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

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE v

APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 00.AD.038.001 0 01128104 2.1.20 4,314.2 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. K/A Task

Title:

Complete Aborted Evolution Log Completed By: Reviews:

Russ Halm Writer Date InstructorMlriter Date Ap provaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 10 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

srw-w-12 5 ~

Rev. 2,(9/93)

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

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)

III. REACTIVITY MANIPULATIONS

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

NONE IV. TASK CONDITIONS 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-I 33-001 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 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

(,

PERFORMANCt CHECKLIST Page 3 of 7 Appl. To/JPM No.: 00.AD.038.001 Student Name:

Step Action Standard Eva1 Comments 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-133-001 CHEMICAL ADDITION TO TURBINE BUILDING CHILLED WATER SYSTEM (Rev. 21) filled out up to step 2.4.10.

Obtain a controlled copy of OP-AD-002 Controlled copy obtained.

Selects the correct section to perform. OP-AD-002 Determines OP-AD-002 Section 8.4 is Section 8.4 appropriate.

Aborted Evolution Control Log (AECL) Form Determines:

OP-AD-002-1 (Attachment H) shall be completed Attachment H will need to be when: completed.

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

Page 1 of 1 2004 NRC Exam As Given

i.

PERFORMANCt CHECKLIST Page 4 of 7 Appl. To/JPM No.: 00.AD.038.001 Student Name:

- ~~

Action Standard Eva1 Comments 4 Completes Attachment H of OP-AD-002 by performing the following:

Places:

Date, Time, and name in the spaces Completing Line 1 provide in line I.

5 Completing Line 2 Places:

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

3k6 Completing Line 3 Places:

Procedure number OP-I 33-001, Revision 21, step 2.4.10 in the spaces provide in line 3 37 Completing Line 4 Places:

TB Chilled Wtr Chem Add Tank In valve I88003 could not be opened in the space provide in line 4

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

Page 1 of 1 2004 NRC Exam As Given

i, PERFORMANCE CHECKLIST Page 5 of 7 Appl. To/JPM No.: 00.AD.038.001 Student Name:

Step Action Standard Eva1 Comments 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.

8 Completing Line 5 Places:

NONE in the space provide in line 5 9 Completing Line 6 Places:

Restart procedure beginning at step 2.4.10 in the space provide in line 6 10 Each AECL activity shall be referenced on the Identifies:

Turnover Sheet of the Operator performing the Turbine Building NPO turnover sheet evolution and be reviewed as part of the Turnover must have a reference to the aborted process until such time as the AECL is no longer evolution, and be reviewed as part of required, or in control.

the Turbine building NPO turnover process until such time as the AECL is no longer required.

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

Page 1 of 1 2004 NRC Exam As Given

Page 6 of 7 i

PERFORMANCECHECKLIST Appl. To/JPM No.: 00.AD.038.001 Student Name:

Step Action Standard Eva1 Comments

I 1 Informs Turbine building NPO of Administrative Informs Turbine building NPO to:

requirements for the aborted evolution.

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

Role-play Turbine building NPO acknowledge the report.

12 Each AECL activity shall be referenced on the Unit Identifies:

Supervisor Turnover Sheet and the affected Plant Unit 1 Control room Supervisors Operator Turnover Sheet. The AECL Form shall be turnover sheet and the Unit 1 Plant maintained by Unit Supervisor in the Control Room operators turnover sheet must have with a copy on the Plant Operator Turnover. 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.

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

Page 1 of I 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Page 7 of 7 i

Appl. To/JPM No.: 00.AD.038.001 Student Name:

Step Action Standard Eva1 Comments

I3 Informs Unit IControl room Supervisor of Informs Unit 1 Control room Supervisor Administrative requirements for the aborted evolution. to:

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

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

EVALUATOR CUE:

This completes the JPM

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

Page 1 of 1 2004 NRC Exam As Given

TASK CONDITIONS A. Unit Iis in Mode I

6. All Plant Equipment required for Mode Iis 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 IPCOM 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 1129104 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: Reviews:

Russ Halm Writer Date InstructorMlriter Date Approval:

Requesting Supv.1C.A. Date Nuclear Trng. Supv. Date Head 15/25 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

--. JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory EvaIuation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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 2100 hour0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months surveillance III. REACTIVITY MAN1PULATIONS This JPM satisfies the requirements of Operational Activity(s):

V' 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

i (

PERFORMANCt CHECKLIST Page 3 of I 2 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Action Standard Eva1 Comments 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.

1 Obtain a controlled copy of SO-100-006 SHIFTLY Controlled copy obtained.

SURVEILLANCE 0PERAT1NG LOG 2 Selects the correct section to perform. Selects item A21 on page 25 of 136 3 Determines Attachment F and L will need to be Determines Attachment F and L will completed 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.

4 Refers to Attachments E and M for instructions on Locates Attachments E and M.

completing Attachments F and L.

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

Page 1 of 1 2004 NRC Exam As Given

i' PERFORMANCt CHECKLIST Page 4 of 12 i:

Appl. To/JPM No.:00.AD.037.051 Student Name:

Step Action Standard Eva1 Comments Determine total number of level increases from the Places I09 in the space provided on 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 SO-100-006 Attachment F. (item b)

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 Places 99 in the space provided on SO-12 hour period on DRWL SUMPS FLOW & LVL 100-006 Attachment F. (item c)

RECORDER LWFR-I 6103 (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 Places 2071 in the space provided on A. (Total Level Increases) ( I 9 gal/level) = total SO-100-006 Attachment F. (item d) gallons.

(109 X 19=2071)

Compute total gallons accumulated for DRWL Sump Places 2079 in the space provided on B. (Total Level Increases) (21 galllevel) = total SO-100-006 Attachment F. (item e) gallons.

(99 X 21=2079)

Critical Step #Critical Sequence STCP-QA-I25B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

{,

PERFORMANCE CHECKLIST Page 5 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Action Standard Eva1 Comments 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).

9 Determine average lnleakage for DRWL Sump A Places 2.88 in the space provided on (total gallons)/(elapsed time in minutes) = average SO-100-006 Attachment F. (item g) inleakage.

(2071/720=2.88)

EVALUATOR NOTE:

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

IO 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous average inleakage recorded from Places 0.02 in the space provided on previous days worksheet for DRWL Sump A. SO-100-006 Attachment F. (item h) 11 Determine the change in inleakage from the last time Places 2.86 in the space provided on the inleakage was determined. (current inleakage) - SO-100-006 Attachment F. (item i)

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

(2.88 - 0.02=2.86)

Critical Step #Critical Sequence STCP-QA-I 258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

/

! I PERFORMAN& CHECKLIST Page 6 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Action Standard Comments 12 Determine average inleakage for DRWL Sump B (total Places 2.89 in the space provided on gallons)/(elapsed time in minutes) = average SO-I 00-006 Attachment F. (item j) inleakage.

(2079/720=2.89)

EVALUATOR NOTE:

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

13 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous average inleakage recorded from Places 0.03 in the space provided on previous days worksheet for DRWL Sump B. SO-100-006 Attachment F. (item k) 14 Determine change in inleakage from the last time the Places 2.86 in the space provided on inleakage was determined. (current inleakage) - SO-100-006 Attachment F. (item I)

(previous inleakage) = change (A)in inleakage. (2.89-0.03=2.86) 15 Determine the total average inleakage (inleakage Places 5.77 in the space provided on Sump A) + (inleakage Sump B). c 5 gpm required. SO-100-006 Attachment F. (item m)

(2.88 + 2.89 = 5.77)

I6 Determine the total change in inleakage from the last Places 5.72 in the space provided on time the inleakage was determined (delta inleakage SO-I 00-006 Attachment F. (item n)

Sump A) + (delta inleakage Sump B). c 2 gpm/24 (2.86 + 2.86 = 5.72) hours required.

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

Page 1 of 1 2004 NRC Exam As Given

i i PERFORMANCt CHECKLIST Page 7 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Standard Eva1 Comments 17 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.

18 Compute total gallons accumulated for DRWL Sump Places 2565 in the space provided on A. (Add total from each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period from SO-100-006 Attachment M. (item Ia)

Attachment F)

(494 + 2071=2565) 19 Compute total gallons accumulated for DRWL Sump Places 2394 in the space provided on B. (Add total from each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period from SO-100-006 Attachment M. (item Ib)

Attachment F)

(315 + 2079=2394) 20 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).

21 Determine average inleakage for DRWL Sump A. Places 1.78 in the space provided on (total gallons)/(elapsed time in minutes) = average SO-100-006 Attachment M. (item I d )

inleakage (2565/1440=1.78)

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

Page 1 of I 2004 NRC Exam As Given

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PERFORMAN& CHECKLIST Page 8 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Action Standard Eva1 Comments 22 Determine average inleakage for DRWL Sump B. Places 1.66 in the space provided on SO-100-006 Attachment M. (item 1e)

(total gallons)/(elapsed time in minutes) = average inleakage (2394/1440=1.66) 23 Determine total percent from last 24 hr time mark on Places 268 in the space provided on DRWL EQUIP DRN TANK LWFR-16103 (Alternate: SO-100-006 Attachment M. (item 2a)

Computer Pt. RLLOOGZ).

24 Compute total gallons accumulated on LEVEL Places 2278 in the space provided on RECORDER LWFR-16103 (Alternate: Computer Pt. SO-I 00-006 Attachment M. (item 2b)

RLLOOGZ). (Total %) (8.5 gal/%) = total gallons (268 X 8.5=2278)

Example: (380%) (8.5 gal) = 3230 gallons 25 Determine total elapsed time in minutes from last 24 hr time mark on LEVEL RECORDER LR/FR-16103 (Alternate: Computer Pt. RLLOOGZ) (1440 minutes).

26 Determine average inleakage recorded on LEVEL Places 1.58 in the space provided on RECORDER LWFR-16103 (Alternate: Computer Pt. SO-I 00-006 Attachment M. (item 2d)

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

(2278/1440=1.58) average inleakage.

27 Compute TOTAL DRYWELL LEAKAGE Places 1.78 in the space provided on SO-100-006 Attachment M. (item 3a)

Record average leakrate from step I.d.

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

Page 1 of 1 2004 NRC Exam As Given

('

PERFORMANCE CHECKLIST Page 9 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Action Standard Eva1 28 Record average leakrate from step 1.e. Places 1.66 in the space provided on SO-100-006 Attachment M. (item 3b) 29 Record average leakrate from step 2.d. Places 1.58 in the space provided on SO-I 00-006 Attachment M. (item 3c) 30 Sum total leakrate (a+b+c) required e25 gpm. Places 5.02 in the space provided on SO-I 00-006 Attachment M. (item 3d)

( I .78 + 1.66 + 1.58 = 5.02)

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

Page I of 1 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Page 10 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Action Standard Eva1 Comments 31 Compares calculated values to the ACCEPTABLE Compares calculated values to the values listed in item A21 of SO-100-006 SHIFTLY ACCEPTABLE values listed in item A21 SURVEILLANCE OPERATING LOG. of SO-100-006 SHIFTLY S URVEILLANCE 0PERAT1NG LOG.

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.

3(c 32 Report the results of the calculation and Reports Leakage rate is greater than determination. the 5 5 gpm limit.

pech Spec 3.4.4. b RCS]

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

Page 1 of 1 2004 NRC Exam As Given

i PERFORMANCt CHECKLIST Page 11 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

~

Step Action Standard Comments EVALUATOR CUE:

FOR SRO CANDIDATES ONLY Give the SRO candidate the second cue sheet that addresses the Tech Spec LCO for RCS Leakage 33 Obtains a copy of the Tech Specs References Tech Spec 3.4.4. b 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 m34 Determines required actions 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

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Page 12 of 12 Appl. To/JPM No.: 00.AD.037.051 Student Name:

Step Action Standard Eva1 Comments EVALUATOR CUE:

This completes the JPM.

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

Page Iof 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 Iis 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 I 0 9 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 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 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 4of4

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE

--- . APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 00.S0.003.05 1 0 02117104 2.2.12 3.013.4 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Determine Jet Pump Operability Completed By: Reviews:

Russ Halm Writer Date InstructorNVriter Date Ap provaI:

Requesting Supv.1C.A. Date Nuclear Trng. Supv. Date Head 30 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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

1. SAFETY CONSIDERATIONS 5*

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.

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

III. REACTIVITY MAN1PULATlONS 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 O f SO-I 00-007, DAILY SURVEILLANCE LOG.

V. INITIATING CUE Using the data provided on Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP of SO-I 00-007, DAILY SURVEILLANCE LOG, complete the remaining items in Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG 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.

VI. TASK STANDARD Recirculation pumps declared OPERABLE; Jet pumps declared INOPERABLE 2004 NRC Exam As Given

/' I'

! (

PERFORMANkt CHECKLIST Page 3 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments 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.

I Obtain a controlled copy of SO-I 00-007 Daily Controlled copy obtained.

Surveillance Log.

2 Selects the correct section to perform. Selects Item 1 3 To determine Recirc PumpslJet Pumps and Flow Determines attachment C is applicable Biased Simulated Thermal Power-Upscale (RPS)

OPERABLE, complete applicable attachments If in dual loop operation, complete attachment C for Recirc Pumps and Jet Pumps 4 Refers to Attachment C

%Critical Step #Critical Sequence STCP-QA-1250 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

i PERFORMANCt CHECKLIST Page 4 of I 4 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Comments

5 Recirc pumps operable if loop jet pump flow mismatch On Attachment C PERFORMANCE maintained within a or b: Enter N/A for item that does DATA SHEET RECIRCULATION not apply. SYSTEM DUAL LOOP

a. 5 Mlbm/hr with core flow 75 Mlbm/hr Compares line g to h

b. I O Mlbm/hr with core flow 5 75 Mlbmlhr Determines that the mismatch between Loop A and Loop B is IMlbm/hr Records: 1 Mlbm/hr on SR 3.4.1 .Iline a Records: N/A on SR 3.4.1 .Iline b Determines Recirc Pumps are operable Circles YES and initials Confirm on SR 3.4.1 .Iline Records: SAT on Recirc Pumps line of item 1 of SO-100-007 Daily Surveillance Log Attachment A

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

Page 1 of 1 2004 NRC Exam As Given

i !

PERFORMANCt CHECKLIST Page 5 of 14

(:

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

~

lstep Action Standard Eva1 Comments 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.

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

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

Page 1 of I 2004 NRC Exam As Given

i ('

PERFORMANCIi CHECKLIST Page 6 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments 7 When recirc pumps operating with flow within limits of On Figure 1 RECIRC PUMP A FLOW a or b above, jet pumps operable if no two (2) VS. SPEED TWO LOOP OPERATION following conditions exist simultaneously: of ATTACHMENT C Recirculation loop drive flow versus recirculation Plots a point corresponding to a:

generator speed differs > 10% from established RECIRC GENERATOR A SPEED patterns. (Plot applicable performance data on figures (SI-14032A) Of 87%

1 and 2 of this attachment)

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

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

Page 1 of 1 2004 NRC Exam As Given

? (

PERFORMANCt CHECKLIST Page 7 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments 8 Recirculation loop drive flow versus total core flow On Figure 3 TOTAL CORE FLOW VS.

differs > 10% from established patterns. (Plot RECIRC PUMP A FLOW TWO LOOP applicable performance data on Figures 3 and 4 of OPERATION of ATTACHMENT C this attachment)

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

Page 1 of 1 2004 NRC Exam As Given

i (,

c PERFORMANCt CHECKLIST Page 8 of 14 Appl. To/JPM NO.:1 SO.OO3.051 Student Name:

I I I Action Standard Eva1 Comments 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 of1 2004 NRC Exam As Given

':I PERFORMAN& CHECKLIST Page 9 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments 9 Calculates LOOP A JET PUMP AP PERCENT Records the following data on DEVIATION FROM THE AVERAGE to be used in Attachment C LOOP A JET PUMP AP Plotting applicable performance data on figure Iof PERCENT DEVIATION FROM THE attachment I 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 I 0 0 =--6.71-A =-343 X 0.1 = -34.3-(Sum of AP%)

JP11 thru 20

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

Page 1 of1 2004 NRC Exam As Given

(

PERFORMANCECHECKLIST Page 10 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step I Action Standard Eva1 Comments 10 Calculates LOOP B JET PUMP AP PERCENT Records the following data on DEVIATION FROM THE AVERAGE to be used in Attachment C LOOP B JET PUMP AP Plotting applicable performance data on figure 2 of PERCENT DEVIATION FROM THE attachment I AVERAGE:

1. JP1_39-(JPI - A ) fA X lOO=-3.17-

2. JP2_3Q-(JP2- A) f A X 100 =-3.17-

3. JP3_37-(JP3 - A ) fA X 100 =--2.12-

4. JP4_39-(JP4 - A ) fA X 100 =-3.17_

5. JP5_39-(JP5 - A ) fA X 100 =-3.17-

6. JP6_39-(JP6 - A ) fA X 100 =-3.17-

7. JP7_3O_(JP7- A) fA X 100 =--20.63-

8. JP8_39_(JP8- A ) + A X 100 =-3.17-

9. JP9_3Q_(JP9- A) + A X 100 =-3.17-IO. JPIO-38-(JPIO - A) f A X 100 =-.53-A =-378 X 0.1 = -37.8-(Sum of AP%)

JPI thru I O

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

Page 1 of 1 2004 NRC Exam As Given

I:' (

PERFORMANCt CHECKLIST Page 11 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments I1 Each jet pump to lower plenum differential pressure On Figure 1 TWO LOOP JET PUMP differs by > 20% from the established patterns, (Plot DISTRIBUTION LOOP A of applicable performance data on figures Iand 2 of ATTACHMENT I 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

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

Page 1 of 1 2004 NRC Exam As Given

i (

PERFORMANCt CHECKLIST Page 12 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments 12 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

=

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

Page 1 of 1 2004 NRC Exam As Given

i' (,

PERFORMAN& CHECKLIST Page 13 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments

+ic 13 When recirc pumps operating with flow within limits of Determines Jet pumps are NOT a or b above, jet pumps operable if no two (2) operable based on two (2) of the following conditions exist simultaneously: 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

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

Page 1 of 1 2004 NRC Exam As Given

i, i (

PERFORMANCE CHECKLIST Page 14 of 14 Appl. To/JPM No.: OO.SO.003.051 Student Name:

Step Action Standard Eva1 Comments

I4 Reports the results of the surveillance. 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.

EVALUATOR CUE:

Role-play shift supervision and acknowledge the report.

EVALUATOR CUE:

That completes this JPM

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

Page 1 of 1 2004 NRC Exam As Given

TASK CONDITIONS

-- A. Unit Iis 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-100-007, DAILY SURVEILLANCE LOG.

INITIATING CUE Using the data provided on Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-100-007, DAILY SURVEILLANCE LOG, complete the remaining items in Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-100-007, DAILY SURVEILLANCE LOG 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.

,\.-

2004 NRC Exam As Given 1 of2

TASK CONDITIONS C

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

INITIATING CUE Using the data provided on Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-100-007, DAILY SURVEILLANCE LOG, complete the remaining items in Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG 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.

2004 NRC Exam As Given 2of2

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 ApprovaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 25/30 C'

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

JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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)

III . REACTIVITY MAN1PULATIONS 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-B31-1N008A.

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 704and 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

{

PERFORMANCE CHECKLIST Page 4 of 10 Appl. TolJPM No.: 00.AD.269.001 Student Name:

Action Standard Eva1 Comments 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 Controlled copy obtained.

Blocking Practices Selects the correct section to perform. Selects section 8.8.1 Using the table in NDAP-QA-0323, Standard Blocking Identifies the need to:

Practices section 8.8.1 identifies the required blocking Ensure all tips withdrawn to IN points, positions, and type of tag to be used. SHIELD position with ball valves closed (steps 3 - 10 of this JPM) prior to applying blocking.

Position N/A No tag required Records on attached form Identifies the need to OPEN breaker 1Y21927 Tip Drive Mechanisms 1S215A-E and RED TAG Records on attached form

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Page 5 of 10 Appl. To/JPM No.: 00.AD.269.001 Student Name:

E Action Standard Eva1 Comments

5 Identifies the need to install a spectacle flange at 1S2104 N2 Purge Line To UI Containment and RED TAG Records on attached form t 3k6 Identifies the need to CLOSE valve 157026 Contn N2 Makeup Supply Hdr Is0 Vlv and RED TAG Records on attached form 7 Identifies the need to:

Notify HP At X3371 When Drywell Access Door Lock Is Unlocked/RemovedAnd When Re-lnstalled/Locked NO TAG required Records on attached form

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

Page 1 of 1 2004 NRC Exam As Given

i r {

PERFORMANCE CHECKLIST Page 6 of 10 Appl. To/JPM No.: 00.AD.269.001 Student Name:

Step Action Standard Eva1 Comments 8 Identifies the need to track the status of the OPS VERY HIGH Rad Door Lock, Drywell Access Door, To Ensure Relocked When Clearance Removed.

NO TAG required Records on attached form EVALUATOR NOTE:

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

9 Identifies the need to:

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

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

Page 1 of 1 2004 NRC Exam As Given

i

\

/

(

PERFORMANCt CHECKLIST Page 7 of 10 Appl. To/JPM No.: 00.AD.269.001 Student Name:

Step Action Standard Eva1 Comments

IO Identifies the need to:

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

Candidate may reference NDAP-QA-0322, ENERGY CONTROL PROCESS, and NDAP-QA-0323, STANDARD BLOCK1NG 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 STCP-QA-1256 Rev.2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

i:

PERFORMANCECHECKLIST Page 8 of 10 Appl. To/JPM No.: 00.AD.269.001 Student Name:

Step Action Standard Eva1 Comments

I1 Use mechanical drawing to identify chilled water Using M-143 Sht.2 , determines the valves following:

Valves 143001A CLOSED Red Tagged 143002A CLOSED Red Tagged 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.

12 Obtain a controlled copy of NDAP-QA-0309, Primary Controlled copy obtained.

Containment Access And Control 13 References appropriate section References section 6.5

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

Page 1 of 1 2004 NRC Exam As Given

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PERFORMANCE CHECKLIST Page 9 of 10 Appl. To/JPM No.: 00.AD.269.001 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

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

I4 For entries at power, a Reactor Operator shall be Reports to the Shift Manager the stationed at the reactor console to monitor reactor following:

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

personnel.

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

%I5 Initially, primary containment entries are limited to Reports to the Shift Manager the 10% power for elevations 704and 719 and 3% following:

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

Critical Step #Critical Sequence 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 Student Name:

Step Action Standard Eva1 Comments

I6 No action shall be taken to change Reactor power Reports to the Shift Manager the levels (e.g., no control rod movements, steady recirc following:

pump speed, steady EHC pressure setpoints, etc.) No action shall be taken to change during power entries. Reactor power levels

I7 If some action is necessary to control Reactor Power Reports to the Shift Manager the (e.g., control rod movement, recirc pump speed or following:

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

18 Following any rod position changes, provide Health Reports to the Shift Manager the Physics with a new Attachment S or OD-7 printout to following:

identify the changes. 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 STCPUA-125B Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam As Given

SRO ONLY 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-B31-1N008A.

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.

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. 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-B31-1N008A.

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 704and 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 IOr 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 2of6

TASK CONDITIONS

-v 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-B31-1N008A.

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.

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 3of6

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-B31-1N008A.

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.

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 4of6

ANSWER KEY DO NOT GIVE TO CANDIDATES (JPM 00.AD.269.001)

Critical components are identified with an asterisk ($)

COMPONENT NAME POSITION TAG ID ENSURE ALL TIPS WITHDRAWN TO IN SHIELD NA NO TAG POSITION WITH BALL VALVES CLOSED PRIOR TO APPLYING BLOCKING.

1Y21927 TIP DRIVE MECHANISMS 1S215A-E OPEN RED TAG

IS2104 N2 PURGE LINE TO U1 CONTAINMENT BLANKED RED TAG SPECTACLE FLANGE

~

157026 CONTN N2 MAKEUP SUPPLY HDR IS0 VLV CLOSE RED TAG DRYWELL OPERATIONS TO NOTIFY HP AT X3371 WHEN N/A NO TAG ACCESS DOOR LOCK IS UNLOCKED/REMOVED AND WHEN DOOR RE-INSTALLED/LOCKED OPS VERY HIGH RAD DOOR LOCK, DRYWELL N/A NO TAG ACCESS DOOR, TRACKED TO ENSURE RELOCKED WHEN CLEARANCE REMOVED.

APPLY COVER OVER CONTROL ROD CONT INSERT ROD AND CONT W/DRAW NIA PINK TAG PUSHBUTTONS ON IC651 TO PREVENT ROD MOVEMENT IAW NDAP-QA-0309

APPLY COVER OVER CONTROL ROD INSERT ROD AND W/DRAW ROD PUSHBUTTONS ON NIA PINK TAG IC651 TO PREVENT ROD MOVEMENT IAW NDAP-QA-0309 143001A CHILLED WATER FISL-B31-1N008A INLET CLOSED RED TAG 143002A CHILLED WTR FISL-B31-1N008A OUTLET CLOSED RED TAG 2004 NRC Exam As Given 5 of 6

CANDIDATE COPY (JPM 00.AD.269.001)

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

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 99.0P.002.001 0 03/0I/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 provaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 15 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

-v-JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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 I1I. REACTIVITY MAN1PULATIONS 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 Page 3 of 8 Appl. TolJPM No.: 99.0P.002.001 Student Name:

~

Step Action Standard Comments 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 Controlled copy obtained.

Monitoring System Selects the correct section to perform. Selects section 3.2 Review the prerequisites. Ensures all prerequisites have been met.

EVALUATOR CUE:

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

Review all precautions. Follows all precautions as applicable.

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

Page 1 of 1 2004 NRC Exam As Given

i i' (1, PERFORMANCt CHECKLIST Page 4 of 8 Appl. To/JPM No.: 99.0P.002.001 Student Name:

Step Action Standard I Eva1 Comments

5 REVIEW printer output and panel indicating lights to Compares the Seismic Monitor printer determine type of event. information and panel indicating light status Attachments A, B, and C Use Attachment A and B to classify and validate the trigger.

Attachment C provides example printouts for further Determines that a Safe Shutdown assistance. Earthquake (SSE) has occurred 6 CONTACT one of the agencies in Attachment D to Simulates contacting one of the confirm the cause of the event was seismic activity. 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 Step #Critical Sequence STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam As Given

{" r' PERFORMANCE CHECKLIST Page 5 of 8 Appl. To/JPM No.: 99.0P.002.001 Student Name:

Step Action Standard Eva1 Comments 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 Determines that ON-000-002 Natural ON-000-002, Natural Phenomena in parallel with this Phenomena performance will be section. required in parallel with completing this procedure.

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 Controlled copy obtained.

Phenomena

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Page 6 of 8 Appl. To/JPM No.: 99.0P.002.001 Student Name:

Step Action Standard Eva1 Comments 9 Record date and time of event. 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 10 Notify Security of event. Simulates a call to Plant security.

EVALUATOR CUE:

Role-play Plant Security and acknowledge the report.

11 Based on event occurrence, Perform following as Refers to section 3.7 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 Iof I 2004 NRC Exam As Given

!/ i PERFORMANCt CHECKLIST Page 7 of 8 Appl. To/JPM No.: 99.0P.002.001 Student Name:

Step Action Standard Eva1 Comments 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

I2 IF OBE

- SSE earthquake occurred: Determines both Units need to be shutdown in accordance with Commence shutdown in accordance with GO-I 00-004 (GO-200-004), Plant Shutdown to Minimum Power. 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 13 Classify Plant status in accordance with EP-PS-100, Controlled copy obtained.

Emergency Director, Control Room.

14 Evaluates information. Identifies SSE as Emergency Plan entry.

EVALUATOR NOTE:

An SSE is a greater magnitude than an OBE.

15 Refers to classification matrix. Selects OA3.

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

Page 1 of 1 2004 NRC Exam As Given

i" (:,'

PERFORMAN& CHECKLIST Page 8 of 8 APP To/JPR ).: 99.0P.002.001 Student Name

~

~~

Step Action Standard Comments 16 Reviews the table of contents for Natural Phenomena. Reviews all of Category OA3.

I7 Choose appropriate emergency action level. Identifies entry into OA3 EAL Threshold value 1 Earthquake at or greater than OBE levels.

Classifies the event as a Alert 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 L--

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.

2004 NRC Exam As Given 1O f 3

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.

2004 NRC Exam As Given 2 of 3

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

Red VRS-05703 Status Strong Motion Accelerograph Green System Trigger RSA-50 Data light Was Red for approximately 15 seconds, NOW it is OFF Cassette Tapes Recordedfor approximately 15 seconds, Now they are idle.

VAH-15701 and VAH-05701 OBE Lights Green VAH-I5701 and VAH-05701 SSE Lights Green Inner Analog Light Red Outer Analog Light 2004 NRC Exam As Given 3 of 3

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE

=---

APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 00.AD.268.001 0 07/26/04 2.2.22 3.414.1 Appl. To 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 Date Approval:

Requesting Supv.1C.A. Date Nuclear Trng. Supv. Date Head 25 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory EvaIuation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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

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:

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

NONE

-- IV. TASK CONDITIONS A. Unit Iwas 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

i' i PERFORMANCE CHECKLIST Page 3 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments EVALUATOR CUE:

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

I Record Date and Time of event. Records:

Today's date and time 2 IF both Recirculation Pumps trip, Immediately Scram Determines from initial conditions that reactor. ONLY 1 pump tripped and Reactor Scram is not warranted.

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

i: i PERFORMANCt CHECKLIST Page 4 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments IF one Reactor Recirculation Pump trips: Determines actual core flow via PlCSY computer point using Form IF operating recirculation pump speed is <75% rated GO-I 00-009-2 Core Flow vs. Core speed ( I 260 rpm), Determine actual core flow by (else Pressure Drop curve is -44 mlb/hr 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 Plot position on Power/Flow Map, NDAP-QA-0338-10. Form NDAP-QA-0338-10, Determines:

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

IF Power/Flow Map indicates operation in Region 1 OR Based on plot from previous step Core Flow is < the Natural Recirculation Line or Determines:

operations in any region not bounded by Power/Flow map, Place MODE SWITCH to SHUTDOWN. N/A

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

Page 1 of 1 2004 NRC Exam As Given

i ( i PERFORMANCt CHECKLIST Page 5 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Action Standard Eva1 Comments

~~ ~ ~

6 Ensure thermal power REDUCED to <70% rod line. Based on plot from previous step Determines:

N/A 7 Reduce operating pump speed to 80% rated pump Based on p l a from previous step speed (80% = 1344 rpm) in accordance with Determines:

OP-I 64-001.

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

Page 1 of 1 2004 NRC Exam As Given

i i PERFORMANCE CHECKLIST Page 6 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

pG ~

Action Standard Eva1 Comments f 8 Comply with COLR Section 8.0 Limits in TRM. 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:

Comply with Tech Spec LCOs 3.4.1 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.

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

Page 1 of 1 2004 NRC Exam As Given

r' (

PERFORMANCt CHECKLIST Page 7 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments 9 For stopped pump, Place RECIRC A(B) MOV OL See CUE BYPS HV-143-F031A(B)/F032A(B) key switch to TEST position.

Ensure RECIRC PUMP A(B) DSCH BYPS HV-143-F032A(B) OPEN.

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

Within 5 minutes, Open RECIRC PUMP A(B) DSCH HV-143-F031A(B).

AFTER 2 minutes, Place RECIRC A(B) MOV OL BYPS HV-I 43-F031A(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.

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.

IO WHEN cause of trip corrected, Restart Reactor Based on initial conditions, this will Recirculation Pump in accordance with OP-I 64-001 occur later.

Reactor Recirculation System.

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

Page 1 of 1 2004 NRC Exam As Given

i'

/,: ,

PERFORMANCE CHECKLIST Page 8 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

~~

Action Standard Eva1 Comments IF pump will be out of service >I hour, Comply with Determines:

GO-I00-009 Single Recirculation Loop Operation. GO-I 00-009 Single Recirculation Loop Operation will need to be addressed.

EVALUATOR NOTE:

GO-100-009 Single Recirculation Loop Operation was previously provided to determine core flow based on D/P.

Obtains a controlled copy of GO-I 00-009 Previously provided.

Reviews prerequisites, precautions and initial Determines:

conditions. Prerequisites, precautions and initial conditions are applicable.

Complete the following: Records the following on the appropriate spaces:

Date:

Date, time candidate signature and 1A Time:

Reactor Recic pump tripped.

This GO is being performed for the following reason:

Signature:

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

Page 1 of 1 2004 NRC Exam As Given

i' i PERFORMANCt CHECKLIST Page 9 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments 15 Comply with COLR Section 8.0 in TRM. Previously determined.

16 Record following for SHUTDOWN/TRIPPED Circles A recirculation pump.

Identification of SHUTDOWN/TRlPPED pump: A or B 17 Date and time pump ShutdownTTripped. Records the following on the appropriate spaces:

Date, time 18 WHILE in single loop operation: Previously determined If OPERATING recirculation pump speed is ~ 7 5 %

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/hrto keep idle loop warm, if possible.

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

Page Iof 1 2004 NRC Exam As Given

i PERFORMANCli CHECKLIST Page 10 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments 19 Within one hour: 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:

Restart idle recirculation pump in accordance with OP-I 64-001. Sl-I 78-321 Setpoint Calibration for OR APRM Channels A-F (Dual Loop Operation to Single Loop Operation or Single Loop Operation to Dual Loop Perform following:

Operation).

IF recirculation pump to be out of service >I2 hours, SI-I 78-209 Weekly Functional Test THEN Notify I&C to perform the following within 12 Average Power Range Monitor hours. (TS 3.4.1):

(APRM) Channels A-F.

SI-?78-321 Setpoint Calibration for APRM Channels SI-I 78-225 Monthly Functional Test of A-F (Dual Loop Operation to Single Loop Operation or Rod Block Monitor Channels A and B.

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

Page 1 of 1 2004 NRC Exam As Given

<' i' PERFORMANCt CHECKLIST Page 11 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments 20 AFTER I&C completes surveillances per preceding Determines the following SOs will step, Perform following: need completed:

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

EVALUATOR CUE:

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

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

Page 1 of 1 2004 NRC Exam As Given

i' PERFORMANCE CHECKLIST Page 12 of 13 Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 Comments

21 While in Single Loop Operation Determines from Attachment A:

WITHIN 15 minutes prior to Increasing thermal power Tech Spec Surveillance SR 3.4.10.5 or Increasing recirculation loop flow, Complete required actions:

Attachment A if EITHER:

Within 15 minutes PRIOR to thermal power I 30% increasing THERMAL POWER:

OR Verify the difference between the bottom head coolant temperature and OPERATING recirculation loop flow (i.e., jet pump flow) the RPV coolant temperature is 5 145°F is I 50% of rated loop flow (21,320 gpm driving flow)

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

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Page 13 of 13 i

Appl. To/JPM No.: 00.AD.268.001 Student Name:

Step Action Standard Eva1 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. 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 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 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.

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

E. 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 Io f 2

TASK CONDITIONS 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:

I Reactor Dower 1 36% I PlCSY Core Flow 41.14 mlbm/hr PlCSY Core dP (NJP51) 1.87 psid Core Flow dP (XR-B21-1R613) 7.2 %

A Recic Lo00 Flow 0.2 mlhm/hr 1 A Recirc Drive Flow I Oaom -1 A Recirc Jet Pump Flow 0 mlbm/hr 1B Reactor Recic pump speed 45%

B Recic Loop Flow 4.07 mlbm/hr B Recirc Drive Flow 21299 gpm B Recirc Jet Pump Flow 41.1 mlbm/hr 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 2of2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE

.b APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 00.EP.003.082 1 02/17/04 2.4.44 4.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

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 provaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 15 Min Time Critical to classify and 15 Min Time Critical to complete PAR Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

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

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

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

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.

v II I. REACTIVITY MANI PU LATlONS 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 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 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.

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

(:

PERFORMANCE CHECKLIST Page 3 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

This is a Time Critical JPM.

a 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.

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

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

Critical Step #Critical Sequence STCP-QA-12%

Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam As Given

[

PERFORMANCt CHECKLIST Page 4 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments 2 Refers to classification matrix. Selects Table F Fission Product Barrier Degradation

3 Choose appropriate emergency action level. Identifies entry into General Emergency FGI Loss of any TWO fission product barriers with a potential loss of the third.

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 2nd15 minute Time Critical 4 Determines appropriate procedure section. Determines TAB E Manage the General Emergency is the appropriate TAB.

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

Page 1 of 1 2004 NRC Exam As Given

(

PERFORMANCE CHECKLIST Page 5 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments Document and communicate the Emergency Announces to Control Room Personnel:

Classification.

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.

If not performed earlier appoint an Emergency Plan Appoints an Emergency Plan Communicator Communicator and instruct himlher to immediately perform EP-PS-126 E Plan Communicator.

If not performed earlier, appoint an NRC communicator. Appoints an NRC Communicator and instruct him/her to perform EP-PS-135 NRC Communicator Generate and approve an ENR form to be transmitted Refers to ENR Form under Tab 9.

by the Emergency Plan Communicator.

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

Page 1 of I 2004 NRC Exam As Given

PERFORMANCt CHECKLIST Page 6 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments 8 Fill out and approve the Emergency Notification Report Fills out and approves the Emergency Form. Notification Report Form as follows:

LINE I.

Call Status:

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

Page 1 of 1 2004 NRC Exam As Given I

PERFORMANCE CHECKLIST Page 7 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments 10 LINE 3.

Emergency Classification:

status.

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

Candidate may paraphrase this description

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

Page 1 of 1 2004 NRC Exam As Given

i /

PERFORMANCt CHECKLIST Page 8 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

~

Step Action Standard Eva1 Comments 11 LINE 4.

The Emergency action level (EAL) number Is:

Records EAL # FGI 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.

12 LINE 5.

Places a checkmark in the No non-routine radiological release box 13 LINE 6 Records Wind Direction is from: I O 0 Wind Speed is: 5 mph 14 LINE 7.

Conclusion:

Places a checkmark in this is a drill box.

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Page 9 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments

~~ ~~

I5 Approves the Emergency Notification Report Form Records the following on space provided:

Approved: - His/Her name Time: - Current time Date: - Current Date EVALUATOR NOTE:

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

16 Give the approved ENR form to the E Plan Provides the filled out ENR form to the E Communicator. 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 #Critical Sequence STCP-QA-125B Rev. 2,(9193)

Page 1 of1 2004 NRC Exam As Given

i" PERFORMANCE CHECKLIST Page 11 of 14 Student Name:

Step Action Standard Eva1 Comments

I8 Choose appropriate PAR. 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 1 1 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

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

Page 1 of 1 2004 NRC Exam As Given

( (

PERFORMANCt CHECKLIST Page 12 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments 19 Shift Manager/ED shall notify the senior state official Refers to-Tab 9 for PAR State Notification using the PAR state notification form at 717-651-2148 Form.

20 Complete PAR State Notification Form. Completes PAR State Notification Form as follows:

Places a checkmark in This Is A Drill box.

2 LINE 1 This is of the Susquehanna Steam Electric Station.

Records their name 22 LINE 2 Places a checkmark in I am the:

Emergency Director at the Susquehanna SES Control Room box.

EVALUATOR NOTE:

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

Critical Step #Critical Sequence 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 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

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

23 LINE 4 A General Emergency has been declared as of Records the JPM start time EVALUATOR NOTE:

Candidate may paraphrase the reason for declaring a General Emergency.

24 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.

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

Page 1 of 1 2004 NRC Exam As Given

PERFORMANCE CHECKLIST Page 14 of 14 Appl. To/JPM No.: SRO 00.EP.003.082 Student Name:

Step Action Standard Eva1 Comments

25 Enters the PAR on the State Notification Form. LINE 6 The PPL Susquehanna Protective Action Recommendation is:

Places a checkmark in Evacuate 0-2 miles and shelter 2-10 miles and advise citizens to take KI in accordance with the state's emergency plans box.

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

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.

Page 1 of 4 2004 NRC Exam As Given

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.

-+--

Page 2 of 4 2004 NRC Exam As Given

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

B. RPV water level is -21 0 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 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 4 of 4 2004 NRC Exam As Given

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