ML050350339

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Draft - Limerick, Section a Operating (Folder 2)
ML050350339
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 11/15/2004
From: Jason White
Exelon Generation Co
To: Conte R
NRC/RGN-I/DRS/OSB
References
50-352/05-301, 50-353/05-301 50-352/05-301, 50-353/05-301
Download: ML050350339 (80)
v • d • e


Text

BUCLEAR GENERATION GROUP EXELON NUCLEAq Limerick Generating Station Job Performance Measure REVIEW OF CONTROL ROOM SUPERVISOR SHIFT TURNOVER CHECKLIST JPM Number: 0701 Revision Number: 000 Date: I 1 /I 1 /04 Developed By:

Instructor Validated By:

SME or Instructor Review By:

Operations Representative Approved By:

Training Department

~~

Date Date Date Date LLOJPM0701 Rev000 Page 1 of 6

L INUCLEAR GENERATION GROUP EXEL ON NUCL EA^

LLOJPMO701 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 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 u

LLOJPM0701 Rev000 Page 2 of 6

L LOJPM0701 REvOOO Job Performance Measure (JPM)

Revision Record (Summary)

1.

INITIAL CONDITIONS:

Unit I and 2 are 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.

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 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.

L LLOJPM0701 Rev000 Page 3 of 6

~ U C L E A R GENERATION GROUP EXELON N U C L E A ~

LLOJPM0701 REvOOO Job Performance Measure (JPM)

Operators Name:

JobTitle:

0 NLO 0 RO SRO 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:

0 No 0

Time Critical: 0 No Estimated Time to Complete: 30 minutes Actual Time Used:

minutes L-

References:

OP-LG-112-101-1000 Rev 0 OP-LG-112-101-1002 Rev 1 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:

Satisfactory 0 Unsatisfactory Comments:

~

Evaluators Name:

(Print)

Evaluators Signature:

Date:

LLOJPM0701 Rev000 Page 4 of 6

[NUCLEAR GENERATION GROUP EXELON NUCLEA~

LLOJPM0701 REvOOO Job Performance Measure (JPM)

JPM Start Time:

~~

Comment Number UNSAT SAT STANDARD ELEMENT N/A (Cue: Provide candidate the Control Room Supervisor Shift Turnover Checklist)

~

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

Reviews the Control Room Supervisor shift turnover check list and finds the following errors:

  • I

.a Find error on page I Unit 1 is in OPCON 5*

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

~~ *I

.b Find error on page I Unit 1 box, I A RHR in shutdown cooling, but DIV I LOCA LOOP testing is scheduled which will cause lose of shutdown cooling.

1.c Find error on page 2 One of the 3 STA, IA check boxs is not checked.

(CUE: You may stop here, you have met the termination criteria for this JPM)

N/A JPM Stop Time:

L L OJPMO70 I Rev000 Page 5 of 6

INUCLEAR GENERATION GROUP EXELON NUCLEAR]

I N ITlAL CON DIT1 ONS:

Unit 1 is in OPCON I 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

Exelan.

3 L

N ucl ear OP-LG-112-101 -I 002 Revision 1 Page I of 2 CONTROL ROOM SUPERVISOR SHIFT TURNOVER CHECKLIST Shift UNIT 1

2 MODE I % POWER

~

PRI CONT EST: (Y/N)

SEC CONT EST: (YIN)

Y Refuel Floor Sec. Cont EST: (YIN)

Significant Activities in progress or planned (for next shift)

T. S. Equip. Status OR Conditions (At LGS -

LCOs i 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Operational limitations Major Equipment Status 01 Conditions Significant Activities in progress or planned (for next shift)

T. S. Equip. Status OR Conditions (At LGS -

LCOs 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Major Equipment Status or Conditions n

UNIT: 2 I

Significant Activities in progress or planned (for next shift)

T. S. Equip. Status OR Conditions (At LGS -

LCOs i 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Operational limitations Major Equipment Status or Conditions

- NOUb

OP-LG-112-101-1002 Revision 1 Page 2 of 2 CONTROL ROOM SUPERVISOR SHIFT TURNOVER CHECKLIST PRE-TURNOVER ITEM REVIEW d

Unified Narrative Log reviewed

[43 LCO/PLCO Reviewed Panel Walkarounds Completed Verify Qualifications Prior to Tak,, ig Shift 0

Control Key Cabinet Reviewed (FNIA if WCS Staffed)

Review Standing Orders for new Entries w

PRO Lr U/2 RO Applicable Turnover Sheets Reviewed:

m U/1 RO Select One of the Following:

0 I am &the STA.

0 I am the STA, the IA function is not required AND I have notified the offgoing STA of my presence on site.

0 I am the STA, the IA function is required,

&JJ I have performed face-to-face turnover with the offgoing STA in the Main Control Room per OP-AA-112-101.

RESPONSIBILITY ASSUMED BY: (Oncoming SSV Signature)

Signature:

Time:

1 9 10 POST-TURNOVER ITEM REVIEW O/A/Rs reviewed for Operability Impact 0

SSV ST Schedule, A-C-134 & Locked Valve Log Reviewed (mN/A if WCS Staffed)

WTPA Log /Report Reviewed Review Daily Orders

]NUCLEAR GENERATION GROUP EXEL ON NUCL EA^

Limerick Generating Station Job Performance Measure INTERPRETATION AND APPLICATION OF OVERTIME LIMITS Developed By:

Validated By:

Review By:

Approved By:

JPM Number: 0700 Revision Number: 000 Date: I 1 /I I

/04 Instructor SME or Instructor Operations Representative Training Department Date Date Date

~~

Date LLOJPM0700 Rev000 Page 1 of 6

I NUCLEAR GENERATION GROUP EXELON NUCLEAA LLOJPM0700 REV000 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 1 I 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:

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

When JPM is revalidated, SME or Instructor sign and date JPM u

LLOJPM0700 Rev000 Page 2 of 6

I NUCLEAR GENERATION GROUP EXELON N U C L E A ~

LLOJPM0700 REvOOO Job Performance Measure (JPM)

Revision Record (Summary)

1.

INITIAL CONDITIONS:

Unit 1 is in OPCON 1 Unit 1 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 if the ROs are allowed to stand Unit I RO.

Information For Evaluators Use:

UNSAT requires written comments on respective step.

e 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.

LLOJPM0700 Rev000 Page 3 of 6

LLOJPM0700 REvOOO Job Performance Measure (JPM)

Operators Name:

Job

Title:

NLO RO 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:

Si mu lator Act u a I Testing E nvi ro n men t :

Testing Method:

Simulate Faulted: 0 No S i m u I ato r Alternate Path: 0 No Time Critical: CI No 0

L Estimated Time to Complete: 30 minutes Actual Time Used:

minutes References :

LS-AA-119 Rev 2 EVALUATION SUM MARY:

Were all the Critical Elements performed satisfactorily?

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

Satisfactory 0 Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

LLOJPM0700 Rev000 L

Page 4 of 6

NUCLEAR GENERATION GRouf EXELON NUCLEAR]

JPM Start Time:

L ELEMENT

  • I.

Reference LS-AA-I 19 to determine which RO's are allowed to assume the Unit 1 RO position (Cue: Provide copy of LS-AA-I 19 if asked for.)

  • 2. Determine candidate I is in violation of LS-AA-1 I 9 limits.

"3. Determine candidate 2is in violation of LS-AA-1 I 9 limits.

  • 4. Determine candidate 3is in violation of LS-AA-I 19 limits.
5. Determine candidate 4i s allowed to assume the Unit 1 RO position.
6. Determine candidate 5 is allowed to assume the Unit I RO position.

(CUE: You may stop here, you have met the termination criteria for this JPM)

JPM Stop Time:

STANDARD LS-AA-119 is obtained Candidate 1 is found in violation of limits if called in. More than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a seven day (168 hr) period Candidate 2 is found in violation of limits if called in. More than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.

Candidate 3 is found in violation of limits if called in. More than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and less than an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 Comment Number LLOJPM070U RevUOU Page 5 of 6

NUCLEAR GENERATION GROUP EXEL ON NUCL EAd Candidate I

INITIAL CONDITIONS:

i Unit I is in OPCON 1 Unit 1 oncoming RO for the 1800-0600 shift has called off sick.

Date is 11/14 Time is 1500 11/7 11/8 11/9 INITIATING CUES:

0600-1800 1600 1530 0600 0800-0700-1800-There are 5 ROs available to fill the position. You are told to perform verification of overtime hours to determine if the ROs are allowed to stand Unit 1 RO.

0600-1800 1600 1530 0600 0600 0800-0700-1800-1800-2 I

1 I

I 0600- I 0600-1800 1800 0800-0800-3 1600 1600 0700-0700-4 1530 1530 0600-I0600 I0600 I0600 5

Work 11/10 0600-1800 1600 1530 0600 0600 0800-0700-1800-1800-1800 1800-1800-1800-11/13 0600-1800 1800 0600-1800-0600 1800-0600 11/14 0200-1000 0600-1100 CANDIDATE

(NUCLEAR GENERATION GROUP EXELON N U C L E A ~

Developed By:

Validated By:

Review By:

Approved By:

Limerick Generating Station Job Performance Measure REVIEW CONTROL ROD EXERCISE ST JPM Number: 0702 Revision Number: 000 Date: I 1 /I I

/04 Instructor SME or Instructor Operations Representative Training Department Date Date Date Date L L OJPM0702 Rev000 Page 1 of 6

INUCLEAR GENERATION GROUP EXEL ON NUCL EA^

L LOJPM0702 REvOOO i

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 1 I 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:
10. 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 JPMO 702 Rev000 Page 2 of 6

(NUCLEAR GENERATION GROUP EXEL ON NUCLEAR]

LLOJPM0702 REvOOO Job Performance Measure (JPM)

Revision Record (Summary)

1.

IN ITlAL CONDITIONS:

Unit 1 is in OPCON 1 INITIATING CUES:

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

Information For Evaluators Use:

UNSAT requires written comments on respective step.

L

  • 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.

LLOJPM0702 Rev000 Page 3 of 6

(NUCLEAR GENERATION GROUP EXELON N U C L E A ~

LLOJPM0702 REvOOO Job Performance Measure (JPMI Operators Name:

Job

Title:

0 NLO 0 RO SRO STA 0 SROCert JPM

Title:

Review Control Rod Exercise ST JPM Number: LLOJPM0701 Revision Number: 000 WA Number and Importance: Generic 2.2.12 Suggested Testing Environment :

Simulator Actual Testing Environment:

Simulator Testing Method: 0 Simulate Faulted:

No Alternate Path:

17 No I7 Time Critical: 17 No Estimated Time to Complete: 30 minutes Actual Time Used:

minutes References :

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

SUMMARY

Were all the Critical Elements performed satisfactorily?

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

0 Satisfactory 0 Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

d-L LOJPM0702 Re v000 Page 4 of 6

INUCLEAR GENERATION GROUP EXELON NUCLEAR(

JPM Start Time:

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

NIA

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

Review ST-107-670-1 for errors and discrepancies and finds the following errors:

  • I

.a Find error on page I

  • I.b Find error on page 22 Comments in Additional Actionnest Comments block, but not signed or dated.

Rod 14-31 found at 06 but left at 04.

  • I.c Find error on page 15 Step 4.6.1.I

.a requires Control rod Position Log attached to ST for as left rod positions. It is not (CUE: You may stop here, you have met the termination criteria for this JPM)

N/A JPM Stop Time:

SAT UNSAT Comment Number L L OJPM0702 Re v000 Page 5 of 6

.(NUCLEAR GENERATION GROUP EXEL ON NUCLEAR(

INITIAL CONDITIONS:

Unit I is in OPCON 1 I N IT I AT I N G C U ES :

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

\\.--

CAN D I DATE

ST-6-I 07-760-1, Rev. 50 Page 1 of 34 ALCIRCB/JHG:eer q,

P.M.

LIMERICK GENERATING STATION L-'

ST-6-1 07-760-1 Test Freq:

Weekly - QR - Initiating Events:

A.

Tech Spec:

4.1.3.7.c 4.1.3.6 B.

4.1.3.1.2 4.1.3.7.b FSAR 4.6.3.1.1.5.b SER 4.6 4.0.5 4.1.3.1.3 C.

TFST:

(Circle SAT or UNSAT - Below)

(UNSAT Results Only)

L' Shift Supervision:....................................

Corrective Action (if required)..............

(ETT A/R - Number)

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

(Sign/Date)

ST 107-760-1, Rev. 50 Page 2 of 34 1.o b

1.1 i

1.2 1.3 J

4 PURPOSE To verify OPERABILITY of each withdrawn control rod AND 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 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 AND by verifying the control rods do not go to OVERTRAVEL position.

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

PREREQUISITES Plant in OPCON 1.

Reactor power level is above the preset power level of the RWM via ROD WORTH MINIMIZER, BELOW LPSP is 1 OC603 OR PMS point A555 reads "GT LPSP.>----.-

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

displayed in POWER field at c

No other testing OR plant condition which could interfere with this test is being performed/present.

RDCS OPERABLE IF known fuel defect(s) exist THEN an evaluation of fully withdrawn control rods, within a 3 x 3 array of the fuel defect(s), has been obtained from Reactor Engineering. This shall include 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 107-760- 1, Rev. 50 Page 3 of 34 3.1 3.2 3.3 3.4 3.5 3.0 PRECAUTIONS 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, THEN 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 immediatelv.

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.

Conditions listed in step 3.6 indicate that there may be a fault in the Rod Select 3.6 3.7 3.8 IF any of the following conditions exist during control rod selection, THEN do AND SSVN shall be immediatelv notified:

attempt control rod movement 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 shih(s),

THEN a Control Rod Position Log edit shall be performed at the end of the shift(s1.

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-6-107-760-1, Rev. 50 Page 4 of 34 3.9 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

r4 L

3.10 any rod does not perform satisfactorily, THEN SSVN shall be informed immediatelv 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-6-1 07-760-1, Rev. 50 Page 5 of 34 INITIALS n

L-It is the responsibility of the person OR persons performing this test to ensure &I blankddata sheets are correctly AND completelv filled in.

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.

P 1

47-4.1.?

VERIFY all prerequisites of Section 2.0 are satisfied.

4.1.2 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.

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

4.2.2 OBTAIN PRO/RO permission to start test.

4.2.3 VERIFY this test is being performed on Unit 1.

p-ro-u(f / 0919 Daterrime

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

4.3 PRELIMINARY DATA L-rq L

4.3.1 RECORD the following:

Present reactor thermal power from PMS.

Rx Power qs.? %

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:

INITIALS

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

ST4-107-760-1, Rev. 50 Page7 of 34 NOTE

1.

Each OPERABLE control rod which is llof 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 AJW there are 110 rod drift alarms.

OR the conditions of 4.4.1.1.e are met AND there are na rod drift alarms.

I I

'3. Steps 4.4 I

the test.

AND4.5 may be performed concurrently to facilitate row-by-row performance of 4.4 FULLY WITHDRAWN CONTROL RODS 4.4.1 PERFORM the following to test each fully withdrawn control rod, one at a time:

rq u

1.

Satisfactory completion of step 4.4.1.I 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 A1 081 91 3 Eva1 60. (Ref 6.1 I )

2.
1.

PERFORM the following:

4 (SO)

a.
b.

C.

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

E 48 is mt being indicated on the Four Rod Display,

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

INSERT the control rod one notch.

ST-6-107-7eO-1, Rev. 50 Page 8 of 34 lhlmALs

d.

VERIFY on the Four Rod Display that the selected Rod indicates position 46.

' l a

e.

E any control rod begins to insert AND settles back to position 48 rHEN PERFORM the following.

C)theMIise, MARK N/A for steps 4.4.1.I

.e, through 4.4.l.l.e.11:

L I.

to position 46.

i

2.

Esuccessf ul, THEN GO TO step 4.4.1.2.

/ m

/ m ATTEMPT another single notch insert

3.

E unsuccessful, THEN PERFORM the following:

a. E control rod does not indicate notch position 46 due to insufficient control rod movement, J

B REVIEW 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 doublenotching without a power reduct ion.

b.

LE a power reduction is required, THEN REDUCE core power in accordance with GP-5 Appendix 2, Sect ion 3. I

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

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

.e.4.

4.

RAISE CRD System Drive pressure by 25 psid, nnt to exceed 350 psid.

ATTEIVIPT a single notch insert.

5.

ST-6-107-780-1, Rev. 50 Page 9 of 34

6.

LE the rod double notches to position 44, THW WITHDRAW the rod to position 48. (Ref 6.1 1)

LE 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 AND increased CRD System Drive pressure was required, THEN INITIATE AIR AND NOTIFY CRD System Manager for trending purposes. (Equipment Status Tagging is nni required.)

7.

.DA El

/El f4+

lpcl

8.
9.

approximately 260 psid.

L THEN ENTER ON-1 04.

I O.

11.

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

I

/

f.

ENSURE CRD System Drive pressure is approximately 260 psid.

g.

LE control rod does not indicate notch position 46 due to WlS problems, THW PERFORM the following, Qthawh, MARK N/A for steps 4.4.1.I

.g.1 through 4.4.1.l

.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 posit ion 44 w it hout a power reduction.

2.
3.
4.
2.
3.

ST-6-107-780-1, Rev. 50 Page 10 of 34 E 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 ablIl GO TO step 4.4.1.1.g.3.

INSERT the control rod one notch to position 44.

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

E Control Rod Position Log is nnt available, THEN RECORD the AS LEFT position of each control rod on Attachment 1.

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

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

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.

4.4.2 WHEN a control rod is withdrawn to FULL OUT position, THEN PERFORM coupling check at panel 1OC603 by notch w it hdraw QE3 continuous withdraw (stall flow check) selected rod.

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

4.4.3

ST-B-1 07-7450-1, Rev. 50 Page 11 of 34 m

v 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 106649.

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

2.

4.4.5 Estep 4.4.4.1 4.4.4.2 are &I satisfactorily performed, AND THEN ENTER initials in the appropriate columnhod in.

n 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 Actionnest Comment section.

ST 107-760- 1, Rev. 50 Page 12of 34 INITIALS

c.

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 Operation CMWT 5 3458 CMWT 2634 CMAPR 5 0.98 CMAPR 5 0.98 CMFLPD 5 0.98 CMFLPD 5 0.98 FLLLP I; 1.0 FLLLP 5 1.O

ST6-107-760-1, Rev. 50 Page 13 of 34

2.

JE thermal limits do LlDf satisfy values shown in step 4.5.1.I, THEN REDUCE core power in accordance w ith GP-5 Appendix 2, Section 3.1, using core flow per Reactor Maneuvering Shutdown Instructions (RMSI) as required to satisfy limits W ENSURE FLLLP remains 5 I

.O.

DtheMl, MARK N/A.

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

Satisfactory completion of step 4.5.2 demonstrates 47-1 -38, "Cooling Header Check Valve," (Typical of 1 85) has exercised closed.

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

1.

PERFORM the following:

DV

a.

V W F Y that selected Rod indicates a proper position on the Four Rod display.

INSERT Control Rod one notch.

V w p / 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.

b.
c.
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 position indication.

RECORD AS LEFT position of each control rod on.

INDICATE N/A in coupling check column of.

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

blank.

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

enwise, the stall flow data column shall be left

ST-lj-107-760-1, Rev. 50 Page 15 of 34 r-./ 4.6 RETURN TO NORMAL 4.6.1 PERFORM the following for final Control Rod Posit ions:

1. E Control Rod Position Log is available THEN PERFORM the following, DtheMl, MARK this step N/A:
a.

OBTAIN Control Rod Position Log AND ATTACH to this test.

b.

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

c.

MARK step 4.6.1.2 N/A.

2. E Control Rod Position Log is nat 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 aB by comparing the AS FOUND, AS LEFT columns on Attachment I.

E any control rods have nat been returned to AS FOUND Posit ion, THEN UST rods AND reason for new position in the Additional Act ion/Test Comments sect ion.

4.6.3 n

L

P 4.6.4 4.6.5 4.6.6 4.6.7 4.6.8 ST-6-107-780-1, 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.

Q~mxise ENTER N/A for this step.

required, THEN RETURN Unit to original power level by raising power in accordance with GP-5 Appendix 2 Section 3.2 Qttmwh, ENTER N/A for this step.

ENSURE IVOR completed on Attachment 2.

NOTIFY ssv AND 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 fi 5.1

\\,

5.2 5.3 5.4 6.0 6.1 6.2 6.3 6.4 6.5 6.6 6.7 All OPERABLE withdrawn control rods have been moved at least one notch to demonstrate OPERABILITY.

During control rod movement, the position indication changes correctly.

Rod coupling has been verified.

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

REFERENCES CM-1, TO1 699 Control Rod Mispositioning LGS-FSAR-Section 4.6.1 FSAR 4.6.3.1.I

.5.b SER 4.6 Pump & Valve lnservice Testing Program Plan General Electric PCIOMR Implementing Procedures, NEDE-21 493 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 6.1 0 GEK-75714, Reactor Manual Control System 6.1 I A I 081 91 3 Eva1 60, Analysis to insert rods to position 44 during CRD kercise

ST-6-107-760-1, Rev. 50 Page 18 of 34 7.O TECHNICAL SPECIFICATIONS 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 F?x Maneuvering Without Shutdown

ST.6-I 07-760-1, Rev. 50 Page 19 of 34 ATTACHMENT 1 Page1 of 15 4.3.2 Control Rod Position Log is not available AS FOUND.

4.6.1 Control Rod Position Log is not available AS LEFT.

Control Rod

~

02-1 9

~

02-23 02-27 02-3 1 02-35 02-39 0243 4.3.2.2, 413.4, 4.4.1.3, 4.5.2.3 Control Rod, Position AS FOUND I AS LEFT SteD Number PerformerlDV

n L-ST-6-I 07-760-1 Rev. 50 Page 20 of 34 ATTACHMENT 1 Page2 of 15 4.3.2.2, 4.3.4, 4.4.1.3, 4.5.2.3 1 AS FOUND I AS LEFT 06-1 5 06-1 9 06-23 06-27 06-31 06-35 06-39 0643 0647 Step Number 4.4.1.I 4.5.2.1 Operability Check Complete Performer/DV 4.4.5 Coupling Check Complete 4.4.3 CRD W/D Stall Flow GPM (if required)

PM PM PM PM PM PM

~

PM

Control Rod 10-1 1 10-1 5 10-19 10-23 10-27 10-31 10-35 10-39 10-43 10-47 10-51 ST-6-107-760-1, Rev. 50 Page 21 of 34 ATTACHMENT 1 Page3of 15 4.3.2.2, 4.3.4, 4.4.1.3, 4.5.2.3 Control Rod, Position AS FOUND AS LEFT 4.4.1.1 4.5.2.1 Operability Check Complete Performer/DV I

4.4.5 I

4.4.3 PM PM PM PM PM PN PN PN

p.

ST-6-107-760-1, Rev. 50 Page 22 of 34 ATTACHMENT I Page 4 of 15 4.4.1.4/4.5.2.6 Current Control Rod Position Log matches 'AS FOUND' Control Rod Position Log.

ST-6-I 07-7430-1, Rev. 50 Page.23 of 34 ATTACHMENT 1 Page 5 of 15 4.3.2.2, 4.3.4, 4.4.1.3, 18-1 1 18-1 5 18-1 9 18-23 18-27 18-31 18-35 18-39 18-43 18-47 18-51 18-55 18-59 Step Number 4.4.1.1 4.4.5 4.4.3 4.5.2.1 Complete Check Flow GPM Complete fif required)

Operability Check Coupling CRD W/D Stall

ST4-I 07-760-1, Rev. 50 Page 24 of 34 ATTACHMENT 1 Page 6 of 15 Control Rod Step Number 4.3.2.2, 4.3.4, 4.4.1.3, 4.4.1.1 4.4.5 4.4.3 4.5.2.3 4.5.2.1 Control Rod, Position Operability Check Coupling CRD WID Stall Complete Check Flow GPM Complete (if required)

ST-6-107-760-1, Rev. 50 Page 25 of 34 n

ATTACHMENT 1 Page 7 of 15 26-59 Step Number 4.4.1. I I

4.4.5 I

4.4.3 4.5.2.1 Complete Check Flow GPM Complete (if required)

Operability Check Coupling CRD W/D Stall

rq ST-fj-107-760-1, Rev. 50 Page 26 of 34 ATTACHMENT 1 Page 8 of 15 5

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

4 30-55 Ph 30-59 Ph A~ACHMENT I Page 9 of 15 x

1

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

c.

I, Step Number 4.3.2.2, 4.4.1.3, 4.4.1.1 4.4.5 4.4.3 4.5.2.3 4.5.2.1 Control Control Rod, Position Operability Check Coupling CRD WID Stall Rod Complete Check Flow GPM Complete (if required)

ST-6-107-760-1, Rev. 50 Page 28 of 34 ATTACHMENT 1 Page 10 of 15 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 29 of 34 ATTACHMENT 1 Page I 1 of 15 42-5 1 42-55 42-59 Y

ST4-107-760-1, Rev. 50 Page 30 of 34 ATTACHMENT 1 Page 12 of 15 4.4.1.4/4.5.2.6 Current Control Rod Position Log matches 'AS FOUND' Control Rod Position Log.

4 Step Number 4.4.1.1 I

4.4.5 I

4.4.3

n Control Rod 50-1 1 50-1 5 50-1 9 50-23 50-27 50-3 1 50-35 50-39 50-43 50-47 50-51 ST-6-107-760-1, Rev. 50 Page 31 of 34 ATTACHMENT 1 Page 13 of 15 Step Number 4.3.2.2, 4.3.4, 4.4.1.3, I 4.4.1.I I

4.4.5 4.5.2.3 4.5.2.1 Control Rod, Position Operability Check Coupling Complete Complete Check 4.4.3 CRD WID Stall Flow GPM (if required)

PM PM PM PM PM PM PM

ST-6-107-760-1, Rev. 50 Page 32 of 34 ATTACHMENT I Page 14 of 15

Control Rod 58-1 9 58-23 58-27 58-31 58-39 58-43 ST-6-107-780-1, 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 1.O The following steps require Independent Verification of Restoration:

REFERENCE STEP NUMBER 4.6.2 VERIFY control rods are in AS FOUND positions, are as identified in the Additional Action/Test Comments section using Control Rod Position Logs AS FOUND, AS LEFT positions from Attachment 1.

I I

I I I

i I I

I I

i 1

I i

I 1

PLANT NAME: LIMEZtICK-1 CYCLE 11 CORCROL ROD POSITIONS 06-59 55 5 1 47 43 39 3s 3 1 27 23 19 15 11 07 L

L 06 -

L 06 4 10 L

06 -

L 06 /

L L

L L

L L

03 02 06 IO 14 l a 22 26 30 34 S = SUBSTITUTE VAZslE L = LPRM

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

SEQUENCE A09D PAGE 1

1O-DEC; -2004 09:22 CALCULATED lO-~FX,'-2004 09:22 PRINTED 06, 06 -

06 &

L L

L 3a 42 46 so 54 sa LOAD LINE S-Y CORE POWER 99.932 CORE FLOW 92.27%

LOAD LINE 105.87%

FLLLP 0.916

' ?

t

)

NUCLEAR GENERATION GROUP 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: I 1 /I I

/04 Instructor Date SME or Instructor Date Operations Representative Date Training Department Date L LO JPM0703 Rev000 Page 1 of 8

INUCLEAR GENERATION GROUP EXELON NUCLEAq LLOJPM0703 REV000 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 11 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.

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

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

cover page.

LLOJPM0703 Rev000 Page 2 of 8

INUCLEAR GENERATION GROUP EXEL ON NUCL EA^

LLOJPM0703 R~v000 Job Performance Measure (JPM)

Revision Record (Summary)

I.

!NITIAL CONDITIONS:

Unit 1 is in OPCON 1 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:

Accumulated Dose Alarms on their Electronic Dosimeter for both workers: 1200 mrem 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 Maximum Whole Body Dose Rate in work area: 400 mrem/hr Time required to enter: 5 minutes Time required to exit: 5 minutes INITIATING CUES:

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

1. Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 & worker 2.
2. If the workers can finish the work without receiving accumulated dose alarms.

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 LLOJPM0703 Rev000 Page 3 of 8

NUCLEAR GENERATION GROUP EXELON NUCLEA~

LLOJPM0703 REvOOO Job Performance Measure (JPM) 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.

"".-_...""._...".--.I..-..

L LOJPM0703 Re v000 Page 4 of 8

INUCLEAR GENERATION GROUP EXELON NUCLEA~

L LOJPM0703 REvOOO Job Performance Measure (JPM)

Operators Name:

JobTitle:

0 NLO 0 RO 0

SRO 0 STA 0 SROCert JPM

Title:

Calculate Stay Time JPM Number: LLOJPM0703 Revision Number: 000 WA Number and importance: Generic 2.3.10 Suggested Testing Environment:

Simulator Actual Testing Environment:

Simulator Testing Method: 0 Simulate Faulted: 0 No Alternate Path: 0 No Time Critical:

No 0

Estimated Time to Complete: 30 minutes Actual Time Used:

minutes References :

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 :

Eva I u ato rs Name:

(Print)

Evaluators Signature:

Date:

L L OJPMO703 Rev000 Page 5 of 8

INUCLEAR GENERATION GROUP EXEL ON NUCL EAd JPM Start Time:

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

I. Determine Maximum Stay Time for the required entry

2. For worker I:
  • 2.a Subtract accumulated dose of 600 mr from accumulated dose alarm of 1200 mr to get remaining dose till alarm.

"2.b Divide Allowable Work Dose by the Maximum Whole Body Dose Rate in work area to get Maximum Stay Time (Worst Case) 2.c Subtract entry and exit time of 10 minutes (5 minutes+f! minutes) from the Maximum Stay Time 1 3. For worker 2:

  • 3.a Subtract accumulated dose of 800 mr from accumulated dose alarm of I200 mr to get remaining dose till 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 Remain/ 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 / 400 mr/hr = 1 hr SAT LLOJPM0703 Rev000 Page 6 of 8

NUCLEAR GENERATION GROUP EXELON NUCLEA~

ELEMENT 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 -1 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 rnin = 50 rnin Worker +Worker = Total 1 Stay 2Stay Stay Time Time Time 80 rnin + 50 min = 130 min Determine work can not be completed N/A JPM Stop Time:

LLOJPM0703 Rev000 Page 7 of 8

NUCLEAR GENERATION GROUP EXELON NUCLEAq INITIAL CONDITIONS:

CANDIDATE Unit 1 is in OPCON 1 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:

Accumulated Dose Alarms on their Electronic Dosimeter for both workers: 1200 mrem 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 Maximum Whole Body Dose Rate in work area: 400 mrem/hr Time required to enter: 5 minutes Time required to exit: 5 minutes INITIATING CUES:

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

3. Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 & worker 2.
4. If the workers can finish the work without receiving accumulated dose alarms.

INUCLEAR GENERATION GROUP EXELON NUCLEA~

Developed By:

Validated By:

Review By:

Approved By:

Limerick Generating Station Job Performance Measure ACTIVATE THE FIRE BRIGADE JPM Number: 0704 Revision Number: 000 Date: 11/11/04 Instructor SME or Instructor Operations Representative Date Date Date Training Department Date L LOJPM0704 Rev000 Page 1 of 7

L L 0 JPMO704 REvOOO L

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.

W

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

When JPM is revalidated, SME or Instructor sign and date JPM LLOJPM0704 Rev000 Page 2 of 7

INUCLEAR GENERATION GROUP EXELON NUCLEA~

L LOJPM0704 REvOOO Job Performance Measure (JPM)

Revision Record (Summary)

1.

INITIAL CONDITIONS:

Unit 1 is in OPCON 1 INITIATING CUES:

Fire alarm 006 FIRE H-6-U, ClRC WATER PUMP STRUCT, is alarming. You are ordered to activate fire brigade per SE-8.

Information For Evaluator's Use:

u 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.

L L 0 JPM0704 Rev000 Page 3 of 7

hUCLEAR GENERATION GROUP EXELON NUCLEAd LLOJPM0704 REvOOO Job Performance Measure (JPM)

JobTitle:

0 NLO 0 RO 0

SRO 0 STA 0 SROCert Operators Name:

JPM

Title:

Activate The Fire Brigade JPM Number: LLOJPM0701 Revision Number: 000 K/A Number and Importance: Generic 2.4.27 Suggested Testing Environment:

Simulator Act u a I Test i n g E nvi ro n men t :

Si m u I a to r Testing Method: 0 Simulate Faulted: 0 No Alternate Path:

No 0

Time Critical:

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

minutes Refe re n ces :

SE-8 Rev 26 Arc 006 FIRE H-6-U W

F-P-00 1 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)

L Evaluators Signature:

Date:

LLOJPM0704 Rev000 Page 4 of 7

\\NUCLEAR GENERATION GROUP EXELON NUCLEAR(

UNSAT JPM Start Time:

Comment Number c

ELEMENT (Cue: Provide copy off SE-8 to candidate)

1. WHEN an actual fire has occurred fire alarm code is annunciated, THEN PRO ANNOUNCE fire at least two times on plant radio AND page as follows:
  • I.a fire notification was by fire alarm annunciator panel, THEN USE exact words from annunciator window in announcement.
  • I

.b IDENTIFY fire alarm code AND fire location.

STANDARD SAT N/A Make announcement 2 times Circ Water Pump Structure Fire alarm code 6-1 NOTE Examples of wording to use:

1.
2.

Fire alarm code (Code number) has been annunciated in (location). Fire Brigade respond.

A fire has been reported at (location). Fire Brigade respond.

  • I.c USE appropriate wording.

I

.d WHEN fire announcements are made for drill, THEN PRECEDE with appropriate wording AND FOLLOW announcement with This is a drill.

This is a drill.

(Cue: Fire Brigade Leader responds over the radio, This is fire brigade leader responding for fire brigade and responding to fire.)

2. ACKNOWLEDGE Fire Brigade member reports of response AND location.

Fire alarm code 6-1 has been annunciated in Circ Water Pump Structure Fire Brigade respond.

This is a drill. This is a drill. Fire alarm code 6-1 has been annunciated in Circ Water Pump Structure Fire Brigade respond.

This is a drill. This is a d ri II.

Acknowledges Fire Brigade leader.

L L OJPMO704 Rev000 Page 5 of 7

ELEMENT

3. ADVISE Fire Brigade Leader of the appropriate Pre-Fire Plan to use from information contained in the Annunciator Response Card for the fire alarm.

(Cue: Provide copy of Arc 006 FIRE H-6-U if requested.)

4. VERIFY fire pump auto start START fire pump at Fire Brigade Leaders request.

(Cue: Annuciators 005 FIRE A-I. Motor Driven Fire Pump Auto Start and 005 FIRE A-2,Motor Driven Fire Pump Running are alarming.

If asked, Motor Driven fire Pump discharge pressure indicates 150 psig.)

5. ADVISE Fire Brigade Leader of additional fire alarm activations.

(Cue: No additional fire alarm activations.)

(Cue: Fire Brigade Leader reports that there was a fire in the Diesel Fire Pump room in the West end in Circ Water Pump Structure but the fire is out. Stationing reflash watch and securing fire scene.)

6. WHEN naturekize of fire is known THEN NOTIFY Power System Director.

(CUE: You may stop here, you have met the termination criteria for this JPM)

JPM Stop Time:

STANDARD Advises Fire Brigade Leader to use fire procedure F-P-001 to respond to the fire.

Verifies Motor Driven Fire Pump Start N/A N/A Notifies Power System Director of fire.

NIA SAT UNSAT Comment Number LLO JPM0704 Re v000 Page 6 of 7

(NUCLEAR GENERATION GROUP EXELON NUCLEAR^

\\- INITIAL CONDITIONS:

Unit I is in OPCON I INITIATING CUES:

Fire alarm 006 FIRE H-6-U, ClRC WATER activate fire brigade per SE-8.

L PUMP STRUCT, is alarming. You are ordered to CANDIDATE

I EXELON NUCLEAR I

I I

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

JPM Number: 0125 Revision Number: 000 Date:

/ /

Developed By:

Validated By:

Review By:

Approved By:

Instructor Date SME or Instructor Date Operations Representative Date Training Department Date LLOJPM0125 Rev000 Page 1 of 8

EXELON NUCLEAR LLOJPMOl25 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 11 below.

1.
2.
3.
4.
5.
6.
7.
8.

L-

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.

LLOJPMO 25 Rev000 Page 2 of 8

EXELON NUCLEAR JOB PERFORMANCE MEASURE (JPM)

Revision Record (Summary)

1. New JPM L L 0 JPMO7 25 SIMULATOR SETUP INSTRUCTIONS:

0 None TASK CONDITIONS:

The following conditions exist on Unit I 0

Startup is in progress with reactor power 3%, Reactor Mode Switch is in Startup/Hot Stand by All Safeguard DC power was lost 20 minutes ago and is not expected to be restored for another hour 0

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 u

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.

LLOJPMOf25 Rev000 Page 3 of 8

EXELON NUCLEAR LLOJPM0725 L

JOB PERFORMANCE MEASURE (JPM)

TITLE: ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

Operators Name:

JobTitle:

NLO 0 RO CI SRO CI STA 0 SROCert JPM

Title:

ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

JPM Number: LLOJPM0125 Revision Number: 000 WA Number and Importance:

Suggested Testing Environment:

Simulator Generic 2.4.41 2.3/4.1 Actual Testing Environment:

Simulator Testing Method: 0 Perform Faulted: 0 No Alternate Path:

No 0

Time Critical: 0 No u Estimated Time to Complete: 15 minutes Actual Time Used:

- minutes

References:

EP-AA-I 008, LGS EMERGENCY ACTION LEVEL (EAL) MATRIX, REV 05 EP-AA-112-100, Rev 5, CONTROL ROOM OPERATIONS EP-MA-114-100, Rev 5, MAROG NOTIFICATIONS EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

0 Yes 0

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:

LL 0 JPMO 125 Re v000 Page 4 of 8

EXELON NUCLEAR LLOJPM0725 JOB PERFORMANCE MEASURE (JPM)

TASK CONDITIONS:

The following conditions exist on Unit 1 0

Startup is in progress with reactor power 3%, Reactor Mode Switch is in Startup/Hot Standby All Safeguard DC power was lost 20 minutes ago and is not expected to be restored for another hour 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.

LLOJPM0125 Rev000 Page 5 of 8

EXELON NUCLEAR LLOJPM0125 JOB PERFORMANCE MEASURE (JPM)

TASK STANDARD(S):

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 Critical Element(s) indicated by I*

in Performance Checklist.

START TIME:

PERFORMANCE CHECKLIST:

ELEMENT STANDARD I

I I

I Number SAT I UNSAT I Comment

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:

3.

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

4.

Review the initiating conditions 5*.

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

6.

NOTE the EAL number associated with the IC 7*.

DECLARE the event

8.

RETURN to the appropriate EP-AA-112 ERO position checklist and immediately begin notifications EP-AA-I 11, Section 4.1 NIA NIA Use EAL Matrix to classify event Determine Site Area Emergency initiating conditions have been exceeded MS3 identified Declare a Site Area Emergency within 15 minutes of the START TIME in Step 1 DECLARATION TIME:

NIA NIA N/A N/A EP-AA-112-100 Attachment I, SHIFT EMERGENCY DIRECTOR CHECKLIST LLOJPM0125 Rev000 Page 6 of 8

EXELON NUCLEAR JOB PERFORMANCE MEASURE (JPM)

14.

APPROVED BY 15*.

STATUS BLOCK

16.

CLASSIFICATION L LOJPM0125 Signature entered THIS IS A DRILL marked SITE AREA EMERGENCY checked

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-I 12,

19.

CLASSIFICATION STATUS I O.

PERFORM Attachment 2, ERO Augmentation I

I I

INITIAL DECLARATION checked

11.

DETERMINE the correct plant-based PAR per the appropriate site-specific PAR flowchart in EP-AA-111, Attachments 2 through 8 20*.

BRIEF NON-TECHNICAL DESCRIPTION 12*.

I

/

I DC electrical power to vital equipment is degraded.

INITIATE required State/Local notifications within 15 minutes of the event classification as required per EP-AA-114 - Refer to EP-MW(MA)-114-100 for instructions on completion and transmittal of StateEounty 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 EP-MA4 14-1 00, MAROG NOTIFICATIONS, Section 4.1 - COMPLETING THE STATElLOCAL NOTIFICATION FORM

13.

Message number - ENTER a sequential number starting with I

1 or equivalent entered 17*.

AFFECTED UNIT I ONE checked I

I I

18*.

DECLARED AT I

I I

Time and Date entered. MS3 entered as EAL#

L L OJPMO 125 Rev000 Page 7 of 8

EXEL ON NUCLEAR JOB PERFORMANCE MEASURE (JPM)

L L OJPMOI 25

!I 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.

NO checked Left blank or NOT APPLICABLE checked Wind direction 120 degrees

  • (Critical)

Wind speed 7 mph (not critical)

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 L LOJPMO I25 Rev000 Page 8 of 8

TASK CONDITIONS:

The following conditions exist on Unit I v

Startup is in progress with reactor power 3%, Reactor Mode Switch is in Startup/Hot Standby All Safeguard DC power was lost 20 minutes ago and is not expected to be restored for another hour 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

MET DA(

.ATTACHMENT 97 1 METEOROLOGICAL 15 MINUTE AVERAGE POINT DATA PID SENSOR DESCRIPTION VALUE EU T I DTULFA T I.SP.U TOWER 1 27'0 FT WIND SPEED p

G l

MPH TlSPlFA T I.SP.I TOWER 1 175 FT WIND SPEED MPH TISSPLFA T I.SP.L TOWER 1 30 FT WIND SPEED 1

4 3

1 MPH T I DRUFA T I.DR.U TOWER 1 270 FT WIND DIRECTION 1-DEG AZ W

T I DRlFA T I.DR.I TOWER 1 175 FT WIND DIRECTION

\\120.01 DEG AZ T

0 T I DRLFA T I.DR.L TOWER 1 30 FT WIND DIRECTION

[

T I

DEG AZ T I DTULFA T I.DT.U-L TOWER 1 266 - 26 FT DELTA TEMP 1-0.31 DEG F T I DTILFA T I.DT.I-L TOWER 1 171 - 26 FT DELTA TEMP

[T DEG F TIATLFA T I DPLFA T I RNFA E

R T I.AT.L TOWER 1 26 FT AMBIENT TEMP T I.DP.L TOWER 1 26 FT DEW POINT T I.RN TOWER 1 PRECIPITATION I

[

85.2 I

[

T I

T 0

E R

2 TZDTULFA T2SPIFA T22SPLFA T2DRUFA T2DRIFA T2DRLFA T2DTU LFA T2DTILFA T2ATLFA T2DPLFA T2.SP.U T2.SP.I T2.SP.L T2.DR.U T2. D R. I T2.DR.L T2. DT. U -L T2.DT.I-L T2.AT.L T2.DP.L 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 TOWER 2 30 FT WIND DIRECTION TOWER 2 304 - 26 FT DELTA TEMP TOWER 2 155 - 26 FT DELTA TEMP TOWER 2 26 FT AMBIEWNT TEMP TOWER 2 26 FT DEW POINT I

0.1 I

I 6.4 I

4.6 1

1115.71 0.4 I

185.01 1

44.81 I

DEG F DEG F INCHES MPH MPH MPH DEG AZ DEG AZ DEG AZ DEG F DEG F DEG F DEG F

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