Text

Draft Section a Operating (RO & SRO) (Folder 2)
	ML042730350
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 50-387/04-302, 50-388/04-302
	Download: ML042730350 (119)
	v • d • e

Appl. To Task

Title:

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

01 I28104 2.1.20 4.314.2 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Complete Aborted Evolution Log Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Approval:

Requesting Supv.1C.A.

Date Nuclear Trng. Supv.

Head Date Date Date of Performance:

JPM Performed By:

10 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #lS.S. #

Performance Evaluation:

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

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

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

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

21) filled out up to step 2.4.13.

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

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

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

NONE IV. TASK CONDITIONS A.

B.

C.

D.

E.

F.

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

During step 2.4.14 TB Chilled Wtr Chem Add Tank Out valve 18801 1 could not be opened.

Maintenance will not be available until dayshift tomorrow to support opening 18801 I valve.

You are the Unit 1 PCOM V. INITIATING CUE Your Supervisor directs you complete the Aborted Evolution Control Log and the administrative activities associated with these conditions as prescribed in OP-AD-002 STANDARDS FOR SHIFT OPERATIONS VI. TASK STANDARD Aborted Evolution Control Log identifies TB Chilled Wtr Chem Add Tank Out valve 18801 1 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.

L' 2004 NRC Exam Rev. 1

i:

Appl. To/JPM No.: 00.AD.038.001 Step PERFORMAN& CHECKLIST Action EVALUATOR NOTE:

0 Ensure a copy of OP-AD-002 Section 8.4 and OP-AD-002 Attachment H is available. OP-I 33-001 2.4 available EVALUATOR NOTE:

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

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

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

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

%Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Determines OP-AD-002 Section 8.4 is appropriate.

Determines:

Attachment H will need to be completed.

Eva1

(:

Page 3 of 7

~~

~

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

Page 1 of 1 2004 NRC Exam Rev. 1

i Page 4 of 7 t

PERFORMANCL CHECKLIST i

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

5 6

7 Action Completes Attachment H of OP-AD-002 by performing the following:

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

+Critical Step

Critical Sequence Student Name:

Standard Places:

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

PI aces :

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

Places:

Procedure number OP-133-001, Revision 20, step 2.4.13 in the spaces provide in line 3 Places:

TB Chilled Wtr Chem Add Tank Out valve 18801 1 could not be opened in the space provide in line 4 Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

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

9 10 PERFORMANCE CHECKLIST Action EVALUATOR NOTE:

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

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

Critical Step

Critical Sequence Student Name:

Standard Places:

NONE in the space provide in line 5 Places:

Restart procedure beginning at step 2.4.14 in the space provide in line 6 Identifies:

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

Eva1

(

Page 5 of 7 Comments STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

i.

Appl. To/JPM No.: 00.AD.038.001 Step X I 1 12 PERFORMANCk CHECKLIST Action Informs Turbine building NPO of Administrative requirements for the aborted evolution.

EVALUATOR CUE:

Role-play Turbine building NPO acknowledge the report.

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

Critical Step

Critical Sequence Student Name:

Standard Informs Turbine building NPO to:

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

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

Original of the AECL is to be maintained by the Unit 1 Control room Supervisor 0

Copy of the AECL is to be maintained with the Plant Operator Turnover sheet.

0 Eva1 Page 6 of 7 Comments STCP-QA-1256 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

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

%I3 PERFORMANCt CHECKLIST Action Informs Unit 1 Control room Supervisor of Administrative req u ire men ts for the aborted evol ut ion.

EVALUATOR CUE:

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

EVALUATOR CUE:

This completes the JPM

+Critical Step

Critical Sequence Student Name:

Standard Informs Unit 1 Control room Supervisor to:

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

(,

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

Page 1 of 1 2004 NRC Exam Rev. 1

1.

2.

3.

.$- 4.

c

(.

5.

ABORTED EVOLUTION CONTROL LOG Attachment H Revision 10 Page 85 of 89 OP-AD-002 System:

Evolution aborted at:

Procedure Number 6 p-33 -00 Rev.

20 Step 2, 4

4 13 Reason procedure stopped or equipment in abnormal alignment.

Task(s) to accomplish prior to restadalignment.

6.

7 I

V PlanVSystem realigned to normal configuration or procedure restarted:

DATE TIME SIGNATURE FORM OP-AD-002-3, Rev. 0, Page 1 of 1

TASK CONDITIONS:

L---

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 2.4.14 TB Chilled Wtr Chem Add Tank Out valve 18801 1 could not be opened.

Maintenance will not be available until dayshift tomorrow to support opening 18801 1 valve.

F. You are the Unit I PCOM INITIATING CUE Your Supervisor directs you complete the Aborted Evolution Control Log and the administrative activities associated with these conditions as prescribed in OP-AD-002 STANDARDS FOR SHIFT OPERATIONS 2004 NRC Exam Rev. 1 1 of2

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 2.4.14 TB Chilled Wtr Chem Add Tank Out valve 18801 1 could not be opened.

Maintenance will not be available until dayshift tomorrow to support opening 18801 1 valve.

F. You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the Aborted Evolution Control Log and the administrative activities associated with these conditions as prescribed in OP-AD-002 STANDARDS FOR SHIFT OPE RATIONS

-=-.--e 2004 NRC Exam Rev. 1 2 of 2

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

00. AD. 037.05 1 0

0 1 I29104 2.1.33 3.414.0 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KIA Task

Title:

Completed By:

Reviews:

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

Russ Halm Writer Date InstructorNVriter Date Ap p rova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

JPM Performed By:

..-/

15/25 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

)

Satisfactory

(

)

Unsatisfactory Eva1 uator Name:

Signature Typed or Printed Comments:

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

Page 1 of 1 2004 NRC Exam Rev. 1 File NO. A14-5B

'V' REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIR0 OO.AD.037.051

1.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

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

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

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

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

NONE IV. TASK CONDITIONS A.

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

6. 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 LFVFR-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 Rev. 1

('

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

PERFORMANCk CHECKLIST

(%

Page 3 of 11 Action EVALUATOR NOTE:

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

Obtain a controlled copy of SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG Selects the correct section to perform.

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

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

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

Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

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

Eva1 Comments STCP-QA-1255 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

i:.

Appl. To/JPM No.: 00.AD.037.051 Step 5

6 7

8 PERFORMAN~L CHECKLIST Page 4 of 11 Action Determine total number of level increases from the last 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period on DRWL SUMPS FLOW & LVL LWFR-I6103 (Point I)

(Alternate: Computer Pt.

RLL004Z) including increase that occurs coincident with start of each pumpdown (indicated by a sharp drop in level; level spike may not be evident).

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

RLL005Z) (Point 2) including increase that occurs coincident with start of each pumpdown (indicated by a sharp drop in level; level spike may not be evident).

Compute total gallons accumulated for DRWL Sump A. (Total Level Increases) (1 9 gal/level) = total gallons.

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

+Critical Step

Critical Sequence Student Name:

Standard Places 109 in the space provided on SO-I 00-006 Attachment F. (item b)

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

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

(I09 X 19=2071)

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

(99 X 21 =2079)

Eva1

=

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

10 11 PERFORMANCk CHECKLIST Action EVALUATOR NOTE:

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

RLL004Z/RLL005Z) (720 mins).

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

EVALUATOR NOTE:

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

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

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

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

Critical Step

Critical Seq ue nce Student Name:

Page 5 of 11 Standard Places 2.88 in the space provided on SO-I 00-006 Attachment F. (item g)

(2071 /720=2.88)

Places 0.02 in the space provided on SO-I 00-006 Attachment F. (item h)

Places 2.86 in the space provided on SO-I 00-006 Attachment F. (item i)

(2.88 - 0.02~2.86)

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

Page 1 of 1 2004 NRC Exam Rev. 1

i' PERFORMAN~L CHECKLIST

(

(:

Page 6 of 11 Appl. To/JPM No.: 00.AD.037.051 Step 12 13 14 15

I 6 Action Determine average inleakage for DRWL Sump B (total gallons)/(elapsed time in minutes) = average inleakage.

EVALUATOR NOTE:

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

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

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

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

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

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

Critical Step

Critical Sequence Student Name:

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

(2079/720=2.89)

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

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

(2.89-0.03=2.86)

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

(2.88 + 2.89 = 5.77)

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

(2.86 + 2.86 = 5.72)

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

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCt CHECKLIST

(:

Page 7 of 11 Appl. To/JPM No.: 00.AD.037.051 Step 17 18 19 20 21 Action After 0900 average inleakage calculation, Enter average inleakage recorded for both 2100 and 0900 in steps g. and j. to next day's worksheet to be used as 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous values in steps h. and k. for 2100 and 0900, respectively.

EVALUATOR CUE:

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

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

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

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

Determine average inleakage for DRWL Sump A.

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

Critical Step

Critical Sequence Student Name:

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

(494 + 2071 =2565)

Places 2394 in the space provided on SO-100-006 Attachment M. (item 1 b)

(31 5 + 2079=2394)

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

(2565/1440=1.78)

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

Page 1 of 1 2004 NRC Exam Rev. 1

('

Appl. To/JPM No.: 00.AD.037.051 Step 22

=

23 24 25 26 27 (L

Page 8 of I 1 i'

PERFORMAN& CHECKLIST Action Determine average inleakage for DRWL Sump B.

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

Computer Pt. RLLOOGZ).

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

RLL006Z). (Total %) (8.5 gal/%) = total gallons Example: (380%) (8.5 gal) = 3230 gallons Determine total elapsed time in minutes from last 24 hr time mark on LEVEL RECORDER LR/FR-l6103 (Alternate: Computer Pt. RLLOOGZ) (1440 minutes).

Determine average inleakage recorded on LEVEL RECORDER LWFR-I6103 (Alternate: Computer Pt.

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

average inleakage.

Compute TOTAL DRYWELL LEAKAGE Record average leakrate from step 1.d.

+Critical Step

Critical Sequence Student Name:

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

(2394/1440=1.66)

Places 268 in the space provided on SO-100-006 Attachment M. (item 2a)

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

(268 X 8.5=2278)

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

(2278/1440=1.58)

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

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

PERFORMANCE CHECKLIST

(

Page 9 of 11 Action Record average leakrate from step 1.e.

Record average leakrate from step 2.d.

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

EVALUATOR CUE:

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

EVALUATOR NOTE:

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

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

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

Page 1 of 1 2004 NRC Exam Rev. 1

Critical Sequence Student Name:

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

Places 1.58 in the space provided on SO-100-006 Attachment M. (item 3c)

Places 5.02 in the space provided on SO-100-006 Attachment M. (item 3d)

(1.78 f 1.66 + 1.58 = 5.02)

Eva1 Comments

Appl. To/JPM No.: 00.AD.037.051 31

32

(:

PERFORMANCL CHECKLIST Page 10 of 11 Action Compares calculated values to the ACCEPTABLE values listed in item A21 of SO-100-006 SHIFTLY SURVEILLANCE OPERATING LOG.

Report the results of the calculation and determination.

EVALUATOR CUE:

Role-play Control room supervisor and acknowledge the report.

EVALUATOR CUE:

This completes the JPM for the ROs ONLY

Critical Step

Critical Sequence Student Name:

Standard Compares calculated values to the ACCEPTABLE values listed in item A21 SURVEILLANCE OPERATING LOG.

of SO-I 00-006 SH I FTLY AND Determines that the 5.77 gpm leakrate calculated in step m of attachment F is GREATER Than Tech Spec allowable value of 5 5 gpm.

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

r e c h Spec 3.4.4.b RCS]

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

Page 1 of 1 2004 NRC Exam Rev. 1

Appl. To/JPM No.: 00.AD.037.051 pG-33

34 PERFORMANCE CHECKLIST Action EVALUATOR CUE:

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

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

Critical Step

Critical Sequence Page 11 of 11 Student Name:

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

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

Enter MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

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

('

(:

PERFORMANCi CHECKLIST Page 12 of 11 Student Name:

Action Standard I Eva1 I Comments EVALUATOR CUE:

This completes the JPM.

acritica'l Step

Critical Sequence STCP-QA-1258 Rev. 2 (993)

Page 1 of 1 2004 NRC Exam Rev. 1

W A NS E Attachment F SO-1 00-006 Revision 43 Page 119 of 136 DRYWELL FLOOR DRAIN INLEAKAGE CALCULATION WORKSHEET (1)

(ADHERENCE LEVEL - STEP-BY-STEP)

NOTE:

Circle Alternate if used.

a.

b.

C.

d.

e.

f.

g*

&,!:.:?i 1.<'.!

'4..-

h.

i.

j.

k.

I.

m.

n.

Time 21 00 Total Level increases LR/FR-16103 Sump A Total Level increases LR/FR-16103 Sump B Z L 5

m gal (Alternate: Computer Pt. RLL004Z)

(Alternate: Computer Pt. RLLOOSZ)

Total Gallons DRWL SUMP A (Total Levels) x (1 9 gal/level)

Total Gallons DRWL SUMP B (Total levels) x (21 gal/level)

Total elapsed time 720 min Average inleakage DRWL SUMP A Average inleakage from previous day Delta inleakage DRWL SUMP A (g-h)

.64gPm (total gal)/(elapsed time) (d/f) 802 -

gpm (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous) for DRWL SUMP A

,bl gpm Average inleakage DRWL SUMP B (total gal)/(elapsed time) (e/f)

Average inleakage from previous day Delta inleakage for DRWL SUMP B (j-k)

L 03 gpm 4

gpm Total average inleakage (g+j) < 5 gpm required i o 13 gpm Total delta inleakage (i+l) < 2 gpm/24 hours

~

gpm required (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous) for DRWL SUMP B 0900 M

2071 gal 2474 gal i_,

Page 1 of 1

Attachment M Revision 43 Page 130 of 136 DRYWELL LEAKAGE CALCULATION WORKSHEET SO-I 00-006 (ADHERENCE LEVEL - STEP-BY-STEP)

NOTE:

Leakage is calculated for the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

b.

Total gallons DRWL Sump 6 (From Attachment F)

c.

Total elapsed time for 24 hr period 1440 min 1440 min

d.

Average inleakage DRWL Sump A d 63 gpm i J B gpm-.

e.

Average inleakage DRWL Sump B e i 4 gpm llb4 gpm (Total gallons)/(elapsed time)

(Total gallons)/(elapsed time)

2.

DRYWELL EQUIPMENT DRAIN LEAKAGE (Identified Leakage)

NOTE:

Circle Alternate if used.

a.

Total percent (Primary: LR/FR-16103)

(Alternate: Computer Pt. RLLOOGZ)

b.

Total gallons (Total percent) (8.5 gal/%)

c.

Total elapsed time for 24 hr period

d.

Average inleakage (Total gallons)/(elapsed time)

3.

TOTAL DRYWELL LEAKAGE

a.

Drywell Floor Drain (Step 1.d) (Unidentified)

b.

Drywell Floor Drain (Step 1.e) (Unidentified)

c.

Drywell Equipment Drain (Step 2.d) (Identified)

d.

Total leakrate (a+b+c) required I 25 gpm 267 268 %

22L% 5 gal 227 8 gal 1440 min 1440 min 1058 gpm 1 ~ 5 8 gpm Page 1 of 1

L-SRO ONLY TASK CONDITIONS Unit I is in Mode 1.

A.

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

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

2004 NRC Exam Rev. I 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@), including time limits, idare required as a result of this determination?

2004 NRC Exam Rev. I 20f4

TASK CONDITIONS A.

u B.

C.

D.

E.

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

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

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

2004 NRC Exam Rev. 1 3 o f 4

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 I09 in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Total level increases on LWFR-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 Rev. 1

a.

b.

C.

d.

e.

f.

g.

p-.

L

h.

i.

j.

k.

I.

m.

n.

Attachment F Revision 43 Page 119 of 136 SO-100-006 DRYWELL FLOOR DRAIN INLEAKAGE CALCULATION WORKSHEET (I)

(ADHERENCE LEVEL - STEP-BY-STEP)

NOTE:

Circle Alternate if used.

Time Total Level increases LR/FR-16103 Sump A (Alternate: Computer Pt. RLL004Z)

Total Level increases LR/FR-16103 Sump B (Alternate: Computer Pt. RLLOOSZ)

Total Gallons DRWL SUMP A (Total Levels) x (1 9 gal/level)

Total Gallons DRWL SUMP B (Total levels) x (21 gal/level)

Total elapsed time Average inleakage DRWL SUMP A (total gal)/(elapsed time) (d/f)

Average inleakage from previous day (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous) for DRWL SUMP A Delta inleakage DRWL SUMP A (g-h)

Average inleakage DRWL SUMP B (total gal)/(elapsed time) (e/f)

Average inleakage from previous day (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months previous) for DRWL SUMP B Delta inleakage for DRWL SUMP B 0-k)

Total average inleakage (g+j) < 5 gpm required Total delta inleakage (i+l) c 2 gpm124 hours required 21 00 0900 Z b 720 min 720 min 4

r-gpm dY gpm J

Page 1 of 1

Attachment M Revision 43 Page 130 of 136 DRYWELL LEAKAGE CALCULATION WORKSHEET SO-1 00-006 (ADHERENCE LEVEL - STEP-BY-STEP)

1.

DRYWELL FLOOR DRAIN LEAKAGE (Unidentified Leakage) 21 00 0900 to to 21 00 0900 NOTE:

Leakage is calculated for the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

a.

Total gallons DRWL Sump A Yo&

gal gal (From Attachment F)

b.

Total gallons DRWL Sump B (From Attachment F)

c.

d.

Total elapsed time for 24 hr period Average inleakage DRWL Sump A (Total gallons)/(elapsed time)

Average inleakage DRWL Sump B (Total gallons)/(elapsed time)

e.

2.

DRYWELL EQUIPMENT DRAIN LEAKAGE (Identified Leakage) 1440 min 1440 min I NOTE:

Circle Alternate if used.

I

a.

Total percent (Primary: LR/FR-16103)

'f 267 (Alternate: Computer Pt. RLLOOGZ)

b.

Total gallons (Total percent) (8.5 gal/%)

c.

Total elapsed time for 24 hr period

d.

Average inleakage (Total gallons)/(elapsed time) 1440 min 1440 min

3.

TOTAL DRYWELL LEAKAGE

a.

Drywell Floor Drain (Step 1.d) (Unidentified) g 6 3 gpm gpm

b.

Drywell Floor Drain (Step I.e) (Unidentified)

' 14 gpm gpm

c.

Drywell Equipment Drain (Step 2.d) (Identified)

I d

59 gpm gpm

d.

Total leakrate (a+b+c) required s 25 gpm 21 3 5 gpm gpm 4

Page 1 of 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO OO.SO.003.051 0

02/17/04 2.2.12 3.0/3.4 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Determine Jet Pump Operability Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Head Date of Performance:

JPM Performed By:

Date Date 30 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO OO.SO.003.051

1.

SAFETY CONSIDERATIONS v

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

I I I. REACTIVITY MAN I PU LATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A.

Unit 1 is operating at 100% power.

B.

Both Reactor Recirc pumps and Loops are in operation.

C.

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

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

RECIRCULATION SYSTEM DUAL LOOP of SO-I 00-007, DAILY SURVEILLANCE LOG, RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG VI. TASK STANDARD Recirculation pumps declared OPERABLE; Jet pumps declared INOPERABLE 2004 NRC Exam Rev. 1

Page 3 of 13

(

PERFORMANCt CHECKLIST Appl. To/JPM No.: OO.SO.003.051 Step Action EVALUATOR NOTE:

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

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

Selects the correct section to perform.

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

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

Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Selects Item 1 Determines attachment C is applicable Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMAN& CHECKLIST Appl. To/JPM No.: OO.SO.003.051 Step Action Recirc pumps operable if loop jet pump flow mismatch maintained within a or b: Enter N/A for item that does not apply.

a. 5 Mlbm/hr with core flow 2 75 Mlbm/hr

b. 10 Mlbm/hr with core flow 5 75 Mlbm/hr

Critical Step

Critical Sequence Student Name:

(;

Page 4 of 13 Standard On Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Compares line g to h Determines that the mismatch between Loop A and Loop B is I Mlbm/hr Records: 1 Mlbm/hr on SR 3.4.1.I line a Records: N/A on SR 3.4.1.I line b Determines Recirc Pumps are operable Circles YES and initials Confirm on SR 3.4.1.1 line Records: SAT on Recirc Pumps line of item 1 of SO-100-007 Daily Surveillance Log Attachment A Eva1 Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

Appl. To/JPM No.: OO.SO.003.051 Step 6

i PERFORMANCt CHECKLIST Page 5 of 13 Action EVALUATOR NOTE:

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

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

EVALUATOR CUE:

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

Critical Step

Critical Sequence Student Name:

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

OR Notifies SRO to contact Reactor Engineering.

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

Page 1 of 1 2004 NRC Exam Rev. 1

[:

(

(,

PERFORMANCt CHECKLIST Page 6 of 13 Appl. To/JPM No.: OO.SO.003.051 Step 7

Action When Fcirc 8' umps operating with flow within limits of a or b above, jet pumps operable if no two (2) following conditions exist simultaneously:

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

Critical Step

Critical Sequence Student Name:

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

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

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

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

AND RECIRC PUMP B FLOW (KGPM) of 33 KGPM Circles YES and initials Confirm on SR 3.4.2.1 line a Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

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

PERFORMANCt CHECKLIST

(

Page 7 of 13 Action Recirculation loop drive flow versus total core flow differs > 10% from established patterns. (Plot applicable performance data on Figures 3 and 4 of this attachment)

EVALUATOR NOTE:

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

Critical Step

Critical Sequence Student Name:

Standard On Figure 3 TOTAL CORE FLOW VS.

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

RECIRC PUMP A FLOW (KGPM) (FR-B31-1R614) 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-B31-1R614) of 33 KGPM AND TOTAL CORE FLOW MLB/HR of 92 MLB/HR Circles NO and initials Confirm on SR 3.4.2.1 line b Eva1 Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

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

(

PERFORMANCk CHECKLIST Page 8 of 13 Action Calculates LOOP A JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE to be used in Plotting applicable performance data on figure 1 of attachment I

Critical Step

Critical Sequence Student Name:

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

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

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

3. JP13_34_(JP13 - A) + A X 100 =---.87-

4. JP14_35-(JP14 - A) + A X 100 =-2.04-

5. JPI5_35-(JP15 - A) f A X 100 =-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) 4 A X 100 =--.87-

9. JP19_35-(JP19 -A) f A X 100 =-2.04-I O. JP20_32-(JP20 - A) + A X 100 =--6.71-A =-343 X 0.1 = -34.3-(Sum of AP%)

JP11 thru 20 Eva1 Comments STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. I

(.

PERFORMANb CHECKLIST Page 9 of 13 i:

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

Critical Step

Critical Sequence Student Name:

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

1.

2.

3.

4.

5.

6.

7.

JP1_3Q-(JPI - A) f A X 100 =-3.17-JP2_3Q-(JP2 -A) f A X 100 =-3.17-JP3_37_(JP3 -A) f A X 100 =--2.I2-JP4_3Q_(JP4 - A) + A X 100 =-3.17-JP5_3Q_(JP5 - A) f A X 100 =-3.17-JP6_39-(JP6 - A) f A X I00 =-3.17-JP7_3O-(JP7 - A) f A X 100 =--20.63-

8. JP8_39-(JP8 - A) f A X 100 =-3.17-

9.

IO. JP10-38-(JPIO - A) + A X 100 =-.53-JP9_3Q-(JP9 -A) f A X 100 =-3.17-A =-378 X 0.1 = -37.8-(Sum of AP%)

JPI thru 10 Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

Appl. To/JPM No.: OO.SO.003.051 Step 11 i

PERFORMANCt CHECKLIST i

Page 10 of 13 Action Each jet pump to lower plenum differential pressure differs by > 20% from the established patterns, (Plot applicable performance data on figures 1 and 2 of attachment I

Critical Step

Critical Sequence Student Name:

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

JP11 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

+20% from the established patterns Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCE CHECKLIST i

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

Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1 i

Page 11 of 13 Student Name:

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

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

Appl. To/JPM No.: OO.SO.003.051 Eva1 Step Comments

I3 i'

PERFORMANCE CHECKLIST Page I2 of 13 Action When$ecirc,&umps operating with flow within limits of a or b above,$

F m p s operable if no two (2) following conditions exist simultaneously:

Critical Step Student Name:

Standard Determines Jet umps are NOT conditions under SR 3.4.2.1 not being met simultaneously.

operable base F on two (2) of the 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 Sequence STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. I

i' PERFORMAN& CHECKLIST Appl. To/JPM No.: OO.SO.003.051 Action Reports the results of the surveillance.

EVALUATOR CUE:

Role-play shift supervision and acknowledge the report.

EVALUATOR CUE:

That completes this JPM

Critical Step

Critical Sequence STCP-QA-lZ5B Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

(

Page 13 of 13 Student Name:

Standard Informs the supervisor that the Jet Fmps 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.

Comments

ACCEPTANCE CRITERIA for DUAL LOOP SR3.4.1.1 Recirc Pumps OPERABLE if loop jet pump flow mismatch maintained within a or b: Enter NA for item that does not apply.

a.

5 Mlbm/hr with core flow 2 75 Mlbm/hr.

b.

10 Mlbm/hr with Core Flow 75 Mlbm/hr.

L:

SR 3.4.2. I When recirc pumps operating with flow within limits of a or b above, Jet Pumps OPERABLE if no two (2)jollowing conditions exist simultaneously:

NOTE:

IF any of these conditions exist, or, E any parameter differs by more than 5% of established value, Notify Reactor Engineering.

Attachment C Revision 37 Page 23 of 56 SO-I 00-007 ACCEPTABLE CONFl RM

/so Mlbm/hr.

Mlbm/hr.

a.

Recirculation loop drive flow versus recirculation generator speed differs > 10%

from established patterns. (Plot applicable performance data on Figures 1 and 2 of this attachment.)

Recirculation loop drive flow versus total core flow differs > 10% from established patterns.

(Plot applicable performance data on Figures 3 and 4 of this attachment.)

b.

NOTE:

Perform ONLY IF a or b above fail. Record applicable data on pages 3 and 4 of this Attachment.

c.

Each jet pump to lower plenum differential pressure differs by > 20% from established patterns, (Plot applicable performance data on Figures 1 and 2 of Attachment I.)

AS FOUND

' 'V Page 2 of 8

Attachment C Revision 37 Page 24 of 56 SO-I 00-007 LOOP A JET PUMP AP PERCENT DEVfATlON FROM THE AVERAGE A = Average Jet Pump AP Loop A (Calculate below)

JP AP%

% JP AP Dev.

1.

JP1 I 34 (JPII -A)+AXlOO= -

s, 87 PLOT ON

2.

JP12 3 5 (JPl2-A)+AX100=

290 4 ATTACHMENT I FIG. 1

3.

JP13 3 4 (JP13-A)+AXl00= +?

7

4.

JP14 ssp (J P I 4 - A) + A X 1 00 = 2:o 4

7.

JP17 3 4 (JP17-A)+AXIOO= -dl7

5.

JPI 5 3 5 (JP15-A)+AX100= 2.04

6.

JP16 3 s (JPIG-A)+AX 100= 2404

,-.-- i

8.

JP18 3 4 (JP18-A)+AX100=.

- I & 7

9.

JPI 9 3 5 (JP19-A)sAX100= 2,04 I O.

JP20 3

(JP20-A)+AXIOO= - 6 4 A = 343 XO.1= 39.3 (Sum of AP%)

J P l l thru 20 i L Page 3 of 8

Attachment C Revision 37 Page 25 of 56 SO-100-007 LOOP B JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE B = Average Jet Pump AP Loop B (Calculate below)

JP AP%

% JP AP Dev.

1.

JPI

2.

JP2

3.

J P3

4.

JP4

5.

JP5

6.

J P6

7.

8.

JP7 JP8

9.

J P9 I O.

JPIO

.37 (JPI -B)+BXlOO=

31 17 PLOT ON FIG. 2 39 (JP2-B)+BX100=

-??* 17 ATTACHMENT I 3 7 (JP3-B)+BXl00=

-2312.

3 7 (JP4 - B) + B X 100 =

3,1'7 3 7 (JP5-B)iBX100=

3.1 1 37 (JP6-B)sBX100=

3,17 9

(JP8-B)+BXXOO=

3.9 1 7 3 0 (JP7 - B) + B X 100 = - Z0,b 3 4

(JP9-B)+BX100=

3. i7 3 8 (JPIO-B)sBXIOO=

4 53 JPI thru 10 i.

I \\.--

Page 4 of 8

Attachment C SO-I 00-007 I

Revision 37 Page 26 of 56 FIGURE - 1 RECIRC PUMP A FLOW VS. SPE ED TWO LOOP OPERATION 60 50 2

y 20 n

IO 0

20 30 40 60 60 70 80 90 t 00 RECIRC GENERATOR A SPEED - % (SI - 14032A)

Attachment C Revision 37 Page 27 of 56 SO-1 00-007 FfGURE - 2 RECIRC PUMP B FLOW VS. SPE ED TWO LOOP OPERATION v

i'...

20 30 40 50 60 70 80 90 100 RECIRC GENERATOR B SPEED - % (SI-140328) v-Page 6 of 8 I.

Attachment C Revision 37 Page 28 of 56 SO-1 00-007 FIGURE - 3 TOTAL CORE FLOW VS. REClRC PUMP A FLOW TWO LOOP OPERATION 0

10 20 30 40 so 60 70 REClRC PUMP A FLOW (KGPM) (FR-BW-lR614)

Page 7 of 8

Attachment C Revision 37 Page 29 of 56 SO-I 00-007 FIGURE - 4 TOTAL CORE FLOW VS. RECIRC PUMP B FLOW w o LOOP OPERATION 0

10 20 30 40 50 60 70 RECIRC PUMP B FLOW (KGPM) (FR-B31-1R614)

Page 8 of 8

Attachment i Revision 37 Page 54 of 56 SO-100-007 FIGURE 1 TWO LOOP JET PUMP DISTRIBUTION LOOP A 30 20 c

I I

11 12 13 14 1s 16 17 18 19 20 JET PUMP NUMBER Page 1 of 2

FIGURE 2 TWO LOOP JET PUMP DISTRIBUTION LOOP B Attachment I Revision 37 Page 55 of 56 SO-I 00-007 40 30 1

2 3

4 6

6 7

8 9

10 Jf3' PUMP NUMBER Page 2 of 2

TASK CONDITIONS A.

Unit I is operating at 100% power.

B.

Both Reactor Recirc pumps and Loops are in operation.

C.

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

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

RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG, RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG 2004 NRC Exam Rev. I 1 of2

TASK CONDITIONS L-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-100-007, DAILY SURVEILLANCE LOG.

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

RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG, RECIRCULATION SYSTEM DUAL LOOP Of SO-I 00-007, DAILY SURVEILLANCE LOG 2004 NRC Exam Rev. I 2 of 2

Attachment C Revision 37 Page 22 of 56 SO-100-007 PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP Record following data:

PARAMETEWINSTRUMENT PANEL READ IN G

a.

GEN 1A SPEED SI-14032A

b.

GEN 16 SPEED SI-14032B I C651 237 O h 1 C651 88-Yo

c.

RECIRC DRIVE FLOW A Primary: FR-B31-1R614 1C652 3 8 Kgpm (Red)

Alternate: FI-B31-1 R617

d.

RECIRC DRIVE FLOW B Primary: FR-B31-1R614 IC652 3 3 Kgpm (Blue)

Alternate: FI-B31-1 R613 L

e.

TOTAL CORE FLOW XR-B2I-lR613 (Red)

IC652 72 Mlb/hr 4

f.

CORE PLATE DP XR-B21-1R613 (Blue) 1 C652 54 %

g.

LOOP A JET PP FLOW FI-B21-1R611A,

IC652 48 t Mlb/hr

h.

LOOP B JET PP FLOW FI-B21-1R611B IC652

4. 7 Mlb/hr I.

JET PUMP DELTA PS JET PUMP INST PANEL 1 C619 UPPER RELAY ROOM JPlO 38%

Continue Recirc Pump/Jet Pump OPERABILITY determination on page 2 of this Form using data above.

L,

~

Page 1 of 8

SRO Appl. To Task

Title:

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

99. OP.002.00 1 0

03/0 1 /04 2.1.25 2.8/3.1 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

K/A Respond to Seismic Monitor System Triggered Completed By:

Reviews:

Russ Halm Writer Date InstructorNVriter Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Head Date Date Date of Performance:

JPM Performed By:

L-15 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

--..-/

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

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

L REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 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.

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

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

2. OP-099-002, Seismic Monitoring System (Revision 1 I )

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

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

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

B. AR-Ol6-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 I 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 i,

2004 NRC Exam Rev. 1

Page 3 of 8 i'

PERFORMAN& CHECKLIST

('

Appl. To/JPM No.: 99.0P.002.001 Action EVALUATOR NOTE:

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

EVALUATOR NOTE:

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

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

Review the prerequisites.

EVALUATOR CUE:

If necessary, Remind the candidate that the evaluation is to be limited to channel 1 ONLY.

Review all precautions.

%Critical Step

Critical Sequence Student Name:

Standard Controlled copy obtained.

Selects section 3.2 Ensures all prerequisites have been met.

Follows all precautions as applicable.

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

Page 1 of 1 2004 NRC Exam Rev. 1

Appl. To/JPM No.: 99.OP.OO2.001 Step

5 6

PERFORMANCt CHECKLIST Action REVIEW printer output and panel indicating lights to determine type of event.

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

Attachment C provides example printouts for further assistance.

CONTACT one of the agencies in Attachment D to confirm the cause of the event was seismic activity.

Critical Step

Critical Sequence Student Name:

Standard Compares the Seismic Monitor printer information and panel indicating light status Attachments A, B, and C Determines that a Safe Shutdown Earthquake (SSE) has occurred Simulates contacting one of the following agencies:

0 National Earthquake Information Center Golden, Colorado PA Bureau of Topographic &

Geologic Survey Penn State Unive~rsity (PSU)

Geosciences Office 0

University of Delaware Delaware Geological Survey Columbia University Eva1 i'

Page 4 of 8 Comments STCP-QA-lZ5B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

4:

PERFORMANCE CHECKLIST Page 5 of 8 Action EVALUATOR CUE:

i' Standard Appl. To/JPM No.: 99.0P.002.001 Student Name:

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

EVALUATOR CUE:

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

appropriate steps of ON-000-002 Natural Phenomena.

Obtain a controlled copy of ON-000-002 Natural Phenomena Determines that ON-000-002 Natural Phenomena performance will be required in parallel with completing this procedure.

Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

10 11 PERFORMANCt CHECKLIST Page 6 of 8

%Critical Step Action Record date and time of event.

Notify Security of event.

EVALUATOR CUE:

Role-play Plant Security and acknowledge the report.

Based on event occurrence, Perform following as applicable:

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

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

Critical Sequence Student Name:

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

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

Refers to section 3.7 Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. To/JPM No.: 99.OP.OO2.001 Step

I 2 13 14 15 16 Action EVALUATOR NOTE:

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

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

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

Evaluates information.

Refers to classification matrix.

Reviews the table of contents for Natural Phenomena.

%Critical Step

Critical Sequence Student Name:

Standard Determines both Units need to be shutdown in accordance with GO-100-004 (GO-200-004), Plant Shutdown to Minimum Power.

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

Identifies SSE as Emergency Plan entry.

Selects OA3.

Reviews all of Category OA3.

Eva1 i:;

Page 7 of 8 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

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

I7 i

PERFORMANCt CHECKLIST Page 8 of 8 Action Choose appropriate emergency action level.

EVALUATOR CUE:

That completes this JPM

Critical Step

Critical Sequence Student Name:

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

Classifies the event as a Alert Eva1 I Comments STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

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 Rev. I 1 Of3

TASK i--

A.

B.

C.

D.

E.

CONDITIONS Both Units are operating at 100% power.

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

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

Ground motion can be felt in the control room.

V. INITIATING CUE You are the shift manager.

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

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

2004 NRC Exam Rev. I 2 of 3

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

VRS-05703 Status

~

Strong Motion Accelerograph System Trigger

~

RSA-50 Data light Cassette Tapes VAH-15701 and VAH-05701 OBE Lights VAH-15701 and VAH-05701 SSE Lights Inner Analog Light

~

Outer Analog Light 2004 NRC Exam Rev. 1 3 0 f 3 Red Green Was Red for approximately 15 seconds, Now it is OFF Recorded for approximately 15

seconds, Now they are idle.

Green Green Red Red

~

For Information Only Indicators Attachment A Revision 11 Page 8 of 11 OP-099-002 less than OBE r--

VAH-15701 and VAH-05701 VAH-15701 and VAH-05701 SSE Lights Green OBE Lights Green EVENT CLASSIFICATION X

Inner Analog Light Red VRS-05703 Status Red I X

X Outer Analog Light Red Printing 3 columns (freq, value, setpoint)

in 3rd column Printing 3 columns (freq, value, setpoint) ** in 3rd column OBE X

X Strong Motion Accelerograph System Trigger Green X

X RSA-50 Data light (on approximately 15 sec)

Red X

X Cassette Tapes Recording (Approximately 15 sec)

X X

Printing 51 frequencies with values in two columns X

X I

Each event classification should receive all of the above list indicators. Omissions or additions of indicators are a means of validating or discrediting the response.

.Page 1 of 1

For Information O n l y L,

1.

2.

3.

L

4.

5.

6.

7.

I

8.

9.

Attachment B Revision 11 Page 9 of 11 OP-099-002 VALIDATION OF A SYSTEM TRIGGER AND CLASSIFICATION System triggers are initiated from VT-05701 (ESW pumphouse), VT-15701 (Unit 1 Containment Foundation), and VT-25701 (Unit 2 Containment Foundation). Only the data from VT-05701 and VT-15701 will printout. The printout will list frequencies, measured values and in the case of an OBE or SSE, the setpoints and flags. Each detector (vr) will supply x, y, and z directional data.

To validate a trigger, all of the indications listed in the table of Attachment A should be seen for the given classification. Channefs 1, 2, and 3 of the printout corresponded to the x, y, and z direction of VT-15701 while channels 4, 5, and 6 corresponded to x, y, and z of VT-05701. Since both detectors are separated from each other, a seismic event will appear similar at each location. Both the affected frequencies and directions will be similar, however, the measured values may differ.

When comparing events less than the OBE, all 51 frequencies will print with their measured values. For OBE or SSE events, only the frequency exceeding its setpoint will be printed. See Attachment C for examples. Compare the x direction (Channels 1 and 4), y direction (Channels 2 to 5) and the z direction (Channels 3 to 6) data from the two detectors. Similar responses in direction and affected frequencies is indicative of a valid seismic event.

Invalid seismic events typically show a response from a single detector which is indicative of the detector being bumped, or equipment induced vibration. An initiation of a trigger from VT-25701 with no response measured on VT-05701 or VT-15701 may indicate the source is induced from a local evolution in Unit 2 Rx Bldg.

Earthquakes of OBE or SSE strength are expected to be felt by personnel onsite.

If the event trigger is declared valid, IMMEDIATELY enter ON-000-002.

If validity is uncertain, outside organization should be contacted to confirm or dismiss the event. Attachment D lists agencies and phone numbers.

If event is invalid NOTIFY 1&C to determine cause or need to PERFORM S1-099-201.

Review TR 3.3.2 for applicability.

Page 1 of 1

\\---

A-

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

VRS-05703 Status Strong Motion Accelerograph System Trigger RSA-50 Data light Cassette Tapes VAH-15701 and VAH-05701 OBE Lights VAH-15701 and VAH-05701 SSE Lights Inner Analog Light Outer Analog Light 2004 NRC Exam Rev. 1 3 0 f 3 Red Green Was Red for approximately 15 seconds, NOW it is OFF Recorded for approximately 15

seconds, Now they are idle.

Green Green Red Red

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 00.AD.269.00 1 0

03/02/04 2.3.10 2.9/3.3 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA Task

Title:

Identify The Blocking Points For A Primary Containment Entry While At Power/Additional power restrictions/controls required by NDAP-QA-0309, Primary Containment Access And Control.

Completed By:

Reviews:

Russ Halm Writer Date I nst ru ctor/VV ri te r Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head L-' Date of Perform an ce :

JPM Performed By:

15/20 Allowed Time (Min.)

Time Taken (Min.)

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. (9193)

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

L-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIR0 OO.AD.269.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

E. 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 NDAP-QA-0323, Standard Blocking Practices (Revision 20)

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

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

NONE W

IV. TASK CONDITIONS A. Unit 1 is pelforming a plant startup.

B. Reactor power is 10%

C. Both reactor recirc pumps are in operation at minimum speed D. A reactor coolant leak exists inside the primary containment, E. A Primary Containment entry is being planned to investigate the reactor coolant leak.

F. Containment has NOT been inerted.

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

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

I.

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

V. INITIATING CUE Your supervisor directs you to prepare a Containment Entry clearance order, IAW NDAP-QA-0309, Primary Containment Access And Control, to support this primary containment entry at Unit 1. Be sure to include the required position and type of tag that will be applied.

(Use the attached sheet to document your blocking points).

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 restrictions/controls required by NDAP-QA-0309, Primary Containment Access And Control

~-..-i 2004 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Page 3 of 8 Appl. To/JPM No.: 00.AD.269.001 Student Name:

Action EVALUATOR NOTE:

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

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

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

(steps 3 - 10 of this JPM)

Standard

/

Controlled copy obtained.

Selects section 8.8.1 Identifies the need to:

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

Position N/A No tag required Records on attached form Identifies the need to OPEN breaker 1 Y21927 Tip Drive Mechanisms 1 S215A-E and RED TAG Records on attached form Eva1 Comments

+Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1

1:

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

5

6 7

PERFORMAN& CHECKLIST Action

Critical Step

Critical Sequence Student Name:

Standard Identifies the need to install a spectacle flange at IS2104 N2 Purge Line To U1 Containment and RED TAG Records on attached form Identifies the need to CLOSE valve 157026 Contn N2 Makeup Supply Hdr Is0 Vlv and RED TAG Records on attached form Identifies the need to:

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

Page 4 of 8 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Page 5 of 8 Appl. To/JPM No.: 00.AD.269.001 Student Name:

Step 8

9 Action EVALUATOR NOTE:

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

Standard 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 Identifies the need to:

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

Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

I O 11 12

(:

PERFORMANCt CHECKLIST Action 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 restrictions/controls.

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

Critical Step

Critical Sequence Student Name:

Standard Identifies the need to:

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

References section 6.5 Eva1 Page 6 of 8 Comments STCP-QA-1256 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Page 7 of 8 A

I. To/JPM N Step

I 3

I4

00.AD.269.001 Action EVALUATOR NOTE:

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

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

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

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

Critical Step

Critical Sequence Student Name:

Standard Reports to the Shift Manager the following:

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

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

Reports to the Shift Manager the following:

Reactor power is restricted to 10% for this entry Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2004 NRC Exam Rev. I

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

I 5

I 6 17 PERFORMAN& CHECKLIST Action No action shall be taken to change Reactor power levels (e.g., no control rod movements, steady recirc pump speed, steady EHC pressure setpoints, etc.)

during power entries.

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

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

EVALUATOR CUE:

That completes this JPM.

Critical Step

Critical Sequence Student Name:

Standard Reports to the Shift Manager the following:

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

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

Reports to the Shift Manager the following:

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

Eva1 Page8of8 I'

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

Critical components are identified with an asterisk (*)

COMPONENT ID

3rclY21927 3rclS2104

157026 DRYWELL ACCESS DOOR NAME ENSURE ALL TIPS WITHDRAWN TO IN SHIELD POSITION WITH BALL VALVES CLOSED PRIOR TO APPLY IN G BLOCK1 N G.

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

APPLY COVER OVER CONTROL ROD CONT INSERT ROD AND CONT W/DRAW PUSHBUTTONS ON IC651 TO PREVENT ROD MOVEMENT IAW NDAP-QA-0309 APPLY COVER OVER CONTROL ROD INSERT ROD AND WIDRAW ROD PUSHBUTTONS ON IC651 TO PREVENT ROD MOVEMENT IAW NDAP-QA-0309 POSITION NA OPEN BLANKED CLOSE N/A N/A N/A N/A TAG NO TAG RED TAG RED TAG RED TAG NO TAG NO TAG PINK TAG PINK TAG 2004 NRC Exam Rev. 1 5 of 6

c-SRO ONLY TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Reactor power is 10%

Both reactor recirc pumps are in operation at minimum speed.

A reactor coolant leak exists inside the primary containment.

A Primary Containment entry is being planned to investigate the reactor coolant leak.

Containment has NOT been inerted.

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

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

The necessary blocking points to support this entry have been applied.

INITIATING CUE As the Unit Supervisor, what additional power restrictionslcontrols 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 Rev. I 1 of6

SRO ONLY TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Reactor power is 10%

Both reactor recirc pumps are in operation at minimum speed.

A reactor coolant leak exists inside the primary containment.

A Primary Containment entry is being planned to investigate the reactor coolant leak.

Containment has NOT been inerted.

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

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

The necessary blocking points to support this entry have been applied.

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 restrictions/controls to the Shift Manager.

2004 NRC Exam Rev. 1 2 o f 6

TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

H.

I.

Unit 1 is performing a plant startup.

Reactor power is 10%

Both reactor recirc pumps are in operation at minimum speed A reactor coolant leak exists inside the primary containment.

A Primary Containment entry is being planned to investigate the reactor coolant leak.

Containment has NOT been inerted.

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

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

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

INITIATING CUE 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. 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 Rev. 1 3 of 6

TASK CONDITIONS A. Unit I is performing a plant startup.

B. Reactor power is 10%

C. Both reactor recirc pumps are in operation at minimum speed D. A reactor coolant leak exists inside the primary containment.

E. A Primary Containment entry is being planned to investigate the reactor coolant leak.

F. Containment has NOT been inerted.

G. The entry will be limited to elevations 704 and 71 9 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. 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 Rev. I 4 of 6

CANDIDATE COPY (JPM 00.AD.269.001) 2004 NRC Exam Rev. 1 6 o f 6

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

03/03/04 2.2.22 3.414.1 Appl. To JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA 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./C.A.

Date Nuclear Trng. Supv.

Date Head 15 Date of Performance:

Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S.

Performance

(

)

Satisfactory

(

)

Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

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

Page 1 of 1 2004 NRC Exam Rev. 1 File No. A14-56

L Reactor power PlCSY Core Flow PlCSY Core dP (NJP51)

Core Flow dP (XR-B21-1 R613)

A Recic Loop Flow A Recirc Drive Flow REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 00.AD.268.001

1.

SAFETY CONSIDERATIONS

~~

36%

41.I4 mlbm/hr 1.87 psid 7.2 %

0.2 mlbm/hr n nnm A.

B.

C.

B Recic Loop Flow B Recirc Drive Flow B Recirc Jet Pump Flow 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.

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

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.

4.07 mlbm/hr 24299 gpm 41.1 mlbm/hr 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. I O RCS Pressure Temperature Limits (Amend 178)

I I I. REACTIVITY MAN I PU LATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE d

IV. TASK CONDITIONS A.

B.

C.

D.

E.

F.

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

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

Maintenance has determined the problem is with the 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.

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

ON-I 64-002, LOSS OF REACTOR RECIRCULATION FLOW has been entered with some portions completed.

The following plant conditions exist:

2004 NRC Exam Rev. 1

V. INITIATING CUE Review and complete as required, ON-1 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 recommendation.

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

2004 NRC Exam Rev. I

i:

PERFORMANCt CHECKLIST Page 3 of 5 Appl. To/JPM No.: 00.AD.268.001 Step I

Action EVALUATOR CUE:

Provide the candidate the marked up copy of ON-164-002.

Reviews ON-I 64-002.

EVALUATOR CUE:

Provide the candidate with Form GO-1 00-009-2 Core Flow vs. Core Pressure Drop curve.

EVALUATOR CUE:

Provide the candidate with Power/Flow Map, Form NDAP-QA-0338-10 EVALUATOR CUE:

I A MG Set will be out of Service for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Critical Step

Critical Sequence Student Name:

Standard Determines ON-164-002 has not been completed and completes the following:

Determine actual core flow via PlCSY computer point using Form GO-I 00-009-2 Core Flow vs. Core Pressure Drop curve is -44 mlblhr Plot position on Power/Flow Map, Form NDAP-QA-0338-10, outside region II.

Ensure thermal power REDUCED to 70% rod line.

Check operating pump speed 80%

rated pump speed.

Checks COLR Section 8.0 Limits in TRM and Tech Spec LCOs 3.4.1.

Verifies length of time I A MG Set will be out of service.

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

2

{,

PERFORMANCt CHECKLIST Page 4 of 5 Action Determines Tech Spec 3.4.1 required actions 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.I

-1 is reset for single loop operation.

Critical Step

Critical Sequence Student Name:

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

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

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

Recirculation Speed is -c or equal to 80%.

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

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

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Page 5 of 5 Appl. TolJPM No.: 00.AD.268.001 Student Name:

I'

\\

Step 3

Action Standard I Eva1 1 Comments Determines GO-I 00-009 Single Recirculation Loop Operation must be entered.

EVALUATOR CUE:

Provide the candidate with a copy of GO-100-009 Single Recirculation Loop Operation.

Obtains Controlled copy of GO-I 00-009 Single Recirculation Loop Operation.

Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMAN& CHECKLIST Page 6 of 5 Step 4

Appl. To/JPM No.: 00.AD.268.001 Action Enters GO-I 00-009 Single Recirculation Loop Operation.

Critical Step

Critical Sequence Student Name:

Standard Checks/Completes the following in GO-100-009 Single Recirculation Loop Operation:

Comply with COLR Section 8.0 in TRM Record Recirculation Pump and date and time of pump trip.

Determine actual core flow.

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 Power/Flow Map.

Maintain OPERATING loop flow

> 40 x I O6 Ibm/hr to keep idle loop warm, if possible.

Verifies the following initiated/complete:

SI-I 78-321, SI-1 78-209, SI-1 78-225, SI-178-327.

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

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCE CHECKLIST

(:

i Appl. To/JPM No.: 00.AD.268.001 Step 5

6 Action EVALUATOR CUE:

Role play as required and report the 18C Surveillances (Sls) have been completed.

Continues with GO-I 00-009 Single Recirculation Loop Operation.

EVALUATOR CUE:

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

Determines Attachment A, Reactor Power Increase During Single Loop Operation of GO-I 00-009 Single Recirculation Loop Operation must be performed.

%Critical Step

Critical Sequence Student Name:

Standard InitiatesNerifies complete:

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

Determines Tech Spec Surveillance SR 3.4.1 0.5 required actions:

Within 15 minutes PRIOR to increasing THERMAL POWER:

Verify the difference between the bottom head coolant temperature and the RPV coolant temperature is 5 145°F Reports this to the Shift manager Eva1 Page 7 of 5 Comments STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Appl. To/JPM No.: 00.AD.268.001 Action Determines Tech Spec Surveillance SR 3.4.1 0.6 required actions before power can be raised.

EVALUATOR CUE:

That completes this JPM

%Critical Step

Critical Sequence Student Name:

Page 8 of 5 Standard Determines Tech Spec Surveillance SR 3.4.10.6 required actions:

Within 15 minutes PRIOR to increasing THERMAL POWER:

Verify the difference between the reactor coolant temperature in the "A" recirculation loop and the RPV coolant temperature is 550°F Reports this to the Shift manager Eva1 Comments STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2004 NRC Exam Rev. 1

TASK CONDITIONS A.

B.

C.

D.

G.

E.

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

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

Maintenance has determined the problem is with the 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.

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

ON-I 64-002, LOSS OF REACTOR RECIRCULATION FLOW has been entered with some portions completed.

The followiqg 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 recommendation.

2004 NRC Exam Rev. 1 I

of2

1 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.

H.

ON-164-002, LOSS OF REACTOR RECIRCULATION FLOW has been entered with some portions completed.

E. The following plant conditions exist:

I Reactor oower I 36%

--1 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 recommendation.

2004 NRC Exam Rev. 1 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE

\\

APPROVAL AND ADMINISTRATIVE DATA SHEET v

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.

KIA Task

Title:

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

Reviews:

Russ Halm Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

15 Min Time Critical Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

Page 1 of 1 2004 NRC Exam Rev. 1 File No. A14-56

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

1.

SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

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

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. EP-PS-1 00 Emergency Director, Control Room (Rev. 19).

B. EP-PS-1 OO-E Manage the General Emergency (Tab E) (Revision 17)

C. Blank copies of Emergency Notification Report.

D. Blank copies of PAR State Notification Form.

111. REACTIVITY MANIPULATIONS

'L This JPM satisfies the following Operational Activity(s):

None IV. TASK CONDITIONS A.

B.

C.

D.

E.

F.

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

You are the Shift Manager and Emergency Director in the control room.

You have just made the INITIAL emergency classification as General Emergency based on Fission Product barrier Degradation FGI "Loss Of ANY Two Barriers AND Loss Or Potential Loss Of The Third Barrier".

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

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

There is no offsite release in progress.

V. INITIATING CUE iri Perform the duties of the Emergency Director and complete the Emergency Notification Report and the PAR State Notification Form in accordance with the appropriate procedure.

2004 NRC Exam Rev. 1

VI. TASK STANDARD L-'

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 Rev. 1

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

{'

PERFORMAN& CHECKLIST Page 3 of 13 Action EVALUATOR NOTE:

This is a Time Critical JPM.

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

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

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

EVALUATOR CUE:

After student reviews Task/Conditions/lnitiating Cue Sheet:

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

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

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

Critical Step STCP-QA-125%

Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

Critical Sequence Student Name:

Standard Obtains copy of EP-PS-100 Emergency Director, Control Room Eva1 Comments

(:

PERFORMANCt CHECKLIST

(:

Page 4 of 13 Appl. To/JPM No.: SRO 00.EP.003.082 Step Action Determines appropriate procedure section.

Document and communicate the Emergency Classification.

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

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

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

Page 1 of 1 2004 NRC Exam Rev. 1

Critical Sequence Student Name:

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

Announces to Control Room Personnel:

I am assuming duties of the Emergency Director.

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

Time and Date of Classification.

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

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

Eva1

~~~

~

Comments

Appl. To/'

Step 7

PM No.: SRO 00.EP.003.082 i

PERFORMANCt CHECKLIST Page 5 of 13 Action Fill out and approve the Emergency Notification Report Form.

EVALUATOR NOTE:

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

EVALUATOR NOTE:

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

Critical Step

Critical Sequence Student Name:

Standard Fills out and approves the Emergency Notification Report Form as follows:

LINE 1.

Call Status:

Places checkmark in This is a drill box Eva1 Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

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

PERFORMANCt CHECKLIST

(.'

Page 6 of 13 Action EVALUATOR NOTE:

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

Candidate may paraphrase this description

Critical Step

Critical Sequence Student Name:

Standard LINE 3.

Emergency Classification:

Places checkmark in General Emergency box Places checkmark in Unit one box Records the JPM start time and date as the Declaration time and date.

Places a checkmark in this represents NAN initial declaration box in classification status.

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

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMANC~ CHECKLIST Page 7 of 13 Student Name:

Appl. To/JPM No.: SRO 00.EP.003.082 Standard Eva1 Comments Step 9

Action 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".

10 11 12 LINE 5.

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

==

Conclusion:==

Places a checkmark in this is a drill box.

Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1

Page 8 of 13

(

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

I3 14 Action Approves the Emergency Notification Report Form EVALUATOR NOTE:

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

Give the approved ENR form to the E Plan Communicator.

EVALUATOR CUE:

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

EVALUATOR NOTE:

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

%Critical Step

Critical Sequence Student Name:

Standard Records the following on space provided:

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

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

Page 1 of 1 2004 NRC Exam Rev. 1

Appl. To/JPM No.: SRO 00.EP.003.082 Step 15 i;

Action Standard Eva1 Comments Make a Protective Action Recommendation (PAR) within 15 minutes.

Refers to Tab 5 Public PAR Guide Refers to Tab 5 Public PAR Guide PERFORMANCt CHECKLIST Page 9 of 13 Student Name:

Critical Step

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

(:

PERFORMANCE CHECKLIST Page Student Name:

Action Choose appropriate PAR.

Critical Step

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

(PA-2)

Has a General Emergency been declared?

Answers YES (PA-3)

Is there a valid dose projection indicating doses of 2 1 REM TEDE or 1 5 REM CDE child thyroid at a distance of > 2miles?

Answers UNKNOWN (PA-4)

Recommend EVACUATING 0-2 MILES AND SHELTERING 2-10 MILES Eva1 i

Oof 1 3 Comments STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2004 NRC Exam Rev. 1

['

["

PERFORMAN& CHECKLIST Appl. To/JPM No.: SRO 00.EP.003.082 17 18 19 20 Action Shift Manager/ED shall notify the senior state official using the PAR state notification form at 717-651-2148 Complete PAR State Notification Form.

EVALUATOR NOTE:

Line 3 of the PAR State Notification Form is left blank until the actual notification is being made.

4Critical Step

Critical Sequence

(

Page I 1 of 13 Student Name:

Standard Refers to Tab 9 for PAR State Notification Form.

Completes PAR State Notification Form as follows:

Places a checkmark in This Is A Drill box.

LINE 1 This is of the Susquehanna Steam Electric Station.

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

Emergency Director at the Susquehanna SES Control Room box.

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

Page 1 of 1 2004 NRC Exam Rev. 1

PERFORMAN& CHECKLIST Appl. To/JPM No.: SRO 00.EP.003.082 Step 21 22 Action EVALUATOR NOTE:

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

EVALUATOR NOTE:

Candidate may paraphrase the reason for declaring a General Emergency.

Critical Step

Critical Sequence

(

Page 12 of 13 Student Name:

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

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

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

Page 1 of 1 2004 NRC Exam Rev. 1

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

.irC 23 LINE 6 The PPL Susquehanna Protective Action Recommendation is:

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

Page 13 of 13 PERFORM AN^ CHECKLIST Student Name:

Enters the PAR on the State Notification Form.

EVALUATOR CUE:

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

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

COMPLETION TI ME:

EVALUATOR NOTE:

Determine the total time the candidate took to make the PAR. This time must be within 15 minutes of beginning the JPM to satisfactorily complete the JPM.

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

Page 1 of 1 2004 NRC Exam Rev. 1

Critical Sequence Eva1 Comments

TASK CONDITIONS A.

B.

C.

D.

E.

F.

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

You are the Shift Manager and Emergency Director in the control room.

You have just made the INITIAL emergency classification as General Emergency based on Fission Product barrier Degradation FGI Loss Of ANY Two Barriers AND Loss Or Potential Loss Of The Third Barrier.

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

Wind direction is I O and speed is 5 mph.

There is no offsite release in progress.

INITIATING CUE Perform the duties of the Emergency Director and complete the Emergency Notification Report and the PAR State Notification Form in accordance with the appropriate procedure.

2004 NRC Exam Rev. 1 Page 1 of 2

TASK CONDITIONS A.

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

B. You are the Shift Manager and Emergency Director in the control room.

C. You have just made the INITIAL emergency classification as General Emergency based on Fission Product barrier Degradation FGI "Loss Of ANY Two Barriers AND Loss Or Potential Loss Of The Third Barrier".

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

E.

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

F.

There is no offsite release in progress.

INITIATING CUE Perform the duties of the Emergency Director and complete the Emergency Notification Report and the PAR State Notification Form in accordance with the appropriate procedure.

2004 NRC Exam Rev. 1 Page 2 of 2

PAR AIRBORNE RELEASES PA-I

- DOSE PROJECTIONS PA-1 EMERGENCYBEEN NO I I EPENTERED I

Tab 5 EP-PS-100-5 DECLARED?

YES RECOMMEND EVACUATION 0-1 0 MILES.

PROJECTION INDICATING DOSES OF 2 1 REM TEDE OR PA-5 NO OR UNKNOWN CONTINUE ASSESSMENT RECOMMEND EVACUATING 0-2 MILES AND SHELTERING 2-10 MILES.

PA-1

?A-4 NOTES:

1. PA-# CAN BE USED TO REFER TO PROCEDURE STEPS FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.

2.

DOSE PROJECTIOYS DO=

INCLUDE DOSE ALREADY RECEIVED.

RESULTING FROY EXPOSURE TO EXTERNAL SOURCES. THE COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) FROM ALL SIGNIFICANT INHALATION PATHWAYS AND THE DOSE DUE TO GROUND DEPOSITION.

3. TEDE - WHOLE BODY (TEDE) IS THE SUM OF EFFECTIVE DOSE EQUIVALENT

4. CDE - COMMITTED DOSE EQUIVALENT TO THE CHILD THYROID.

EP-AD-000-126, Revision 10, Page 1 of 6

Tab 5 EP-PS-100-5 RADIONUCLIDE PAR LIQUID RELEASES EC Values (NCiIrnl)

NOTES:

1. PL# CAN BE USED TO REFER TO PROCEDURE STEPS FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.

CALLS TO DANVILLE ARE COURTESY INFORMATION CALLS ONLY.

PROTECTIVE ACTION RECOMMENDATlON CALLS MUST BE MADE BY DEPIBRP.

2.

ENTRY INDICATIONS OF A POTENTIAL LIQUID RELEASE

- UNISOLABLE RADWASTE TANK RELEASE

- LEAK TO COOLING TOWER BASIN

- LEAK TO SPRAY POND PL-1 4

PL-2 c

ENSURE CHEMIESD TAKES AND ANALYZES SAMPLES TO THE RIVER NO ACTION TIRIBUTABLE TO TH

\\ EVENT? /

RAD PERSONNEL NOTIFY DEPIBRP THAT A RELEASE 1 HAS OCCURRED I

I I

No I

c I

I PL-4 No RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE

,I__,

HAS OCCURRED CHEMlFTD EVALUATES RELEASE vs PAG PL-7 1

RAD PERSONNEL NOTIFY DEPlBRP OES RELEASE WCEE EC VALUES OR DOES THE SUM OF EC FRACTIONS EXCEED 0.85 REQUIRED PL-10 RAD PERSONNEL NOTIFY DEPlBRP FOR DOWNSTREAM USERS TO DIVERT WATER SUPPLY & ESTIMATED TIME OF ARRIVAL OF RELEASE AT DANVILLE L

PL-9 EP-AD-000-126, Revision 10, Page 2 of 6

W Tab 5 EP-PS-100-5 PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE AIRBORNE RELEASES Q

PA-I MONITOR CONDITIONS FOR PAR APPLICATION The following conditions should be continuously evaluated to determine if a PAR should be implemented or changed:

Plant status and prognosis for changes in conditions Onsite radiological conditions Status of actual or potential radioactive releases Offsite dose projections or actual offsite radiological conditions Escalation in Emergency Classification (i.e., General)

(GO to PA-2)

PA-2 HAS A GENERAL EMERGENCY BEEN DECtARED?

0 YES - If a GENERAL EMERGENCY has been declared, a PAR must be made within 15 minutes of the emergency declaration. The PAR requirement is found in NUREG-0654. (Go to PA-3)

O NO-If a GENERAL EMERGENCY has not been declared, continue to monitor plant status, parameter trends, and prognosis for termination or escalation of the event. (GO to PA-I)

PA-3 IS THERE A VALID DOSE PROJECTION INDICATING DOSES OF 2 1 REM TEDE OR 2 5 REM CDE CHILD THYROID AT A DISTANCE OF > 2 MILES?

0 YES - If the projected doses at 2 miles are 2 1 REM TEDE or 2 5 REM CDE child thyroid, then full evacuation (0-10 miles) is recommended.

(GO to PA-5)

O NO/UNKNOWN - (GO to PA-4)

O PA-4 RECOMMEND EVACUATION 0-2 MILES; SHELTER 2-10 MILES Limited Evacuation (0-2 miles) and sheltering is appropriate for events that are significant enough to cause a General Emergency classification and dose projections are low, unknown, or below full evacuation guidelines.

O PA-5 EVACUATE 0-10 MILES Full evacuation of members of the general public is recommended at this point based on the emergency classification and dose projections.

EP-AD-000-126, Revision I O, Page 3 of 6

Tab 5 EP-PS-100-5 i /

LIQUID O

PL-I ENTRY This section is entered when there are indications of a potential unplanned radioactive liquid release.

Indications of potential unplanned releases include:

an unisolable radwaste tank release leaks to cooling tower basin leak to spray pond (GO to PL-2)

PL-2 CHEMISTRY/ENVIRONMENTAL SAM PLI NGDIRECTOR (ESD)

TAKES AND ANALYZES SAMPLE (GO to PL-3)

PL-3 IS THERE AN UNPLANNED RELEASE TO THE RIVER?

+

0 YES - An unplanned release to the river has occurred when event-related radioactive materials are released to the river that are not controlled by the release methodologies described in the ODCM and applicable Chemistry procedures.

(GO to PL-4)

C1 NO-If there is no unplanned release to the river, then no notifications are required and monitoring should continue.

Q PL-4 RAD PERSONNEL NOTIFY DEP/BRP THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to BRP will be made by the RPC (TSC),

Dose Assessment Supervisor, or Radiological Liaison at the EOF.

DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.

(GO to PL-5) b EP-AD-000-126, Revision 10, Page 4 of 6

Tab 5 EP-PS-100-5 LIQUID (CONT'D)

PL-5 IS RELEASE 2 TECHNICAL REQUIREMENTS LIMITS (AT THE RELEASE POINT)?

0 YES - Releases are at or greater than Technical Requirements limits when Chemistry determines that the limits are exceeded based on methodologies described in the ODCM and applicable Chemistry procedures.

(GO to PL-6)

O NO-If the release is < Technical Requirements limits, then no further notifications are required and monitoring should continue.

O PL-6 RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to Danville will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.

DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.

(GO to PL-7)

O PL-7 CHEM/FTD EVALUATES RELEASE VERSUS PAGs The results of the sample analysis are compared to the PAGs for radionuclides in drinking water. The analysis calculates the expected concentration at Danville, taking into account the dilution afforded by the river.

PL-8 DOES RELEASE EXCEED PAGs (AT DANVILLE)?

0 YES - If a single isotope exceeds its effluent concentration (EC) value or the sum of EC fractions exceeds 0.85, then a protective action recommendation should be made for downstream water users (e.g.,

Danville) to DIVERT DRINKING WATER supply to a backup supply or terminate user intake until the release has passed.

(GO to PL-9)

O NO-If the PAGs.are not exceeded, monitoring should continue and the State should be notified that no PAR for the liquid release is required.

(GO to PL-IO)

EP-AD-000-126, Revision 10, Page 5 of 6

Tab 5 EP-PS-100-5 LIQUID (CONTD) u LI PL-9 RAD PERSONNEL NOTIFY DEP/BRP OF PAR Depending on which facility is activated, the PAR notification to DEP/BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF. The PAR FORM shall be used to document the PAR.

DO NOT COMMUNICATE THE PROTECTIVE ACTION RECOMMENDATION TO DANVILLE. THE DEPlBRP IS RESPONSIBLE FOR THIS COMMUNICATION AND ANY COMMUNICATION TO OTHER DRINKING WATER SUPPLIERS OR WATER USERS.

O PL-IO RAD PERSONNEL NOTIFY DEP/BRP No PAR is required. Depending on which facility is activated, the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF shall notify DEP/BRP that no PAR is required.

EP-AD-000-126, Revision 10, Page 6 of 6

Tab 9 Control #

- EP-PS-100-9 1 EMERGENCY NOTIFICATION REPORT 1

1. Call Status:

THIS IS A DRILL THIS IS AN ACTUAL EVENT

2.

This is:

at Susquehanna Steam Electric Station.

(Communicator's Name)

My telephone number is:

Notification time is:

(Callback telephone number)

(Time notification initiated)

3.

EMERGENCY CLASSIFICATION:

[7 UNUSUAL EVENT 0 SITE AREA EMERGENCY

[7 ALERT 0 GENERAL EMERGENCY The event has been terminated.

UNIT: [7 ONE Declaration DATE:

Time:

(Time classification/

(Date classification/

termination declared) termination declared)

Two ONE&TWO IN CLASSIFICATION STATUS THIS REPRESENTS NAN:

INITIAL DECLARATION 0

ESCALATION NOCHANGE

4.

The Emergency Action Level (EAL) Number is:

BRIEF NON-TECHNICAL DESCRlPTlON OF THE EVENT:

For initial declaration, static update, or escalation, provide current classification EAL number only.

For significant events, or when directed by the ED, RM, or EOFSS, provide a brief description.

0 AN AIRBORNE NON-ROUTINE RADIOLOGICAL RELEASE IN PROGRESS

5.

THEREIS:

No 17 A LIQUID

6.

WIND DIRECTION IS FROM:

. WIND SPEED IS:

mph.

(Data from 10 meter meteorological tower, available on PICSY.)

7.

==

Conclusion:==

THIS IS A DRILL 0

THIS IS AN ACTUAL EVENT APPROVED:

Time:

Date:

(ED, RM, or EOFSS)

(Time form approved)

(Date form approved)

EP-AD-000-310, Revision 6, Page 1 of 1

i Tab9 EP-PS-100-9 PROTECTIVE ACTION RECOMMENDATION STATE NOTIFICATION FORM THIS IS A DRILL 0 THIS IS AN ACTUAL EVENT (This form is to be used to communicate PPCs Protective Action to the senior state official at 71 7-651-21 48.)

1.

2.

3.

4.

9

5.

This is of the Susquehanna Steam Electric Station.

(Fill in your name) am the: 0 c]

Emergency Director at the Susquehanna SES Control Room Emergency Director at the Technical Support Center Recovery Manager at the Emergency Operations Facility am about to provide a Protective Action Recommendation. Do Lhave the Senior State Micial on the line?

Name A General Emergency has been declared as of This declaration was made due to:

6.

7.

The PPL Susquehanna Protective Action Recornmendation is:

0 Evacuate 0-10 miles and advise citizens to take KI in accordance with the states emergency plans.

Evacuate 0-2 miles and shelter 2-1 0 miles and advise citizens to take Kt in accordance with the states emergency plans.

Divert Danville drinking water supply from the Susquehanna River Evacuate beyond IO miles (specrfy distance /

and advise citizens to take KI in accordance with the states emergency plans.

Datflime:

EP-AD-000-077, Revision 1, Page 1 of 1 L

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