits are being exceeded. Report the results of the calculation and determination to your supervisor.

VI. TASK STANDARD Unidentified RCS leakage is determined to be 5.77 gpm. A determination is made that RCS leakage is in excess of Tech Spec allowable value of 5 5 gpm.

2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 Step 1

2 3

4 i

PERFORMANCt CHECKLIST

(

Page 3 of I 2 Action EVALUATOR NOTE:

To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet Attachments F and M filled out for the 2100 hour0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months surveillance.

Obtain a controlled copy of SO-100-006 SHIFTLY SURVEILLANCE 0 P E RAT1 N G LOG Selects the correct section to perform.

Determines Attachment F and L will need to be completed EVALUATOR NOTE:

The candidate may refer to Attachments E and M for the instructions on how to complete Attachments F and L. This JPM is written to follow this guidance. The candidate does not need to use Attachments E and M to complete the JPM, rather the candidate need only correctly complete Attachments F and L to successfully complete this JPM.

Refers to Attachments E and M for instructions on completing Attachments F and L.

+Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Selects item A21 on page 25 of 136 Determines Attachment F and L will need to be completed Locates Attachments E and M.

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

Page 1 of 1 2004 NRC Exam As Given

i' PERFORMANCt CHECKLIST Appl. To/JPM No.: 00.AD.037.051 Step Action Determine total number of level increases from the last I 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period on DRWL SUMPS FLOW & LVL LWFR-16103 (Point I ) (Alternate: Computer Pt.

RLLOO4Z) including increase that occurs coincident with start of each pumpdown (indicated by a sharp drop in level; level spike may not be evident).

Determine total number of level increases for the last 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period on DRWL SUMPS FLOW & LVL RECORDER LWFR-I 61 03 (Alternate: Computer Pt.

RLLOOSZ) (Point 2) including increase that occurs coincident with start of each pumpdown (indicated by a sharp drop in level; level spike may not be evident).

Compute total gallons accumulated for DRWL Sump A. (Total Level Increases) (I9 gal/level) = total gallons.

Compute total gallons accumulated for DRWL Sump B. (Total Level Increases) (21 galllevel) = total gallons.

Critical Step

Critical Sequence Student Name:

i:

Page 4 of 12 Standard Places I09 in the space provided on SO-100-006 Attachment F. (item b)

Places 99 in the space provided on SO-100-006 Attachment F. (item c)

Places 2071 in the space provided on SO-100-006 Attachment F. (item d)

(109 X 19=2071)

Places 2079 in the space provided on SO-100-006 Attachment F. (item e)

(99 X 21 =2079)

Eva1 Comments STCP-QA-I25B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 Step 9

I O 11 PERFORMANCE CHECKLIST

{,

Page 5 of 12 Action EVALUATOR NOTE:

Total elapsed time in minutes for the last 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months time period on LWFR-16103 (Alternate: Computer Pts.

RLL004Z/RLL005Z) (720 mins).

Determine average lnleakage for DRWL Sump A (total gallons)/(elapsed time in minutes) = average inleakage.

EVALUATOR NOTE:

0.02 needed in the next step was provided as a carry-over item in the initial conditions.

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous average inleakage recorded from previous days worksheet for DRWL Sump A.

Determine the change in inleakage from the last time the inleakage was determined. (current inleakage) -

(previous inleakage) = change (A) in inleakage.

Critical Step

Critical Sequence Student Name:

Standard Places 2.88 in the space provided on SO-100-006 Attachment F. (item g)

(2071/720=2.88)

Places 0.02 in the space provided on SO-100-006 Attachment F. (item h)

Places 2.86 in the space provided on SO-100-006 Attachment F. (item i)

(2.88 - 0.02=2.86)

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

Page 1 of 1 2004 NRC Exam As Given

/

Appl. To/JPM No.: 00.AD.037.051 Step 12 13 14 15

I6 I

PERFORMAN& CHECKLIST Page 6 of 12 Action Determine average inleakage for DRWL Sump B (total gallons)/(elapsed time in minutes) = average in leakage.

EVALUATOR NOTE:

0.03 needed in the next step was provided as a carry-over item in the initial conditions.

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous average inleakage recorded from previous days worksheet for DRWL Sump B.

Determine change in inleakage from the last time the inleakage was determined. (current inleakage) -

(previous inleakage) = change (A) in inleakage.

Determine the total average inleakage (inleakage Sump A) + (inleakage Sump B). c 5 gpm required.

Determine the total change in inleakage from the last time the inleakage was determined (delta inleakage Sump A) + (delta inleakage Sump B). c 2 gpm/24 hours required.

Critical Step

Critical Sequence Student Name:

Standard Places 2.89 in the space provided on SO-I 00-006 Attachment F. (item j)

(2079/720=2.89)

Places 0.03 in the space provided on SO-1 00-006 Attachment F. (item k)

Places 2.86 in the space provided on SO-100-006 Attachment F. (item I)

(2.89-0.03=2.86)

Places 5.77 in the space provided on SO-1 00-006 Attachment F. (item m)

(2.88 + 2.89 = 5.77)

Places 5.72 in the space provided on SO-I 00-006 Attachment F. (item n)

(2.86 + 2.86 = 5.72)

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 Step 17 18 19 20 21 i

i PERFORMANCt CHECKLIST Page 7 of 12 After 0900 average inleakage calculation, Enter average inleakage recorded for both 2100 and 0900 in steps g. and j. to next day's worksheet to be used as 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous values in steps h. and k. for 2100 and 0900, respectively.

EVALUATOR CUE:

If necessary inform the candidate that it is not necessary to perform this transposition for this JPM.

Compute total gallons accumulated for DRWL Sump A. (Add total from each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period from Attachment F)

Compute total gallons accumulated for DRWL Sump B. (Add total from each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period from Attachment F)

Determine total elapsed time in minutes for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period (1440 minutes).

Determine average inleakage for DRWL Sump A.

(total gallons)/(elapsed time in minutes) = average inleakage

Critical Step

Critical Sequence Student Name:

Standard Places 2565 in the space provided on SO-100-006 Attachment M. (item I a)

(494 + 2071 =2565)

Places 2394 in the space provided on SO-100-006 Attachment M. (item I b)

(31 5 + 2079=2394)

Places 1.78 in the space provided on SO-100-006 Attachment M. (item Id)

(2565/1440=1.78)

Eva1 Comments STCP-QA-1 25B Rev. 2 (9/93)

Page 1 of I 2004 NRC Exam As Given

(

Appl. To/JPM No.: 00.AD.037.051 Step 22 23 24 25 26 27 i

PERFORMAN& CHECKLIST

(

Page 8 of 12 Student Name:

Action Determine average inleakage for DRWL Sump B.

(total gallons)/(elapsed time in minutes) = average inleakage Determine total percent from last 24 hr time mark on DRWL EQUIP DRN TANK LWFR-16103 (Alternate:

Computer Pt. RLLOOGZ).

Compute total gallons accumulated on LEVEL RECORDER LWFR-16103 (Alternate: Computer Pt.

RLLOOGZ). (Total %) (8.5 gal/%) = total gallons Example: (380%) (8.5 gal) = 3230 gallons Determine total elapsed time in minutes from last 24 hr time mark on LEVEL RECORDER LR/FR-16103 (Alternate: Computer Pt. RLLOOGZ) (1440 minutes).

Determine average inleakage recorded on LEVEL RECORDER LWFR-16103 (Alternate: Computer Pt.

RLLOOGZ) (total gallons)/(elapsed time in minutes) =

average inleakage.

Compute TOTAL DRYWELL LEAKAGE Record average leakrate from step I

.d.

Critical Step

Critical Sequence Standard Eva1 Comments Places 1.66 in the space provided on SO-1 00-006 Attachment M. (item 1 e)

(2394/1440=1.66)

Places 268 in the space provided on SO-1 00-006 Attachment M. (item 2a)

Places 2278 in the space provided on SO-I 00-006 Attachment M. (item 2b)

(268 X 8.5=2278)

Places 1.58 in the space provided on SO-I 00-006 Attachment M. (item 2d)

(2278/1440=1.58)

Places 1.78 in the space provided on SO-1 00-006 Attachment M. (item 3a)

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 Step 28 29 30

( '

PERFORMANCE CHECKLIST Page 9 of 12 Action Record average leakrate from step 1.e.

Record average leakrate from step 2.d.

Sum total leakrate (a+b+c) required e25 gpm.

EVALUATOR CUE:

If necessary, remind candidate that they were asked to report the results to the supervisor.

EVALUATOR NOTE:

The total leakage is greater than 2 gpm in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , however the Tech Spec is in a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period.

Therefore more information and calculation would be needed to determine if this Tech Spec has been exceeded. It is not necessary for this JPM to perform this additional assessment.

+Critical Step

Critical Sequence Student Name:

Standard Places 1.66 in the space provided on SO-100-006 Attachment M. (item 3b)

Places 1.58 in the space provided on SO-I 00-006 Attachment M. (item 3c)

Places 5.02 in the space provided on SO-I 00-006 Attachment M. (item 3d)

( I.78 + 1.66 + 1.58 = 5.02)

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

Page I of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 31 3(c 32 PERFORMANCt CHECKLIST Page 10 of 12 Action Compares calculated values to the ACCEPTABLE values listed in item A21 of SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG.

Report the results of the calculation and determination.

EVALUATOR CUE:

Role-play Control room supervisor and acknowledge the report.

EVALUATOR CUE:

This completes the JPM for the ROs ONLY

Critical Step

Critical Sequence Student Name:

Standard Compares calculated values to the ACCEPTABLE values listed in item A21 S U RVE I LLAN CE 0 P E RAT1 NG LOG.

of SO-100-006 SHIFTLY AND Determines that the 5.77 gpm leakrate calculated in step m of attachment F is GREATER Than Tech Spec allowable value of 5 5 gpm.

Reports Leakage rate is greater than the 5 5 gpm limit.

pech Spec 3.4.4. b RCS]

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 Step 33 m34 i

PERFORMANCt CHECKLIST Page 11 of 12

~

Action EVALUATOR CUE:

FOR SRO CANDIDATES ONLY Give the SRO candidate the second cue sheet that addresses the Tech Spec LCO for RCS Leakage Obtains a copy of the Tech Specs EVALUATOR CUE:

It may be necessary to ask the candidate what additional actions would be required IF the RCS leakage cannot be reduced below 5 gpm Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Determines required actions

Critical Step

Critical Sequence Student Name:

Standard References Tech Spec 3.4.4. b Determines the following actions will be required:

Restore leakage to below 5 gpm Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months If leakage cannot be reduced to below 5 gpm then:

Enter MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.037.051 Step PERFORMANCt CHECKLIST Page 12 of 12 Action Standard Eva1 Comments EVALUATOR CUE:

This completes the JPM.

Student Name:

Critical Step

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

Page I of 1 2004 NRC Exam As Given

SRO ONLY TASK CONDITIONS Unit 1 is in Mode 1 A.

SO-I 00-006 SHIFTLY SURVEILLANCE OPERATING LOG the unidentified RCS Leakage was determined to be 5.8 gpm.

INITIATING CUE What Technical Specifications action(s), including time limits, idare required as a result of this determination?

2004 NRC Exam As Given 1 Of4

-- SRO ONLY TASK CONDITIONS Unit 1 is in Mode 1 A.

SO-I 00-006 SHIFTLY SURVEILLANCE OPERATING LOG the unidentified RCS Leakage was determined to be 5.8 gpm.

INITIATING CUE What Technical Specifications action(s), including time limits, is/are required as a result of this determination?

2004 NRC Exam As Given 2Of4

TASK CONDITIONS

\\--

A.

Unit I is at 100°/~ power. Sometime during the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Drywell sump inleakage began increasing.

B.

It is 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months and time to perform SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOGS C. Total level increases on LWFR-16103 for Sump A are I09 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Total level increases on LWFR-I6103 for Sump B are 99 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E.

Total percent rise in LWFR-16103 fotwarded over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is 268%

INITIATING CUE Your supervisor directs you to Determine RCS leakage by performing the Drywell Floor Drain inleakage calculation IAW with SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG and determine if any Tech Spec limits are being exceeded. Report the results of the calculation and determination to your supervisor.

2004 NRC Exam As Given 3of4

~.

~

~~

TASK CONDITIONS B.

C.

D.

E.

Unit 1 is at 100% power. Sometime during the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Drywell sump inleakage began increasing.

It is 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months and time to perform SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOGS Total level increases on LWFR-16103 for Sump A are 109 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Total level increases on LWFR-16103 for Sump B are 99 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Total percent rise in LWFR-16103 forwarded over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is 268%

INITIATING CUE Your supervisor directs you to Determine RCS leakage by performing the Drywell Floor Drain inleakage calculation IAW with SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG and determine if any Tech Spec limits are being exceeded. Report the results of the calculation and determination to your supervisor.

2004 NRC Exam As Given 4 o f 4

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0

00. S0.003.05 1 0

0211 7104 2.2.12 3.013.4 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Completed By:

Reviews:

Determine Jet Pump Operability Russ Halm Writer Date InstructorNVriter Date Ap prova I:

Requesting Supv.1C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

JPM Performed By:

30 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #lS.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-125A Rev. 2. (9/93)

Page 1 of 1 2004 NRC Exam As Given File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO OO.SO.003.051

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.

5*

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 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 SO-I 00-007 Daily Surveillance Log (Revision 37)

I I I. REACTIVITY MAN1 PU LATl ONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A.

Unit 1 is operating at 100% power.

6. Both Reactor Recirc pumps and Loops are in operation.

C.

The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG.

V. INITIATING CUE Using the data provided on Attachment C PERFORMANCE DATA SHEET complete the remaining items in Attachment C PERFORMANCE DATA SHEET and determine Recirc pump and jet pump operability IAW Item 1 of SO-100-007, DAILY SURVEILLANCE LOG. Report the results of the surveillance to your supervisor.

RECIRCULATION SYSTEM DUAL LOOP of SO-I 00-007, DAILY SURVEILLANCE LOG, RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG VI. TASK STANDARD Recirculation pumps declared OPERABLE; Jet pumps declared INOPERABLE 2004 NRC Exam As Given

/'

Appl. To/JPM No.: OO.SO.003.051 Step I

2 3

4 I' !

PERFORMANkt CHECKLIST

(

Page 3 of 14 Action EVALUATOR NOTE:

0 Provide the candidate with the filled-out Attachment C of SO-I 00-007 (Marked as JPM DATA SHEET 1).

0 The second JPM DATA SHEET will be given to the candidate once the candidate determines that the recirc pumps are NOT within their required flow limits in step 8 of this JPM.

Obtain a controlled copy of SO-I 00-007 Daily Surveillance Log.

Selects the correct section to perform.

To determine Recirc PumpslJet Pumps and Flow Biased Simulated Thermal Power-Upscale (RPS)

OPERABLE, complete applicable attachments If in dual loop operation, complete attachment C for Recirc Pumps and Jet Pumps Refers to Attachment C

%Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Selects Item 1 Determines attachment C is applicable Eva1 Comments STCP-QA-1250 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: OO.SO.003.051 Step

5 i

PERFORMANCt CHECKLIST Page 4 of I 4 Action Recirc pumps operable if loop jet pump flow mismatch maintained within a or b: Enter N/A for item that does not apply.

a. 5 Mlbm/hr with core flow 75 Mlbm/hr

b. I O Mlbm/hr with core flow 5 75 Mlbmlhr

Critical Step

Critical Sequence Student Name:

Standard On Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Compares line g to h Determines that the mismatch between Loop A and Loop B is I Mlbm/hr Records: 1 Mlbm/hr on SR 3.4.1.I line a Records: N/A on SR 3.4.1.I line b Determines Recirc Pumps are operable Circles YES and initials Confirm on SR 3.4.1.I line Records: SAT on Recirc Pumps line of item 1 of SO-100-007 Daily Surveillance Log Attachment A Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCt CHECKLIST lstep 6

i Appl. To/JPM No.: OO.SO.003.051 Action EVALUATOR NOTE:

If any of these conditions exist, or If any parameter differs by than more than 5% of established value, candidate should notify Reactor Engineering.

Notifies Reactor Engineering directly that surveillance parameters differ from established values by more than 5% or notifies SRO to contact Reactor Engineering.

EVALUATOR CUE:

Role-play Reactor Engineering or SRO and acknowledge the report.

Critical Step

Critical Sequence Student Name:

(:

Page 5 of 14 Standard Contacts Reactor Engineering directly Notifies that surveillance parameters differ from established values by more than 5%.

OR Notifies SRO to contact Reactor Engineering.

Eva1

~

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

Page 1 of I 2004 NRC Exam As Given

i PERFORMANCIi CHECKLIST Appl. To/JPM No.: OO.SO.003.051 Step 7

Action When recirc pumps operating with flow within limits of a or b above, jet pumps operable if no two (2) following conditions exist simultaneously:

Recirculation loop drive flow versus recirculation generator speed differs > 10% from established patterns. (Plot applicable performance data on figures 1 and 2 of this attachment)

Critical Step

Critical Sequence Student Name:

('

Page 6 of 14 Standard On Figure 1 RECIRC PUMP A FLOW VS. SPEED TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to a:

RECIRC GENERATOR A SPEED (SI-14032A) Of 87%

AND RECIRC PUMP A FLOW (KGPM) of 38 KGPM On Figure 2 RECIRC PUMP B FLOW VS. SPEED TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to a:

RECIRC GENERATOR B SPEED (SI-14032B) of 88%

AND RECIRC PUMP B FLOW (KGPM) of 33 KGPM Circles YES and initials Confirm on SR 3.4.2.1 line a Eva1 Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: OO.SO.003.051 Step 8

?

PERFORMANCt CHECKLIST

(

Page 7 of 14 Action Recirculation loop drive flow versus total core flow differs > 10% from established patterns. (Plot applicable performance data on Figures 3 and 4 of this attachment)

EVALUATOR NOTE:

Perform only if a or b above fail. Record applicable data on pages 3 and 4 of this attachment

Critical Step

Critical Sequence Student Name:

Standard On Figure 3 TOTAL CORE FLOW VS.

RECIRC PUMP A FLOW TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to a:

RECIRC PUMP A FLOW (KGPM) (FR-831-lR614) Of 38 KGPM AND TOTAL CORE FLOW MLB/HR of 92 MLB/HR On Figure 4 TOTAL CORE FLOW VS.

RECIRC PUMP B FLOW TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to a:

RECIRC PUMP A FLOW (KGPM) (FR-831-1R614) Of 33 KGPM AND TOTAL CORE FLOW MLB/HR of 92 MLB/HR Circles NO and initials Confirm on SR 3.4.2.1 line b Eva1 Comments STCP-QA-1 25B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM NO.: 1 Action c

Standard Eva1 Comments SO.OO3.051 i

PERFORMANCt CHECKLIST

(,

Page 8 of 14 Student Name:

I I

I EVALUATOR CUE:

Provide the candidate with the filled-out Attachment C Of SO-I 00-007.

(Marked as JPM DATA SHEET 2)

Critical Step

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMAN& CHECKLIST Appl. To/JPM No.: OO.SO.003.051 Step 9

Action Calculates LOOP A JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE to be used in Plotting applicable performance data on figure I of attachment I

%Critical Step

Critical Sequence I:'

Page 9 of 14 Student Name:

Standard Records the following data on Attachment C LOOP A JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE:

1. JPI 1_34-(JPI 1 - A) + A X 100 =--.87-

2. JP12_35-(JP12 -A) + A X 100 =-2.04-

3. JP13_34-(JPl3 -A) + A X 100 --.87-

4. JP14_35_(JP14 - A) + A X 100 =-2.04-

5. JPl5_35_(JPl5 - A) + A X I00 =-2.04-

6. JP16_35_(JP16 -A) f A X 100 =-2.04-

7. JP17_34-(JP17 - A) + A X 100 =--.87-

8. JP18_34-(JP18 - A) + A X 100 =--.87-

9. JP19_35-(JPl9 - A) f A X 100 =-2.04-I O. JP20_32-(JP20 - A) + A X I00 =--6.71-A =-343 X 0.1 = -34.3-(Sum of AP%)

JP11 thru 20 Eva1 Comments STCP-QA-125B Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST 10 Appl. To/JPM No.: OO.SO.003.051 Calculates LOOP B JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE to be used in Plotting applicable performance data on figure 2 of attachment I Step I Action

Critical Step

Critical Sequence

(

Page 10 of 14 Student Name:

Standard Records the following data on Attachment C LOOP B JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE:

1.

2.

3.

4.

5.

6.

7.

8.

9.

I O. JPIO-38-(JPIO - A) f A X 100 =-.53-JP1_39-(JPI -A) f A X lOO=-3.17-JP2_3Q-(JP2 - A) f A X 100 =-3.17-JP3_37-(JP3 -A) f A X 100 =--2.12-JP4_39-(JP4 -A) f A X 100 =-3.17_

JP5_39-(JP5 -A) f A X 100 =-3.17-JP6_39-(JP6 -A) f A X 100 =-3.17-JP7_3O_(JP7 - A) f A X 100 =--20.63-JP8_39_(JP8 -A) + A X 100 =-3.17-JP9_3Q_(JP9 - A) + A X 100 =-3.17-A =-378 X 0.1 = -37.8-(Sum of AP%)

JPI thru I O Eva1 Comments STCPQA-125B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: OO.SO.003.051 Step I 1 I:'

PERFORMANC t CHECKLIST

(

Page 11 of 14 Action Each jet pump to lower plenum differential pressure differs by > 20% from the established patterns, (Plot applicable performance data on figures I and 2 of attachment I

Critical Step

Critical Sequence Student Name:

Standard On Figure 1 TWO LOOP JET PUMP DISTRIBUTION LOOP A of ATTACHMENT I Plots the following points:

JPI 1 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP12 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP13 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP14 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP15 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP16 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP17 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP18 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP19 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP20 and -6.71 % DEVIATION FROM THE MEAN DELTA P VALUE Determines that all points are within 220% from the established patterns Eva1 Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: OO.SO.003.051 Step 12

=

i PERFORMANCt CHECKLIST

(

Page 12 of 14 Action

Critical Step

Critical Sequence Student Name:

Standard On Figure 2 TWO LOOP JET PUMP DISTRIBUTION LOOP B of ATTACHMENT I Plots the following points:

JPI and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP2 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP3 and -2.12 % DEVIATION FROM THE MEAN DELTA P VALUE JP4 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP5 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP6 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP7 and -20.63 % DEVIATION FROM THE MEAN DELTA P VALUE JP8 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP9 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPIO and.53 % DEVIATION FROM THE MEAN DELTA P VALUE Determines that jet pump 7 is NOT within 220% from the established patterns Circles YES and initials Confirm on SR 3.4.2.1 line c Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

i' PERFORMAN& CHECKLIST Step

+ic 13

(,

Page 13 of 14 Action When recirc pumps operating with flow within limits of a or b above, jet pumps operable if no two (2) following conditions exist simultaneously:

Appl. To/JPM No.: OO.SO.003.051

Critical Step

Critical Sequence Student Name:

Standard Determines Jet pumps are NOT operable based on two (2) of the conditions under SR 3.4.2.1 not being met simultaneously.

Circles NO and initials Confirm on SR 3.4.2.1 Records: UNSAT on Jet Pumps line of item 1 of SO-100-007 Daily Surveillance Log Attachment A Eva1 Comments STCP-QA-1256 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

i i

Appl. To/JPM No.: OO.SO.003.051 Step

I4 PERFORMANCE CHECKLIST Action Reports the results of the surveillance.

EVALUATOR CUE:

Role-play shift supervision and acknowledge the report.

EVALUATOR CUE:

That completes this JPM

Critical Step

Critical Sequence

(

Page 14 of 14 Student Name:

Standard Informs the supervisor that the Jet pumps are not operable due to:

The plot of RECIRC GENERATOR B SPEED vs.

RECIRC PUMP B FLOW Is outside the maximum allowable 10%

band AND The plot of:

JP7 VS. % DEVIATION FROM THE MEAN DELTA P VALUE Is outside the maximum allowable 20%

band.

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

Page 1 of 1 2004 NRC Exam As Given

TASK CONDITIONS A.

Unit I is operating at 100% power.

B.

Both Reactor Recirc pumps and Loops are in operation.

C.

The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-1 00-007, DAILY SURVEILLANCE LOG.

INITIATING CUE Using the data provided on Attachment C PERFORMANCE DATA SHEET complete the remaining items in Attachment C PERFORMANCE DATA SHEET and determine Recirc pump and jet pump operability IAW Item 1 of SO-100-007, DAILY SURVEILLANCE LOG. Report the results of the surveillance to your supervisor.

RECIRCULATION SYSTEM DUAL LOOP Of SO-1 00-007, DAILY SURVEILLANCE LOG, RECIRCULATION SYSTEM DUAL LOOP Of SO-1 00-007, DAILY SURVEILLANCE LOG

,\\.-

2004 NRC Exam As Given 1 of2

TASK CONDITIONS A.

Unit 1 is operating at 100% power.

B. Both Reactor Recirc pumps and Loops are in operation.

C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C PERFORMANCE DATA SHEET C

RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG.

INITIATING CUE Using the data provided on Attachment C PERFORMANCE DATA SHEET complete the remaining items in Attachment C PERFORMANCE DATA SHEET and determine Recirc pump and jet pump operability IAW Item 1 of SO-100-007, DAILY SURVEILLANCE LOG. Report the results of the surveillance to your supervisor.

RECIRCULATION SYSTEM DUAL LOOP Of SO-1 00-007, DAILY SURVEILLANCE LOG, RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG 2004 NRC Exam As Given 2 o f 2

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

00. AD.269.00 1 0

03/02/04 2.3. I O 2.913.3 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Identify The Blocking Points For A Primary Containment Entry While At PowerlAdditional power restrictionslcontrols required by NDAP-QA-0309, Primary Containment Access And Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Date Ap p rova I:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

C' JPM Performed By:

25/30 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance

(

)

Satisfactory

(

)

Unsatisfactory Evaluation:

Evaluator Name:

Signatu re Typed or Printed Comments:

v STCP-QA-125A Rev. 2, (9/93)

Page 1 of 1 2004 NRC Exam As Given File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 00.AD.269.001

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.

11.

REFERENCES NDAP-QA-0323, Standard Blocking Practices (Revision 21 )

NDAP-QA-0309, Primary Containment Access And Control (Revision 14)

NDAP-QA-0322, Energy Control Process (Rev. 15)

I II. REACTIVITY MAN1 PULATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A. Unit 1 is performing a plant startup.

B. Reactor power is 10%

C. Both reactor recirc pumps are in operation at minimum speed D. A chilled water leak exists at the inlet flange to Reactor Recirc Pump 1A motor winding chilled water flow transmitter FISL-B31-1 N008A.

E. A Primary Containment entry is being planned to repair this leak.

F. Containment has NOT been inerted.

G. The entry will be limited to elevations 704 and 719 only.

H. NDAP-QA-0309, Primary Containment Access And Control is being used to control this entry.

I. Step 6 of Attachment Q Primary Containment Initial Entry Checklist - Modes 1 Or 2 of NDAP-QA-0309, Primary Containment Access And Control requires the necessary blocking points to be applied in support of this entry.

V. INITIATING CUE Your supervisor directs you to prepare a Containment Entry clearance order, IAW NDAP-QA-0309, Primary Containment Access And Control, to support this primary containment entry at Unit 1.

In addition to the Containment entry Blocking points, identify the chilled water valve blocking points necessary to repair this leak. Be sure to include the required position and type of tag that will be applied. (Use the attached sheet to document your blocking points).

2004 NRC Exam As Given

VI. TASK STANDARD The Critical components listed in the answer key are in the stated position with the stated type tag identified. SROs identify additional power restrictionskontrols required by NDAP-QA-0309, Primary Containment Access And Control

\\-

2004 NRC Exam AS Given

Appl. TolJPM No.: 00.AD.269.001

{

PERFORMANCE CHECKLIST Page 4 of 10 Action EVALUATOR NOTE:

0 Candidate may refer to NDAP-QA-0309, Primary Containment Access And Control to locate the step referenced in the initiating cue.

Obtain a controlled copy of NDAP-QA-0323, Standard Blocking Practices Selects the correct section to perform.

Using the table in NDAP-QA-0323, Standard Blocking Practices section 8.8.1 identifies the required blocking points, positions, and type of tag to be used.

(steps 3 - 10 of this JPM)

Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Selects section 8.8.1 Identifies the need to:

Ensure all tips withdrawn to IN SHIELD position with ball valves closed prior to applying blocking.

Position N/A No tag required Records on attached form Identifies the need to OPEN breaker 1Y21927 Tip Drive Mechanisms 1 S215A-E and RED TAG Records on attached form Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.269.001 E

5 3k6 7

PERFORMANCE CHECKLIST Page 5 of 10

%ritical Step Action

Critical Seq uence Student Name:

Standard Identifies the need to install a spectacle flange at 1 S2104 N2 Purge Line To U I Containment and RED TAG Records on attached form Identifies the need to CLOSE valve 157026 Contn N2 Makeup Supply Hdr Is0 Vlv and RED TAG Records on attached form Identifies the need to:

Notify HP At X3371 When Drywell Access Door Lock Is Unlocked/Removed And When Re-lnstalled/Locked NO TAG required Records on attached form Eva1 Comments t

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

Page 1 of 1 2004 NRC Exam As Given

i Action r

Standard Eva1 Identifies the need to track the status of Appl. To/JPM No.: 00.AD.269.001 Step 8

9 PERFORMANCE CHECKLIST EVALUATOR NOTE:

The next two items will be required since the reactor is at 10% power.

Student Name:

the OPS VERY HIGH Rad Door Lock, Drywell Access Door, To Ensure Relocked When Clearance Removed.

NO TAG required Records on attached form Identifies the need to:

Apply A Cover Over Control Rod CONT INSERT ROD AND CONT W/DRAW Pushbuttons On 1 C651 To Prevent Rod Movement And PINK TAG Records on attached form

Critical Step

{

Page 6 of 10 Comments

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

Page 1 of 1 2004 NRC Exam As Given

i

\\

Appl. To/JPM No.: 00.AD.269.001 Step

I O

/

PERFORMANCt CHECKLIST

(

Page 7 of 10 Action EVALUATOR NOTE:

Candidate may reference NDAP-QA-0322, ENERGY CONTROL PROCESS, and NDAP-QA-0323, STANDARD BLOCK1 NG PRACTICES, before determining what chilled water valves will need to be addressed.

If candidate chooses blocking points other than 143001A and 143002A, these will need to be evaluated for acceptability.

EVALUATOR NOTE:

Drawing is M-143 sheet 2; grid location is C-7.

Critical Step

Critical Sequence Student Name:

Standard Identifies the need to:

Apply A Cover Over Control Rod INSERT ROD AND W/DRAW ROD Pushbuttons On 1 C651 To Prevent Rod Movement And PINK TAG Records on attached form Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.269.001 Step

I 1

12 13 i:

PERFORMANCE CHECKLIST Page 8 of 10 Action Use mechanical drawing to identify chilled water valves EVALUATOR NOTE:

Maintenance will deal with the draining of the fluid, therefore it is NOT required to open valve 143-F066A and remove the blind flange.

EVALUATOR CUE:

That completes this JPM FOR the RO candidates EVALUATOR CUE:

FOR SRO CANDIDATES ONLY Give the SRO candidate the second cue sheet that addresses additional power restrictionskontrols.

Obtain a controlled copy of NDAP-QA-0309, Primary Containment Access And Control References appropriate section

Critical Step

Critical Sequence Student Name:

Standard Using M-143 Sht.2, determines the following:

Valves 143001A CLOSED Red Tagged 143002A CLOSED Red Tagged Controlled copy obtained.

References section 6.5 Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Appl. To/JPM No.: 00.AD.269.001 Step

I4

%I5 Action EVALUATOR NOTE:

Due to the nature of the initiating cue, it is acceptable for the candidate to paraphrase the responses.

For entries at power, a Reactor Operator shall be stationed at the reactor console to monitor reactor power while personnel are in the drywell. Upon observing any unexpected power increase, the operator shall immediately place the reactor mode switch in shutdown and notify the drywell entry personnel.

Initially, primary containment entries are limited to 10% power for elevations 704 and 71 9 and 3%

power for elevation 738 and above. Entries at power levels higher than 10% shall be allowed only after sufficient radiological information has been obtained as determined by the Radiation Protection Manager.

Critical Step

Critical Sequence

(

Page 9 of 10 Student Name:

Standard Reports to the Shift Manager the following:

A Reactor Operator shall be stationed at the reactor console to monitor reactor power while personnel are in the drywell.

Upon observing any unexpected power increase, the operator shall immediately place the reactor mode switch in shutdown and notify the drywell entry personnel.

Reports to the Shift Manager the following:

Reactor power is restricted to 10% for this entry Eva1 Comments STCP-QA-1256 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Page 10 of 10 Appl. To/JPM No.: 00.AD.269.001 Step

I6

I7 18 Action No action shall be taken to change Reactor power levels (e.g., no control rod movements, steady recirc pump speed, steady EHC pressure setpoints, etc.)

during power entries.

If some action is necessary to control Reactor Power (e.g., control rod movement, recirc pump speed or EHC pressure setpoint change), confirm with containment Health Physics Supervision that all individuals have exited the drywell before implementing the action.

Following any rod position changes, provide Health Physics with a new Attachment S or OD-7 printout to identify the changes.

EVALUATOR CUE:

That completes this JPM.

Critical Step

Critical Sequence Student Name:

Standard Reports to the Shift Manager the following:

No action shall be taken to change Reactor power levels Reports to the Shift Manager the following:

If some action is necessary to control Reactor Power (e.g., control rod movement, recirc pump speed or EHC pressure setpoint change), confirm with containment Health Physics Supervision that all individuals have exited the drywell before implementing the action.

Reports to the Shift Manager the following:

Following any rod position changes, provide Health Physics with a new Attachment S or OD-7 printout to identify the changes.

Eva1 Comments STCPUA-125B Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

SRO ONLY TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Reactor power is 10%

Both reactor recirc pumps are in operation at minimum speed A chilled water leak exists at the inlet flange to Reactor Recirc Pump 1A motor winding chilled water flow transmitter FISL-B31-1 N008A.

A Primary Containment entry is being planned to repair this leak.

Containment has NOT been inerted.

The entry will be limited to elevations 704 and 71 9 only.

NDAP-QA-0309, Primary Containment Access And Control is being used to control this entry.

Step 6 of Attachment Q Primary Containment Initial Entry Checklist - Modes 1 Or 2 of NDAP-QA-0309, Primary Containment Access And Control requires the necessary blocking points to be applied in support of this entry.

INITIATING CUE As the Unit Supervisor, what additional power restrictions/controls are you required to implement, per NDAP-QA-0309, Primary Containment Access And Control, during this entry. Report these additional power restrictionslcontrols to the Shift Manager.

2004 NRC Exam As Given 1 of6

i-- SRO ONLY TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Reactor power is 10%

Both reactor recirc pumps are in operation at minimum speed A chilled water leak exists at the inlet flange to Reactor Recirc Pump 1A motor winding chilled water flow transmitter FISL-B31-1 N008A.

A Primary Containment entry is being planned to repair this leak.

Containment has NOT been inerted.

The entry will be limited to elevations 704 and 71 9 only.

NDAP-QA-0309, Primary Containment Access And Control is being used to control this entry.

Step 6 of Attachment Q Primary Containment Initial Entry Checklist - Modes I Or 2 of NDAP-QA-0309, Primary Containment Access And Control requires the necessary blocking points to be applied in support of this entry.

INITIATING CUE As the Unit Supervisor, what additional power restrictionskontrols are you required to implement, per NDAP-QA-0309, Primary Containment Access And Control, during this entry. Report these additional power restrictionskontrols to the Shift Manager.

2004 NRC Exam As Given 2 o f 6

TASK CONDITIONS

-v A.

B.

Reactor power is 10%

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Both reactor recirc pumps are in operation at minimum speed A chilled water leak exists at the inlet flange to Reactor Recirc Pump 1A motor winding chilled water flow transmitter FISL-B31-1 N008A.

A Primary Containment entry is being planned to repair this leak.

Containment has NOT been inerted.

The entry will be limited to elevations 704 and 719 only.

NDAP-QA-0309, Primary Containment Access And Control is being used to control this entry.

Step 6 of Attachment Q Primary Containment Initial Entry Checklist - Modes 1 Or 2 of NDAP-QA-0309, Primary Containment Access And Control requires the necessary blocking points to be applied in support of this entry.

INITIATING CUE Your supervisor directs you to prepare a Containment Entry clearance order, IAW NDAP-QA-0309, Primary Containment Access And Control, to support this primary containment entry at Unit 1.

In addition to the Containment entry Blocking points, identify the chilled water valve blocking points necessary to repair this leak. Be sure to include the required position and type of tag that will be applied. (Use the attached sheet to document your blocking points).

c-2004 NRC Exam As Given 3 o f 6

TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Reactor power is 10%

Both reactor recirc pumps are in operation at minimum speed A chilled water leak exists at the inlet flange to Reactor Recirc Pump 1A motor winding chilled water flow transmitter FISL-B31-1 N008A.

A Primary Containment entry is being planned to repair this leak.

containment has NOT been inerted.

The entry will be limited to elevations 704' and 719' only.

NDAP-QA-0309, Primary Containment Access And Control is being used to control this entry.

Step 6 of Attachment Q Primary Containment Initial Entry Checklist - Modes 1 Or 2 of NDAP-QA-0309, Primary Containment Access And Control requires the necessary blocking points to be applied in support of this entry.

INITIATING CUE Your supervisor directs you to prepare a Containment Entry clearance order, IAW NDAP-QA-0309, Primary Containment Access And Control, to support this primary containment entry at Unit 1.

In addition to the Containment entry Blocking points, identify the chilled water valve blocking points necessary to repair this leak. Be sure to include the required position and type of tag that will be applied. (Use the attached sheet to document your blocking points).

2004 NRC Exam As Given 4 o f 6

ANSWER KEY DO NOT GIVE TO CAN DI DATES (JPM 00.AD.269.001)

Critical components are identified with an asterisk ($)

COMPONENT ID

1 Y21927

IS2104

1 57026 DRYWELL ACCESS DOOR 143001A 143002A NAME ENSURE ALL TIPS WITHDRAWN TO IN SHIELD POSITION WITH BALL VALVES CLOSED PRIOR TO APPLYING BLOCKING.

TIP DRIVE MECHANISMS 1 S215A-E N2 PURGE LINE TO U1 CONTAINMENT SPECTACLE FLANGE CONTN N2 MAKEUP SUPPLY HDR IS0 VLV OPERATIONS TO NOTIFY HP AT X3371 WHEN DOOR LOCK IS UNLOCKED/REMOVED AND WHEN RE-INSTALLED/LOCKED OPS VERY HIGH RAD DOOR LOCK, DRYWELL ACCESS DOOR, TRACKED TO ENSURE RELOCKED WHEN CLEARANCE REMOVED.

APPLY COVER OVER CONTROL ROD CONT INSERT ROD AND CONT W/DRAW PUSHBUTTONS ON IC651 TO PREVENT ROD MOVEMENT IAW NDAP-QA-0309 APPLY COVER OVER CONTROL ROD INSERT ROD AND W/DRAW ROD PUSHBUTTONS ON IC651 TO PREVENT ROD MOVEMENT IAW NDAP-QA-0309 CHILLED WATER FISL-B31-1 N008A INLET CHILLED WTR FISL-B31-1N008A OUTLET POSITION NA OPEN BLANKED CLOSE N/A N/A NIA NIA CLOSED CLOSED TAG NO TAG RED TAG RED TAG

~

RED TAG NO TAG NO TAG PINK TAG PINK TAG RED TAG RED TAG 2004 NRC Exam As Given 5 of 6

CANDIDATE COPY (J PM 00.AD.269.001)

POSITION COMPONENT I ID NAME 2004 NRC Exam As Given 6 of 6 TAG

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 99.0P.002.001 0

03/0 I

/04

2. I

.25 2.8/3.1 Appl. To JPM Number Rev. No.

Date NUREG I123 Sys. No.

WA Task

Title:

Respond to Seismic Monitor System Triggered Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Date Ap prova I:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

JPM Performed By:

-v-15 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:

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

Page 1 of 1 2004 NRC Exam As Given File No. Al4-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 99.0P.002.001

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.

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 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

1. AR-016-001, Seismic Mon System Triggered (G06) (Revision 35)

2. OP-099-002, Seismic Monitoring System (Revision 11)

3. ON-000-002, Natural Phenomena (Revision 17)

4. EP-PS-100, Emergency Director Control Room, REV. 18 I1 I. REACTIVITY MAN1 PU LATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A. Both Units are operating at 100% power.

B. AR-016-GO6, Seismic Mon System Triggered Alarm has been received.

C. The printout of channel information has been obtained D. There is NO ongoing work in either Rx Building basements (Elev. 645) OR in the ESW pumphouse.

E. Ground motion can be felt in the control room.

V. INITIATING CUE You are the Shift Manager.

Given the following Channel 1 Seismic Monitor printer information and panel indicating light status:

EvaluateNalidate the event trigger IAW appropriate procedure, and REPORT any required actions (Base the evaluation/validation on Channel 1 ONLY) to the evaluator.

VI. TASK STANDARD Determines:

1. The Seismic event trigger to be valid at the SSE level

2. Both Units will require shutdowns

3. Classifies the event as an Alert Emergency

\\=...

2004 NRC Exam As Given

/

PERFORMANCt CHECKLIST Appl. TolJPM No.: 99.0P.002.001 Step Action EVALUATOR NOTE:

0 Provide the candidate with seismic monitor printout and the panel indicating light status.

EVALUATOR NOTE:

Candidate may refer to the Alarm response procedure first, before referring to OP-099-002, Seismic Monitoring System. This is acceptable.

Obtain a controlled copy of OP-099-002 Seismic Monitoring System Selects the correct section to perform.

Review the prerequisites.

EVALUATOR CUE:

If necessary, Remind the candidate that the evaluation is to be limited to channel I ONLY.

Review all precautions.

Critical Step

Critical Sequence Student Name:

~

Standard Controlled copy obtained.

Selects section 3.2 Ensures all prerequisites have been met.

Follows all precautions as applicable.

Page 3 of 8 Comments STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

i i'

PERFORMANCt CHECKLIST Appl. To/JPM No.: 99.0P.002.001 Student Name:

Step

5 6

Critical Step (1,

Page 4 of 8 Action Standard I Eva1 Comments REVIEW printer output and panel indicating lights to determine type of event.

Use Attachment A and B to classify and validate the trigger.

Attachment C provides example printouts for further assistance.

Compares the Seismic Monitor printer information and panel indicating light status Attachments A, B, and C Determines that a Safe Shutdown Earthquake (SSE) has occurred CONTACT one of the agencies in Attachment D to confirm the cause of the event was seismic activity.

Simulates contacting one of the following agencies:

0 National Earthquake Information Center Golden, Colorado 0

PA Bureau of Topographic &

Geologic Survey 0

Penn State University (PSU)

Geosciences Office 0

University of Delaware 0

Delaware Geological Survey Columbia University

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 99.0P.002.001 Step PERFORMANCE CHECKLIST Action

{"

EVALUATOR CUE:

Role-play the contacted agency, and inform the candidate:

There is confirmed seismic activity along the East coast of the United States from South Carolina to New York.

If cause of the event was seismic activity, perform ON-000-002, Natural Phenomena in parallel with this section.

EVALUATOR CUE:

Role-play shift supervision and inform the candidate that another operator will complete the remaining steps of OP-099-002. You are to perform the appropriate steps of ON-000-002 Natural Phenomena.

Obtain a controlled copy of ON-000-002 Natural Phenomena

%Critical Step

Critical Sequence Student Name:

r' Page 5 of 8 Standard Determines that ON-000-002 Natural Phenomena performance will be required in parallel with completing this procedure.

Controlled copy obtained.

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 99.0P.002.001 Step 9

10 11 PERFORMANCt CHECKLIST Page 6 of 8 Action Record date and time of event.

Notify Security of event.

EVALUATOR CUE:

Role-play Plant Security and acknowledge the report.

Based on event occurrence, Perform following as applicable:

IF seismic triggering event occurred, Perform section 3.7 EVALUATOR NOTE:

Earthquakes of this magnitude are expected to be felt by personnel. Building vibration and rattling of objects is typical.

Critical Step

Critical Sequence STCPUA-1PSB Rev. 2 (9/93)

Page I of I 2004 NRC Exam As Given Student Name:

Standard Has shift supervision authorize the use of this procedure by signing the appropriate space provided in the procedure.

Records; Date and time in the space provided Simulates a call to Plant security.

Refers to section 3.7 Eva1 Comments

!/

Appl. To/JPM No.: 99.0P.002.001 Step

I2 13 14 15 PERFORMANCt CHECKLIST Action EVALUATOR NOTE:

Due to the nature of the JPM it may be necessary to ask the candidate to verbalize hidher intentions with regard to the plant status in the next step IF OBE SSE earthquake occurred:

Commence shutdown in accordance with GO-I 00-004 (GO-200-004), Plant Shutdown to Minimum Power.

Classify Plant status in accordance with EP-PS-100, Emergency Director, Control Room.

Evaluates information.

EVALUATOR NOTE:

An SSE is a greater magnitude than an OBE.

Refers to classification matrix.

Critical Step

Critical Sequence Student Name:

Standard Determines both Units need to be shutdown in accordance with GO-I 00-004 (GO-200-004),

Plant Shutdown to Minimum Power.

Directs control room crew to make preparations to begin shutdown of both Units Controlled copy obtained.

Identifies SSE as Emergency Plan entry.

Selects OA3.

Eva1 i

Page 7 of 8 Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

APP To/JPR Step 16

I7

).: 99.0P.002.001 i"

PERFORMAN& CHECKLIST Action Reviews the table of contents for Natural Phenomena.

Choose appropriate emergency action level.

EVALUATOR CUE:

That completes this JPM

++Critical Step

Critical Sequence

(:,'

Page 8 of 8 Student Name

~~

Standard Reviews all of Category OA3.

Identifies entry into OA3 EAL Threshold value 1 Earthquake at or greater than OBE levels.

Classifies the event as a Alert

~

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

Page 1 of 1 2004 NRC Exam As Given

TASK A.

B.

C.

D.

L--

E.

CONDITIONS Both Units are operating at 100% power.

AR-016-GO6, Seismic Mon System Triggered Alarm has been received.

The printout of channel information has been obtained There is NO ongoing work in either Rx Building basements (Elev. 645) OR in the ESW pumphouse.

Ground motion can be felt in the control room.

V. INITIATING CUE You are the shift manager.

Given the following Channel 1 Seismic Monitor printer information and panel indicating light status:

EvaluateNalidate the event trigger IAW appropriate procedure, and REPORT any required actions (Base the evaluation/validation on Channel 1 ONLY) to the evaluator.

2004 NRC Exam As Given 1 O f 3

TASK A.

B.

C.

D.

E.

CONDITIONS Both Units are operating at 100% power.

AR-016-GO6, Seismic Mon System Triggered Alarm has been received.

The printout of channel information has been obtained There is NO ongoing work in either Rx Building basements (Elev. 645) OR in the ESW pumphouse.

Ground motion can be felt in the control room.

V. INITIATING CUE You are the shift manager.

Given the following Channel 1 Seismic Monitor printer information and panel indicating light status:

EvaluateNalidate the event trigger IAW appropriate procedure, and REPORT any required actions (Base the evaluation/validation on Channel 1 ONLY) to the evaluator.

2004 NRC Exam As Given 2 of 3

SEISMIC MONITOR PANEL INDICATING LIGHT STATUS (JPM 99.0P.002.001)

VRS-05703 Status Strong Motion Accelerograph System Trigger RSA-50 Data light Cassette Tapes VAH-15701 and VAH-05701 OBE Lights VAH-I5701 and VAH-05701 SSE Lights Inner Analog Light Outer Analog Light 2004 NRC Exam As Given 3 of 3 Red Green Was Red for approximately 15 seconds, NOW it is OFF Recorded for approximately 15

seconds, Now they are idle.

Green Green Red

=---

SRO Appl. To PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 00.AD.268.001 0

07/26/04 2.2.22 3.414.1 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Determine required Tech Spec actions for Single loop operations, including any additional actions or surveillances required for increasing power during single loop operation.

Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Approval:

Requesting Su pv.1C.A.

Date Nuclear Trng. Supv.

Head Date Date Date of Performance:

JPM Performed By:

25 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance

(

)

Satisfactory

(

) Unsatisfactory Eva I uat ion :

Evaluator Name:

Sig nature Typed or Printed Comments:

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

Page 1 of 1 2004 NRC Exam As Given File No. A14-58

1.

II.

111.

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO OO.AD.268.001 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:

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.

REFERENCES Tech Specs 3.4.1 Recirc Loops operating (Amend 178) 3.2.1 APLHGR (Amend 178) 3.2.2 MCPR (Amend 178) 3.2.3 LHGR (Amend 178) 3.3.1.1 Instrumentation (Amend 178) 3.4.1 0 RCS Pressure Temperature Limits (Amend 178)

ON-164-002, Loss Of Reactor Recirculation Flow (Rev. 20)

GO-100-009, Single Recirculation Loop Operation (Rev. 14)

NDAP-QA-0338 Attachment C (Rev. 6)

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

NONE IV. TASK CONDITIONS A. Unit I was performing a power ascension following a refueling outage with Reactor power at - 49% when the 1A Reactor Recic pump tripped.

B. The 1A Reactor Recirc Pump is not isolated and has been declared NOT in Operation IAW Technical Specifications.

C. Maintenance has determined the problem is with the ?A Recirc MG set and it will take a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to repair the problem.

D. Direction has been given to raise reactor power while the I A Recirc MG is being repaired.

E. The following plant conditions exist:

2004 NRC Exam As Given

V. INITIATING CUE Review and complete as required, ON-164-002, LOSS OF REACTOR RECIRCULATION FLOW.

Report to the Shift Manager if Reactor Power can be raised and the Tech Spec actions and or surveillances that will be required to support the present plant conditions and the intended power increase.

VI. TASK STANDARD All Tech Spec required actions identified and reported to the Shift Manager.

2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.268.001 Step I

2 i'

i PERFORMANCE CHECKLIST Page 3 of 13 Action EVALUATOR CUE:

Provide the candidate a copy of ON-164-002.

Record Date and Time of event.

IF both Recirculation Pumps trip, Immediately Scram reactor.

EVALUATOR NOTE:

WHEN operating recirculation pump speed is <75%

rated speed (1260 rpm), Core Pressure Drop (Le.,

Core Plate DP) is used to determine actual core flow due to inaccuracies associated with indicated core flow.

EVALUATOR CUE:

Provide the candidate with GO-100-009, Single Recirculation Loop Operation (Rev. 14) when candidate indicates the need for this procedure in the next step.

Critical Step

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

Page 1 of 1 2004 NRC Exam As Given Student Name:

Standard Records:

Today's date and time Determines from initial conditions that ONLY 1 pump tripped and Reactor Scram is not warranted.

Eva1 Comments

Appl. To/JPM No.: 00.AD.268.001 Step i:

i PERFORMANCt CHECKLIST Page 4 of 13 Action IF one Reactor Recirculation Pump trips:

IF operating recirculation pump speed is <75% rated speed ( I 260 rpm), Determine actual core flow by (else N/A):

Display Core Pressure Drop via PlCSY computer point NJP51 - Core PL Press OR if PlCSY unavailable via XR-621-1R613, Blue Pen: Core Plate DP.

Determine actual core flow using Form GO-100-009-2 Core Flow vs. Core Pressure Drop curve.

EVALUATOR CUE:

Provide the candidate with Power/Flow Map, Form NDAP-QA-0338-10 (Attachment C) for use in the next step.

Plot position on Power/Flow Map, Form NDAP-QA-0338-10.

IF Power/Flow Map indicates operation in Region 1 OR Core Flow is < the Natural Recirculation Line or operations in any region not bounded by Power/Flow map, Place MODE SWITCH to SHUTDOWN.

+Critical Step

Critical Sequence STCP-CLA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given Student Name:

Standard Determines actual core flow via PlCSY computer point using Form GO-I 00-009-2 Core Flow vs. Core Pressure Drop curve is -44 mlb/hr Plot position on Power/Flow Map, Form NDAP-QA-0338-10, Determines:

outside region I and II AND below the 70% rod line.

Based on plot from previous step Determines:

N/A Eva1 Comments

i Appl. To/JPM No.: 00.AD.268.001 6

7

(

PERFORMANCt CHECKLIST i

Page 5 of 13 Action

~~

~

Ensure thermal power REDUCED to <70% rod line.

Reduce operating pump speed to 80% rated pump speed (80% = 1344 rpm) in accordance with OP-I 64-001.

EVALUATOR NOTE:

It is not intended to have the candidate actually verify the thermal power limits in the next step. This would require additional data and additional evaluations that would be supported by reactor engineering. It is only necessary to identify the need to VERIFY these limits within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to meet the Critical portion of the step.

4Critical Step

Critical Sequence Student Name:

Standard Based on plot from previous step Determines:

N/A Based on pla from previous step Determines:

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

Page 1 of 1 2004 NRC Exam As Given

i pG f 8 Appl. To/JPM No.: 00.AD.268.001 PERFORMANCE CHECKLIST Action

~

Comply with COLR Section 8.0 Limits in TRM.

Comply with Tech Spec LCOs 3.4.1 EVALUATOR CUE:

Role play as required and report the core thermal limits are met.

Role play as required and report the Flow Biased Simulated Thermal Power-High allowable value of table 3.3.1.1-1 is reset for single loop operation.

Critical Step

Critical Sequence Student Name:

i Page 6 of 13 Standard Determines Tech Spec 3.4.1 required actions within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:

Verify the following core thermal power limits within the limits specified in the COLR.

LCO 3.2.1 APLHGR LCO 3.2.2 MCPR LCO 3.2.3 LHGR Verify LCO 3.3.1.1 RPS instrumentation function 2.b Flow Biased Simulated Thermal Power-High allowable value of table 3.3.1.I-1 is reset for single loop operation.

Recirculation Speed is < or equal to 80%.

Declare A Recirc Loop not in operation Reports this to the Shift manager.

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

Page 1 of 1 2004 NRC Exam As Given

r' Appl. To/JPM No.: 00.AD.268.001 Step 9

I O

(

PERFORMANCt CHECKLIST Page 7 of 13 Action For stopped pump, Place RECIRC A(B) MOV OL BYPS HV-143-F031A(B)/F032A(B) key switch to TEST position.

Ensure RECIRC PUMP A(B) DSCH BYPS Close RECIRC PUMP A(B) DSCH HV-143-F031A(B).

Within 5 minutes, Open RECIRC PUMP A(B) DSCH AFTER 2 minutes, Place RECIRC A(B) MOV OL BYPS HV-I 43-F031 A(B)/F032A(B) key switch to NORM position.

Prior to restart of pump, Notify Duty Reactor Engineer to perform an evaluation of core thermal limits and preconditioning.

HV-143-F032A(B) OPEN.

HV-143-F031A( B).

EVALUATOR CUE:

Due to the nature of this JPM (being an ADMIN JPM),

once the candidate indicates intentions to perform these steps Provide a CUE to the candidate that these steps have been completed.

WHEN cause of trip corrected, Restart Reactor Recirculation Pump in accordance with OP-I 64-001 Reactor Recirculation System.

mCritical Step

Critical Sequence Student Name:

Standard See CUE Based on initial conditions, this will occur later.

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.268.001 i'

PERFORMANCE CHECKLIST

/,:,

Page 8 of 13 Action IF pump will be out of service >I hour, Comply with GO-I 00-009 Single Recirculation Loop Operation.

EVALUATOR NOTE:

GO-1 00-009 Single Recirculation Loop Operation was previously provided to determine core flow based on D/P.

Obtains a controlled copy of GO-I 00-009 Reviews prerequisites, precautions and initial conditions.

Complete the following:

Date:

Time:

This GO is being performed for the following reason:

Signature:

%Critical Step

Critical Sequence Student Name:

Standard Determines:

GO-I 00-009 Single Recirculation Loop Operation will need to be addressed.

Previously provided.

Determines:

Prerequisites, precautions and initial conditions are applicable.

Records the following on the appropriate spaces:

Date, time candidate signature and 1A Reactor Recic pump tripped.

Eva1

~~

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.268.001 Step 15 16 17 18 i'

PERFORMANCt CHECKLIST i

Page 9 of 13 Action Comply with COLR Section 8.0 in TRM.

Record following for SHUTDOWN/TRIPPED recirculation pump.

Identification of SHUTDOWN/TRlPPED pump:

A or B Date and time pump ShutdownTTripped.

WHILE in single loop operation:

If OPERATING recirculation pump speed is ~75%

rated speed (1260 rpm), Determine actual core flow by (else N/A):

Plot position and all power changes on Power/Flow Map Maintain Reactor operation conditions below the 80%

rod line and outside Region II of the PowerlFlow Map.

Maintain OPERATING loop flow > 40 x 1061bm/hr to keep idle loop warm, if possible.

Critical Step

Critical Sequence Student Name:

Standard Previously determined.

Circles A Records the following on the appropriate spaces:

Date, time Previously determined Eva1 Comments STCP-QA-1258 Rev. 2 (9/93)

Page I of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.268.001 Step 19 PERFORMANCli CHECKLIST i

Page 10 of 13 Student Name:

Action Within one hour:

Restart idle recirculation pump in accordance with OP-I 64-001.

OR Perform following:

IF recirculation pump to be out of service >I2 hours, THEN Notify I&C to perform the following within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . (TS 3.4.1):

SI-?78-321 Setpoint Calibration for APRM Channels A-F (Dual Loop Operation to Single Loop Operation or Single Loop Operation to Dual Loop Operation).

SI-I 78-209 Weekly Functional Test Average Power Range Monitor (APRM) Channels A-F.

SI-I 78-225 Monthly Functional Test of Rod Block Monitor Channels A and 6.

EVALUATOR CUE:

Role play as required and report the I&C Surveillances (Sls) have been completed.

Critical Step

Critical Sequence Standard Contacts I&C to perform the following within I 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

Sl-I 78-321 Setpoint Calibration for APRM Channels A-F (Dual Loop Operation to Single Loop Operation or Single Loop Operation to Dual Loop Operation).

SI-I 78-209 Weekly Functional Test Average Power Range Monitor (APRM) Channels A-F.

SI-I 78-225 Monthly Functional Test of Rod Block Monitor Channels A and B.

Eva1 Comments STCP-QA-1Z5B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: 00.AD.268.001 Step 20 PERFORMANC t CHECKLIST i'

Page 11 of 13 Action AFTER I&C completes surveillances per preceding step, Perform following:

SO-I 78-002 Verification of APRM Scram and Rod Block Settings AND, Verify Core Thermal Limits SO-I 00-007.

EVALUATOR CUE:

Role play as required and report the Surveillances have been completed.

Critical Step Student Name:

Standard Determines the following SOs will need completed:

SO-I 78-002 Verification of APRM Scram and Rod Block Settings AND, Verify Core Thermal Limits SO-I 00-007.

Eva1 Comments

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

Page 1 of 1 2004 NRC Exam As Given

i' Appl. To/JPM No.: 00.AD.268.001 Step

21 PERFORMANCE CHECKLIST Page 12 of 13 Action While in Single Loop Operation WITHIN 15 minutes prior to Increasing thermal power or Increasing recirculation loop flow, Complete Attachment A if EITHER:

thermal power I 30%

OR OPERATING recirculation loop flow (i.e., jet pump flow) is I 50% of rated loop flow (21,320 gpm driving flow)

Critical Step

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

Page 1 of 1 2004 NRC Exam As Given Student Name:

Standard Determines from Attachment A:

Tech Spec Surveillance SR 3.4.10.5 required actions:

Within 15 minutes PRIOR to increasing THERMAL POWER:

Verify the difference between the bottom head coolant temperature and the RPV coolant temperature is 5 145°F Tech Spec Surveillance SR 3.4.1 0.6 required actions:

Within 15 minutes PRIOR to increasing THERMAL POWER:

Verify the temperature difference between the reactor coolant within the loop not in operation and coolant in the RPV is 5 50°F Reports this to the Shift manager Eva1 Comments

PERFORMANCt CHECKLIST Action i

Page 13 of 13 Standard Appl. To/JPM No.: 00.AD.268.001 Student Name:

Eva1 Step Comments 22 Maintain running recirc pump speed as follows: (TS Previously determined

~

3.4.1 )

I 80% rated pump speed (1344 rpm),

AND Maintain Reactor operation conditions outside Region II of Power/Flow Map.

EVALUATOR CUE:

That completes this JPM

+Critical Step

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

Page 1 of 1 2004 NRC Exam As Given

TASK CONDITIONS A.

B.

C.

D.

E.

Unit 1 was performing a power ascension following a refueling outage with Reactor power at - 49% when the 1A Reactor Recic pump tripped.

The 1A Reactor Recirc Pump is not isolated and has been declared NOT in Operation IAW Technical Specifications.

Maintenance has determined the problem is with the I A Recirc MG set and it will take a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to repair the problem.

Direction has been given to raise reactor power while the 1A Recirc MG is being repaired.

The following plant conditions exist:

INITIATING CUE Review and complete as required, ON-I 64-002, LOSS OF REACTOR RECIRCULATION FLOW.

Report to the Shift Manager if Reactor Power can be raised and the Tech Spec actions and or surveillances that will be required to support the present plant conditions and the intended power increase.

2004 NRC Exam As Given I

of2

PlCSY Core Flow PlCSY Core dP (NJP51)

Core Flow dP (XR-B21-1R613)

A Recic Lo00 Flow TASK CONDITIONS 41.14 mlbm/hr 1.87 psid 7.2 %

0.2 mlhm/hr A.

Unit 1 was performing a power ascension following a refueling outage with Reactor power at - 49% when the 1A Reactor Recic pump tripped.

B. The ?A Reactor Recirc Pump is not isolated and has been declared NOT in Operation IAW Technical Specifications.

C.

Maintenance has determined the problem is with the 1A Recirc MG set and it will take a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to repair the problem.

D. Direction has been given to raise reactor power while the 1A Recirc MG is being repaired.

E. The following plant conditions exist:

A Recirc Jet Pump Flow B Recic Loop Flow B Recirc Drive Flow B Recirc Jet Pump Flow 1 B Reactor Recic pump speed I Reactor Dower 1 36%

I 0 mlbm/hr 45%

4.07 mlbm/hr 21299 gpm 41.1 mlbm/hr 1 A Recirc Drive Flow I Oaom

-1 L

INITIATING CUE Review and complete as required, ON-I 64-002, LOSS OF REACTOR RECIRCULATION FLOW.

Report to the Shift Manager if Reactor Power can be raised and the Tech Spec actions and or surveillances that will be required to support the present plant conditions and the intended power increase.

2004 NRC Exam As Given 2 o f 2

.b SRO Appl. To Task

Title:

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 00.EP.003.082 1

02/17/04 2.4.44 4.0 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Classify GE, Complete the Emergency Notification Report and the PAR State Notification Form IAW EP-PS-100 Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Date Ap prova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

JPM Performed By:

15 Min Time Critical to classify and 15 Min Time Critical to complete PAR Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

(

)

Unsatisfactory

(

)

Satisfactory Performance Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

Page 1 of 1 2004 NRC Exam As Given File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.EP.003.082 1-

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. 19).

B. EP-PS-100-E Manage the General Emergency (Tab E) (Revision 17)

C. Blank copies of Emergency Notification Report.

D. Blank copies of PAR State Notification Form.

II I. REACTIVITY MAN I PU LATl ONS v

This JPM satisfies the following Operational Activity(s):

None IV. TASK CONDITIONS A. A Large LOCA has occurred on Unit 1, Unit 2 is in Refueling Mode.

B. RPV water level is -210 inches C. The control room crew has implemented EP-DS-002, RPV and primary Containment Flooding D. You are the Shift Manager and Emergency Director in the control room.

E. The Health Physics supervisor has informed you that the first offsite dose projection will not be available for 30 minutes.

F. Wind direction is I O 0 and speed is 5 mph.

G. There is no offsite release in progress.

H. No initial Emergency classifications have been made as of yet.

Procedure 2004 NRC Exam As Given

V. INITIATING CUE Cue #I Make the initial Emergency classification.

Cue #2 As the Emergency Director, complete the Emergency Notification Report and the PAR State Notification Form in accordance with the appropriate procedures.

VI. TASK STANDARD Classify the event as a General Emergency complete the Emergency Notification Report approved with a general emergency classification. PAR of EVACUATING 0-2 MILES AND SHELTERING 2-10 MILES made to the Senior State Official.

2004 NRC Exam As Given

Appl. To/JPM No.: SRO 00.EP.003.082 Step 1

(:

PERFORMANCE CHECKLIST Page 3 of 14 Action EVALUATOR NOTE:

a This is a Time Critical JPM.

This JPM should be performed in a location where the student will not be interrupted.

0 Ensure that a copy of EP-PS-100 is available for use by the student.

Ensure a blank PAR State Notification Form and Emergency Notification Report Form is available to be completed by the student.

a EVALUATOR CUE:

After student reviews TasWConditionsllnitiating Cue Sheet:

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

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

Record Start Time Obtains copy of EP-PS-100 Emergency Director, Control Room.

Student Name:

Standard Obtains copy of EP-PS-100 Emergency Director, Control Room

Critical Step

Critical Sequence Eva1 Comments STCP-QA-12%

Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Appl. To/JPM No.: SRO 00.EP.003.082 Step 2

3 4

Action Refers to classification matrix.

Choose appropriate emergency action level.

EVALUATOR CUE:

Enter STOP time for lst 15 minute Time Critical EVALUATOR CUE:

Provide the candidate with CUE sheet # 2 that addresses filling out the ENR form and making the PAR for a General Emergency.

f EVALUATOR CUE:

Enter START time for 2nd 15 minute Time Critical Determines appropriate procedure section.

Critical Step

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

Page 1 of 1 2004 NRC Exam As Given Student Name:

[

Page 4 of 14 Standard Selects Table F Fission Product Barrier Degradation Identifies entry into General Emergency FGI Loss of any TWO fission product barriers with a potential loss of the third.

Determines TAB E Manage the General Emergency is the appropriate TAB.

Eva1 Comments

Appl. To/JPM No.: SRO 00.EP.003.082 Step PERFORMANCE CHECKLIST Action

Critical Step Document and communicate the Emergency Classification.

If not performed earlier appoint an Emergency Plan Communicator If not performed earlier, appoint an NRC communicator.

Generate and approve an ENR form to be transmitted by the Emergency Plan Communicator.

Critical Sequence Student Name:

(

Page 5 of 14 Standard Announces to Control Room Personnel:

I am assuming duties of the Emergency Director.

General Emergency Classification declared based on Fission Product barrier Degradation FGI Loss Of ANY Two Barriers AND Loss Or Potential Loss Of The Third Barrier.

Time and Date of Classification.

Appoints an Emergency Plan Communicator and instruct himlher to immediately perform EP-PS-126 E Plan Communicator.

Appoints an NRC Communicator and instruct him/her to perform EP-PS-135 NRC Communicator Refers to ENR Form under Tab 9.

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

Page 1 of I 2004 NRC Exam As Given

Appl. To/JPM No.: SRO 00.EP.003.082 Step 8

PERFORMANCt CHECKLIST Action Fill out and approve the Emergency Notification Report Form.

EVALUATOR NOTE:

The communicator will fill out the communicator name, callback telephone number, and time notification is initiated. (Line 2 of the Emergency Notification Report Form).

EVALUATOR NOTE:

JPM start time should be used as the Declaration time on line 3 in the next step.

Critical Step

Critical Sequence Student Name:

Page 6 of 14 Standard Fills out and approves the Emergency Notification Report Form as follows:

LINE I.

Call Status:

Places checkmark in This is a drill box Eva1 Comments STCP-QA-125B Rev. 2. (9193)

Page 1 of 1 2004 NRC Exam As Given I

Appl. To/JPM No.: SRO 00.EP.003.082 Step 10 PERFORMANCE CHECKLIST Page 7 of 14 Action Standard LINE 3.

Emergency Classification:

Student Name:

FGI alone is sufficient for the Brief Non-Technical Description for the initial notification.

Candidate may paraphrase this description status.

%Critical Step STCP-PA-125B Rev. 2. (9193)

Page 1 of 1 2004 NRC Exam As Given

Critical Sequence Eva1 Comments

i Appl. To/JPM No.: SRO 00.EP.003.082 Step 11 12 13 14

/

PERFORMANCt CHECKLIST Page 8 of 14 Action

Critical Step

Critical Sequence Student Name:

~

Standard LINE 4.

The Emergency action level (EAL) number Records EAL # FGI Is:

Brief non -technical description of the event:

Fission Product barrier Degradation FGI Loss Of ANY Two Barriers AND Loss Or Potential Loss Of The Third Barrier.

LINE 5.

Places a checkmark in the No non-routine radiological release box LINE 6 Records Wind Direction is from: I O 0 Wind Speed is: 5 mph LINE 7.

==

Conclusion:==

Places a checkmark in this is a drill box.

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

Page 1 of 1 2004 NRC Exam As Given

Appl. To/JPM No.: SRO 00.EP.003.082 Step

I5 16 PERFORMANCE CHECKLIST Page 9 of 14 Action

~~

Approves the Emergency Notification Report Form EVALUATOR NOTE:

Candidate may review the filled out ENR form with the E Plan Communicator.

Give the approved ENR form to the E Plan Communicator.

EVALUATOR CUE:

If necessary, Role-play the communicator and accept the filled out form.

EVALUATOR NOTE:

It is acceptable to use either the PAR Airborne Releases flowchart OR the Public Protective Action Recommendation Guide to make the PAR determination in the following step.

Critical Step Student Name:

Standard Records the following on space provided:

Approved: - His/Her name Time: - Current time Date: - Current Date Provides the filled out ENR form to the E Plan Communicator.

Eva1 Comments

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Step

I8 i"

Page 11 of 14 Action Choose appropriate PAR.

Critical Step

Critical Sequence Student Name:

Standard Determines PAR by answering the questions posed in either the flowchart OR the Public Protective Action Recommendation Guide as follows:

(PA-2)

Has a General Emergency been declared?

Answers YES (PA-3)

Is there a valid dose projection indicating doses of 11 REM TEDE or 2 5 REM CDE child thyroid at a distance of > 2miles?

Answers UNKNOWN (PA-4)

Recommend EVACUATING 0-2 MILES AND SHELTERING 2-10 MILES Eva1 Comments STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam As Given

(

PERFORMANCt CHECKLIST Appl. To/JPM No.: SRO 00.EP.003.082 Step 19 20 2

22 Action Shift Manager/ED shall notify the senior state official using the PAR state notification form at 717-651-2148 Complete PAR State Notification Form.

EVALUATOR NOTE:

Line 3 of the PAR State Notificatior until the actual notification is being Form is left blank nade.

Critical Step

Critical Sequence Page 12 of 14 Student Name:

Standard Refers to-Tab 9 for PAR State Notification Form.

Completes PAR State Notification Form as follows:

Places a checkmark in This Is A Drill box.

LINE 1 This is of the Susquehanna Steam Electric Station.

Records their name LINE 2 Places a checkmark in I am the:

Emergency Director at the Susquehanna SES Control Room box.

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

Page 1 of 1 2004 NRC Exam As Given

i PERFORMANCE CHECKLIST Page 13 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Step 23 24 Action EVALUATOR NOTE:

JPM start time should be used as the declaration time on line 4 in the next step.

EVALUATOR NOTE:

Candidate may paraphrase the reason for declaring a General Emergency.

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

Page 1 of 1 2004 NRC Exam As Given

Critical Sequence Student Name:

Standard LINE 4 A General Emergency has been declared as of Records the JPM start time LINE 5 This declaration was made due to:

Fission Product barrier Degradation FGI Loss Of ANY Two Barriers AND Loss Or Potential Loss Of The Third Barrier.

Eva1 Comments

Appl. To/JPM No.: SRO 00.EP.003.082 Step

25 PERFORMANCE CHECKLIST Page 14 of 14 Action Enters the PAR on the State Notification Form.

EVALUATOR CUE:

Once the candidate simulates/indicates dialing the number to notify the senior state official, inform the candidate the JPM is complete.

Note the time of completion. This will be used to determine if the "Time Critical" portion of the JPM was completed satisfactorily.

COMPLETION TIME:

EVALUATOR NOTE:

Determine the total time the candidate took to make the EAL declaration AND PAR. Each time must be within 15 minutes to satisfactorily complete the JPM.

Critical Step

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

Page 1 of 1 2004 NRC Exam As Given Student Name:

Standard LINE 6 The PPL Susquehanna Protective Action Recommendation is:

Places a checkmark in Evacuate 0-2 miles and shelter 2-1 0 miles and advise citizens to take KI in accordance with the state's emergency plans box.

Eva1 Comments

CUE SHEET #2 TASK CONDITIONS A.

A General Emergency has just been declared as the initial emergency classification.

INITIATING CUE As the Emergency Director, complete the Emergency Notification Report and the PAR State Notification Form in accordance with the appropriate procedures.

2004 NRC Exam As Given Page 1 of 4

CUE SHEET #2 TASK CONDITIONS A. A General Emergency has just been declared as the initial emergency classification.

INITIATING CUE As The Emergency Director, complete the Emergency Notification Report and the PAR State Notification Form in accordance with the appropriate procedures.

-+--

2004 NRC Exam As Given Page 2 of 4

TASK CONDITIONS A.

A Large LOCA has occurred on Unit 1, Unit 2 is in Refueling Mode.

B.

RPV water level is -210 inches C. The control room crew has implemented EP-DS-002, RPV and primary Containment Flooding Procedure D. You are the Shift Manager and Emergency Director in the control room.

E. The Health Physics supervisor has informed you that the first offsite dose projection will not be available for 30 minutes.

F.

Wind direction is I O and speed is 5 mph.

G. There is no offsite release in progress.

H.

No initial Emergency classifications have been made as of yet.

INITIATING CUE Make the initial Emergency classification Page 3 of 4 2004 NRC Exam As Given

TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

A Large LOCA has occurred on Unit 1, Unit 2 is in Refueling Mode.

RPV water level is -21 0 inches The control room crew has implemented EP-DS-002, RPV and primary Containment Flooding Procedure You are the Shift Manager and Emergency Director in the control room.

The Health Physics supervisor has informed you that the first offsite dose projection will not be available for 30 minutes.

Wind direction is I O o and speed is 5 mph.

There is no offsite release in progress.

No initial Emergency classifications have been made as of yet.

INITIATING CUE Make the initial Emergency classification 2004 NRC Exam As Given Page 4 of 4

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