Text

Final - Section a Operating (Folder 3) - Job Performance Measure, Erp Classification and Reporting (Time Critical)
	ML050380271
Person / Time
Site:	Limerick
Issue date:	01/05/2005
From:	Jason White; Exelon Generation Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	JPM 0095, Rev. 004
	Download: ML050380271 (103)
	v • d • e

~

EXELON NUCLEAR W

Limerick Generating Station Job Performance Measure ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

JPM Number: 0095 Revision Number: 004 Date:

/ /

Developed By:

Validated By:

Review By:

Approved By:

Instructor SME or Instructor Date Date Operations Representative Date Training Department Date I LLOJPM0095 Rev004 Page 1 of 8

EXELON NUCLEAR JOB PERFORMANCE MEASURE VALIDATION CHECKLIST c

NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (WA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev.

Date

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

then revise the JPM.

cover page.

9. Pilot test the JPM:

L, I O. If the JPM cannot be performed as written with proper responses,

11. When JPM is revalidated, SME or Instructor sign and date JPM I LLOJPM0095 Rev004 Page 2 of 8

EXELON NUCLEAR d

Revision Record (Summary)

I 1. Revision 004, Format Change. Changed step 10 to be Non-Critical. Changed wind speed and direction standard to reflect expectations. Changed task standard for notification from 13 minutes to 12 minutes.

SIMULATOR SETUP INSTRUCTIONS:

None TASK CONDITIONS:

I The following conditions exist on Unit 1 :

0 0

SBLC has initiated 2 Reactor Feed Pumps tripped 10 minutes ago, and have subsequently been restored RPS and ARI failed to insert control rods Level dropped to -50 inches Reactor level is being maintained at approximately -70 inches per T-I 17 I

Reactor power is 35% and decreasing at 3% per minute Suppression Pool Temperature is 107 O F and rising slowly INITIATING CUES: This Task is Time Critical This JPM will start after you have reviewed the task conditions and tell the evaluator that you are ready to begin.

You are required to make the ERP classification and subsequent call outs. All communications should be made as if a drill is in progress.

Information For Evaluators Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the Comment Number column. Then annotate that comment in the Comments section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

L I LLOJPMOO95 Rev004 Page 3 of 8

EXELON NUCLEAR TITLE: ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

Operators Name:

JobTitle:

0 NLO 0 RO SRO 0 STA SRO Cert JPM

Title:

ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

JPM Number: LLOJPM0095 Revision Number: 004 K/A Number and Importance:

Generic 2.4.41 2.3/4.1 Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method:

Perform Faulted:

No Alternate Path:

No Time Critical:

No Estimated Time to Complete: 15 minutes Actual Time Used:

minutes

References:

EP-AA-1008, LGS EMERGENCY ACTION LEVEL (EAL) MATRIX, REV 05 EP-AA-I 12-1 00, Rev 5, CONTROL ROOM OPERATIONS EP-MA-I 14-100, Rev 5, MAROG NOTIFICATIONS EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

0 Yes No The operators performance was evaluated against the standards contained in this JPM, and has been determined to be:

0 Satisfactory 0 Unsatisfactory Evaluators Name:

(Print)

Evaluators Signature:

Date:

I LLOJPM0095 Rev004 Page 4 of 8

EXELON NUCLEAR TASK CONDITIONS:

7 The following conditions exist on Unit 1 :

0 I

2 Reactor Feed Pumps tripped 10 minutes ago, and have subsequently been restored RPS and ARI failed to insert control rods Level dropped to -50 inches Reactor level is being maintained at approximately -70 inches per T-I 17 SBLC has initiated Reactor power is 35% and decreasing at 3% per minute Suppression Pool Temperature is 107 OF and rising slowly INITIATING CUES:

I This Task is Time Critical.

This JPM will start after you have reviewed the task conditions and tell the evaluator that you are ready to begin.

You are required to make the ERP classification and subsequent call outs. All communications should be made as if a drill is in progress.

I LLOJPM0095 Rev004 Page 5 of 8

L I

ELEMENT EXELON NUCLEAR STANDARD SAT UNSAT Comment Number TASK STANDARD(S):

4.

Review the initiating conditions 5*.

applicable to the operating mode IF the EAL Threshold Values have been met or exceeded, then:

A SITE AREA EMERGENCY is declared within 15 minutes of the candidate beginning the classification.

Notification form completed and ready for Shift Communicator within 12 minutes of declaring the SITE AREA EMERGENCY.

Use EAL Matrix to classify event Determine Site Area Emergency initiating conditions have been exceeded Critical Element(s) indicated by *I in Performance Checklist.

START TIME:

PERFORMANCE CHECKLIST:

1.

Evaluator note time candidate begins reviewing EALs

2.

When an abnormal condition is being evaluated, REFER to the appropriate Station EAL Matrix and PERFORM the following:

N/A

3.

IDENTIFY the Unit Mode for the state of the plant prior to the abnormal condition N/A

6.

NOTE the EAL number I MS4 identified associated with the IC 7*.

DECLARE the event Declare a Site Area Emergency within 15 minutes of the START TIME in Step 1 DECLARATION TIME:

8.

RETURN to the appropriate EP-AA-112 ERO position checklist and immediately begin notifications N/A EP-AA-112-100 Attachment I SHIFT EMERGENCY DIRECTOR CHECKLIST I LLOJPM0095 Rev004 Page 6 of 8

EXELON NUCLEAR 9*.

ANNOUNCE the event classification to the Control Room Staff, and over the plant Public Address (PA) system based on pre-scripted message guidelines in EP-AA-112, I O.

PERFORM Attachment 2, ERO Augmentation

11.

DETERMINE the correct plant-based PAR per the appropriate site-specific PAR flowchart in EP-AA-111, Attachments 2 through 8

~~

12*.

INITIATE required State/Local notifications within 15 minutes of the event classification as required per EP-AA-I 14 - Refer to EP-MW(MA)-114-100 for instructions on completion and transmittal of State/County notifications Make announcement per scripted message Contact Shift Communicator to initiate callout per Attachment 2

LGS/PBAPS is Attachment 8 N/A - No PAR for SAE Direct Shift Communicator to perform notification within 12 minutes of DECLARATION TIME. (15 minutes minus time for Communicator to receive form and make roll call)

Note: This step is graded after the next section L

EP-MA-114-100, MAROG NOTIFICATIONS, Section 4.1 - COMPLETING THE STATElLOCAL I

NOTIFICATION FORM

13.

Message number - ENTER a sequential number starting with 1

14.

APPROVED BY 15*.

STATUS BLOCK I 16*.

CLASSIFICATION I 17*.

AFFECTED UNIT I 18*.

DECLARED AT

19.

CLASSIFICATION STATUS 20*.

BRIEF NON-TECHNICAL DESCRl PTl ON I

or equivalent entered Signature entered THIS IS A DRILL marked SITE AREA EMERGENCY checked I

I ONE checked I

I I

I

/

Time and Date entered. MS4 entered as EAL#

I I

INITIAL DECLARATION checked Auto and manual SCRAM not successful or equivalent entered. (Critical that something is entered that identifies the event)

I LLOJPM0095 Rev004 Page 7 of 8

EXELON NUCLEAR 21 *.

NON-ROUTINE RADIOLOGICAL RELEASE STATUS

22.

PAR

23.

METEOROLOGY CUE: Provide MET DATA Attachment 24*.

STATUS CUE: (When State and Local Notification Form is given to Shift Communicator)

You have met the termination criteria for the JPM.

I JPM Stop Time:

NO checked Left blank or NOT APPLICABLE checked Wind direction 120 degrees Wind speed 7 mph This is a drill checked (Critical that at least one of the two status blocks on the page is marked correctly and no contradictory info is marked. If contradictory info is marked, then the incorrect step is UNSAT. If one block is blank and the other is correct, then the blank block is N/A)

N/A N/A I LLOJPM0095 Rev004 Page 8 of 8

TAS K CO N D IT1 0 N S :

The following conditions exist on Unit 1 :

b I

2 Reactor Feed Pumps tripped 10 minutes ago, and have subsequently been restored SBLC has initiated 0

RPS and ARI failed to insert control rods Level dropped to -50 inches Reactor level is being maintained at approximately -70 inches per T-I 17 Reactor power is 35% and decreasing at 3% per minute Suppression Pool Temperature is 107 O F and rising slowly IN IT1 AT1 N G CUES:

This Task is Time Critical.

This JPM will start after you have reviewed the task conditions and tell the evaluator that you are ready to begin.

You are required to make the ERP classification and subsequent call outs. All communications should be made as if a drill is in progress.

I

MET DA{

T 0

W E

R I

T 0

W E

R 2

4TTAC HM ENT 971 METEOROLOG PID SENSOR T I DTULFA T I SPlFA T12SPLFA T I DRUFA T I DRIFA T I DRLFA T I DTULFA T I DTILFA TIATLFA T I DPLFA T I RNFA i

CAL 15 MINUTE AVERAGE POINT DATA DESCRIPTION VALUE EU T I.SP.U TOWER 1 270 FT WIND SPEED I

6.1 I

MPH T I.SPA TOWER I 175 FT WIND SPEED r

1 M PH T I.SP.L TOWER I 30 FT WIND SPEED I

4.3 I

MPH T I.DR.U TOWER 1 270 FT WIND DIRECTION 1

DEG AZ T I.DR.I TOWER 1 175 FT WIND DIRECTION piiq DEG AZ T I.DR.L TOWER I 30 FT WIND DIRECTION I

116.2 I

DEG AZ T I.DT.U-L TOWER 1 266 - 26 FT DELTA TEMP pj3-l DEG F T I.DT.I-L TOWER 1 171 - 26 FT DELTA TEMP DEG F T I.AT.L T I.DP.L T I.RN TOWER 1 26 FT AMBIENT TEMP I

85.2 TOWER 1 26 FT DEW POINT 1

TOWER 1 PRECIPITATION 1

DEG F DEG F INCHES T2DTU LFA T2SPIFA T22S PL FA T2DRUFA T2D RI FA T2DRLFA TZDTULFA T2DTILFA T2ATLFA T2DPLFA T2.SP.U T2.SP.I T2.SP.L T2. DR. U T2.DR.I TOWER 2 304 FT WIND SPEED TOWER 2 159 FT WIND SPEED TOWER 2 30 FT WIND SPEED TOWER 2 304 FT WIND DIRECTION TOWER 2 159 FT WIND DIRECTION 1

4 6

1 1

1 MPH MPH MPH DEG AZ DEG AZ T2.DR.L TOWER 2 30 FT WIND DIRECTION I 115.6 1

DEG AZ T2. DT. U -L TOWER 2 304 - 26 FT DELTA TEMP

/-2E-/

DEG F T2.DT.I-L DEG F T2.AT.L TOWER 2 26 FT AMBIEWNT TEMP

/-7Eiq DEG F T2.DP.L TOWER 2 26 FT DEW POINT pG-1 DEG F TOWER 2 155 - 26 FT DELTA TEMP

EXELON NUCLEAR Limerick Generating Station Job Performance Measure INTERPRETATION AND APPLICATION OF OVERTIME LIMITS JPM Number: 0700 Revision Number: 000 Date:

/ /

Developed By:

Validated By:

Review By:

Approved By:

Instructor Date SME or instructor Date 0 pe rat i on s Representative Date Training Department Date LLOJPM0700 Rev000 Page 1 of 6

EXEL ON NUCLEAR LLOJPM0700 REvOOO Job Performance Measure (JPML JOB PERFORMANCE MEASURE VALIDATION CHECKLIST c

NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (WA) references are included.

3. Performance location specified. (in-plant, control room, or si m u I ato r)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev.

Date

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

then revise the JPM.

cover page.

9. Pilot test the JPM:

I O. If the JPM cannot be performed as written with proper responses,

11. When JPM is revalidated, SME or Instructor sign and date JPM LL 0 JPM 0 700 Re v000 Page 2 of 6

EXELON NUCLEAR LLOJPM0700 REvOOO Job Performance Measure (JPM)

L REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Unit I is in OPCON I Unit I oncoming RO for the 1800-0600 shift has called off sick Date is 11/14 Time is 1500 INITIATING CUES:

There are 5 ROs available to fill the position. You are told to perform verification of overtime hours to determine which RO, if any, can stand the entire shift. Explain why or why not.

L TASK STANDARD:

Determine which ROs can stand the entire shift and why or why not.

Information For Evaluators Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the Comment Number column. Then annotate that comment in the Comments section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

LL OJPM0700 Re v000 L:

Page 3 of 6

EXELON NUCLEAR L L 0 JPMO7OO REvOOO c-Job Performance Measure (JPM)

Operators Name:

JobTitle:

0 NLO 0 RO 0

SRO 0 STA 0 SROCert JPM

Title:

Interpretation and Applications of Overtime Limits JPM Number: LLOJPM0700 Revision Number: 000 WA Number and Importance: Generic 2.1. I O Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method:

Simulate Faulted:

No Alternate Path:

No Time Critical:

No Estimated Time to Complete: 30 minutes Actual Time Used:

m in Utes b

References:

LS-AA-I 19 Rev 2 EVALUATION SUM MARY:

Were all the Critical Elements performed satisfactorily?

0 Yes No The operators performance was evaluated against the standards contained in this JPM, and has been determined to be:

0 Satisfactory 0 Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

L LOJPM0700 Rev000 Page 4 of 6

EXELON NUCLEAR UNSAT JPM Start Time:

Comment Number ELEMENT

I. Reference LS-AA-119 to determine which RO's are allowed to assume the Unit I RO position (Cue: Provide copy of LS-AA-119 if asked for)

2. Determine candidate 1 cannot stand entire shift and would be in violation of LS-AA-I 19 limits

3. Determine candidate 2 cannot stand entire shift and would be in violation of LS-AA-I 19 limits

4. Determine candidate 3 cannot stand entire shift and would be in violation of LS-AA-119 limits

5. Determine candidate 4 can stand entire shift in the Unit 1 RO position because they are in compliance with LS-AA-1 I 9 limits

6. Determine candidate 5 can stand entire shift in the Unit I RO position because they are in compliance with LS-AA-119 limits (CUE: "You may stop here, you have met the termination criteria for this JPM")

JPM Stop Time:

c STANDARD LS-AA-I 19 is obtained Candidate I is found in violation of limits if called in (More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a seven day (1 68 hr) period)

Candidate 2 is found in violation of limits if called in (More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period)

Candidate 3 is found in violation of limits if called in (More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period and less than an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break between work periods)

Candidate 4 is found in compliance with limits if called in Candidate 5 is found in compliance with limits if called in N/A SAT LLOJPM0700 Rev000 Page 5 of 6

EXELON NUCLEAR RO Candidate 1

2

\\v INITIAL CONDITIONS:

Work Hours 1 In 11/8 11/9 11/10 11/11 11/12 11/13 11/14 0600-0600-0600-0600-0600-0600-1800 1800 1800 1800 1800 1800 0800-0800-0800-0800-0800-0600-0200-Unit I is in OPCON 1 Unit 1 oncoming RO for the 1800-0600 shift has called off sick Date is 1 1/14 Time is I500 3

INITIATING CUES:

1600 1600 1600 1600 1600 1800 1000 0700-0700-0700-0700-0700-0600-There are 5 ROs available to fill the position. You are told to perform verification of overtime hours to determine which RO, if any, can stand the entire shift. Explain why or why not.

4 5

1530 1530 1530 1530 1530 1100 0600-1800-1800-1800-1800-1800 0600 0600 0600 0600 0600 0600 0600 0600 0600 0600 1800-1800-1800-1800-1800-1800-CANDIDATE c

I EXEL ON NUCLEAR I

Limerick Generating Station Job Performance Measure REVIEW OF CONTROL ROOM SUPERVISOR SHIFT TURNOVER CHECKLIST JPM Number: 0701 Revision Number: 000 Date:

/ /

Developed By:

Validated By:

Review By:

Approved By:

Instructor SME or Instructor

~~

0 pe ration s Re pres e n t a t ive Training Department Date

\\

Date Date Date L L OJPMO70 I Rev000 Page I of 6

I EXELON NUCLEAR I

L L OJPM0707 REvOOO Job Performance Measure (JPM)

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through I 1 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (WA) references are included.

3. Performance location specified. (in-plant, control room, or si mu I a tor)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev.

Date

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

then revise the JPM.

cover page.

L with an asterisk (*).

9. Pilot test the JPM:

I O. If the JPM cannot be performed as written with proper responses, 1 I.

When JPM is revalidated, SME or Instructor sign and date JPM L L OJPMO70 I Rev000 Page 2 of 6

EXELON NUCLEAR LLOJPM0701 REvOOO

.d Job Performance Measure (JPM)

REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Unit 1 and 2 are in OPCON I The electronic OPs Log is unavailable due to a software error INITIATING CUES:

Control Room Supervisor Shift Turnover Checklist has been completecl. Review the Control Room Supervisor Shift Turnover Checklist.

1-d TASK STANDARD:

Find errors on Control Room Supervisor Shift Turnover Checklist.

Information For Evaluators Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the Comment Number column. Then annotate that comment in the Comments section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

- The timeclock starts when the candidate acknowledges the initiating cue.

L LO JPM070 I Rev000 Page 3 of 6

EXELON NUCLEAR LLOJPM0701 REvOOO Job Performance Measure (JPM)

Operators Name:

JobTitle:

0 NLO 0 RO 0

SRO 0 STA 0 SROCert JPM

Title:

Review Of Control Room Supervisor Shift Turnover Checklist JPM Number: LLOJPM0701 Revision Number: 000 WA Number and Importance: Generic 2.1.3 Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method:

Simulate Faulted:

No Alternate Path:

No Time Critical:

No L Estimated Time to Complete: 30 minutes Actual Time Used:

minutes References :

OP-LG-112-101-1000 Rev 0 OP-LG-112-101-1002 Rev I EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

0 Yes No The operators performance was evaluated against the standards contained in this JPM, and has been determined to be:

0 Satisfactory 0 Unsatisfactory Comments:

Evaluators Name:

(Print) u Evaluators Signature:

Date:

L LOJPM0701 Rev000 Page 4 of 6

EXEL ON NUCLEAR I

L LOJPM0701 REvOOO Y

Job Performance Measure (JPM)

JPM Start Time:

ELEMENT

-1 (Cue: Provide candidate the Control Room Supervisor Shift Turnover Checklist)

I. Review the Control Room Supervisor shift turnover checklist for errors and discrepancies

I

.a Find error on page I 1.c Find error on page 2 (CUE: You may stop here, you have met the termination criteria for this JPM)

JPM Stop Time:

STANDARD N/A Reviews the Control Room Supervisor shift turnover check list and finds the following errors:

Unit I is in OPCON 5*

with fuel moves in progress, but Refuel Floor Sec. Cont is NOT established.

Unit I box, 1A RHR in shutdown cooling, but DIV 1 LOCA LOOP testing is scheduled which will cause lose of shutdown cooling One of the 3 STA, IA check boxs is not checked N/A SAT UNSAT Comment Number L L OJPMO70 I Rev000 Page 5 of 6

W I

EXELON NUCLEAR I

INITIAL CONDITIONS:

Unit 1 is in OPCON 1 The electronic OPs Log is unavailable due to a software error INITIATING CUES:

Control Room Supervisor Shift Turnover Checklist has been completed. Review the Control Room Supervisor Shift Turnover Checklist.

CANDIDATE

EXELON NUCLEAR Developed By:

Validated By:

Limerick Generating Station Job Performance Measure REVIEW CONTROL ROD EXERCISE ST JPM Number: 0702 Revision Number: 000 Date:

/ /

Instructor SME or Instructor Review By:

Operations Representative Date Date Date Approved By:

I I

Training Department Date LLOJPM0702 Rev000 Page 1 of 6

L L OJPMO702 REvOOO Job Performance Measure (JPM)

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through I I below.

1.

2.

3.

4.

5.

6.

7.

8.

9.

Task description and number, JPM description and number are identified.

Knowledge and Abilities (WA) references are included.

Performance location specified. (in-plant, control room, or simulator)

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards identified and verified by SME review.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev.

Date Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

I O. If the JPM cannot be performed as written with proper responses,

11. When JPM is revalidated, SME or Instructor sign and date JPM then revise the JPM.

cover page.

L LO JPM0702 Rev000 Page 2 of 6

EXELON NUCLEAR L LOJPM0702 REvOOO Job Performance Measure (JPM)

REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Unit 1 is in OPCON 1 INITIATING CUES:

ST-6-1 07-760-1, Control Rod Exercise, has been completed. You are asked to review ST-6-1 07-760-1 for completeness and accuracy.

TASK STANDARD:

Find errors on ST-6-1 07-760-1, Control Rod Exercise Information For Evaluators Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the Comment Number column. Then annotate that comment in the Comments section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectat ions.

Some operations that are performed from outside of the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

LLOJPM0702 Rev000 Page 3 of 6

EXELON NUCLEAR L LOJFM0702 REvOOO Job Performance Measure (JPM)

Operators Name:

JobTitle:

0 NLO 0 RO 0

SRO 0 STA 0 SROCert JPM

Title:

Review Control Rod Exercise ST JPM Number: LLOJPM0702 Revision Number: 000 WA Number and Importance: Generic 2.2.1 2 Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method:

Simulate Faulted:

No Alternate Path:

No Time Critical:

No L Estimated Time to Complete: 30 minutes Actual Time Used:

m in Utes References :

ST-6-107-760-1 Rev 50 EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

0 Yes No The operators perfonnance was evaluated against the standards contained in this JPM, and has been determined to be:

0 Satisfactory 0 Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

L L LOJPM0702 Rev000 Page 4 of 6

EXELON NUCLEAR JPM Start Time:

ELEMENT (Cue: Provide candidate marked up copy of ST-6-107-760-1)

1. Review ST-107-670-1 for errors and discrepancies I

.a Find error on page 1

I

.b Find error on page 15 (CUE: If requested hand as left Control Rod Position Log to candidate)

I.c Find error on page 30 (CUE: You may stop here, you have met the termination criteria for this JPM)

JPM Stop Time:

STANDARD N/A Review ST-107-670-1 for errors and discrepancies and finds the following errors:

Comments in Add it iona I Act ionnes t Comments block, but not signed or dated Step 4.6.1.I

.a requires Control Rod Position Log attached to ST for as left rod positions. It is not attached.

Control Rod 46-31 As Found position does not match As Found Control rod Position Log N/A L L OJPM0702 Rev000 Page 5 of 6

EXELON NUCLEAR INITIAL CONDITIONS:

Unit 1 is in OPCON INITIATING CUES:

I ST-6-1 07-760-1, Control Rod Exercise, has been complete. You are asked to review ST 107-760-1.

CANDIDATE

c) P.M.

\\d ST-6-107-760-1, Rev. 50 Page 1 of 34 ALC/RCB/J HG:.eer G R A F LIMERICK GENERATING STATION ST-6-1 07-760-1 Test Freq:

Weekly - aB - Initiating Events:

A.

Tech Spec:

4.1.3.7.c 4.1.3.6 4.1.3.1.2 4.1.3.7.b 4.O.5 4.1.3.1.3 FSAR 4.6.3.1.1.5.b SER 4.6 I E 3 3 i E : (Circle SAT or UNSAT - Below)

UNSAT - Test Results of one aB more Asteri Performed by:....T...... m&@,.

.............. (Sign/D Reviewed by (SSV).....&T..... sxk..............

\\

.fl (UNSAT Results Only)

................ (ETT pc A/R - Number)

Person making entry.......................................................

(SignlDate)

ST-6-107-760-1, Rev. 50 Page 2 of 34 1.0 PURPOSE 1.1 To verify OPERABILITY of each withdrawn control rod A N D its position indicating system by moving each OPERABLE control rod at least one notch during operation above the preset power level of the Rod Worth Minimizer (RWM) in OPCON 1. CM-1 u

1.2 To ensure the Control Rods are coupled to their respective drive mechanisms by observing any indicated response on nuclear instrumentation while withdrawing control rods to fully withdrawn position A N D by verifying the control rods do not go to OVERTRAVEL position.

1.3 This test satisfies lnservice Testing requirements for 47-1-38, "Cooling Header Check Valve," (all 185 HCU's).

2.0 PREREQUISITES J

1 Plant in OPCON 1.

.2 Reactor power level is above the preset power level of the RWM via ROD WORTH MINIMIZER, BELOW LPSP is not displayed in POWER field at 1 OC603 OR PMS point A555 reads "GT LPSP.II------

E a load drop is required per Section 4.4 OR Section 4.5, THEN Power System Director has been informed of power reduction A N D a release obtained as required by the Power System Director.

d

-I/

c 2.3 L

A No other testing A5 RDCS OPERABLE d E known fuel defect(s) exist OR plant condition which could interfere with this test is being performed/present.

THEN an evaluation of fully withdrawn control rods, within a 3 x 3 array of the fuel defectb), has been obtained from Reactor Engineering. This shall inciude evaluation of affected control rods being inserted to notch position 44 and required power reductions, if any, to accomplish the insertion.

Otherwise, it is acceptable for all fully withdrawn control rods to be inserted to notch position 44 at full power. (Ref. 6.1 1)

ST-6-1 07-760-1, Rev. 50 Page 3 of 34 3.0 PRECAUTIONS 3.1 CI -

3.2 3.3 3.4 3.5 Steps marked SO in the right hand margin of the body of the procedure require a sign off in Attachment 1.

IF a procedural step can not be completed OR any other difficulty is encountered during this test,

%EN a comment shall be entered in the Additional Action/Test Comments section.

IF a step denoted as a Tech Spec Requirement, marked with an asterisk(*), can not be successfully completed, THEN Shift Supervision (SSVN) shall be notified immediately.

Steps marked with (I) represents specific Code testing OR evaluation requirements which must be completed satisfactorily.

Any observed abnormality shall be documented in the Additional Action/Test Comments section AND brought to the attention of SSVN.

NOTE Conditions listed in step 3.6 indicate that there may be a fault in the Rod Select A Module.

L I u

3.6 3.7 3.8 IF any of the following conditions exist during control rod selection, THEN do not attempt control rod movement AND SSVN shall be immediately notified:

Pushbutton of the selected control rod does light.

The wrong set of pushbuttons light.

More than one set of pushbuttons light.

The correct set of pushbuttons light dimly.

IF performance of this test carries over to subsequent shiftk),

THEN a Control Rod Position Log edit shall be performed at the end of the shift(s).

WHEN exercising control rods, THEN the "CRD Hydraulic HI TEMP" alarm may be introduced.

Acknowledging the alarm at 1OCOO7 may wait until after the completion of the exercise in order to avoid responding repetitiously.

ST 107-760- 1, Rev. 50 Page 4 of 34 3.9 If performing this test as a result of a control rod being immovable because of excessive friction or mechanical interference, THEN this test must be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Irr u

3.10 E any rod does not perform satisfactorily, THEN SSVN shall be informed imrnediatelv to address applicable Tech Spec actions.

3.1 1 Since this is a repetitive task of long duration, consideration should be given to taking frequent breaks to avoid rod mis-positioning.

ST 1 07-760- 1, Rev. 50 Page 5 of 34 b

NOTE IN IT1 ALS It is the responsibility of the person OR persons performing this test to ensure AND comdetely filled in.

blanks/data sheets are correctly 4.0 PROCEDURE 4.1 PREPARATION NOTE IF during this test control rod(s) are moved in either direction for reasons other than proof of OPERABILITY, THEN that movement can be used to fulfill the requirements of this test by observing that the control rod position indicating system responds correctly during rod movement AND initialing the operability check column on Attachment 1. N/A shall be entered in stall flow data column for these rods.

4.1.1 4.1.2 VERIFY all prerequisites of Section 2.0 are satisfied.

VERIFY no CRD Accumulator Trouble Lights are lit.

1.

IF a CRD Accumulator trouble light is lit THEN DISPATCH an EO to investigate the Accumulator.

r d h 4.2 SHIFT PERMISSION TO TEST 4.2.1 OBTAIN SSV permission to start test.

L 4.2.2 OBTAIN PRO/RO permission to start test.

4

[2-I0-0(4 / O q 'i Oate/Time 4.2.3 VERIFY this test is being performed on Unit 1.

ST-6-1 07-760- 1, Rev. 50 Page 6 of 34 INITIALS 4.3 PRELIMINARY DATA P

W 4.3.1 RECORD the following:

Present reactor thermal power from PMS.

Rx Power qq.9 %

L Date/Time 4.3.2 PERFORM the following prior to starting test:

1.

E Control Rod Position Log is available, THEN PERFORM the following, Otherwise, MARK this step N/A:

a.

OBTAIN a copy of a control rod position printout using Control Rod Position Log AND ATTACH to this test.

b.

ENTER N/A on first page of Attachment 1 in the space provided for Control Rod Position Log not available for AS FOUND.

c.

MARK step 4.3.2.2 as N/A.

4-

2.

E Control Rod Position Log is not available, THEN RECORD position of each rod in the AS FOUND column of Attachment 1 using the PMS AND ENTER initials in the space provided for Control Rod Position Log not available for AS FOUND.

4.3.3 ENTER N/A in the Operability Check AND Coupling Check columns of Attachment 1 for each control rod which is at position 00 OR has been declared INOPERABLE.

4.3.4 E Control Rod Position Log was obtained, THEN RECORD the 'As Found' positions of all partially withdrawn rods in Attachment 1.

m 1-A

NOTE

1.

Each OPERABLE control rod which is nnt fully inserted is determined OPERABLE by moving the control rod one notch.

2.

The Rod Position Information System (RPIS) is determined OPERABLE by verifying that the rod position numeral changes by.02 AND there are M rod drift alarms.

nS the conditions of 4.4.1.I

.e are met BND there are M rod drift alarms.

3.

Steps 4.4 BND 4.5 may be performed concurrently to facilitate row-by-row performance of the test.

ST-6-107-7BO-1, Rev. 50 Page 7 of 34 4.4 FULLY WITHDRAWN CONTROL RODS 4.4.1 PERFORM the following to test each fully withdrawn control rod, one at a time:

n i/

NOTE

1.

Satisfactory completion of step 4.4.1.1 demonstrates 47-1 -38, "Cooling Header Check Valve," (Typical of 185) has exercised closed.

A double notch from 48 to 44 has been generically evaluated as acceptable from a reactivity standpoint by A I 081 91 3 Eva1 60. (Ref 6.1 1 )

2.

P n

."-&so)

I.

PERFORM the following:

a.

VERIFY on the 4 Rod Display that the selected Rod indicates position 48.

b.

E 48 is nnt being indicated on the Four Rod

Display, THEN VERIFY full-out indication is present on the Full Core Display AND PMS.

lpcl

c.

INSERT the control rod one notch.

lpcl I

ST-6-107-760-1, Rev. 50 Page8 of 34 l u u A J s

d.

VERIFY on the Four Rod Display that the

- lpcl selected Rod indicates position 46.

E any control rod begins to insert Af!Ul settles back to position 48 THEN PERFORM the following.

Otherwise, MARK N/A for steps 4.4.1.I

.e, through 4.4.1.1.e. 1 1 :

1.

2.

Esuccessful,

e.

/ m

/ m i

ATTEMPT another single notch insert to position 46.

L THEN GO TO step 4.4.1.2.

3. E unsuccessful, THEN PERFORM the following:

a. E control rod does naf indicate notch position 46 due to insufficient control rod movement, THEN R E V I M evaluation provided by Reactor Engineering per step 2.6 to determine if it is acceptable to insert the rod to position 44 due to an inadvertent double-notching without a power reduction.

b. E a power reduction is required, THW REDUCE core power in accordance with GP-5 Appendix 2, Section 3. I

, using core flow per Reactor Maneuvering Shutdown Instructions (RMSI) to required power level.

Otherwise, MARK this step N/A AND GO TO step 4.4.1. I

.e.4.

4.

RAISE CRD System Drive pressure by 25 psid, not to exceed 350 psid.

ATTEMPT a single notch insert.

5.

I

ST4-107-760-1, Rev. 50 Page 9 of 34

6.

E the rod double notches to position 44, J l E N WITHDRAW the rod to position 48. (Ref 6.1 1)

E rod fails to latch at position 46 AND CRD System Drive Pressure is less than 350 psid, THEN REPEAT step 4.4.1.I

.e.4.

ENSURE CRD System Drive pressure is E rod failed to latch at notch position 46, E rod did latch at notch position 46 ablcl increased CRD System Drive pressure was required, THEN INITIATE AIR abLn NOTIFY CRD System Manager for trending purposes. (Equipment Status Tagging is nat required.)

ANNOTATE cover sheet to indicate that raised pressure/f low adjust ment/ON-I 04 entry was required.

7.

.NA lpcl

/m approximately 260 psid.

i u/ El THEN ENTER ON-I 04.

dLPc

8.

9.

I O.

J L

H

/ m

11.

I

f.

ENSURE CRD System Drive pressure is approximately 260 psid.

g.

E control rod does nat indicate notch position 46 due to WlS problems, THEN PERFORM the following, iXhem&e, MARK N/A for steps 4.4.1.1.g. 1 through 4.4.1.1.g.3:

1.

REVIEW evaluation provided by Reactor Engineering per step 2.6 to determine if it is acceptable to insert the control rod one notch to position 44 without a power reduct ion.

n L

NOTE I.

2.

E CRD withdrawal stall flow data is required, THEN coupling check step shall be performed using continuous withdraw.

Stall flow check is required for first test performance each month.

ST-6-107-760-1, Rev. 50 Page 1 0 of 34

2.

LE a power reduction is required THEN REDUCE core power in accordance with GP-5 Appendix 2, Section 3.1, using core flow per Reactor Maneuvering Shutdown Instruction (RMSI) to required power level.

C)therw, MARK this step N/A ahlll GO TO step 4.4.1.1.g.3.

3.

INSERT the control rod one notch to posit ion 44.

2.

WITHDRAW control rod to position 48 while observing control rod posit ion indication.

IE Control Rod Position Log is nat available, THW RECORD the AS LEFT position of each control rod on Attachment 1.

3.

4.

Periodically DEMAND Control Rod Position Logs ANQ ENSURE control rod positions match

'As Found' Control Rod Position Log as required by Attachment 1.

4.4.2 WHEN a control rod is withdrawn to FULL OUT position, THEN PERFORM coupling check at panel 1OC603 by 1

notch withdraw QE3 continuous withdraw (stall flow check) selected rod.

4.4.3 E

this is the first performance of the month, THEN RECORD stall flow from FI-46-I R604, "Drive Water Flow Indicator" (FL), in Attachment 1, otherwise the stall flow data column shall be left blank.

7 L

ST 1 07-760-1, Rev. 50 Page 11 of 34 I NIT1 A LS P

\\.

4.4.4 PERFORM the following:

1.

VERIFY the following:

Annunciator ROD OVERTRAVEL remains clear at panel 108 REACTOR.

Individual rod selected indicates 48 on Four Rod Display, (ROD HEIGHT) at panel 1OC603.

Individual rod selected RED out light is Lit on the Full Core Display at panel 10C649.

E 48 is not indicated on the Four Rod Display at panel 1 OC603, THEN VERIFY full out indication is present on the Full Core Display at panel 10C649 AND PMS.

2.

4.4.5 E s t e p 4.4.4.1 4.4.4.2 are g&l satisfactorily performed, AND m

L -

THEN ENTER initials in the appropriate columnhod in.

4.4.6 E s t e p 4.4.4.1 4.4.4.2 isunsat, OR THEN REFER TO step 3.10 AND ENTER a comment in the Additional Action/Test Comment section.

ST-6-1 07-760-1, Rev. 50 Page 12 of 34 L,

4 NOTE IF no partially withdrawn rods, THEN all steps in 4.5 are N/A.

4.5 PARTIALLY WITHDRAWN CONTROL RODS 4.5.1 PERFORM the following to ensure there is adequate margin to thermal limits:

1.

REQUEST 3D Monicore case AND CHECK the following:

Two Loop Operation Sinale Lo00 ODeration CMWT 3458 CMWT 2634 CMAPR 2 0.98 CMAPR 0.98 CMFLPD 0.98 CMFLPD 0.98 FLLLP 2 1.O FLLLP < 1.0

ST~-IO7-780-1, Rev. 50 Page 13 of 34

2. LE thermal limits do mt satisfy values shown in step 4.5.1.I, THEN REDUCE core power in accordance with GP-5 Appendix 2, Section 3.1, using core flow per Reactor Maneuvering Shutdown lnst ruct ions (RMSI) as required to satisfy limits AND ENSURE FLLLP remains < 1.O.

ntheMl, MARKN/A.

3. VERIFY thermal limits are less than or equal to values specified in step 4.5.1.I.

NOTE Satisfactory completion of step 4.5.2 demonstrates 47-1 -38, "Cooling Header Check Valve," (Typical of 185) has exercised closed.

4.5.2 PERFORM the following to test each partially withdrawn control rod, one at a time:

1.

PERFORM the following:

a.

b.

C.

VERIFY that selected Rod indicates a proper posit ion on the Four Rod display.

INSERT Control Rod one notch.

I VERIFY selected Rod indicates a position two less than above on the Four Rod display (Example: Position 08 to 06)

AND proper nuclear inst rumentat ion response was observed.

2.

3.

4.

5.

6.

ST-6-107-760-1, Rev. 50 Page 14 of 34 WITHDRAW control rod to original position while observing control rod posit ion indication.

RECORD AS LEFT position of each control rod on Attachment I.

INDICATE N/A in coupling check column of.

E stall flows are being recorded, THEN ENTER N/A in stall flow column.

Qthwke, the stall flow data column shall be left blank.

Periodically DEMAND Control Rod Position Log AND ENSURE control rod positions match As Found Control Rod Position Log as required by Attachment 1.

ST-6-107-760-1, Rev. 50 Page 15 of 34 t-L-

4.6 RETURNTONORMAL 4.6.1 PERFORM the following for final Control Rod Posit ions:

1.

E Control Rod Position Log is available THEN PERFORM the following, Qihmwk, MARK this step N/A:

a.

OBTAIN Control Rod Position Log AND ATTACH to this test.

L

b.

ENTER N/A on first page of Attachment I in space provided for Control Rod Position Log not available for AS LEFT.

c.

MARK step 4.6.1.2 N/A.

4-

2.

LE Control Rod Position Log is not available THEN ENTER initials on first page of Attachment 1 in space provided for Control Rod Position Log nnt available for AS LEFT.

4.6.2 VERIFY all control rods which were moved one notch to verify operability are returned to their original position by comparing Control Rod Position Logs obtained QR by comparing the AS FOUND, AS LEFT columns on.

E any control rods have nnt been returned to AS FOUND Posit ion, THEN UST rods Action/Test Comments section.

4.6.3 reason for new position in the Additional

n L

4.6.4 4.6.5 4.6.6 4.6.7 4.6.8 CI b

ST-6-1Q7-760-1, Rev. 50 Page 16 of 34 DOCUMENT in Additional Action/Test comments section any CRD stall flow greater than or equal to 3.5 gpm.

ENTER N/A for this step.

E

required, THEN RETURN Unit to original power level by raising power in accordance w it h GP-5 Appendix 2 Sect ion 3.2 Qtbxise, ENTER N/A for this step.

ENSURE IVOR completed on Attachment 2.

NOTIFY ssv PRO/RO of the following:

Test completion Test results ENSURE cover sheet is correctly AND completely filled in.

ST-6-107-760-1, Rev. 50 Page 17 of 34 5.0 ACCEPTANCE CRITERIA 5.1 All OPERABLE withdrawn control rods have been moved at least one notch L

to demonstrate OPERABILITY.

5.2 During control rod movement, the position indication changes correctly.

5.3 Rod coupling has been verified.

5.4 Steps denoted with IS1 (I) asterisk (* ) have been completed satisfactorily.

6.0 REFERENCES

6.1 CM-1, TO1 699 Control Rod Mispositioning 6.2 LGS-FSA R-Sect ion 4.6.1 6.3 FSAR4.6.3.1.1.5.b 6.4 SER4.6 6.5 6.6 Pump & Valve lnservice Testing Program Plan General Electric PCIOMR Implementing Procedures, NEOE-21493 9

\\/-

6.7 M-47, P&ID - Control Rod Drive Hydraulic - Part B 6.8 GEK-75711, Control Rod Drive System 6.9 GEK-75712, Control Rod Drive Hydraulic System 6.10 GEK-75714, Reactor Manual Control System 6.1 1 A1081913 Eva1 60, Analysis to insert rods to position 44 during CRD Exercise

ST-6-107-760-1, Rev. 50 Page 18 of 34 7.0 TECHNICAL SPECIFICATIONS c 7*1 4.0-5 7.2 4.1.3.7.c 7.3 4.1.3.6 7.4 4.1.3.1.2 7.5 4.1.3.7.b 7.6 4.1.3.1.3 8.0 INTERFACING PROCEDURES 8.1 GP-5 Appendix 2, Planned Rx Maneuvering Without Shutdown

ATTACHMENT 1 Page 1 of 15 4.3.2.2, 4.3.4, 4.4.1.3, 4.5.2.3 Control Rod, Position AS FOUND I AS LEFT 4.3.2 Control Rod Position Log is not available AS FOUND.

4.6.1 Control Rod Position Log is not available AS LEFT.

4.4.1.1 4.4.5 4.5.2.1 Operability Check Coupling Complete Complete Check PerformerIDV Control Rod 02-1 9 02-27 02-3 1 02-35 02-39 02-43 ST4-107-760-1, Rev. 50 Page19 of 34 lNirlALS i

I

-(* 1 I

L 4.4.3 CRD W/D Stall Flow G PM (if required)

PM PM PM PM PM PM PM

r W

Control Rod ATTACHMENT 1 Page 2 of 15 Control Rod, Position ST-6-107-760-1, Rev. 50 Page 2 0 of 34 AS FOUND I AS LEFT I

O6-I5 I O6-I9 I 7 06-23 06-27 06-3 1 06-35 06-39 06-43 06-47 Step Number 4.4.1.1 4.5.2.1 Operability Check Complete PerformerIDV 4.4.5 Coupling Check Complete fii 4.4.3 CRD WID Stall Flow GPM (if required)

PM PM PM PM PM

~

PM

_ _ ~

PM PM PM

Control Rod 10-1 1 10-15 10-19 10-23 10-27

~~

10-31 10-35 10-39 10-43 10-47 10-51 ATTACHMENT 1 Page 3 of 15 ST-6-107-760-1 Rev. 50 Page21 of 34 Step Number 4.3.2.2, 4.3.4, 4.4.1.3, 4.5.2.3 Control Rod, Position AS FOUND I AS LEFT 4.4.1.1 4.5.2.1 Operability Check Complete PerformerIDV I

4.4.5 4.4.3 Coupling CRD WID Stall Check Flow G PM

-I=-- Complete (if required)

Iff- (*)

PM PM PM PM PM PM PM PM PM PM

ST-6-I 07-760-1, Rev. 50 Page 22 of 34 ATTACHMENT 1 Page 4 of 15 n

lNlTlALS 4.4.1.4/4.5.2.6 Current Control Rod Position Log matches 'AS FOUND' Control Rod Position Log.

Control Rod 18-03 18-07 18-1 1 18-15 18-1 9 18-23 18-27 18-31 18-35 18-39 18-43 18-47 18-51 18-55 18-59 ATTACHMENT 1 Page 5 of 15 ST-6-107-760-1, Rev. SO Page23 of 34 SteD Number 4.4.3 4.3.2.2, 4.3.4, 4.4.1.3, I 4.4.1.1 I

4.4.5 CRD WID Stall Flow G PM

{if required)

PM PM PM PM PM PM PM PM PM PM PM PM PM PM PM

Control Rod 4.3.2.2, 4.3.4, 4.4.1.3, 4.4.1.1 4.4.5 4.5.2.3 4.5.2.1 Control Rod, Position Operability Check Coupling Complete Check

~

22-03 4.4.3 CRD W/D Stall Flow GPM 22-07 22-1 1 22-1 5 22-1 9 22-23 22-27 22-3 1 22-35 22-39 22-43 22-47 22-55 22-59 ST-6-107-760-1, Rev. 50 Page 24 of 34 ATTACHMENT 1 Page 6 of 15

ST-6-107-760-1, Rev. 50 Page25 of 34 ATTACHMENT 1 Page 7 of 15 Step Number (4.3.2.2, 4.3.4, 4.4.1.3, I 4.4.1.1 1

4.4.5 1

4.4.3 26-31 26-35 26-39 26-43 26-47 26-51 26-55 26-59 1

ST6-107-760-1, Rev. 50 Page 26 of 34 ATTACHMENT I Page 8 of 15 4

4.4.1.4/4.5.2.6 Current Control Rod Position Log matches 'AS FOUND' Control Rod Position Log.

~~

Control Rod 30-03 30-07 30-1 1

30-1 5 30-1 9 30-23 30-27 30-31 30-35 30-39 30-43 30-47 30-5 1

30-55 30-59 Step Number Page 9 of 15

ST-6-107-760-1, Rev. 50 Page 27 of 34 d

34-59 I

Control Rod 38-03 38-07 38-1 1

38-1 5

38-1 9 38-23 38-27 38-31 38-35 38-39 38-43 38-47 38-51 38-55 38-59 ST-6-107-760-1, Rev. 50 Page 28 of 34 ATTACHMENT 1 Page 10 of 15 Step Number 1-4.3.2.2. 4.3.4, 4.4.1.3, I 4.4.1.1 4.4.5 4.4.3

ST4-107-760-1, Rev. 50 Page 29 of 34 ATTACHMENT 1 Page 11 of 15 5

4.4.5 4.4.3 II 4.3.2.2, 4.3.4, 4.4.1.3, 4.5.2.3 Control Control Rod, Position 4.4.1.I 4.5.2.1 Operability Check Complete PM PM PM

(*I I PM N

PM

'1 W

4.3.2.2, 4.3.4, 4.4.1.3, 1 4.4.1.I ST4-107-7.60-1, Rev. 50 Page 30 of 34 ATTACHMENT 1 Page 12 of 15 4.4.5 4.4.3 -4 4.4.1.4/4.5.2.6 Current Control Rod Position Log matches 'AS FOUND' Control Rod Position Log.

Control Rod 46-07 46-1 1 46-1 5 46-1 9 46-23 46-27 46-3 1 46-35 46-39 46-43 46-47 46-51 46-55

h L

ST-6-107-760-1, Rev. 50 Page 31 of 34 ATTACHMENT 1 Page 13 of 15 3

SteD Number 4.3.2.2, 4.34, 4.4.1.3, 4.4.1.I 4.5.2.1 Complete 50-1 1 50-1 5 50-1 9 50-23 50-27 50-3 I 4.4.5 Coupling Check Complete 4.4.3 CRD WIDXall Flow GPM

{if required)

PM PM

~

PM PM PM PM PM PM PM PM PM

Control Rod 54-1 5 54-1 9 54-23 54-27 54-3 1 54-35 54-39 54-43 54-47 ST-6-I 07-760-1, Rev. 50 Page 3 2 of 34 ATTACHMENT 1 Page 14 of 15 SteD Number 4.3.2.2, 4.3.4, 4.4.1.3, I 4.4.1.I I

4.4.5 I

4.4.3

ST-6-107-760-1, Rev. 50 Page 33 of 34 ATTACHMENT 1 Page 15 of 15

ST-6-107-760-1, Rev. 50 Page 34 of 34 ATTACHMENT 2 Page 1 of 1 lN OFPFN IWNT VFRl FIC'.ATION OF RFSTORATIO N n

L 1,O The following steps require Independent Verification of Restoration:

REFERENCE STEP NUMBER nt rol 3s re in AS FOUND positions, are as identified in the Additional ActionITest Comments sect ion using Control Rod Posit ion Logs AS FOUND, AS LEFT positions from Attachment 1.

I PLANT NAME: LIMERICK-1 CYCLE 11 CONTROL ROD POSITIONS PAGE 1

10-DEC-2004 09:22 CALCULATED IO-DEC-2004 09:22 PRINTED i

59 I

L 5 5 I

51 47 43 39 L

L 06-06 35 31 06 4 10 LI L

i 27 23 I

19 15 L

I L

06 -

06 F 03 02 L

06 10 L

14 18 L

22 26 L

30 34 S = SUBSTITUTE VALUE L = LPRM

-99 = MISSING CONTROL ROD POSITION CONTROL ROD DENSITY 4.21%

SEQUENCE A09D 06, 06 -

06 /

L L

L 38 42 46 5 0 54 58 LOAD LINE

SUMMARY

CORE POWER 99.93%

CORE FtoW 92.27%

LOAD LINE 105.87%

FLLLP 0.916 I

I

?

PLANT NAME: LIMERICK-I CYCLE 11 CONTROL ROD POSITIONS 59 55 51 47 43 39 35 31 27 23 19 L

L L

06 L' 06 06 06 06./

10 06 06 -

L 15 11 07 L i:

PAGE 1

10-DEC-2004 13:56 CALCULATED 10-DEC-2004 13:56 PRINTED 06 03 L

L L

02 06 10 1 4 18 22 26 30 34 38 42 46 50 54 58 S = SUBSTITUTE VALUE L = LPRM

-99 = MISSING CONTROL CONTROL ROD DENSITY SEQUENCE A09D ROD POSITION 4.21%

LOAD LINE

SUMMARY

CORE POWER 99.93%

CORE FLOW 92.67%

LOAD LINE 105.54%

FLLP 0.914 I.

... I..

. a..

EXELON NUCLEAR Developed By:

Validated By:

Review By:

Approved By:

Limerick Generating Station Job Performance Measure CALCULATE STAY TIME JPM Number: 0703 Revision Number: 000 Date:

/ /

Instructor Date SME or Instructor Date Operations Representative Date Training Department Date LL 0 JPMO703 Rev000 Page 1 of 9

EXELON NUCLEAR L L OJPMO703 REvOOO Job Performance Measure (JPM)

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST c

NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through I 1 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (WA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev.

Date

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

then revise the JPM.

cover page.

9. Pilot test the JPM:

I O. If the JPM cannot be performed as written with proper responses,

11. When JPM is revalidated, SME or Instructor sign and date JPM L L 0 JPM0703 Rev000 Page 2 of 9

I EXELON NUCLEAR I

LLOJPM0703 REV000 Job Performance Measure (JPM)

REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Unit I is in OPCON I Work is being performed in the Unit 1 Main Steam Chase Additional high radiation exposure controls are required Two workers are performing the work Job conditions and information are as follows:

ii Dose Rate Alarms on their Electronic Dosimeter for both workers: 600 mrem/hr Accumulated Dose Alarms on their Electronic Dosimeter for both workers:

1200 mrem RWP Approval Dose Alarm for both workers: 1200 mrem Stop Work Dose Rate for both workers: 600 mremlhr Worker 1 has 600 mrem accumulated dose on his Electronic Dosimeter from his first entry Worker 2 has 800 mrem accumulated dose on his Electronic Dosimeter from his first entry 3 man-hrs are required to finish the work Time required to enter: 5 minutes Time required to exit: 5 minutes Work is to be performed in the Unit 1 Main Steam Chase against the Containment Wall INITIATING CUES:

Use RP-LG-460-2000, Additional High Radiation Exposure Controls attachment 3 and survey map to determine:

1.

2.

Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 and worker 2 If the workers can finish the work without receiving accumulated dose alarms L LO JPMO703 Rev000 Page 3 of 9

EXEL ON NUCLEAR LL 0 JPM0703 REvOOO Job Performance Measure (JPM)

TASK STANDARD:

Calculate stay time for workers 1 and 2 until dose alarms reached and if work can be finished in the allotted time.

Information For Evaluators Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the Comment Number column. Then annotate that comment in the Comments section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct L the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

L LOJPM0703 Rev000 Page 4 of 9

I EXELON NUCLEAR I

LLOJPM0703 REVOOO Job Performance Measure (JPM)

Operators Name:

JobTitle:

0 NLO RO 0

SRO 0 STA 0 SROCert JPM

Title:

Calculate Stay Time JPM Number: LLOJPM0703 Revision Number: 000 WA Number and Importance: Generic 2.3.1 0 Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method:

Simulate Faulted:

No Alternate Path:

No Time Critical:

No u

Estimated Time to Complete: 30 minutes Actual Time Used:

minutes References :

EVALUATION SUM MARY:

Were all the Critical Elements performed satisfactorily?

0 Yes No The operators performance was evaluated against the standards contained in this JPM, and has been determined to be:

0 Satisfactory I7 Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

c LLOJPM0703 Rev000 Page 5 of 9

UNSAT EXELON NUCLEAR I

Comment Number JPM Start Time:

ELEMENT (Cue: Provide copy of RP-LG-460-2000 and survey map)

1. Determine Maximum Stay Time for the required entry

2. For worker 1 :

2.a Subtract accumulated dose of 600 mr from accumulated dose alarm of 1200 mr to get remaining dose until alarm

2.b Divide Allowable Work Dose by the Maximum Whole Body Dose Rate in work area to get Maximum Stay Time (Worst Case)

-1 2.c Subtract entry and exit time of 10 minutes (5 minutes+5 minutes) from the Maximum Stay Time

3. For worker 2:

3.a Subtract accumulated dose of 800 mr from accumulated dose alarm of 1200 mr to get remaining dose until alarm

3.b Divide Allowable Work Dose by the Maximum Whole Body Dose Rate in work area to get Maximum Stay Time (Worst Case)

STANDARD N/A Maximum Stay Time Determined to be:

Accum - Accum = Remain Dose Dose Dose Alarm Alarm 1200 mr - 600 mr = 600 mr

~

Remain1 Max =

Max Dose Dose Stay Alarm Rate Time 600mr / 400 mr/hr = 1.5 hr Max - Entry = Max Stay Exit Allow Time Time Time 90 min - 10 min = 80 min Accum - Accum = Remain Dose Dose Dose Alarm Alarm 1200 mr - 800 mr = 400 mr Remain/ Max =

Max Dose Dose Stay Alarm Rate Time 400mr I400 mrlhr = 1 hr SAT L L OJPM0703 Rev000 Page 6 of 9

UNSAT I

EXELON NUCLEAR I

Comment Number ELEMENT I

3.c Subtract entry and exit time of 10 minutes (5 minutes+5 minutes) from the Maximum Stay Time

4. Calculate if man-hrs are exceeded:

4.a Add worker I Maximum Stay Time of 80 minutes to worker 2 Maximum Stay Time of 50 minutes

4.b Determine work can not be competed due to combined stay time less than required 3 man-hrs (180 minutes) remaining (CUE: You may stop here, you have met the termination criteria for this JPM)

STANDARD Max - Entry = Max Stay Exit Allow Time Time Time 60 min - 10 min = 50 min Worker + Worker = Total 1 Stay 2Stay Stay Time Time Time 80 rnin + 50 min = 130 rnin Determine work can not be completed N/A SAT JPM Stop Time:

LLOJPM0703 Rev000 Page 7 of 9

INITIAL CONDITIONS:

c Unit 1 is in OPCON 1 Work is being performed in the Unit I Main Steam Chase Additional high radiation exposure controls are required Two workers are performing the work Job conditions and information are as follows:

Dose Rate Alarms on their Electronic Dosimeter for both workers: 600 mrem/hr Accumulated Dose Alarms on their Electronic Dosimeter for both workers:

1200 mrem RWP Approval Dose Alarm for both workers: 1200 mrem Stop Work Dose Rate for both workers: 600 mrem/hr Worker 1 has 600 mrem accumulated dose on his Electronic Dosimeter from his first entry Worker 2 has 800 mrem accumulated dose on his Electronic Dosimeter from his first entry 3 man-hrs are required to finish the work Time required to enter: 5 minutes Time required to exit: 5 minutes Work is to be performed in the Unit I Main Steam Chase against the Containment Wall INITIATING CUES:

--J Use RP-LG-460-2000, Additional High Radiation Exposure Controls attachment 3 and survey map to determine:

1.

2.

Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 and worker 2.

If the workers can finish the work without receiving accumulated dose alarms.

CANDIDATE i/

ARW SURVEY FORM

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04-52 BATE:

12/24/04 nw:.........................................................

0900 SUWTY No:.......................................................

Phil Heart Art Star Joe Tech JBT in'Xf3

_____.__._________.________i______

w,mn BY:

i..................... IICtSSR.Wfi SERIAL GU X E fALlD

-0 No i

i INSTRUMENT S E R M CAI CLE VNJD HI I

'io INSTRUMENT NO R d 2 A j

33-3333 RM-14 33-4444 x

Work Area low Dose Area i

N/A

~

400 i cm.:mcml:+

Cat :3oUn/GA Contamination

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Floor

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<lk 1 1 Floor c l k 5

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m b des *le Wk.3 Survey in support of valve work in Main Steam Chase near.

Containment Wall, Remote Monitoring required for workers.

12/24/04

>NE:

Joe Joo m-mm B'C

EXELON NUCLEAR Limerick Generating Station Job Performance Measure DETERMINATION OF EQUIPMENT AVAILABILITY FOR FIRE SAFE SHUTDOWN JPM Number: 0711 Revision Number: 000 Date:

/ /

Developed By:

Instructor Validated By:

SME or Instructor Review By:

Operations Representative Approved By:

Training Department Date Date Date Date LLOJPM071 I Rev000 Page I of 6

EXELON NUCLEAR LLOJPM0711 REvOOO Job Performance Measure (JPM)

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through I 1 below.

I.

2.

3.

4.

5.

6.

7.

8.

9.

Task description and number, JPM description and number are identified.

Knowledge and Abilities (WA) references are included.

Performance location specified. (in-plant, control room, or si mu I ato r)

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards identified and verified by SME review.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev.

Date Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

I O. If the JPM cannot be performed as written with proper responses, 1 I.

When JPM is revalidated, SME or Instructor sign and date JPM then revise the JPM.

cover page.

LLOJPAhO71 I Rev000 Page 2 of 6

EXELON NUCLEAR LLOJPM0711 REvOOO i/

Job Performance Measure (JPM)

REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Annunciator 006 FIRE, CONT EL 254 INVERT RM 1, is in alarm.

INITIATING CUES:

CRS has told you to determine which Unit I MSRVs are available for Fire Safe Shutdown.

TASK STANDARD:

Determination of equipment availability for Fire Safe Shutdown per FSSGs.

L Information For Evaluators Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the Comment Number column. Then annotate that comment in the Comments section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The time clock starts when the candidate.............

acknowledges

............. the initiating cue.

LLOJPM071 I Rev000 Page 3 of 6

EXELON NUCLEAR LLOJPM0711 REvOOO

-.J Job Performance Measure (JPM)

JobTitle:

0 NLO 0 RO 0

SRO 0 STA 0 SROCert Operators Name:

JPM

Title:

Determination Of Equipment Availability For Fire Safe Shutdown JPM Number: LLOJPM0711 Revision Number: 000 WA Number and Importance: Generic 2.4.27 Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method:

Simulate Faulted:

No Alternate Path:

No Time Critical:

No Estimated Time to Complete: 15 minutes Actual Time Used:

minutes

References:

1 FSSG-3020 2FSSG-3020 FSSG Map EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

0 Yes No The operators performance was evaluated against the standards contained in this JPM, and has been determined to be:

0 Satisfactory 0 Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

LLOJPMO71 I Rev000 Page 4 of 6

EXELON NUCLEAR

3. Find Static Inverter room for Unit I on FSSA 3000 Sheet 4 of 10 JPM Start Time:

Finds the Static Inverter room for Unit I on FSSA 3000 Sheet 4 of I O ELEMENT

5. Determines which MSRVs are available for Fire Safe Shutdown for Unit I ISAT I UNSAT STANDARD Determines that MSRVs C, A and N are available

1. Reference ARC 006 13L I Finds ARC 006 13L I

(CUE: If Fire Brigade is contacted for extent of fire, respond, Fire is restricted to the Unit 1 inverter room.)

2. Obtain FSSA 3000 Sheet 4 of I O FSSA 3000 Sheet 4 of I O is obtained

4. Determines which FSSG to use for area Determines to use I FSSG-3020 (CUE: You may stop here, you have met the termination criteria for this JPM)

NIA JPM Stop Time:

Comment Number LLOJPMO71-1 Rev000 Page 5 of 6

EXELON NUCLEAR u

INITIAL CONDITIONS:

Annunciator 006 INITIATING CUES:

FIRE, CONT EL 254 INVERT RM 1, is in alarm.

CRS has told you to determine which Unit 1 MSRV's are available for Fire Safe Shutdown.

c CANDIDATE

L 2

3 i

3 1

1 1

1 3

I I

1. FA Code: 5-2-4 ALARM WORDING:

CONT EL 254 INVERT RM I OPERATOR ACTIONS:

1. Dispatch fire brigade to area to investigate.

2.

Reference:

Fire Procedure F-A-452.

S22.7.A LGS Emergency Plan Annex, Table 3-1 FSSA-3000 Sheet 4 of 10 SE-8 CAUSES :

1. Smoke Detector Alarm Panel initiation indicating fire at Elev. 254 Control Enclosure Inverter Room I.

ANNUNCIATOR# :

N/A SETPOINT:

0 N/A DEVICE ( S )

A4-124 SD-1O5A thru SD-105D

REFERENCES:

1. M-779 Sht. 26

2. E-1652 ARC-MCR-006 I3L, REV. 1 PAGE 1 OF 1

I I

UNIT I ONLY SYSTEM Reactor Vessel EXELON NUCLEAR LIMERICK GENERATING STATION FIRE SAFE SHUTDOWN GUIDE PARAMETER INSTRUMENT LOCATION Level LI 1 R010 RSP 1O-C201 Pressure PI 1 RO 1 1 RSP 1O-C201 IFSSG-3020 FIRE AREA 020 FIRE GUIDE Unit 1 Static Inverter Compartment (El. 254'-0")

Suppression Pool IFSSG-3020, Rev. 6 Page 1 of 16 JET/W DA/RCB: jml Level LI-55-141 RSP 1O-C201 Tem per at u re TI-41-1 01 MCR 1O-C626 Tern Der at u re TI-41 -1 02 RSP 1O-C201 1.o EQUIPMENT AVAILABLE FOR FIRE SAFE SHUTDOWN 1.1 PROTECTED INSTRUMENTS SYSTEM PARAMETER INSTRUMENT LPCI-A Flow FI 5 1 - 1 ROO5 RClC Flow FI 1 ROO 1 - 1 LOCATION RSP 1O-C201 RSP 1O-C201 1.2 LEVEL CONTROL SYSTEMS AND PROTECTED INSTRUMENTS

IFSSG-3020, Rev. 6 Page 2 of 16 JET/WDA/RCB:jml I

UNIT I ONLY

\\-A 1.3 PRESSURE CONTROL SYSTEMS AND PROTECTED HAND SWITCHES SYSTEM MSRV-A PARAMETER HAND SWITCH LOCATION Control PSV-41-1 FOI 3A RSP 10-C201 MSRV-C MSRV-N 1.4 DECAY HEAT REMOVAL SYSTEMS AND PROTECTED INSTRUMENTS ISYSTEM IPARAMETER IINSTRUMENT ILOCATION Control PSV-41-1 FO13C Control PSV 1 F013N SDC-A Alt. SDC-A Flow F151-1 ROO5 Flow Fl51-1 ROO5 Supp. Pool Coolina-A RSP 1O-C201 Flow RSP 1O-C201 RH RS W -A using OA-P506 1.5 PROTECTED ELECTRICAL POWER SYSTEMS AND PROTECTED ESW Pressure PI-01 2-001 A-2 Pressure PI-05 1 - 1 05A-2 SYSTEM COMPONENTS 4 KV BUS D11 SAFEGUARD SWITCHGEAR IO-AI 15 I

I I

SYSTEM ESW-A D21 SAFEGUARD SWITCHGEAR 20-AI 15 D23 SAFEGUARD SWITCHGEAR 20-AI 17 PARAMETER INSTRUMENT Flow FI-I 1-01 3A DIESELS Pressure ID1 1 DIESEL GENERATOR 1A-G501 I

PI-1 1 -003A-2 D21 DIESEL GENERATOR 2A-G501 D23 DIESEL GENERATOR 2C-G501 using AND/OR OA-P548 OC-P548 LO CAT1 0 N c

1FSSG-3020, Rev. 6 Page 3 of 16 J ET/WDA/RCB:jml I

UNIT I ONLY 1

2.0 VENTILATION AREA Inverter Rooms Aux. Equipment / RSP Room Control Room 4 KV Switchaear Rooms TEMP.

TIME ACTION 130.F 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Per SE-1-3 120.F 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Per SE-1-3 120.F 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Per SE-1-3 122.F 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Per SE-1-3

- 3.0 CONTINGENCY ACTIONS

. Attachment I

- OPERATOR 1 ACTIONS 3.1 ALIGNMENT OF EQUIPMENT FOR D11 DIESEL GENERATOR OPERATION (PROMPT ACTION)

ALIGNMENT OF EQUIPMENT FOR SPC/SDC OPERATION ALIGNMENT OF EQUIPMENT FOR MSRV OPERATION 3.2 3.3

. Attachment 2 - OPERATOR 2 ACTIONS 3.4 ALIGNMENT OF EQUIPMENT FOR RClC OPERATION (PROMPT ACTION)

ALIGNMENT OF EQUIPMENT FOR SPClSDC OPERATION OPEN RClC VACUUM BREAKER ISOLATION VALVE ALIGNMENT OF EQUIPMENT FOR LONG TERM ESW OPERATION 3.5 3.6 3.7

. Attachment 3 - OPERATOR 3 ACTIONS 3.8 MAN THE RSP (PROMPT ACTION) c

I L

4.0 RETURN TO NORMAL 1FSSG-3020, Rev. 6 Page 4 of 16 J ET/WDA/RCB:jml UNIT 1 ONLY 4.1 REVIEW Safe Shutdown Guide AND PERFORM the following:

Section 3.0 in "Step Number" and "Equipment Number" columns of Attachment 4.

RECORD information for all components manipulated in SEQUENCE restoration steps as necessary.

. GENERATE Clearances and Action Requests for all components that can NOT be restored.

I NlTlA LS 4.2 ENSURE all components manipulated in Section 3.0 are returned to normal have clearance applied.

5.0 REFERENCES

5.1 c

Calculation LF-0016-020, Fire Area 020 Fire Safe Shutdown Analysis 5.2 Specification NE-0294, "Fire Safe Shutdown Analysis Specification" 5.3 SE-1-3, "Protected Ventilation Source" 5.4 S92.9.N, "Routine Inspection of the Diesel Generator"

ATTACHMENT 1 OPERATOR 1 ACTIONS VALVE HV-11-132A UNIT 1 ONLY SHEET 1 OF 6 BREAKER BREAKER DESCRIPTION INITIALS D114-D-G-19 "DI 1 DIESEL GEN ESW "A" OUTLET VALVE HV-11-132A" IFSSG-3020, Rev. 6 Page 5 of 16 JET/WDA/RCB:jml HV-11-132A I NIT1 ALS "DI 1 DIESEL GEN ESW "A" OUTLET OPEN VA LV E "

3.1 ALIGNMENT OF EQUIPMENT FOR D11 DIESEL GENERATOR OPERATION NOTE Steps 3.1.1 through 3.1.3 are performed in 1 DG-217-311 A - Generator Room A.

3.1.1 E following valve can NOT be positioned normally, THEN OPEN the associated breaker:

3.1.2 ENSURE the following valve positioned as indicated:

1 L

ATTACHMENT 1 IFSSG-3020, Rev. 6 Page 6 of 16 J ET/W DA/RCB:jml I NIT1 ALS OPERATOR 1 ACTIONS UNIT 1 ONLY SHEET 2 OF 6 3.1.3 D 1 1 safeguard Bus is de-energized AND D11 Diesel Failed to Auto Start THEN PERFORM the following:

1.

PLACE 43-AG501 I "LOCAL REMOTE SELECTOR SWITCH" to "LOCAL" at 1A-C514, "DI 1 DIESEL GENERATOR ELEC INSTR CONTROL BOARD."

2.

PLACE HS-092-186Af "DIFF/GROUND TRIP BYPASS" switch to " F I RE".

I

3.

PLACE Engine Control (CSL) to "START" AND HOLD until Engine firedsustains itself.

4. VERIFY D11 GEN BKR is CLOSED in MCR AND Bus Voltage is nominal 4.2 KV.

5.

PERFORM running checks per S92.9.N, "Routine Inspection of the Diesel Generator."

3.2 ALIGNMENT OF EQUIPMENT FOR SPC/SDC OPERATION 3.2.1 E HV-51-1F008, "RHR SHUTDOWN CLG SUCTION OUTBRD PCIV" can NOT be opened normally, THEN PERFORM the following:

1.

OPEN breaker D124-R-GI-5 "RHR SHUTDOWN CLG SUCTION OUTBRD PClV HV-51-1 F008" (1 6-21 7-304).

2.

Manually OPEN valve HV-5 1 - 1 F008 ( 1 6-238-309).

c 3.2.2 I

ATTACHMENT 1 IFSSG-3020, Rev. 6 Page 7 of 16 J ET/WDA/RCB:jml SHEET 3 OF 6 INITIALS OPERATOR 1 ACTIONS UNIT 1 ONLY IF HV-51-1F068A, "1A RHR HTX. RHR S.W. OUTLET VLV" can NOT be opened normally, THEN PERFORM the following:

NOTES

1. Step 3.3.1 utilizes Nitrogen Gas bottle pressure or DG starting air pressure to open HV-059-129B, "Instrument Gas Outbrd B" (DRYWELL B), and to operate A/C/N MSRV Valves.

2. NO actions are required UNLESS/UNTIL control of MSRV valves is lost.

3. Figure 1 is drawing for air jumper installation.

4. Air jumpers and tools required for step 3.3.1 are stored in safeguard room mezzanine (1 6-238-309).

1.

OPEN breaker D134-R-H-19 "1A RHR HTX. RHR S.W. OUTLET

( 1 5-20 1 -200).

2.

Manually POSITION valve HV-5 1 - 1 F068A approximately 1 50 turns OPEN (1 5-201 -203).

3.3 ALIGNMENT OF EQUIPMENT FOR MSRV OPERATION 3.3.1 E PClG is NOT available, THEN PERFORM the following:

1.

CUT leads at condulet on top of SV-059-152A, "N2 SUPPLY TO ADS SYS LONG TERM N2 SUPPLY TO ADS SYS" (1 1-217-304).

2.

CLOSE HV-059-129B(AS) "INST GAS OUTBRD AIR SUPPLY VLV", ( 1 5-241 -306).

I d

ATTACHMENT 1 1FSSG-3020, Rev. 6 Page 8 of 16 J ET/W DA/RCB:jml SHEET 4 OF 6 INITIALS OPERATOR 1 ACTIONS I

UNIT 1 ONLY b

3.3.1 (Continued)

3.

CONNECT "TEE" air jumper from 59-1 143, "Backup N2 HDR.

OUTBRD. Leak Test VLV." (1 5-238-309) to 59-1 098, "'B' PRI.

AND to regulator inlet of HV-059-129B (1 5-241 -306).

CONT. INST. GAS HDR. OUTBRD. DRN TO DRW X," (1 5-241-306)

4.

CONNECT air jumper from regulator outlet to HV-59-1296 (1 5-241-306) valve inlet (bypassing the solenoid valve).

I

5.

OPEN 59-1 143.

6.

OPEN 59-1098.

7. VERIFY HV-59-129B OPEN.

SV-059-150A HV-059-151 A I

Regulator "Tee" Jumper 59-1007B HV-059-1298 FIGURE 1

I u

ATTACHMENT 1 IFSSG-3020, Rev. 6 Page 9 of 16 J ET/W DA/RCB: j m I OPERATOR 1 ACTIONS UNIT 1 ONLY SHEET 5 OF 6 I N IT1 A LS NOTES

1. The following step provides long term compressed gas to MSRV valves in the event that the N2 bottles have been exhausted.

2. The PClG N, bottles provide sufficient capacity to operate the A/C/N MSRV Valves for a limited time. Step 3.3.2 provides an indefinite supply of compressed gas utilizing the D1 1 DG starting air receiver.

3. Air jumper and door stop for step 3.3.2 are stored in a locked safe shutdown cabinet in the DG access corridor.

4. Figure 2 is drawing for air jumper installation.

~~

~

~~

3.3.2 diesel generator starting air compressor pressure is required to operate MSRV valves, THEN PERFORM the following:

1.

L OPEN door # I 64 from Diesel room 31 1A to Diesel Corridor 313, AND SECURE door # I 6 4 open.

2.

CONNECT air jumper from 20-1 172A "A AIR SUP TO LONG connection downstream of LF-059-110 "AIR SUPPLY LINE FILTER TO LONG TERM N, INSTRUMENT GAS" TERM N2 INSTR GAS OUTER ISOL VLV" (1 DG-217-311 A) to

( 1 DG-2 1 7-3 1 3-CORRIDOR).

3.

OPEN the following valves:

20-1171A 59-1 137 59-1 138

ATTACHMENT 1 IFSSG-3020, Rev. 6 Page 10 of 16 JET/WDA/RCB:jml OPERATOR I ACTIONS I

UNIT 1 ONLY SHEET 6 OF 6 INITIALS l.4, 3.3.2 (Continued)

4. Slowly THROTTLE OPEN valve 20-1 172A to maintain starting air pressure above 225 psi at PI-020-1 28A-1 "START AIR RESERVOIR PRESS".

FIGURE 2

I u

b ATTACHMENT 2 IFSSG-3020, Rev. 6 Page 1 I of 16 JETIWDAIRCB:jml SHEET 1 OF 3 INITIALS OPERATOR 2 ACTIONS UNIT I ONLY NOTES

1. The following conditions indicate HV-49-1 F007, "RCIC Main Steam Supply lnbrd PClV (INBOARD)", has failed closed.

.. RCIC fails to inject on manual auto start signal

. HV-49-1 F007, INBOARD, has position indication DIV 3 power has been disrupted

2. Step 3.4.1 will supply Div 1 power to HV-49-1 F007 AND allow use of RCIC.

3.4.1 HV-49-1 F007, "RCIC MAIN STEAM SUPPLY INBRD PCIV" can NOT be opened normally, THEN PERFORM the following:

1.

OPEN breaker D134-R-E-13, "RCIC MAIN STEAM SUPPLY INBRD PClV (EMERG PWR SUPPLY) HV-49-1 F007".

NOTE A screwdriver AND LV-100 key are required for the following step.

2.

UNLOCK I

AND OPEN terminal box 1 OTB49-1 F007 ( 1 5-253-402).

3.

PLACE 43-CB22313, "MANUAL TRANSFER SWITCH," (located in terminal box 1 OTB49-1 F007) in EMERGENCY If (R15-253-402)

I L,

ATTACHMENT 2 OPERATOR 2 ACTIONS 1 FSSG-3020, Rev. 6 Page 12 of 16 J ET/W DA/RCB:jml UNIT I ONLY SHEET 2 OF 3 INITIALS 3.4.1 (Continued)

4.

UNLOCK AND CLOSE breaker D114-R-C-31, "RCIC MAIN STM SUPPLY I

INBRD PClV ( EMERG PWR SUPPLY) HV-49-1 F007" (1 1-283-506).

5.

PLACE HS-49-107-2, "RCIC Main Steam Supply INBRD PCIV" (INBOARD), to "OPEN" at 1 OC201.

6.

ENSURE HV-49-1 F007, INBOARD, opens.

7.

OPEN AND LOCK breaker D 1 14-R-C-3 1 (1 1-283-506).

8. RETURN 43-CB22313, "MANUAL TRANSFER SWITCH," to N 0 R MA L.

3.5 3.5.1 ALIGNMENT OF EQUIPMENT FOR SPC/SDC OPERATION L

HV-51-1FOIOA, " I C RHR PP. Full Flow Test Return VLV."

can NOT be closed normally, THEN PERFORM the following:

1.

OPEN breaker D134-R-H-23, " I C RHR PP. FULL FLOW TEST RETURN VLV. HV-51-1F010Ar' (15-201-200).

2.

Manually CLOSE valve HV-51-1 FO1 OA (1 1-230-304).

I b

ATTACHMENT 2 IFSSG-3020, Rev. 6 Page 13 of 16 J ET/WDA/RCB:jml SHEET 3 OF 3 INITIALS OPERATOR 2 ACTIONS UNIT I ONLY 3.6 OPEN RCIC VACUUM BREAKER ISOLATION VALVE 3.6.1 HV-49-1 F084, "RCIC TURB EXHAUST VACUUM BREAKER PClV (INBOARD)" can NOT be opened normally, THEN PERFORM the following:

1.

OPEN breaker D134-R-E-27, "RCIC TURB EXHAUST VACUUM BREAKER PClV HV-49-1 F084" (1 5-253-402 - Corridor).

2.

Manually OPEN HV-49-1 F084 (1 5-201-203).

3.7 ALIGNMENT OF EQUIPMENT FOR LONG TERM ESW OPERATION 3.7.1 E HV-01 1-01 5A, "A ESW DISCH TO B RHR SERV WTR,"

can NOT be closed normally, THEN PERFORM the following:

1.

OPEN breaker D134-D-G-22 "ESW "A" DISCH TO SPRAY L

POND/CLG. TOWER HV-11-015A" (1 DG-217-311 C).

2.

Manually CLOSE valve HV-01 1-01 5A (P/T-201-202).

ATTACHMENT 3 IFSSG-3020, Rev. 6 Page 14 of 16 JET/WDA/RCB:jml OPERATOR 3 ACTIONS UNIT I ONLY SHEET 1 OF 1 IN IT1 A LS 3.8 MAN THE RSP NOTE Control/Monitoring of any or all of the following may NOT be available in the MCR:

MSRVS RClC RHR ESW RHRSW L

Therefore, it will be necessary to man the RSP to provide for proper operation of affected systems.

3.8.1 E system control OR indication is NOT available THEN PERFORM the following:

1.

2.

CONTROL/MONITOR systems as necessary.

SEND an Operator to the RSP.

I Step Number i

ATTACHMENT 4 RETURN TO NORMAL Required Restored By IVOR By Equipment Number (Location)

Position Sequence INITIALS INITIALS UNIT I ONLY SHEET 1 OF 2 IFSSG-3020, Kev. 6 Page 15 of 16 J ET/W D A/RC B: jm I

i I

Step Number

(

ATTACHMENT 4 RETURN TO NORMAL Required Restored By IVOR By Equipment Number (Location)

Position Sequence INITIALS INITIALS UNIT 1 ONLY I

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IFSSG-3020, Rev. 6 Page 16 of 16 JET/WDA/RCB:jml I

I SHEET 2 OF 2 I

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2FSSG-3020, Rev. 2 Page 1 of 6 G JS/RCB/CEP: jml Reactor Vessel Suppression Pool UNIT 2 ONLY LeveVPressure XR-42-2R623A MCR 20-C601 Level LI-52-240A MCR 20-C626 Tem per at u re TI-4 1 -20 1 MCR 20-C626 EXELON NUCLEAR LIMERICK GENERATING STATION FIRE SAFE SHUTDOWN GUIDE SYSTEM LPCI-A ZFSSG-3020 FIRE AREA 020 FIRE GUIDE Unit 1 Static Inverter Compartment (El. 254'-0")

PARAMETER INSTRUMENT LO CAT1 0 N Flow FI-5 1 -2R603A MCR 20-C601 NOTE NO PROMPT ACTIONS REQUIRED ADS-H ADS-K 1.o EQUIPMENT AVAILABLE FOR FIRE SAFE SHUTDOWN Control PSV-41-2FO13H MCR 20-C626 Control PSV-41-2FO13K MCR 20-C626 1.I PROTECTED INSTRUMENTS SYSTEM I

PARAMETER I

INSTRUMENT I

LOCATION I

1.2 LEVEL CONTROL SYSTEMS AND PROTECTED INSTRUMENTS ILPCI-c IFlow IFI-5 1 -2R603C IMCR 20-C601 I

lRClC IFlow IFI-49-2R600-1 IMCR 20-C648 1.3 PRESSURE CONTROL SYSTEMS AND PROTECTED HAND SWITCHES SYSTEM I

PARAMETER I HANDSWITCH I LOCATION IADS-E lcontrol IPSV-41-2FO13E IMCR 20-C626 I

IADS-M I Control IPSV-41-2FOI 3M IMCR 20-C626 I

IADS-s I Control 1PSV-41-2FOI 3s IMCR 20-C626

2FSSG-3020, Rev. 2 Page 2 of 6 G J S/ RC B/C E P: j m I SYSTEM Alt. SDC -A Supp. Pool Cooling-A RHRSW-A UNIT 2 ONLY 1.4 DECAY HEAT REMOVAL SYSTEMS AND PROTECTED INSTRUMENTS PARAMETER INSTRUMENT L 0 CAT1 0 N Flow FI-5 1 -2R603A MCR 20-C601 Flow FI-5 1 -2R603A MCR 20-C601 Flow FI-5 1 -2R602A MCR 00-C667 using OC-P506 Pressure PI-5 1 -205A-1 MCR 00-C667 1.5 PROTECTED ELECTRICAL POWER SYSTEMS AND PROTECTED ESW SYSTEM COMPONENTS 4 KV BUS D11 SAFEGUARD SWITCHGEAR IO-AI 15 D21 SAFEGUARD SWITCHGEAR 20-AI 15 D23 SAFEGUARD SWITCHGEAR 20-AI 17 DIESELS D11 DIESEL GENERATOR 1A-G501 D21 DIESEL GENERATOR 2A-G501 D23 DIESEL GENERATOR 2C-G501 I

SYSTEM I

PARAMETER ESW-A LFlow Inverter Rooms 130°F 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Per SE-1 -3 Aux. Equipment/RSP Room 1 20°F 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Per SE-1 -3 Control Room 120°F 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Per SE-1-3 4 KV Switchgear Rooms 122°F 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Per SE-1-3 using I Pressure AND/OR OA-P548 OC-P548 INSTRUMENT I LO CAT1 0 N 2.0 VENTILATION I AREA I TEMP.

I TIME I ACTION

2FSSG-3020, Rev. 2 Page 3 of 6 GJS/RCB/CEP:jml UNIT 2 ONLY 3.0 CONTINGENCY ACTIONS - OPERATOR 1 ACTIONS 3.1 ALIGNMENT OF EQUIPMENT FOR LONG TERM ESW OPERATION 4.0 4.1 4.2 5.0 5.1 5.2 5.3 - OPERATOR 2 ACTIONS 3.2 MAN THE RSP RETURN TO NORMAL REVIEW Safe Shutdown Guide AND PERFORM the following:

RECORD information for all components manipulated in Section 3.0 in "Step Number" and "Equipment Number" columns of Attachment 4.

SEQUENCE restoration steps as necessary.

INITIALS GENERATE Clearances and Action Requests for all components that can NOT be restored.

ENSURE all components manipulated in Section 3.0 are returned to normal OR have clearance applied.

REFERENCES Calculation LF-0016-020, Fire Area 020 Fire Safe Shutdown Analysis Spec if i c a t i o n N E- 0 2 94, " Fi re Safe S h ut d o w n An a I y s i s Spec if i ca t io n "

SE-1-3, "Protected Ventilation Source"

I u

ATTACHMENT 1 OPERATOR 1 ACTIONS UNIT 2 ONLY SHEET 1 OF 1 2FSSG-3020, Rev. 2 Page 4 of 6 G JSIRCBICEP: jml INITIALS 3.1 ALIGNMENT OF EQUIPMENT FOR LONG TERM ESW OPERATION 3.1.1 E HV-01 1-01 5A, "A ESW DISCH TO B RHR SERV WTR,"

can NOT be closed normally, THEN PERFORM the following:

1.

OPEN breaker D134-D-G-22 "ESW "A" DISCH TO SPRAY POND/CLG. TOWER HV-11-015A" (IDG-217-31 IC).

2.

Manually CLOSE valve HV-01 1-01 5A (P/T-201-202).

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I ATTACHMENT 2 2FSSG-3020, Rev. 2 Page 5 of 6 G JS/RCB/CEP:jml OPERATOR 2 ACTIONS UNIT 2 ONLY SHEET 1 OF 1 INITIALS NOTE ControI/Monitoring of the following may NOT be available in the MCR:

RHRSW Therefore, it will be necessary to man the RSP to provide for proper operation of affected systems.

3.2 MAN THE RSP 3.2.1 E system control OR indication is NOT available THEN PERFORM the following:

1.

SEND an Operator to the RSP.

2. CONTROL/MONITOR systems as necessary.

L c

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ATTACHMENT 3 RETURN TO NORMAL UNIT 2 ONLY SHEET 1 OF 1 2FSSG-3020, Rev. 2 Page 6 of 6 G JS/RCB/CEP:jml Step Required Restored By IVOR By Number Equipment Number (Location)

Position Sequence INITIALS INITIALS I

ML050380271

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