Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML102920658
Person / Time
Site:	Limerick
Issue date:	08/20/2010
From:	Goff C; Exelon Generation Co, Exelon Nuclear
To:	Caruso J; Region 1 Administrator
	Hansell S
Shared Package
ML100560247	List: IR 05000352/2010302; ML101650598; ML102720677; ML102870021; ML102920654; ML102920658; ML102920661; ML102920664; ML102920667; ML102920669; ML102920673; ML102920676; ML103080887;
References
	NUREG-1021, TAC U01767
	Download: ML102920658 (254)
	v • d • e

Sincerely, ~

~f),

Manager-Operator Training-LGS Exelon Generation Corp. LLC

Enclosures:

Documents stated above to Mr. J. Caruso only cc: J. Caruso, USNRC, Region I (w/encl)

S. Hansell, USNRC, Region I (w/o encl)

E. DiPaolo USNRC Senior Resident Inspector, LGS (w/o encl)

NRC Document Control Desk, USNRC, Washington, DC (w/o encl)

bcc: W. Maguire-GML 5-1 (w/o encl)

E. Callan-GML 5-1 (w/o encl)

P. Gardner - GML 5-1 (w/o encl)

R. Dickinson- LLC-319 (w/o encl)

C. Goff- LLC-319 (w/o encl)

R. Monahan LLC-319 (w/o encl)

J. Hunter III 88B 2-4 (w/o encl)

A. Columbus 88B 4-1 (w/o encl)

PA DERBRP Inspector, LG8 88B2-4 (w/o encl)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: LGS Date of Examination: 10104/10 Examination Level: RO I8l SRO D Operating Test Number: ILT09-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations N,S G.2.1.3 Shift Turnover Checklist Conduct of Operations Equipment Control N,R G.2.2.12 Review ST-6-047-370-1, Pre Control Rod Withdrawal Check Radiation Control D,R,P G.2.3.11 Gaseous Effluent Release Rate Determination (2008 RO A3)

Emergency M,S G.2.4.12 Activate Site~Alarm Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; S 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (S 1; randomly selected)

Exelon Nuclear Job Performance Measure PERFORM A SHIFT TURNOVER (RO)

JPM Number: 0750 Revision Number: 000 Date: I I Developed By:

Instructor Date Validated By:

SME or Instructor Date Review By:

Operations Representative Date Approved By:

Training Department Date

LLOJPM0750 REV 0000 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. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) 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 _ _ _ _ __

9. Pilot test the JPM:

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

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LLOJPM0750 Rev 000 Page20f 7

LLOJPM0750 REV 0000 REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Both units are in OPCON 1

Date is 10101/10

Present time is 06:00 Shift Reactor Operators are awaiting oncoming shift personnel

Shift staffing consisted of normal compliment for upcoming shift INITIATING CUES:

It is 06:00, You are the oncoming Unit 1 Reactor Operator and are preparing to take day shift duties. You are to complete the Reactor Operator Shift Turnover Checklist, and be prepared to present the shift turnover checklist at the shift meeting.

TASK STANDARD:

Complete Reactor Operators shift turnover checklist and identify any discrepancies and address any concerns prior to assuming shift duties.

LLOJPM0750 Rev 000 Page30f 7

LLOJPM0750 REV 0000 Information For Evaluator's 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.

.I.~.~. .~i.~.~.~!.c::>g.~. ~!.~r.:!.~ . ~.~.~~. .~.~~. .~~~.?i.9.~!~. .~g.~~.c::>~I.~.?9.~~. .!b.~. .~.r.:'~!.i.~!.i.~.9..g~.~.:. . . . . . . . . . . . . . . . . . . . . . . . . . . . .

LLOJPM0750 Rev 000 Page 4 of 7

LLOJPM0750 REV 0000 Operator's Name:

Job

Title:

0 NLO 0 RO 0 SRO 0 STA o SRO Cert JPM

Title:

PERFORM A SHIFT TURNOVER (RD)

JPM Number: LLOJPM0750 Revision Number: 000 KIA Number and Importance: G2.1.3 3.7/3.9 G2.1.18 3.6/3.8 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Simulate Faulted: Yes Alternate Path: No Time Critical: No Estimated Time to Complete: 20 minutes Actual Time Used: _ _ minutes

References:

OP-AA-112-101 Rev 6 OP-LG-1 08-1 04-1 000 Rev 0 OP-LG-112-101 Rev 5 RX OPERATORS LOG OP-LG-112-1 01-F-04 Rev 2 GP-5, Steady State Operation EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? o Yes 0 No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory 0 Unsatisfactory Comments:

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ __ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ __ Date: -------

LLOJPM0750 Rev 000 Page 5 of 7

LLOJPM0750 REV 0000 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain copy of OP~LG~ 112~ 101- OP-LG~ 112-1 01-F-04 is F-04 to determine requirements for obtained shift turnover Cue: Provide copy of OP-LG-112 101-F-04 if requested

2. Determine shift turnover checklist Shift turnover checklist requirements for oncoming RO must be completed prior to taking shift

3. Unified Narrative Log N/A Reviewed:

Cue: Log is Reviewed

4. Offgoing Shift Average CTP Review Operators Log and and 3D Monicore P1 Report P1 to verify reactor is Reviewed: operating within limits as designated by GP-5, Cue: Provide copy of RX Steady state Operation OPERATORS LOG #01 and 3D Monicore P1 to candidate

4a. Review 3D Monicore sheet and Identify on Operators Log identify Y2 hr average power to be the Y2 hr. CTP average is greater than 3458 MWT greater than 3458 MWT 4b. Notify SSV that reactor power Candidate may choose to must be lowered to ensure notify SSV or reference compliance to the CTP 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months GP-5, Steady State average limit. Operation 4c. Reference GP-5, Steady State Reference GP-5, "Note" Operations, Note on page 3 identifying V2 hr average "CTPMON core thermal power used to ensure 1hr averages" and verify CTP half average is not exceeded hour average should be used to ensure CTP 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average limit is not exceeded

4d. Review P1 Report and identify MFLCPR identified> 1.0' MFLCPR is > 1.0 4e. Notify SSV that reactor power SSV notified MFLCPR is must be lowered to ensure >1.0 compliance to the CTP 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average limit.

LLOJPM0750 Rev 000 Page 60f 7

LLOJPM0750 REV 0000 4f. Reference GP-14, Resolution of Candidate may chose to Thermal Limit Violation or GP-S, reference procedures or Steady State Operation notify SSV of violation

S. ST Log Reviewed: ST Log Reviewed and Identify ST Log is not filled out verified Time/Date that properly. Time/Date Equipment Equipment is INOP and is INOP and Time/Date when OPERABLE or Equipment is Operable /Action ACTION NUMBER marked number marked N/A vs actual as NIA vs actual Time/Date Time/Date required to be filled in. entered Cue: Provide copy of OP-LG-1 OS 104-1000 to candidate

6. Annunciator Status Reviewed: Annunciator status reviewed and any annunciators alarmed Cue: Annunciator status reviewed understood by oncoming and verified to satisfactory RO

7. Review Reactor Maneuvering Reactor Maneuvering Shutdown Instructions: Shutdown Instructions reviewed Cue: Provide copy of Reactor Maneuvering Shutdown Instructions S. Unit Control Panel Walked N/A Down:

Cue: Unit 1 Control Panel walkdown completed

9. I have no change in Health No change in medical Status (Ref OP-AA-105-101) condition that could disqualify me from standing shift:

10. Verify Qualifications Prior to Qualifications Prior to Taking Shift: Taking Shift N/A due to a classroom turn-over environment (CUE: "You may stop here, you N/A have met the termination criteria for this JPM")

JPM Stop Time: _ __

LLOJPM0750 Rev 000 Page 70t 7

INITIAL CONDITIONS:

Both units are in OPCON 1

Date is 10/01/10

Present time is 06:00 Shift Reactor Operators are awaiting oncoming shift personnel

Shift staffing consisted of normal compliment for upcoming shift INITIATING CUES:

It is 06:00, You are the oncoming Unit 1 Reactor Operator and are preparing to take day shift duties. You are to complete the Reactor Operator Shift Turnover Checklist, and be prepared to present the shift turnover checklist at the shift meeting.

LLOJPM0750 Rev 000

ATTACHMENT 1 COMPLETING THE ST/RT STATUS LOG (SHORT DURATION TIME CLOCK LOG) performer enters Test number and description periormer enters his/her name.

performer circles the Test day.

(A,B or Any)

~ determines if the test makes required equipment ioop.

res y For equipment that is made INOP but !!!ll required (redundant equipment such as APRMS, SBlC pumps, Offgas H2 monitors; answer HQ..

N 0i.

§llcircles YES in the ~ circles NO in the

'Required Equipment INOP' 'Required Equipment INOP" column. column.

.!?li:lL determines,

+

per Tech Specs, il delayed entry into Yes Actions/Compensatory Measures is allowed.

~

No y

I circles NO in the ~ circles YES in the "Delayed Entry Allowed' column I ~ circles NIA in the

'Delayed Entry Allowed' column.

I

'Delayed Entry Allowed" column. and enters the delay time allowed by Tech Specs in Ill!! bl!!n~

~ ll.'L enters

~

N/A in the

~liststhe "Required Action/Required Compensatory

~enters NIA in the Required Actions/Required Compensatory Measure" column.

"Required Action/Required Measures numbers which are required Compensatory Measure Number" for the equipment made INOP.

column.

II the test affects both units, log it only in the Unit associated with the test number.

but log IheTech Specs for l:<2!b. Units in that log.

I I PerffJflH£ enters the Test start time

... and date.

Plutgrm!l[ enters theTes! start time and date .

f'flQiRO enters the time/date when the test makes equipment inop. PHOiRO enters N/A in the 11 equip is already Inop. "Time/Date Equipment INOP" l.I:uw. enter Reg Action/PLCO Number. llIl!L "Time/Date Equipment Operable"

.!. cQlumns.

f'HOJ£Fl enters the time/date when the test returns equipment to service.

11 equip is not returned to operable.

l.I:uw. enter Reg Actlon/PLCO Number.

I Pllrformer enters the time/date the test is complete .

I

[ .s..s:L reviews ST/RT Log.

I LLOJPM0750 Rev 000

OP-LG-1 08-1 04-1 000 ST/RT STATUS LOG (SHORT DURATION TIME CLOCK LOG)

CIRCLE ONE (PRO I R01 I R02)

Test Req'd Delayed Required Per- Test Time/ Time/Date Time/Date Test Test Number/ Description Action/Required former Start Eqpt Operable Complete Day Eqpt Entry Date Compensatory Timel OR Action Inop? Allowed? Measure Number Eqpt Number Date Inop A ~Hrs ST-2-026-617-1 Reactor Coolant Sys Leakage RISH-26-1 K600

(

B Any foP N/A 3.4.3.1 I&C 0400 10101/10 N/A N/A A Yes Yes - Hrs B No No Any N/A A Yes Yes_Hrs B No No Any N/A A Yes Yes__Hrs B No No Any N/A A Yes Yes_Hrs B No No Any N/A A Yes Yes_Hrs B No No Any N/A A Yes Yes_Hrs B No No Any N/A LLOJPM0750 Rev 000

PAGE SEQl fENCE NO 6

li*jFRICl I 14 IO-OCT-2010 06: 00 CALCULATED

->Y<E PI,}(J\I1ETEP.5 3D I"lONICORE 1O-OCT-201O 06:00 PRINTED r,)~'; J:::F:. M\',T 34~7. PE1<IODIC LOG r;YdI:E l*1vm lU . CASE ID FMLD 1100805071002 F Lt):'J f.1LB /HR 91.793 CALC RESULTS RESTART FMLDII00805070919 FP;,PDR 0.815 LPRM ABSOLUTE FULL CORE SUB,':: BTU/LB 22.93 Keff 1. 0049 PR PSla 1057.7 XE vJORTH % -2.11 LOPill LINE

SUMMARY

CORE r*1HD/sT 50000.0 XE RATED 0.93 CORE POl'lER 100.0%

C'[CLE l\U*mh3T 22000.0 AVE 'IF 0.451 CORE FLOW 91.8?

J¥~PP 1.420 FLLLP 0.920 LOJill LINE 105.8%

CORRECTION FACTOR: MFLCPR= l. 000 f>.1FLPD= 1. 000 MAPRAT= l. 000 ZBB= 2.23 ft OPTION: ImTS 2 LOOPS ON r1ANUAL FLOW MCPRLIM= l.330 FCBB= N!h MOST LIr1ITING LOCATIONS (NON-SYMMETRIC) flFLCPR LOC fJIFLPD LOC MAP RAT LOC PCRAT LOC 1.010 31 42 0.793 15 5 0.776 45-16 5 0.845 33 4 1.006 31-46 0.792 17 16 5 0.774 15-18 5 0.833 53 5 1.004 33-32 0.785 47 20- 5 0.773 17 5 0.828 57 28- 4 1.000 31-38 0.783 45 5 0.771 47 5 0.822 47 5 0.991 45-32 0.781 47-16 5 0.771 29 5 0.778 15 5 0.988 23-32 0.776 31-46-12 0.768 31-46-12 0.777 17 5 0.987 27 36 0.773 29-48-12 0.768 17 5 0.777 31-46 12 0.983 47-38 0.772 19 5 0.765 45 5 0.777 47 5 0.977 25-34 0.772 17 5 0.763 19 5 0.774 45 5 0.983 37-48 0.771 29 38- 8 0.762 47 5 0.771 29 8 SEQ. 1\.-*2 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 0.287 25 00 0.328 24 59 02 0.369 23 L 04 0.491 22 5'-

. ::> 06 0.693 21 51 08 0.734 20

!., 10 0.797 19 47 12 0.902 18 43 06 C06 14 0.923 17 L 16 0.964 16 39 18 l. 033 15 35 06 06 20 1.046 13 J, 22 1.102 13 31 24 1. 196 12 27 06 06 26 1. 214 11 L 28 1. 266 10

')

~

-)

.J 30 1. 352 09 D 06 06 32 l . 369 08 L 34 l. 410 07 1 p N 36 l.478 06 11 38 l.491 05 L 40 1.278 04 42 0.924 03 1, L L L 10 L 1, 44 0.853 02 u; 10 14 18 2~ 26 30 34 38 42 46 SO 54 58 46 0.426 01 N.'BRAGE P,l\Dlj-c], POI'iEF' DISTRIBUTION I:J~} t; 1 4 G B

, ; T'>.1 1'1\ , (111 1 -'e (l"i

PAGE SEQUENce N t( ; ,t ., ~ ~,':-;Tj<.L~::Er ~ ... ST.?\ iJS IO-OCT-WIO ",):00 CALClILATED f'1J..-LDl<E'l TF;r! 1 ff~}r ~ ~EI~lJIl'~JS IO-OCT-'"!0I0 06:00 PRINTED CASE ID FMLD 1I0080507I002 r, .2 8.8 5.7 RESTART FMLD II O()H()5070919 10.2 2. ~.9 7. LPRM ABSOLUTE - FULL CORE I, .6 2. 3.0 6.0

.1 4. 5.1 6.0 .;;: OF TIPS UOT SCANNED:

(,D 23.3 3'.9 4C1.0C 47.6 40.1 30.2 FIIILED SENSORS:

2').1) 45.8 52.7 52.5 53.5 35.2 IJPRfvl ( NONE FAILED)

B :;> J .. j 54.\) (,1.1 60.5 62.5 39.0 U.*t S6.3 65.1 60.7 68.7 35.2 LPRI*l ( 0 PAN1,CEA REJECTED)

OTHER SENSORS a TOTAL)

_1 '"

u ~ ~

.) :..J * .:'12.0 44.7 *12.0 45.0 40.1 25.0 SUB RODS 42.3 5'+/-.9 51.1 51.A 54.9 53.5 27.9 NONE

}J 0.7 3.2 56.8 S6.S 61. 4 62.5 26.1

";.. Sl.3 67 2 53.4 52.4 63.0 68.8 18.4 T TIP RUN RECOMMENDED C f*1FLCPR LOCl: .TION "3D 37.5 42.5 49.1 SO.6 42.0 42.5 28.5 M MAPRAT LOCATION C 45.5 47.7 65.6 63.9 51. 8 52.4 33.0 D MFLPD LOCATION B 54.9 54.0 71.0 68.0 56.6 60.6 33.1 P PCRAT LOCATION

~

-'"'- 55.1 49.9 67.0 65.3 52.5 60.8 25.2 * - rmLTIPLE LOCATION 25D 36.9 41.7 48.5 49.2 44.7 39.9 28.0 C 44.7 50.2 59.0 65.7 51. 3 52.7 32.2 B 54.4 57.4 64.0 71.1 57.0 61.3 32.3 "A 57.6D 55.9 61.8 67.0 53.5 65.7 24.5 17D 31. 5 40.5 41. 6 42.5 42.0 37.9 19.1 C 36.4 50.4 50.2 47.7 55.0 45.8 19.1 B 39.7 58.7 57.4 54.1 63.4 54.1 14.6 A 32.8 64.3 55.8 49.7P 67.3M 56.7 9.2 09D 31.6 36.9 37.5 35.6 23.4 C 36.3 44.7 45.5 42.4 25.2 B 39.7 54.4 55.0 50.9 21.6 A 32.7 57.4 54.9 51.2 13.5 08 16 24 32 40 48 56 CORE SU1'11LI;RY CORE PONER 100.0 96 CALC SUB FLOW 87.2% DF l'iEAS PSI 12.50 CORE FLON 91.8% OPER SUB FLOW 1. 0% DP C):"LC PSI 12.50 LOJm LIHE 105.8 FLOH BASIS r'iEl~S FEEDWTR FLOVI fJJLB /HR 15.10 APR1'l CALIBRATION 1 2 3 4 REP...DING 99.9 100.0 99.9 99.9 IW;'.F 1.001 1.000 1.001 1.001 1\ PEl*! - CTf' -0.1 0.0 0.1 -0.1 TI P RUNS REcor*ll*nmmm 2*TPIll~7S : ~JCt,TE

,- T"JE PU";~'v' r*1LB/HE 8.64 TT~l~r

~l!l~ TE~j1P DFG. F ,1 eLl

Exelon Nuclear Job Performance Measure EVALUATE ST-6-047-370-1, PRE CONTROL ROD WITHDRAWAL CHECK FOLLOWING CORE ALTERATIONS

..IPM Number: 0752 Revision Number: 000 Date: _ - - J _ - - J _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Review By:

Operations Representative Date Approved By:

Training Department Date

LLOJPM0752 Rev 000 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. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) 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 Examiner review.

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

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

Procedure Rev. Date _ _ _ _ __

9. Pilot test the JPM:

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

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the ..IPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

1. When "IPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LLOJPM0752 Rev 000 Page 2 of 6

LLOJPM0752 Rev 000 REVISION RECORD (Summary):

New Revision SIMULATOR SETUP INSTRUCTIONS:

None JPM Setup Instructions:

Provide a yellow copy of a Partial ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations.

TASK STANDARD:

The candidate should report the test is not completed properly due to procedure steps not signed off correctly and Control Rod 34-03 Pre Control Rod Withdrawal Checks not performed.

TASK CONDITIONS:

Unit 1 is in OPCON 5, with Reactor Vessel Head still on Today's date is 10101/2010. You are the oncoming DAY shift RO Partial SUNeillance Test, ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations, was initiated on night shift.

Pre-Control Rod Withdrawal Checks are required for Control rods 10 11, 18-15,34-03 and 42-15.

ST-6-107-632-1, One Rod Out Interlock Verification Testing is in sUNeiliance

ST-6-047-750-1, CRD Accumulator Pressure Check,is NOT in sUNeillance

NF-AA-330-1 001, Core Verification Guideline, is in compliance INITIATING CUE:

You are the oncoming RO and are to review Partial ST 04 7 -370-1, Pre Control Rod Withdrawal Check Following Core Alterations. The procedure should be reviewed and submitted to the SRO for verification prior to withdrawing the deSignated 4 Control Rods.

LLOJPM0752 Rev 000 Page 3 of 6

LLOJPM0752 Rev 000 Information for Evaluator's 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.

LLOJPM0752 Rev 000 Page 4 of 6

LLOJPM0752 Rev 000 Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

0 RO o SRO o STA o SRO JPM

Title:

EVALUATE ST-6-047-370-1, PRE CONTROL ROD WITHDRAWAL CHECK FOLLOWING CORE ALTERATIONS JPM Number: 0752 Revision Number: 000 KIA Number and Importance: G2.1.20 RD 4.6 SRD 4.6 Suggested Testing Environment: Classroom Actual Testing Environment:

Testing Method: Classroom Faulted: Yes Alternate Path: No Time Critical: No Estimated Time to Complete: 30 min Actual Time Used: _ _minutes

References:

ST 04 7-370-1 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? - Yes - No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: - Satisfactory - Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: ___________________ (Print)

Evaluator's Signature: Date: _ __

LLOJPM0752 Rev 000 Page 5 of 6

LLOJPM0752 Rev 000 PERFORMANCE CHECKLIST:

JPM Start Time ELEMENT STANDARD SAT UNSAT Comment Number

1. Hand the applicant: Review the handouts

ST 047 -370-1

JPM cue sheet

2. RO identifies Additional ActionlTest Additional ActionlT est J

Comments section of ST-6-047-370-1 is not signed by person making comments Comments section of ST 047-370-1 is not signed \; 1~~

°v ~

v I"

'Z I

v

3a. RO candidate reviews test and Step 4.5.7 not completed prior identifies step 4.5.7 not verified, Unit to SRO verification 1 is in OPCON 5, with Reactor

~.\v' Vessel Head still on, as designated on initiating conditions. Step required to be completed prior to submitting to the SRO for verification.

~~

3b. RO candidate identifies step 4.5.11 SRO verification required prior must be completed prior to to moving control rod withdrawing control rod.

4. RO candidate identifies per ST-2-047-400-1 identified as ATTACHMENT 1 that "CRD the most limiting and is over-Accumulators ST" ST-2-047-400-1 due as of 9/27/1 0 ~ '1 \

with the over-due-date of 9/27/10 makes it out of surveillance and the most limiting ST

5. RO candidate identifies of the 4 Control rod 34-03 Section 4.5 control rods to be tested control rod requirements not completed 34-03 per ATTACHMENT 2 has not been identified and section 4.5 requirement not met prior to SRO I

verification.

~~-

6. RO candidate identifies control rod Control Rod 18-15, HCU 18-15 Accumulator pressure is 945 accumulator pressure is 945 psig which is below the TECH SPEC whereas TECH SPECS required 955 psig requirement for operability is 955 psig.

control rod operability CUE: (You may stop here. You have reached the termination criteria for this JPM)

JPM Stop Time ~_ _ __

LLOJPM0752 Rev 000 Page 6 of 6

LLOJPM0752 Rev 000 TASK CONDITIONS:

Unit 1 is in OPCON 5, with Reactor Vessel Head still on Today's date is 10/01/2010. You are the oncoming DAY shift RO Partial Surveillance Test, ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations, was initiated on night shift.

Pre-Control Rod Withdrawal Checks are required for Control rods 10-11, 18 15,34-03 and 42-15.

ST-6-107-632-1, One Rod Out Interlock Verification Testing is in surveillance

ST-6-047-750-1, CRD Accumulator Pressure Check, is NOT in surveillance

NF-AA-330-1 001, Core Verification Guideline, is in compliance INITIATING CUE:

You are the oncoming RO and are to review Partial ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations. The procedure should be reviewed and submitted to the SRO for verification prior to withdrawing the designated 4 Control Rods.

Exelon Nuclear Job Performance Measure Determine Offgas Effluent Activity Release Rate JPM Number: 0760 Revision Number: 000 Date: / /

Developed By:

Instructor Date Validated By:

SME or Instructor Date Review By:

Operations Representative Date Approved By:

Training Department Date

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

2. Knowledge and Abilities (K/A) 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 Examiner 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 _ _ _ _ __

9. Pilot test the ...IPM:

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

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LLOJPM0760 RevOOO Page2of8

REVISION RECORD (Summary):

JPM SETUP INSTRUCTIONS:

Provide applicant copy of GP-5 "STEADY STATE OPERATIONS"

Provide calculator to applicant INITIAL CONDITIONS:

Unit 1 is in OPCON 1

RR-26-1 R601 "An SJAE Discharge Rad Monitor reads 11 OmRem/hr

RR-26-1R601 "8" SJAE Discharge Rad Monitor reads 131mRem/hr

FR-69-115 (scfm) Point 2 Reads 35 scfm

FIT-070-150 at local panel, 10C582 reads 35 scfm INITIATING CUES:

Per GP-5, Steady State Operations, calculate the average offgas pre-treatment radioactivity release rate TASK STANDARD:

The applicant should calculate the average pre-treatment release rate to be 4619 to 5105 (4862 +/- 5%)

The following placard is mounted to the 10C600 panel:

U/10FFGAS SUM OF SIX 140 K"A" 1.18 K"8" 1.13 DATE: 10101/10 LLOJPM0760 RevOOO Page 30(8

Information for Evaluator's 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.

LLOJPM0760 RevOOO Page 4 of8

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

- NLO X RO SRO - STA SRO Cert JPM

Title:

Determine Offgas Effluent Activity Release Rate

..IPM Number: 0760 Revision Number: 000 KIA Number and Importance: G2.3.11 Ability to Control Radiation Releases (CFR:

41.11 /43.4/45.1 O) IMPORTANCE RO 3.8 SRO 4.3 Suggested Testing Environment: Classroom - Group Actual Testing Environment:

Testing Method: Table-top Faulted: Yes Alternate Path: No Time Critical: No Estimated Time to Complete: JJL Actual Time Used:_ _ _minutes

References:

GP-5, Steady State Operation Revision 145 EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? -Yes -No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: - Satisfactory - Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ {Print}

Evaluator's Signature: Date: -----

LLOJPM0760 RevOOO Page50f8

NOTE: Critical Element(s) indicated by'* in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD I SAT I UNSAT Comment Number

1. CALCULATE Off-gas release rates N/A for the A AND B channels using the following equation:

RR = RLx F x K Where:

RR =Release Rate for A(B)

(!lCi/second)

=

RL Radiation Level of SJAE as indicated on RR-26-*R601 (mRem/hour)

F =Off-gas flow as indicated by FR-69-*15 (scfm),

Point 2 K =C Conversion Factor for A(8) data (posted on panel *OC600)

2. Channel A (Point 1) Calculate "A" channel release RR =__ mRem/hour x _ _CFM x = 4543 ~Ci/sec

_K_ 11 0 x 35 x 1 .18 =4543 RR= __._ __

/lCi/second

3. Channel B (Point 2) Calculate "8" channel release RR =_ _ mRem/hour x __CFM x = 5181 ~Ci/sec

__K_ 131 x 35 x 1.13 = 5181 RR= _ __

/lCi/second i

I LLOJPM0760 RevOOO Page 6 018

II ELEMENT i STANDARD SAT UNSAT Comment Number

4. CALCULATE the average of the A Calculate the average release AND B channel values to obtain rate the average Off-gas pretreatment release rate as follows:

ARR= (4543 +5181)/2 = 4862 ARR = (RR "A") + (RR "B")

IJCi/sec 2

Where:

ARR = Average Off-gas Acceptable band is 4619 to Pretreatment Release 5105 (4862 +1- 5%)

Rate (j.tCi/second)

RR "A" = Release Rate value for "A" Channel (!-lei/second)

RR "8" = Release Rate value for "B" Channel (j.tCi/second)

ARR=( )+( )

2 ARR= j.tCi/second (CUE: You may stop here; you have N/A N/A met the termination criteria for this JPM.)

JPM Stop Time _ _ _ __

LLOJPM0760 RevOOO Page 70f8

INITIAL CONDITIONS:

Unit 1 is in OPCON 1

RR-26-1 R601 "An SJAE Discharge Rad Monitor reads 11 OmRem/hr

RR-26-1 R601 "8" SJAE Discharge Rad Monitor reads 131 mRem/hr

FR-69-115 (scfm) Point 2 Reads 35 scfm

FIT-070-150 at local panel, 10C582 reads 35 scfm INITIATING CUES:

Per GP-5, Steady State Operations, calculate the average offgas pre-treatment radioactivity release rate The following placard is mounted to the 10C600 panel:

U/10FFGAS SUM OF SIX 140 K"A" 1.18 K"8" 1.13 DATE: 10/01/10

Exelon Nuclear Job Performance Measure RO Only - INITIATE SITE EVACUATION JPM Number: LLOJPM0761 Revision Number: 000 Date: _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0761, Revision 000 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure EP-AA-113-F-04 Rev: _ _

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the J PM.

12. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 2 of 6

LLOJPM0761, Revision 000 REVISION RECORD (Summary)

1. Revision 000, New based on 2002 ILT JPM SIMULATOR SETUP INSTRUCTIONS

1. This JPM must be performed in the Simulator, any IC may be used TASK STANDARD:

Evacuation Alarm Sounded and Announcement made per EP-AA-113-F-04 INITIAL CONDITIONS:

1. A Site Area Emergency drill has been declared

2. Drill conditions require a site evacuation, Evacuating personnel shall:

Exit the protected area via the TSC Guard Station

Exit the site via Evergreen Road

Assemble at the Pottstown Limerick Airport INITIATING CUES:

The Control Room Supervisor has directed you to sound the site evacuation alarm for the entire plant and make the plant announcement for evacuation per EP-AA-113-F-04, Section 5, LGS SITE EVACUATION ALARM / ANNOUNCEMENT INSTRUCTIONS Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 3 of 6

LLO...IPM0761, Revision 000 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _Job

Title:

O SED ORO OSM OSRO o STAIIA o OTHER JPM

Title:

RO Only -INITIATE SITE EVACUATION JPM Number: LLOJPM0097 Revision Number: 009 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 2.4.39 RO: 3.9 Suggested Testing Environment: Simulator or quiet area with appropriate Emergency Plan documents Alternate Path: OYes !ZINo SRO Only: OYes !ZINo Time Critical: !ZIYes ONo Reference(s):

Procedure EP-AA-113 -F-04 Rev: ---::...:.--

H Actual Testing Environment: !ZI Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate !ZI Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 4 of 6

LLOJPM0761, Revision 000 JPM Start Time: _ _ __

C J0 t- !;c G)G)

E,c STEP ELEMENT STANDARD <C en EE en Z o :::J

>> OZ

1. SET the "Siren Tone Generator" selector switch, located on MCR Panel 00C650, to the Switch set to SIREN SIREN (harmonic tone) position. - -

2. PULL OUT the "Evacuation Alarm and River Warning Select" switch, located on MCR Panel 00C650.

ROTATE the "Evacuation Alarm and River Switch set to PLANT ALARM Warning Select" switch to the PLANT and pushed in to sound the ALARM position, and PUSH selector alarm switch IN.

QUE: When Switch is pushed in "Alarm is Sounding"

3. Sound alarm for approximately 30 seconds

- QUE: When Switch is pulled out "Alarm is no longer sounding" Alarm sounded for approximately 30 seconds Switch pulled out to stop alarm - -

4. Return "EVACUATION ALARM AND RIVER WARNING SELECT" switch to "OFF" position Switch selected to OFF to silence alarm. -

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 5 of 6

INITIAL CONDITIONS:

1. A Site Area Emergency drill has been declared

2. Drill conditions require a site evacuation, Evacuating personnel shall:

Exit the protected area via the TSC Guard Station

Exit the site via Evergreen Road

Assemble at the Pottstown Limerick Airport INITIATING CUES:

The Control Room Supervisor has directed you to sound the site evacuation alarm for the entire plant and make the plant announcement for evacuation per EP-AA-113-F-04, Section 5, LGS SITE EVACUATION ALARM / ANNOUNCEMENT INSTRUCTIONS SRRS: 3D.105 (when utilized for operator initial or continuing training)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: LGS -- Date of Examination: 10/04/10 Examination Level: RO DSRO ~ Operating Test Number: ILT09-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations N,S G.2.1.3 Shift Turnover Checklist Conduct of Operations N,R G.2.1.B Coordinate Personnel Activates Outside the Control Room

~

Equipment Control N,R G.2.2.12 Review ST-6-047-370-1, Pre Control Rod Withdrawal Check Radiation Control D,R,P G.2.3.6 Review and Approve a Liquid Rad Waste Discharge Permit, (200B SRO A3)

Emergency D,R G.2.4.21 Make an E-plan Classification, Procedures/Plan (0131 )

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; :5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (:5 1; randomly selected)

Exelon Nuclear Job Performance Measure PERFORM A SHIFT TURNOVER (SRO)

JPM Number: 0751 Revision Number: 000 Date: / /

Developed By:

Instructor Date Validated By:

SME or Instructor Date Review By:

Operations Representative Date Approved By:

Training Department Date

LLOJPM0751 REVOOO.DOC 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. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) 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 _ _ _ _ __

9. Pilot test the JPM:

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

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LLOJPM0751 RevOOO.doc Page 2 of 8

LLOJPM0751 REVOOO.DOC Job Performance Measure (JPM)

REVISION RECORD (

SUMMARY

)

New Revision SIMULATOR SETUP INSTRUCTIONS:

None INITIAL CONDITIONS:

Date is 10101/10

Present time is 06:00 Control Room Shift Supervisor is awaiting oncoming shift personnel

Shift staffing consisted of normal compliment for upcoming shift

Unit 1 in OPCON 2: GP-2 Reactor Startup

Reactor power presently is 8% power

At 04:00 commenced raising reactor pressure from 920 - 960 psig.

Unit 2 in OPCON 1: 100% power INITIATING CUES:

It is 06:00, You are the oncoming Unit 1 Control Room Shift Supervisor and are preparing to take day shift duties. You are to complete the Control Room Shift Supervisor Shift Turnover Checklist, identify any TECH SPEC concerns, and be prepared to perform the shift briefing meeting.

TASK STANDARD:

Complete Control Room Supervisor Shift Turnover Checklist and identify any discrepancies and address any concerns prior to assuming shift duties.

TECH SPECS are required for this JPM LLOJPM0751 RevOOO.doc Page 3 of 8

LLOJPM0751 REVOOO.DOC Job Performance Measure (JPM)

Information For Evaluator's 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 .

.::r.:~.~. .!!,r.:r!~,<?!,??~. !?.!.~.r:!!?".IJI'..~~,~.,.!~,~.,g~~,9..i~.~~~. .~?~.~?~I,~.9.Q,~!?,.,!.~.~.,.!.~!~,i~~.~~.Q,. <?,,!,~.:,...."",......,.,.....,......,.....",.......,......"..,.

LLOJPM0751 RevOOO.doc Page 4 of 8

LLOJPM0751 REVOOO.DOC Job Performance Measure (JPM)

Operator's Name:

Job

Title:

a NLO a RO 0 SRO 0 STA 0 SRO Cert JPM

Title:

PERFORM A SHIFT TURNOVER (SRO)

..'PM Number: LLOJPM0751 Revision Number: 000 KIA Number and Importance: G2.1.3 3.7/3.9 G2.1.18 3.6/3.8 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Simulate Faulted: Yes Alternate Path: No Time Critical: No Estimated Time to Complete: 30 minutes Actual Time Used: _ _minutes

References:

OP-AA-112-101 Rev 6 TECH SPECS OP-LG-112-101 Rev 5 OP-LG-112-1 01-F-02 Rev 2 EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? o Yes 0 No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

LLOJPM0751 RevOOO.doc Page 5 of 8

LLOJPM0751 REVOOO.DOC JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain copy of OP-LG-112-101-F-02 to OP-LG-112-101-F-02 determine requirements for shift turnover is obtained Cue: Provide copy of OP-LG-112-1 01-F-02 AND Action Log (Actions expiring 48 hrs)

TECH SPECS required

2. Determine that shift turnover checklist Shift turnover checklist requirements are completed for must be completed oncoming SRO prior to taking shift Control Room Supervisors Shift Turnover Offgoing supervisor's Checklist responsibility UNIT 1 2 Identify Unit 1 is at 8%

reactor power MODE/% 2/8% 1/100%

POWER Unit 2 is at 100%

reactor power PRI CONT N Y EST: (YIN)

SECCONT Y Y EST: (YIN)

Refuel Floor Sec. Cont EST: N (YIN)

Note: Candidate may review Unit 1, Common, Unit 2 turnover checklist in any order

3. Determine Unit 1 is in OPCON 2 TECH SPEC 3.6.1.1 (STARTUP) with Primary Containment requires Primary not established and Containment in Unit 2 is in OPCON 1 OPCON 2 3a. Candidate references TECH SPECS TECH SPECS 3.6.1.1 to verify OPCON 2 requirements referenced Primary for Primary Containment Containment must be Note: TECH SPECS required for Primary established W/11 hr.

Containment determination or HOT SHUTDOWN W/112 hrs.

4a. Candidate references TECH SPECS HPCI operability 3.5.1 to identify HPCI operability determination W II 12 determination must be performed within hrs of RPV pressure of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of RPV pressure exceeding 920 psig.

920 psig. or RPV pressure reduced to

, <200 psig.

LLOJPM0751 RevOOO.doc Page 6 of 8

LLOJPM0751 REVOOO.OOC I 4b. Unit 1 T.S. Equip. Status OR Both HPCI and RCIC Conditions (LCOs.s 72hrs) -Identify must be declared the following systems must be declared operable W/112 hrs of operable W II 12 hrs of RPV pressure RPV pressure exceeding 920 psig. exceeding 920 psig.

HPCI, T.S. 3.5.1

RCIC, T.S. 3.7.3

5. Unit 2 Significant Activities in progress N/A or planned (for next shift) - Identify upcoming shift events

024 EOG operability run

ECCS Lineup verification 5a. Unit 2 T.S. Equip. Status OR TECH SPECS Conditions (LCOs.s 72hrs) -Identify referenced for EOG 024 EOG T.S. 3.B.1.1.a and (action e) requirements requirements

6. Common Significant Activities in progress or planned (for next shift)

Identify following activities:

Schuylkill River pump house cleanup

6a. Common T.S. Equip. Status OR TECH SPECS Conditions (LCOs.s 72hrs) -Identify referenced for SBGT the following requirements

Identify "8" S8GT INOP and is required to be operable for Unit 1 to enter OPCON 1 Candidate references TECH SPECS 3.6.5.3 to identify SBGT operability requirements Note: Candidate continues with page 2 of Shift Turnover Checklist

5. Unified Narrative Log reviewed: N/A Cue: Narrative Log reviewed 6 I have no change in health status: (Ref N/A OP-AA-1 05-1 01)

7. Review LCO/PLCO expiration dates: - Identify actions Identify LCO/PLCO's expiration dates in required to meet LCO's ESOMS t Cue: Action Log is from ESOMS LLOJPM0751 RevOOO.doc Page 7 of 8

LLOJPM0751 REVOOO.DOC I Note: ACTION LOG may be reviewed in conjunction with significant activities for Unit 1, Unit 2 and Common

7a. ACTION LOG reviewed - Action Log - Unit 1 activities-Actions expiring 48 hrs. coincide with HPCI/RCIC operability Unit 1, Unit 2, and Common significant and SBGT operability activities. requirements for OPCON 1 Unit 2, D24 EDG test run

8. Panel Walkarounds Completed: N/A Cue: Panel Walkdowns complete

9. Control Key Cabinet Reviewed: N/A Cue: WCS is staffed

10. Verify Availability of TRIP Pens: N/A Cue: TRIP Pens available

13. Verify Qualifications Prior to Taking N/A Shift:

Cue: Qualifications verified

11. STA status: Required to make STA determination prior to taking shift or releasing Cue: You are not the STA previous CRS (CUE: "You may stop here, you have met N/A the termination criteria for this JPM")

JPM Stop Time: _ __

LLOJPM0751 RevOOO.doc Page 8 of 8

LLOJPM0751 REVOOO.DOC INITIAL CONDITIONS:

Date is 10101/10

Present time is 06:00 Control Room Shift Supervisor is awaiting oncoming shift personnel

Shift staffing consisted of normal compliment for upcoming shift

Unit 1 in OPCON 2: GP-2 Reactor Startup

Reactor power presently is 80/0 power

At 04:00 commenced raising reactor pressure from 920 - 960 psig.

Unit 2 in OPCON 1: 100% power INITIATING CUES:

It is 06:00, You are the oncoming Unit 1 Control Room Shift Supervisor and are preparing to take day shift duties. You are to complete the Control Room Shift Supervisor Shift Turnover Checklist, identify any TECH SPEC concerns, and be prepared to perform the shift briefing meeting.

LLOJPM0751 RevOOO.doc

OP-LG-112-101-F-02 CONTROL ROOM SUPERVISOR SHIFT TURNOVER CHECKLIST DATE: 10/10/10 Shift Day UNIT 1 2 MODE I % POWER 2/8% 1 /100%

PRI CONT EST: (YIN) N Y SEC CONT EST: (YIN) Y Y Refuel Floor Sec. Cont EST: (YIN) N (If two supervisors are staffed, each SSV will fill out the checklist for the applicable unit.)

UNIT: 1 Significant Activities in GP-2 actions, Enter OPCON 1 and raise RPV pressure to 960 psig progress or planned (for HPCI PV&F test ST-6-055-230-1 preparations for "Night" shift next shift)

Primary Containment not established T. S. Equip. Status OR HPCI and RCIC operability 12 hrs after reaching adequate steam press of 920 Conditions psig.

(LCOs ~ 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

D RHRSW INOP Operational limitations HPCI HV-055-1 F001 Steam Admission Valve stroke time >17 (Max Allowable 16.68 sec) and is being evaluated by EDM (Expected time 6 hrs.)

Major Equipment Status or Conditions COMMON Significant Activities in Schuylkill River pump house cleanup progress or planned (for next shift)

T. S. Equip. Status OR 3.6.5.3 "B" SBGT INOP due to heater repairs Conditions (LCOs ~ 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

Major Equipment Status or Conditions UNIT: 2 Significant Activities in D24 EDG operability run planned progress or planned (for ECCS lineup verification next shift)

T. S. Equip. Status OR D24 EDG 3.8.1.1.a (action e)

Conditions D RHRSW PP INOP (LCOs:O; 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

Operational limitations Maintain 100 % power Major Equipment Status or 2B RFP vibration (system mgr notified)

Conditions

OP-LG-112-101-F-02 OP-LG-112-F-02 1.0 PRE-TURNOVER ITEM REVIEW o Unified Narrative Log reviewed o I have no change in health status. (Ref OP-AA-1 05-1 01 )

o Review LCO/PLCO expiration dates o Panel Walkarounds Completed o Control Key Cabinet Reviewed (0 N/A if WCS Staffed) o Verify Availability of TRIP Pens o Verify Qualifications Prior to Taking Shift Select One of the Following:

o I am not the STA. o I !!!!! the STA, the IA function is !!2! o I!!!!! the STA, the IA function is required required, MiQ I have notified the offgoing STA MiQ I have performed of my presence on site. face-to-face turnover with the offgoing STAin the Main Control Room per OP-AA-112-1 01.

RESPONSIBILITY ASSUMED BY: (Oncoming SSV Signature)

Signature: AJ Candidate Date: 10/10/10 Time: 06:00 POST-TURNOVER ITEM REVIEW o AIRs reviewed for Operability Impact o SSV ST Schedule, A-C-134 & Locked Valve Log Reviewed (0 N/A if WCS Staffed) o TPA Log /Report Reviewed o Review Daily Orders o Unified Narrative Log Reviewed o An SCBA with the correct mask size is staged at my workstation o When making Operability or Potential Operability determinations have in hand and utilize OP-AA-108-115.

o I have verified my schedule for the next two weeks.

Applicable Turnover Sheets Reviewed: o u/1 RO o

u/2RO o

PRO STA: IA if required: _

Action Log - Action expiring 48. hours from 10/01/2010 06:00 Total Entry Action Hours to Admin Hours to Completion Action LCOTR#I LCOTR DatelTime DatelTime Action DatelTime Admin DateITime Hours Action Statement Status Active: Unit 1 Demonstrate the OPERABILITY of 10/01/201005:00 10/01/201017:00 11 10110/201005:00 1*TS*10*06oo HPCI WII12 hours of RPV steam TS,1 4.5.1.2.a Dome pressure >920 psig Restore INOP RHRSW pp WII 9/20/201006:00 10120/201006:00 0*TS-1-0610 30 days TS,13.7.1.1 Restore "B" SBGT to OPERABLE 9/23/201006:00 9/30/2010 06:00 -24 0*TS*l-0620 W/17 Days TS,1 3.6.5.3 Active: Unit 2 Restore INOP RHRSW pp WII 9/20/2010 06:00 10/20/2010 06:00 0-TS-1-0610 30 days TS,13.7.1.1 Restore "B" SBGT to OPERABLE 9/23/201006:00 9/30/2010 06:00 *24 o*TS-1-D620 WII7 Days TS,l 3.6.5.3 Common

Exelon Nuclear Job Performance Measure Coordinate Personnel Activities Outside the Control Room JPM Number: LLOJPM0759 Revision Number: 000 Date:

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

JPM STUDENT WORKSHEET 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure Rev:

Procedure _ _ _ _ _ _ _ __

Rev: --

Procedure Rev:

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 2 of 5

JPM STUDENT WORKSHEET REVISION RECORD (Summary)

1. Revision 000, N/A SIMULATOR SETUP INSTRUCTIONS N/A INITIAL CONDITIONS:

Initial Conditions:

th

Today is October 8

Unit 1 Reactor power is 100%, Unit 2 Reactor power is 100%,

During your training week, you are reviewing the work schedule for your EOs for the first day of the day shift next week October 11 th

You have 4 Equipment Operators (EO 1 through EO 4) who are scheduled to report to your shift on day shift

EO 1 has been on medical leave since Jan. 1, 2010 and this will be his very first day back at the site in 2010

Working Hour Restrictions will not be evaluated INITIATING CUES:

Given a work schedule and the qualification reports for the EOs on your crew, determine who can be assigned to perform the scheduled work, shown below and on the attached schedule TASK STANDARD:

The attached table is completed as in the key Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 3 of 5

JPM STUDENT WORKSHEET JPM

SUMMARY

Operator's Name:_ _ _ _ _ _Job

Title:

O SED 0 SM I:8'JSROORO 0 STAliA 0 OTHER JPM

Title:

Coordinate Personnel Activities Outside the Control Room JPM Number: LLOJPM0759 Revision Number: 000 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: G.2.1.8 (4.1)

Suggested Testing Environment: Classroom Alternate Path: DYes I:8'JNo SRO Only: I:8'JYes ONo Time Critical: DYes I:8'JNo Reference(s): Procedure Rev: 27 Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant I:8'J Other Testing Method: 0 Simulatel:8'J Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: (Print)

Evaluator's Signature: Date: _ _ _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 4 of 5

JPM STUDENT WORKSHEET JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Determines what tasks EO 1 Determines that EO 1 cannot can be assigned to perform. be assigned to any tasks.

NOTE: EO 1 is not currently qualified as an on-shift EO.

Also, E01 cannot enter the RCA due to the lapse of GET training.

2. Determines what tasks EO 2 Determines that EO 2 can be can be assigned to. assigned to all Tasks except Task 4.

NOTE: Task 4 requires an OJT Trainer qualification.

3. Determines what tasks EO 3 Determines that EO 3 can be can be assigned to. assigned to all Tasks except Task 2 and Task 4.

NOTE: Task 4 requires an OJT Trainer qualification and Task 2 requires a torque wrench qualification. EO 3 OJT Qualification will expire prior to the scheduled OJT.

4. Determines what tasks EO 4 Determines that EO 4 can be can be assigned to. assigned to all Tasks.

NOTE: Determines that EO 4 can be assigned to all Tasks.

CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time: _ __

SRRS: 30.105 (when utilized for operator initial or continuing training) Page 5 of 5

JPM STUDENT WORKSHEET INITIAL CONDITIONS:

Initial Conditions:

th

Today is October 8

Unit 1 Reactor power is 100%, Unit 2 Reactor power is 100%,

During your training week, you are reviewing the work schedule for your EOs for the first day of the day shift next week October 11 th

You have 4 Equipment Operators (EO 1 through EO 4) who are scheduled to report to your shift on day shift

EO 1 has been on medical leave since Jan. 1,2010 and this will be his very first day back at the site in 2010

Working Hour Restrictions will not be evaluated INITIATING CUES:

Given a work schedule and the qualification reports for the EOs on your crew, determine who can be assigned to perform the scheduled work, shown below and on the attached schedule:

Task 1

- Hang tags inside the RCA for a fire suppression/detection system (0830 - 0900)

- Remove the tags hung above following work on the fire system (1500 - 1530)

Task 2

- Perform a surveillance inside the RCA which includes the use of a calibrated torque wrench (0900 -1400)

Task 3

- Perform Fire Watch duties inside the RCA during the fire suppression/detection system tag-out (0900 - 1500)

Task 4

- Perform OJT with EOI inside the RCA (1530 - 1900)

Task 5

- Perform Building Operator (RB, TB, Radwaste, Intake) duties (0800 - 2000)

SRRS: 30.105 (when utilized for operator initial or continuing training)

JPM STUDEN I NORKSHEET 0800 0900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000

. I ...1<1 I .. I**

1 D Hang Tags (>>1 Remove Tags T

A 12 S

KI3 S

Work Schedule SRRS: 30.105 (when utilized for operator initial or continuing training)

JPM STUDENT WORKSHEET State Yes or No, if the EO can be assigned to the tasks listed, as scheduled. Note: An EO can be assigned to multiple tasks, if qualified.

Task 1 Task 2 Task 3 Task 4 TaskS EO 1 No No No No No E02 Yes Yes Yes No Yes E03 Yes No Yes No Yes E04 Yes Yes Yes Yes Yes

Task 1

- Hang tags inside the RCA for a fire suppression/detection system (0830 0900)

- Remove the tags hung above following work on the fire system (1500 -1530)

Task 2

- Perform a surveillance inside the RCA which includes the use of a calibrated torque wrench (0900 - 1400)

Task 3

- Perform Fire Watch duties inside the RCA during the fire suppression/detection system tag-out (0900 - 1500)

Task4 Perform OJT with EO 6 inside the RCA (1530 - 1900)

Task S

- Perform Building Operator (RB, TB, Radwaste, Intake) duties (0800 - 2000)

SRRS: 30.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Peliormance Measure EVALUATE ST-6-047-370-1, PRE CONTROL ROD WITHDRAWAL CHECK FOLLOWING CORE ALTERATIONS (SRO)

JPM Number: 0753 Revision Number: 000 Date: _ - - f _ - - f _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Review By:

Operations Representative Date Approved By:

Training Department Date

LLOJPM0753 Rev 000 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to ..IPM usage, revalidate JPM using steps 8 through 11 below.

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

2. Knowledge and Abilities (KIA) 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 Examiner 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 _ _ _ _ __

9. Pilot test the JPM:

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

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

1. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LLOJPM0753 Rev 000 Page 2 of 7

LLOJPM0753 Rev 000 REVISION RECORD (Summary):

New Revision SIMULATOR SETUP INSTRUCTIONS:

None JPM Setup Instructions:

Provide a yellow copy of a Partial ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations.

Provide copy of Unit 1 TECH SPECS TASK STANDARD:

The candidate should report the test is not completed properly due to procedure steps not signed off correctly, no SQR signature, 34-03 Pre Control Rod Withdrawal Checks not performed, and HCU accumulators are out of surveillance.

TASK CONDITIONS:

Unit 1 is in OPCON 5, with Reactor Vessel Head still on Today's date is 10101/2010. You are the oncoming DAY shift SRO Partial Surveillance Test, ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations, was initiated on night shift and to be reviewed by the RO and submitted for SRO approval so the 4 Control Rods can be withdrawn.

Pre-Control Rod Withdrawal Checks are required for Control rods 10-11, 18-15,34-03 and 42-15.

ST-6-107-632-1, One Rod Out Interlock Verification Testing is in surveillance

ST-6-047-750-1, CRD Accumulator Pressure Check, is NOT in surveillance

NF-AA-330-1 001, Core Verification Guideline, is in compliance INITIATING CUE:

You are the oncoming SRO and are to review Partial ST-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations. The procedure requires SRO approval prior to withdrawing the 4 deSignated Control Rods. Identify any discrepancies and 1 or TECH SPEC concerns that are required to be addressed prior to withdrawing the 4 Rods LLOJPM0753 Rev 000 Page 3 of 7

LLOJPM0753 Rev 000 Information for Evaluator's 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.

LLOJPM0753 Rev 000 Page 4 of 7

LLOJPM0753 Rev 000 Operator's Name: _ _~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

0 RO o SRO o STA o SRO JPM

Title:

EVALUATE ST-6-047-370-1, PRE CONTROL ROD WITHDRAWAL CHECK FOLLOWING CORE ALTERATIONS JPM Number: 0753 (SRO) Revision Number: 000 KIA Number and Importance: G2.1.20 RO 4.6 SRO 4.6 Suggested Testing Environment: Classroom Actual Testing Environment:

Testing Method: Classroom Faulted: Yes Alternate Path: No Time Critical: No Estimated Time to Complete: 30 min Actual Time Used: _ _minutes

References:

ST-6-047-370-1 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? - Yes - No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: - Satisfactory - Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: --

LLOJPM0753 Rev 000 Page 5 of 7

LLOJPM0753 Rev 000 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number Note: Hand the applicant: Review the handouts

ST-6-047-370-1

..!PM cue sheet

Unit 1 TECH SPECS

1. SRO candidate identifies comments Signatures required in the partial test is not signed by authorizing the partial and the initiator and authorized and SQR review and approval dated by an SQR required for any change submitted

2. SRO candidate reviews test and Step 4.5.7 not completed prior identifies step 4.5.7 not verified. to SRO verification (Unit 1 is in OPCON 5, with Reactor Vessel Head still on, as designated on initiating conditions). This step is required to be completed prior to submitting to the SRO for verification.

3. SRO candidate identifies step 4.5.11 SRO verification required prior must be completed prior to to moving control rod withdrawing control rod.

4. SRO candidate identifies per ST-2-047-400-1 identified as ATTACHMENT 1 that "CRD the most limiting with an Over Accumulators ST-2-047-400-1 with due-date of 9/27/10 the over-due-date of 9/27/10 makes it out of surveillance and the most limiting ST

5. SRO candidate identifies of the 4 Control rod 34-03 Section 4.5 control rods to be tested control rod requirements not completed 34-03 per ATTACHMENT 2 has not been identified and section 4.5 requirement not met prior to SRO verification.

~~-~----

6. SRO candidate identifies control Control Rod 18-15, HCU rod 18-15 accumulator pressure is accumulator pressure is 945 945 psig which is below the TECH whereas TECH SPECS SPEC required 955 psig operability is 955 psig.

requirement for control rod operability LLOJPM0753 Rev 000 Page 6 of 7

LLOJPM0753 Rev 000 II ELEMENT STANDARD I SAT UNSAT Comment Number 7 SRO references TECH SPEC TECH SPECS referenced and 3.1.3.5, and determines all control actions taken for an INOP rod scram accumulators are scram accumulator (action b) required to be operable in OPCON 5 and takes actions for a control rod with a INOP scram accumulator CUE: (You may stop here. You have reached the termination criteria for this JPM)

JPM Stop Time _ _ _ __

LLOJPM0753 Rev 000 Page 7 of 7

TASK CONDITIONS:

Unit 1 is in OPCON 5, with Reactor Vessel Head still on Today's date is 10/01/2010. You are the oncoming DAY shift SRO Partial Surveillance Test, 8T-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations, was initiated on night shift and to be reviewed by the RO and submitted for SRO approval so the 4 Control Rods can be withdrawn.

Pre-Control Rod Withdrawal Checks are required for Control rods 10-11, 18-15, 34-03 and 42-15.

8T-6-1 07-632-1, One Rod Out Interlock Verification Testing is in surveillance

ST-6-047-750-1, CRD Accumulator Pressure Check, is NOT in surveillance

NF-AA-330-1 001, Core Verification Guideline, is in compliance INITIATING CUE:

You are the oncoming SRO and are to review Partial 8T-6-047-370-1, Pre Control Rod Withdrawal Check Following Core Alterations. The procedure requires 8RO approval prior to withdrawing the 4 designated C . . . CH 8PEC c e required to be addressed prior to withdrawing 1

Exelon Nuclear Job Performance Measure Authorize Liquid Radioactive Inventory Release From the Floor Drain Sample Tank JPM Number: 0761 Revision Number: 000 Date: I I Developed By:

Instructor Date Validated By:

SME or Instructor Date Review By:

Operations Representative Date Approved By:

Training Department Date LLOJPM0761 Rev 000 Page 1 of 7

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

2. Knowledge and Abilities (KIA) 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 Examiner 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 _ _ _ _ __

9. Pilot test the JPM:

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

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the ...IPM"

11. When JPM is revalidated, Examiner sign and date JPM cover page.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME I Instructor Date SM E I Instructor Date SME I Instructor Date LLOJPM0761 RevOOO Page 2 of 7

REVISION RECORD (Summary):

JPM Setup Instructions:

Provide a completed copy of S63.1.C (Inventory Release from 00T308 Floor Drain Sample Tank Number 2 to Cooling Tower Slowdown Line)

TASK STANDARD:

Applicant should identify that cooling tower blowdown flow is below the required 5000 gpm and should NOT authorize the release TASK CONDITIONS:

Floor Drain Sample Tank #2 has been sampled satisfactorily for river release

The RWEO is performing S63.1.C and has requested FSSV review and approval to commence release to the river.

The RWEO has the discharge permit ST-S-061-S70-0 which was received from Chemistry indicating FDST 2 is sat for river release.

Cooling tower blowdown flow is now at 4000 gpm.

No Hold Pond release is in progress.

INITIATING CUE:

You are direct to perform the shift supervisory review required per S63.1.C Step 4.3.7.

When complete, note your answer on the JPM cue sheet.

LLOJPM0761 RevOOO Page 30t 7

Information for Evaluator's 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.

LLOJPM0761 RevOOO Page 4 of 7

Operator's Name: _________________________

Job

Title:

0 SED OSM [gJSRO 0 STAliA D OTHER JPM

Title:

Review and Approve a Radioactive Liquid Discharge JPM Number: 0761 Revision Number: 000 KIA Number and Importance: G2.3.11 Ability to control radiation releases.

(CFR: 41.11 143.4/45.10) IMPORTANCE RO 3.8 SRO 4.3 Suggested Testing Environment: Classroom - Group Actual Testing Environment: Classroom Testing Method: Table top - Group Faulted: No Alternate Path: No Time Critical: No Estimated Time to Complete: 30 min Actual Time: minutes

References:

1. S63.1.C Rev 33 (Inventory Release from 00T308 Floor Drain Sample tank Number 2 to Cooling Tower Slowdown Line EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? - Yes -No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: - Satisfactory - Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

LLOJPM0761 RevOOO Page 5 of 7

NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Hand out the JPM cue sheet and a Start the task when all completed copy of S63.1.C applicants acknowledge they are ready to begin the JPM.

2. Hand out a completed copy of All applicants begin the JPM S63.1.C for review. Log the start time.

3. Review the completed copy of Review S63.1.C and JPM cue S63.1.C and the JPM Cue sheet. sheet.

4. Determine if the release can be If the applicant determines the authorized. release can be authorized, initial step 4.3.7 on S63.1.C.

This is incorrect.

5. Step 4.3.7 not signed If the applicant determines the release should NOT be authorized, then do NOT initial step 4.3.7 of S63.1.C and complete the JPM answer sheet stating that the cooling tower blowdown flow is less than the required amount (5000 gpm).

Cue: You may stop here, you have met Log completion time.

the termination criteria for this JPM JPM Stop Time _ _ _ __

LLOJPM0761 RevOOO Page 60t 7

HANDOUT PAGE TASK CONDITIONS:

Floor Drain Sample Tank #2 has been sampled satisfactorily for river release

The RWEO is performing S63.1.C and has requested FSSV review and approval to commence release to the river.

The RWEO has the discharge permit ST-S-061-S70-0 which was received from Chemistry indicating FDST 2 is sat for river release.

Cooling tower blowdown flow is now at 4000 gpm.

No Hold Pond release is in progress.

INITIATING CUE:

You are direct to perform the shift supervisory review required per S63.1.C Step 4.3.7.

When complete, note your answer on the JPM cue sheet.

ANSWER Key:

Circle the appropriate answer:

1. Release is APPROVED.

2. Release is NOT approved: state the reason for disapproval below:

LLOJPM0761 RevOOO Page t0f 7

Exelon Nuclear Job Peliormance Measure SRO Only - Emergency Classification (TIME CRITICAL)

JPM Number: LLOJPM0097 Revision Number: 010 Date: _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0097, Revision 010 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 9 and 12 below.

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

2. Knowledge and Abilities (K/A) references are included.

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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. Verity the procedure(s) referenced by this JPM reflects the current revision:

Procedure EP-AA-1008 Rev: -

Procedure EP-AA-111 Rev:

Procedure EP-AA-111-F-08 Rev:

Procedure EP-AA-112-100-F-01 Rev:

Procedure EP-AA-112-100-F-07 Rev:

Procedure EP-AA-112-F-09 Rev:

Procedure EP-MA-114-100 Rev:

Procedure EP-MA-114-100-F-01 Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verity performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 2 of 9

LLOJPM0097, Revision 010 REVISION RECORD (Summary)

1. Revision 10, minor format changes, no rev markers used SIMULATOR SETUP INSTRUCTIONS

1. This JPM can be performed in either the Simulator or any other quiet area, provided appropriate Emergency Plan documents are provided in that area. If the Simulator is being used, perform the following:

Reset the Simulator to IC-17 NOTE: It is acceptable to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

Insert Remote Functions:

o RZZ002 (Met Data Wind Direction) at 311 0 o RZZ003 (Met Data Wind Speed) at 5 MPH

2. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

3. This completes the setup for this JPM.

4. If the Simulator is NOT being used, ensure the following is available for candidate use:

T-103

Sticker Book, Brief Non-Technical Descriptions

EP-AA-100B, Both Hot and Cold Matrix

EP-AA-111, Emergency Classification and Protective Action Recommendations

EP-AA-111-F-OB, Limerick / Peach Bottom Plant Based PAR Flowchart

EP-AA-112-1 00-F-01 , Shift Emergency Director Checklist

EP-AA-112-1 00-F-07, Mid-Atlantic RO Notification or Augmentation

EP-AA-112-F-09, Emergency Public Address Announcements

EP-MA-114-100, Mid - Arlantic State / Local Notifications

EP-MA-114-100-F-01, State/Local Notification form SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 3 of 9

LLOJPM0097, Revision 010 INITIAL CONDITIONS:

Unit 1 conditions are as follows:

T==O o 'A' Steam Line has ruptured in the Outboard MSIV Room.

o Group 1 Isolation signal is received due to high Steam Line Flow o "An Steam Line Inboard And Outboard MSIVs have failed to isolate automatically or manually.

T == 5 minutes o All control rods are fully inserted o Reactor Coolant Activity starts to increase T = 15 minutes o RPV pressure is 850# and lowering o RPV level is 18" and steady o DW pressure is 0.3 psig o DW Rad Monitor is reading 1.1 OE+03 (11 OORlhr) o Reactor Coolant Activity is 370uCi/gm o Outboard MSIV Room temperature is 210 degrees F o Security and HP personnel have confirmed a steam release outside secondary containment from blowout panels INITIATING CUES:

This Task is Time Critical This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin.

No prior classifications or notifications have been made. You are required to make the highest classification based on the given plant conditions and make subsequent call outs. All communications should indicate a drill.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 4 of 9

LLOJPM0097, Revision 010 Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 5 of 9

LLOJPM0097, Revision 010 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _ _Job

Title:

D SED DSM DSRO STAliA 0 OTHER JPM

Title:

SRO Only - Emergency Classification JPM Number: LLOJPM0097 Revision Number: 009 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 2.4.41 RO: 2.9 SRO: 4.6 Suggested Testing Environment: Simulator or quiet area with appropriate Emergency Plan documents Alternate Path: DYes 1:8] No SRO Only: I:8]Yes DNo Time Critical: !25JYes DNo Reference{ s):

Procedure EP-AA-1008 Rev: 18 Procedure EP-AA-111 Rev: 16 Procedure EP-AA-111-F-08 Rev: D Procedure EP-AA-112-100-F-01 Rev: K Procedure EP-AA-112-100-F-07 Rev: E Procedure EP-AA-112-F-09 Rev: C Procedure EP-MA-114-100 Rev: 13 Procedure EP-MA-114-100-F-01 Rev: H Actual Testing Environment: 1:8] Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate r8J Perform Estimated Time to Complete: 25 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes DNo The operator's performance was evaluated against standards contained within this ..IPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:

Evaluator's Name: ____________________ (Print)

Evaluator's Signature:____________________ Date:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 6 of 9

LLOJPM0097, Revision 010 JPM Start Time: _ _ __

ELEMENT STANDARD NOTE:

IF another SRO is requested to perform an independent Peer Check CUE: A Peer Check will not be provided for this JPM

1. Review the Initiating Conditions EAL Matrix(s) used to classify applicable to the operating mode event

2. Call EP Communicator to the Main Control Room EP Communicator called to the CUE: Wait 5 minutes, then report Main Control Room as the EP Communicator

---t---------------------

3. If EAL Threshold Values have Determine General Emergency been met or exceed ed, then initiating conditions have been exceeded FG1:

FCB Loss: 1.c.1 OR 1.d.1

RCB: Loss 2.d.1. AND 2.d.2.a OR 2.d.1 AND 2.d.2.b

PCB Loss 3.d.1 a AND 3.d.1.b, or 3.d.3

-~

4. Declare the event Declares a General Emergency (12 minute clock to get form to within 15 minutes of JPM Start EP Communicator starts)

Declaration Time: _ _ __

- --------+------~---------~--~-_+_--t--_I

5. rctivate the ERO Direct EP communicator to Activate the ERO I

6. Complete EP-MA-11 4-100-F-01, State/Local Event Notification N/A Form as follows:

6a. Utility Message No. 1 (or equivalent) 6b. Emergency Director Approval Signature entered SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 7 of 9

LLOJPM0097, Revision 010

....C a..

~ CI) e.D CI)

STEP ELEMENT STANDARD ~

(f)

Z eo e::::J

> ,OZ I

6c. Block 1 Call Status (NOTE: Step is not critical if Block "This is a Drill" checked 8 (Step 5.s) is completed SAT) - -- -

6d. Block 2 Station "limerick" checked - I

6e. Block 3.a Emergency "General Emergency" checked Classification - - -

r-

6f. Block 3.b Affected Units

~-~~

"ONE" checked - - -

6g. Block 3.c Declared At (Time) Correct time of declaration entered (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock) - - -

6h. Block 3.c Declared At (Date) I Correct date entered - - -

6i. Block 3.d This Represents AlAn ! "Initial Declaration" checked - - -

6j. Block 4. Emergency Action Level (NOTE: Step is not critical if Block IFG1" Entered 4 (Step 5.1) is completed SAT) - -I I

6k. Block 4 Emergency Action Level Alphanumerically "Foxtrot Golf One", written in the area next to (NOTE: this step is N/A if sticker FG1 for correct action is used) - - -

Sticker FG 1 placed in block or the

61. Block 4 Brief Non-Technical following (or equivalent) entered:

Description "Loss of 2 of 3 fission product (NOTE: Step is not critical if Block barriers with actual or potential 4 (Step 5.D is completed SAT) loss of the third barrier.

Protective actions will be recommended for the public" -. -

6m. Block 5 Non-Routine ~adiological I"AIRBORNE radiological release Release Status

in-progress" checked - - -

6n. Block 6 Meteorology Wind direction "311.0" deg az NOTE: Tower 1: 175' entered

60. Block 6 Meteorology Wind speed "5.0" mph entered I NOTE: Tower 1: 175' - - -

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 8 of 9

LLOJPM0097, Revision 010

....t: :r...

I-l 0< G>!

STEP ELEMENT STANDARD 0< tJ) z EE tJ) E :::l 0

Oz I

6p. Block 7 Utility Protective Action "b. The PROTECTIVE ACTION Recommendation RECOMMENDATION (PAR) from the utility is:" checked

6q. Block 7 Utility Protective Action N/A Recommendation SHELTER "EVACUATE" checked

6r. Block 7 Utility Protective Action Recommendation EVACUATE Evacuate 360 DEGREES FROM 0 MILES (SITE BOUNDRY) TO .::§:

MILES entered Evacuate THE FOLLOWING SECTORS FROM " 5" MILES TO "10" MILES entered SECTORS ESE, SE, and SSE checked

6s. Block 8 Conclusion (NOTE: Step is not critical if Block "This is a Drill" checked

. 1 (Step S.c) is completed SAT) - - -

7. Initiates State and Local Shift Communicator directed to Notifications initiate required State and local notifications within 12 minutes of CUE: Continue acting as Shift event classification Communicator, and repeat back directions provided by student, as Time State/Local required Notification Form To EP Communicator: - - -

8. Place-keep in EP-AA-112-1 OO-F 01, Shift Emergency Director N/A Checklist to perform required actions

9. Announce event classification to IControl Room staff notified of I Control Room staff I event classification 1- -

You have met the termination criteria for this JPM JPM Stop Time:

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 9 of 9

LLOJPM0097,Re~s~n010 917METEOROLOGICAL 15 MINUTE AVERAGE POINT DATA PID SENSOR DESCRIPTION VALUE EU T1DTULFA T1.SP.U TOWER 1 270 FT WIND SPEED 14.2 MPH T1SPIFA T1.SP.1 TOWER 1 175 FT WIND SPEED 5.0 MPH T12SPLFA T1.SP.L TOWER 1 30 FT WIND SPEED 16.9 MPH T

T1DRUFA T1.DR.U TOWER 1 270 FT WIND DIRECTION 160.1 DEGAZ 0

W T1DRIFA T1.DR.1 TOWER 1 175 FT WIND DIRECTION 311.0 DEGAZ T1DRLFA T1.DR.L TOWER 1 30 FT WIND DIRECTION 174.9 DEGAZ E

T1DTULFA T1.DT.U-L TOWER 1 266 - 26 FT DELTA TEMP -0.3 DEG F R

T1DTILFA T1.DT.I-L TOWER 1 171 - 26 FT DELTA TEMP 0.7 DEG F 1 T1ATLFA T1.AT.L TOWER 1 26 FT AMBIENT TEMP 85.2 DEG F T1DPLFA T1.DP.L TOWER 1 26 FT DEW POINT 45.00 DEG F T1RNFA Ti.RN TOWER 1 PRECIPITATION 0.1 INCHES T2DTULFA T2.SP.U TOWER 2 304 FT WIND SPEED 13.4 MPH T2SPIFA T2.SP.1 TOWER 2 159 FT WIND SPEED 15.2 MPH T T22SPLFA T2.SP.L TOWER 2 30 FT WIND SPEED 14.1 MPH 0 T2DRUFA T2.DR.U TOWER 2 304 FT WIND DIRECTION 132.7 DEGAZ W T2DRIFA T2.DR.1 TOWER 2 159 FT WIND DIRECTION 141.7 DEGAZ E T2DRLFA T2.DR.L TOWER 2 30 FT WIND DIRECTION 143.6 DEGAZ R T2DTULFA T2.DT.U-L TOWER 2 304 - 26 FT DELTA TEMP -0.2 DEG F T2DTILFA T2.DT.I-L TOWER 2 155 - 26 FT DELTA TEMP 0.4 DEGF 2

T2ATLFA T2.AT.L TOWER 2 26 FT AMBIEWNT TEMP 85.0 DEG F T2DPLFA T2.DP.L TOWER 2 26 FT DEW POINT 44.81 DEG F DATE: TODAY TIME: NOW SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0097, Revision 010 INITIAL CONDITIONS:

Unit 1 conditions are as follows:

T=O o 'A' Steam Line has ruptured in the Outboard MSIV Room.

o Group 1 Isolation signal is received due to high Steam Line Flow o "An Steam Line Inboard And Outboard MSIVs have failed to isolate automatically or manually.

T = 5 minutes o All control rods are fully inserted o Reactor Coolant Activity starts to increase T = 15 minutes o RPV pressure is 850# and lowering o RPV level is 18" and steady o OW pressure is 0.3 psig o OW Rad Monitor is reading 1.1 OE+03 (11 OORJhr) o Reactor Coolant Activity is 370uCi/gm o Outboard MSIV Room temperature is 210 degrees F o Security and HP personnel have confirmed a steam release outside secondary containment from blowout panels INITIATING CUES:

This Task is Time Critical This ..'PM will start when you tell the evaluator that you are aware of task conditions and are ready to begin.

No prior classi'fications or notifications have been made. You are required to make the highest classification based on the given plant conditions and make subsequent call outs.

All communications should indicate a drill.

SRRS: 30.105 (when utilized for operator initial or continuing training)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10/04/10 Exam Level: RO 181 SRo-ID SRO-U 0 Operating Test No.: ILT09-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. CRD Hydraulic System I Perform Reactor, Startup, Alternate A, D, L, S, P 1 Path (2008 JPM A)

b. Manually place a RFP in Service, Alternate Path N,A,S 2

,r,

c. Transfer HPCI From Pressure Control Mode to Level Control A,N,S 4 Mode, Alternate Path

d. Primary Containment N2 Makeup (0523) fZ~ D,S 5

e. Transfer D13 from 101 to 201 (0519) A,D,S 6

f. Control Rod Exercise Test (0107) D,S 7

g. Comp Cooling Water / Align RECW for DW Cooling (2008 JPM G) A. D. EN. S, 8 P

h. Manually Isolate the RE Enclosure (0022) D,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Bypassing and Removing the *A RPS and UPS Static Inverter from D.R 6 Service (0203) f

j. Alignment of Equipment or Operation for Shutdown Cooling (Fire E, N, L, R, 4 Safe Shutdown) (0267)

k. RO, SRO-I , SRO-U, Scram and MSIV closure from the AER A,D,E,L,R 7 (0261)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant ~1/<=1/<=1 (EN)gineered safety feature - I - I ;::1 (control room system)

(L)ow-Power 1 Shutdown ;::1/;::1/<=1 (N)ew or (M)odified from bank including 1(A) ;::2/;::2/?1 (P)revious 2 exams :5 31:5 31 S 2 (randomly selected)

(R)CA ?1/?1/?1

,S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10/04/10 Exam Level: RO 0 SRO-I f8I SRO-U 0 Operating Test No.: ILT09-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System! JPM Title Type Code* Safety Function

a. CRD Hydraulic System I Perform Reactor, Startup, Alternate A,D,L,S,P 1 Path (2008 JPM A)

b. Manually place a RFP in Service, Alternate Path N,A,S 2

c. Transfer HPCI From Pressure Control Mode to Level Control A,N,S 4 Mode, Alternate Path

d. Primary Containment N2 Makeup (0523) D,S 5

e. Transfer 013 from 101 to 201 (0519) A,D,S 6 f

g. Comp Cooling Water I Align RECW for OW Cooling (2008 JPM G) A, D, EN, S, 8 P

h. Manually Isolate the RE Enclosure (0022) D,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Bypassing and Removing the *A RPS and UPS Static Inverter from D,R 6 Service (0203)

j. Alignment of Equipment or Operation for Shutdown Cooling (Fire E, N, L, R, 4 Safe Shutdown) (0267)

k. RO, SRO-I , SRO-U, Scram and MSIV closure from the AER A,D,E,L,R 7 (0261 )

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-II SRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - / - / <!:1 (control room system)

(L)ow-Power / Shutdown ;:>:1/~1/<!:1 (N)ew or (M)odified from bank including 1(A) <!:2/~2/?1

{P)revious 2 exams ~ 3 / s; 3/ s; 2 (randomly selected)

(R)CA <!:1/?1/?1 IS)imulator

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: LGS Date of Examination: 10/04/10 Exam Level: RO D SRO-I D SRO-U 181 Operating Test No.: ILT09-1 .

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1JPM Title Type Code* Safety Function

a. CRD Hydraulic System 1 Perform Reactor, Startup, Alternate A,D, L, S, P 1 Path (2008 JPM A)

b. Manually place a RFP in Service, Alternate Path N,A,S 2 c.

d.

e.

f

g. Camp Cooling Water 1 Align RECW for OW Cooling (2008 JPM G) A, 0, EN, S, 8 P

. h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

. i. Bypassing and Removing the *A RPS and UPS Static Inverter from D.R 6 Service (0203)

j. Alignment of Equipment or Operation for Shutdown Cooling (Fire E, N, L. R. 4 Safe Shutdown) (0267) k.

@ All RO and SRO-I control room (and in-plant) systems must be different and selVe different safety functions; all 5 SRO-U systems must selVe different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank ~9/~8/==>4 (E)mergency or abnormal in-plant ;::1/21/;::1 (EN)gineered safety feature - / - / ;::1 (control room system)

(L)ow-Power I Shutdown 21/;::1/21 (N)ew or (M)odified from bank including 1(A) 22/;::2/;::1 (P)revious 2 exams ==> 3/ s; 31 s; 2 (randomly selected)

(R)CA 21/21/2:1

~S)imulator

Exelon Nuclear Job Performance Measure PERFORM REACTOR STARTUP (ALTERNATE PATH)

JPM Number: LLOJPM0755 Revision Number: 000 Date: _ _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0755, Revision 000 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure Rev: _ __

Procedure Rev: - - -

Procedure __________ Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME I Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 2 of 11

LLOJPM0755, Revision 000 REVISION RECORD (Summary)

1. N/A Revision 000 , based on C JPM A -2008 Limerick operating Test SIMULATOR SETUP INSTRUCTIONS SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 3 of 11

LLOJPM0755, Revision 000 SIMULATOR SETUP INSTRUCTIONS

1. Reset to IC 6, or a startup IC with RPV pressure of approximately 150 psig with 1A CRO Pump in operation.

2. Load above malfunctions and triggers

3. Select Rod 38-35

4. Provide Rod move Sheet with steps marked off IN'-riAL CONDITIONS:

Unit 1 is at 3% power and RPV pressure is 151 psig

1B CRO Pump is out of service for bearing replacment

RPV level is 35 inches, being controlled by LlC~ 120 in automatic

A plant startup is in progress per GP~2, Appendix 1, Reactor Startup and Heatup

Control rods are being withdrawn per Control Rod Move Sheet Sequence 10:.

LGSimSU-1.0 on Step 13

The next rod move step is to withdraw Control Rod 22-27 using Single notch move from position 12-30 as directed on Control Rod Move Sheet.

TASK STANDARD:

Address the loss of CRO flow per ON-107 and respond to the subsequent resulting failure of two scram accumulators by tripping the reactor.

INITIATING CUES:

You are the Reactor Operator. You have been directed to continue with the startup by withdrawing control rods in accordance with the control rod move sheet.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 4 of 11

LLOJPM0755, Revision 000 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _Job

Title:

O SED 0 SM OSRO ORO o STAIIA 0 OTHER JPM

Title:

PERFORM REACTOR STARTUP (ALTERNATE PATH)

..IPM Number: LLOJPM0755 Revision Number: 000 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 201001 A2.04 (3.8, 3.9)

Suggested Testing Environment: Simulator Alternate Path: ~Yes ONo SRO Only: DYes ~No Time Critical: DYes ~No Reference(s):

Procedure: ON-1 07, CRD Problems Rev: 15 Procedure: S46.6.C, Placing Alt CR Water Filter In Service Rev: 08 Actual Testing Environment: ~ Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate ~ Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 5 of 11

LLOJPM0755, Revision 000 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number NOTE Trigger 1 is activated when withdraw pushbutton is depressed, this activates:

CRD Pump discharge valve closes to simulate drive water filter clog

ANN-MCR-108-G4, CRD Drive Water Filter Hi Delta P

ANN-MCR-108-H4, CRD Charging Water LO Press

1. NOTCH withdraw control Notch withdraw CR 22-27, rods per CR Move Sheet Seq from 12 to 48.

1D: LGS Sim U-1.0.

Alternate Path Starts Now:

Informs supervisor of high 2 Observes indications of high filter dip and alarm.

dip, clogged drive water filter.

Cue: If necessary, direct applicant to respond to alarm.

3. Reference ARCs: Inform supervisor of ON-1 07 entry

MCR-108-H4, CRD Charging Water LO Press

MCR-108-G4, CRD Drive Water Filter Hi Delta P Cue: When informed of ARC direction, hand copy of ON-107 to applicant and State the following:

The CRS directs you to perform the actions of ON-1 07.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 6 of 11

LLOJPM0755, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

4. PER ON-107: Direct EO to place alternate IF CRD Pump is running but drive water filter in service CRD drive flow is insufficient, per S46.6.C THEN PERFORM one of the following as applicable:

PLACE alternate CRD Drive Water Filter, in service per S46.6.C.

PLACE alternate CRD Flow Control Valve, in service per S46.6.8 Cue: After 1 minute:

Toggle remote function RCR018 (A CRD pump discharge valve) to OPEN (to simulate valving in the alternate drive water filter)

Delete ANN 108 Reactor G4 (CRD Drive Water Filter Hi dP)

As EO, Report :

The Alternate Drive Water Filter is in Service. I will write an ETT to replace the filter.

After 1 minute:

Toggle remote function RCR018 (A CRD pump discharge valve) to CLOSE (to simulate cloging in the alternate drive water filter)

Toggle ANN 108 Reactor G4 (CRD Drive Water Filter Hi dP) to ON 5 seconds after Valve closure Activate Trigger 2 (Accumulator trouble alarms) and pump trip SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 7 of 11

LLOJPM0755, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

5. Observes indications of high Informs supervisor of high dIp, clogged drive water filter. filter dIp and alarm.

Cue: if asked to investigate drive water filter Report:

FIN team is aware of filter problem and is expediting paperwork to replace the filter with hi dIp.

6. Accumulator Trouble Rod Inform supervisor.

22-35, Refer to ARC-MCR-1 08-F1, AND CRD Accumulator Trouble.

ARC-MCR-1 08-F1 , CRD Accumulator Trouble.

6.a Follow Tech. Spec 3.1.3.5, Inform Supervisor of Tech pertaining to control rod Spec scram accumulators.

Cue: CRS will review Tech.

Specs.

6.b Dispatch Operator to inspect Dispatches EO to HCU HCU.

Cue: After 1 minute, Report:

Cause of accumulator trouble is low pressure, pressure is 940 psig.

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 8 of 11

LLOJPM0755, Revision 000 ELEMENT STANDARD SAT UNSAT Comment I Number

7. PER ON-107: Inform CRS of required IF one CRD scram actions for single inoperable accumulator is inoperable, accumulator.

THEN PERFORM the following within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s:

RESTORE the inoperable accumulator to operable OR DECLARE associated control rod inoperable.

IF above step is not completed, THEN TAKE action to be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

8. Accumulator Trouble Rod Inform supervisor.

46-19, Refer to ARCs:

AND

108-F1, CRD ARC-MCR-1 08-F1 , CRD Accumulator Trouble Accumulator Trouble.

108 REACTOR G-2 AND 1AJ1 B CRD Water Pump Trip of 1A CRD pump Motor Overcurrent Cue: After 1 minute, Report: Dispatches EO to HCU and 1ACRD pump

Cause of accumulator trouble is low pressure, pressure is 940 psig.

After 4 minutes, Report:

1A CRD Pump tripped on overcurrent. I'm continuing to investigate.

9. PER ON-107:

IF more than one CRD scram accumulator is inoperable, THEN PERFORM the following:

9.a DECLARE the associated Inform CRS Control Rod control rods inoperable. 46-19 is inoperable SRRS: 30.105 (when utilized for operator initial or continuing training)

I Page 9 of 11

LLOJPM0755, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number 9.b IF the control rod associated Attempts to insert a with any inoperable CRD withdrawn control rod one scram accumulator is notch.

withdrawn, THEN immediately VERIFY at least one CRD pump is operating:

INSERT a withdrawn control rod one notch.

OR

IF loss of RMCS prevents control rod motion, THEN CHECK charging water header pressure ~ 1400 psig on PSH-46*N600, "CHARGING WATER PRESSURE" (PX) at

OC603 Cue: IF RO wants to attempt to insert Control rod and asks for guidance on which rod to insert:

RE Directs inserting selected Rod.

Note:

The selected rod will NOT insert. This action is used per procedure to define whether or not a CRD pump is operating. Attempt to move control rod will be unsuccessful indicating NO CRD pumps are operating for the purpose of the subsequent IFrrHEN step in ON-107.

9.c IF no CRD pump is operating N/A AND reactor pressure is greater than or equal to 900 psig, START at least one CRD pump within 20 minutes SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 10 of 11

LLOJPM0755, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

9.d IF nQ CRD pump is operating Scram Collars armed AND reactor pressure is less Scram Pushbuttons than 900 psig, depressed Then PERFORM the following: Reactor Mode Switch placed in "SHUTDOWN,"

Manually SCRAM the reactor AND PLACE Reactor Mode Switch in "SHUTDOWN,"

AND ENTER T-100 OR T-101, as applicable.

CUE: You have met the termination criteria for the JPM. You may stop here I JPM Stop Time: _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 11 of 11

Initial Conditions:

Unit 1 is at 3% power and RPV pressure is 151 psig

1B CRD Pump is out of service for bearing replacement

RPV level is 35 inches, being controlled by LlC-120 in automatic

A plant startup is in progress per GP-2, Appendix 1, Reactor Startup and Heatup

Control rods are being withdrawn per Control Rod Move Sheet Sequence ID:

LGSimSU-1.0 on Step 13

The next rod move step is to withdraw Control Rod 22-27 using Single notch move from position 12-30 as directed on Control Rod Move Sheet.

Initiating Cue:

You are the Reactor Operator. You have been directed to continue with the startup by withdrawing control rods in accordance with the control rod move sheet.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure MANUALLY PLACE 3RD RFP IN SERVICE (ALTERNATE PATH)

JPM Number: LLOJPM0754 Revision Number: 000 Date: _ _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLO..IPM0754, Revision 000 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure Rev: - -

Procedure _ _ _ _ _ _ _ __ Rev: - -

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate 11 . If the J PM cannot be performed as written with proper responses, then revise the ..IPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 2 of 10

LLOJPM0754, Revision 000 REVISION RECORD (Summary)

1. NtA Revision 000 SIMULATOR SETUP INSTRUCTIONS SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 3 of 10

LLOJPM0754, Revision 000 SIMULATOR SETUP INS"rRUCTIONS

1. Reset to IC that supports removal of 1 RFPT, Rx Power z 60%.

INITIAL CONDITIONS:

1. Unit 1 is at % Power

2. "1 C" RFPT is in Standby in accordance with S06.1.A U/1

3. "1 C" RFPT has been in Standby at 2300 RPM for 60 minutes

4. Minimum Recirculation Flow established in Auto Mode per S06.0.A U/1

5. Lube Oil Cooler Outlet temperature is 113°F

6. An RO is stationed at the Reactor Recirc Pump Controls at 10C602

7. All S06.1 .C U/1 Prerequisites are complete for placing the 1C Reactor Feed Pump in service.

8. FWLCS is operational

9. FWLCS sequence was initiated, and initiation failed.

TASK STANDARD:

"1 C" RFP in Standby due to high vibration condition.

INITIATING CUES:

You are directed by Shift Supervision to MANUALLY place the "1 C" Reactor Feed Pump in service from Standby per S06.1.C U/1. Procedure is complete up to and including step __,

continue at step __.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 4 of 10

LLOJPM0754, Revision 000 JPM

SUMMARY

Operator's Name:,_ _ _ _ _ _ _ _ _ _ _Job

Title:

O SED 0 SM OSRO ORO o STAll A 0 OTHER JPM

Title:

MANUALLY PLACE 3RD RFP IN SERVICE (ALTERNATE PATH)

JPM Number: LLOJPM0754 Revision Number: 000 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 295001 A4.02 3.9/3.7 Suggested Testing Environment: Simulator Alternate Path: L8JYes ONo SRO Only: OYes L8JNo Time Critical: OYes L8JNo Reference(s): Procedure S06.1.C U/1 Rev: 14 Procedure S06.2.C U/1 Rev: 10 Procedure 506.0.E U/1 Rev: 10 Actual Testing Environment: L8J Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate L8J Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this ,JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: -----

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 5 of 10

LLOJPM0754, Revision 000 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. ENSURE the following: The Initial conditions are Oncoming Feed Pump has referenced to verify that the been adequately warmed. "1 C" RFP has been adequately warmed 1.a HV-006-108C, "1C" RFP HV-006-1 08C is verified Disch Vlv is closed for the closed.

oncoming RFP 1.b HIC-006-106C, "C" RFP Min HIC-006-106C is verified in Flow Control in AUTO for the AUTO oncoming RFP

2. IF 1A RFP is being placed IN N/A SERVICE, "rHEN ENSURE HV-006 138A, "1A RFP BPV, is closed.

3. IF third RFP is being placed IN SERVICE THEN PERFORM the following:

3.a REFER TO current P-1 edit FLLLP is verified to be <0.92 AND VERIFY FLLLP is <0.92

3.b ACCESS screen FW LC_O1, Screen FWLC_01 is Process Overview, at FWLCS accessed Operator Station

3.c SELECT blue bordered box FLLLP <0.92 Box is outlined next to "Reset" in FLLLP in white

<0.92 Dialog Box until it is outlined in white AND then release.

3.d SELECT Activate" (D4) Activate" (D4) Dialog Key is Dialog Key selected SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 6 of 10

LLOJPM0754, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number 3.e AND VERIFY box next to FLLLP <0.92 Dialog Box is "Reset" in FLLLP <0.92 solid blue with a white circle Dialog Box turns solid blue in the center.

with a white circle in the center.

4. PLACE FIC-M 1-1 R601 C, IIC FIC-M1-1 R601C "C" RFPT RFPT Speed Controller" Speed Controller" (FEED (FEED PUMP A(B, C), in PUMP C) in IIAUTO "AUTO II for oncoming RFP

5. IF PMS Computer Point N/A KOOONSS (K001 NSS, K002NSS) has been substituted, THEN RESTORE per RT-6 038-800-1.

QUE: Another operator will perform RT-6-038-800-1

6. OPEN HV-006-108A(B,C), HV-006-108C, "1C" RFP "1A(B,C) RFP Disch Vlv" Disch Vlv Opened (FEED, DISCH A(B,C>>, for oncoming RFP at panel 10C651 6.a AND VERIFY FWLCS RPV level monitored maintains RPV level

7. VERIFY the following N/A automatic actions:

7.a Oncoming RFPT speed rises Oncoming RFPT speed rises, until oncoming RFP discharge RFP discharge pressure is pressure is nominal 10 psig nominal 10 psig below RPV below RPV pressure pressure 7.b WHEN oncoming RFP Oncoming RFP begins discharge pressure nominal feeding RPV 10 psig below RPV pressure, THEN oncoming RFPT speed slowly rises until oncoming RFP begins feeding RPV !

8. VERIFY oncoming AND Oncoming AND running running RFP(s) are RFP(s) are maintaining RPV maintaining RPV level level SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 7 of 10

LLOJPM0754, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number Alternate Path Starts Now:

9. Respond to Annuciators: NOTE: 107 ANNs for Vibration Alarm and Danger

107 REACTOR 1-2, will only come in once and Vibration Alarm Alert remain in alarm

107 REACTOR 1-3, (trigger 2 and 3 keep alarms Vibration Alarm Danger on once they are received)

102 FEED C-2, 1C RFPT HI Vibration 9a. Monitor RFPT vibration levels Monitor Vibration levels on on Vibration Monitoring VMS System (VMS) AND DAS terminals.

9b. IF RFPT vibration on BOTH Candidate lowers speed by:

VMS probes (X& Y) on a bearing are >5 mils, Manual (MAN) pushbutton on THEN raise/lower RFPT FIC-M1-1R601C, RFPT speed to clear HI VIBRATION Speed Controller in MANUAL alarm by performing one of the following: OR HS-006-149C, 1C RFPT

Raising/lowering RFPT Speed Cont. SW speed using FIC-MI 1R601 C, RFPT Speed Controller in MANUAL OR

HS-006-149C, "1C RFPT Speed Cont. SW" (MSC) per S06.0.E U/1.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 8 of 10

LLOJPM0754, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number 9c. IF RFPT vibration on BOTH Identify when vibration on VMS probes (X&Y) on a BOTH VMS probes bearing bearing are >8 mils, are >8 mils, transition to take THEN lower Rx power per RFP out of service.

GP-3 OR GP-5 Appendix 2, as applicable, to within the capability of the remaining RFP(s) AND remove 1C RFPT from service per SOS.2.C U/1.

Que: If asked if reactor power needs to need to be lowered, respond as CRS "Rx power is within the capability of the remaining RFPs

10. Remove 1C RFPT from service per SOS.2.C U/1 Evaluator note: Candidate may elect to use either of the flowing to remove the RFP from service:

FWLCS Semi-Automatic Sequence

Manually Removing RFP From Service If candidate elects to perform FWLCS Semi-Automatic Sequence provide the follow Que:

The FWLCS Semi-Automatic for Removing 1C RFP from service to Standby initiation has failed

FWLCS is operational

Supervision directs you to use the manual method of removing a RFP from IN SERVICE to IN STANDBY

11. ENSURE HIC-00S-10SC, lie HIC-OOS-10SC in auto RFP Min Flow Control"(FLOW), for offgoing RFP in "AUTO" OR minimum flow requirements for offgoing RFP are being met in accordance with SOS.O.A U/1, Manual Adjustment Of Reactor Feed SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 9 of 10

LLOJPM0754, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number Pump Minimum Recirculation Flow.

11.a For RFPs remaining IN FIC-M1-1 RS01 C, in AUTO SERVICE, VERIFY FIC-M1- Sufficient maneuvering room 1RS01A(B,C). "A(B,C) available.

RFPT Speed controller" (FEED PUMP, A(B,C), S),

in "AUTO" AND sufficient maneuvering room available.

11.b PLACE FIC-M1-1RS01C, "C FIC-M1-1RS01C in Manual RFPT Speed Controller" in "Manual" (MAN).

11.c PERFORM the following: N/A 11.c.1 IF while executing Step, N/A the discharge check valve for the offgoing RFP cycles open/closed,THEN continuously REDUCE the speed of the offgoing RFPT using FIC-M1 1RS01 C until the discharge check valve for the offgoing RFP remains closed AND NOTIFY SSV.

11.c.2 Slowly LOWER the FIC-M1-1RS01C used to speed of the offgoing slowly lower speed to RFPT to IN STANDBY approximately 2300 rpm using FIC-M1-1 RS01C, "C RFPT Speed Controller" 11.d VERIFY HV-00S-105C, "1C HV-00S-1 05C closed RFP Disch Chk Vlv" is closed at panel 1OCS51 .

CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time:

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 10 of 10

INITIAL CONDITIONS:

Unit 1 is at % Power

"1 C" RFPT is in Standby in accordance with S06.1.A U/1

"1 C" RFPT has been in Standby at 2300 RPM for 60 minutes

Minimum Recirculation Flow established in Auto Mode per S06.0.A U/1

Lube Oil Cooler Outlet temperature is 113°F

An RO is stationed at the Reactor Recirc Pump Controls at 10C602

All S06.1.C U/1 Prerequisites are complete for placing the 1C Reactor Feed Pump in service.

FWLCS is operational

FWLCS sequence was initiated, and initiation failed.

INITIATING CUES:

You are directed by Shift Supervision to MANUALLY place the "1C" Reactor Feed Pump in service from Standby per S06.1 .C u/1. Procedure is complete up to and including step __,

continue at step _ _.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Transfer HPCI From Pressure Control Mode to Level Control Mode, Alternate Path JPM Number: LLOJPM0756 Revision Number: 000 Date: _ _ _ _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLO..fPM0756, Revision 000 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM re'flects the current revision:

Procedure Rev:

Procedure _ _ _ _ _ _ _ __ Rev:

Procedure Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 2 of 8

LLO...IPM0756, Revision 000 REVISION RECORD (Summary)

1. N/A SIMULATOR SETUP INSTRUCTIONS

1. Reset simulator to IC 17

2. Scram the reactor and close the MSIVs

3. Start HPCI and RCIC

4. Trip condensate pumps by closing Condensate Pump Discharge Valves

5. Establish HPCI in Pressure Control

6. Establish level approximately 20" with RCtC (no initiation signal for HPCI)

7. Load the following:

TRIGGERS:

NONE SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 3 of 8

LLOJPM0756, Revision 000 INITIAL CONDITIONS:

1. Reactor Scram has occurred on an inadvertent closure of all MSIVs

2. No Condensate pumps are available

3. HPCI and RCIC started on low reactor level

4. HPCI is in pressure control

5. RCIC was controlling level but recently it tripped. The trip cannot be reset.

6. Another Operator is controlling Reactor pressure with SRVs TASK STANDARD:

Place HPCI in Injection Mode, and respond to failure of suction valves to swap to suppression pool, by opening valves.

INITIATING CUE:

Shift Supervision directs you to transfer HPCI from pressure control mode to injection mode using S55.7. A, "Transfer of HPCI from Pressure Control Mode to Injection Mode and Back",

to restore and maintain reactor level between 12.5" and 54" Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 4 of 8

LLOJPM0756, Revision 000 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _Job

Title:

D SED 0 SM DSRO 0 RO o STNIA 0 OTHER JPM

Title:

Transfer HPCI From Pressure Control Mode to Level Control Mode, Alternate Path JPM Number: LLOJPM0756 Revision Number: 000 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 206000 A4.04 3.7/3.7 Suggested Testing Environment: Simulator Alternate Path:1:8J Yes o No SRO Only: DYes No Time Critical: DYes I:8J No Reference(s):

Procedure: S55.7.A, Transfer of HPCI From Pressure Control Mode to Injection Mode and Back Rev 08 Procedure: ARC-117 -A3, Condensate Storage Tank LO Levell Suction Transfer Rev 00 Actual Testing Environment: I:8J Simulator 0 Control Room 0 In-Plant o Other Testing Method: 0 Simulatel:8J Perform Estimated Time to Complete: 15 minutesActual Time Used: _ _ minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? oNo oYes The operator's performance was evaluated against standards contained within this JPM and has been determined to be: 0 Satisfactory o Unsatisfactory Comments:

Evaluator's Name: ______________________ (Print)

Evaluator's Signature: _________________ Date: _ _~_ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 5 of 8

LLOJPM07S6, Revision 000 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number Evaluators note, the following is from:

SSS.7.A Transfer of HPCI From Pressure Control Mode to Injection Mode and Back, Transfer From Pressure Control Mode to Injection Mode Section.

Driver Note: Maintain Reactor pressure between 900 and 10S0 by manually opening an SRV

1. PLACE FIC-S5-*R600, "HPCI FIC-SS-1 R600 "HPCI Pump Pump Discharge Flow Discharge Flow Controller" Controller" (FL), in placed in manual "MANUAL."

2. REDUCE HPCI Turbine Speed reduced to speed to approximately 22S0 approximately 22S0 RPM rpm

3. CAUTION: Prolonged N/A operation at or near min flow may cause HPCI Pump degradation.

4. CLOSE HV-SS-*FOOa, "HPCI HV-SS-1 FOOa, "HPCI Test Test Loop Shutoff" (TEST Loop Shutoff" closed ISOL).

S. OPEN HV-SS-*F10S, "HPCI HV-S5-1F10S, "HPCI Pump Pump Discharge PCIV" (TO Discharge PCIV" opened MAIN FEED A), to inject through Feedwater System.

6. IF required to inject through N/A Core Spray System, THEN throttle OPEN HV-5S-*F006, "HPCI Pump Discharge Valve" (INJECTION).

Cue: If Asked:

Injection through the Core Spray System is not required SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 6 of a

LLOJPM0756, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

7. ADJUST FIC-55-*R600, FIC-55-*R600, "HPCI Pump "HPCI Pump Discharge Flow Discharge Flow Controller Controller" (FL), to achieve adjusted based on Reactor desired flow. level

8. IF desired FIC-55-1 R600 setpoint is AND setpoint is matched to matched to actual flow, actual flow, and placedJn "AUTO."

THEN PLACE FIC-55-*R600 in "AUTO."

ALTERNATE PATH BEGINS HERE Activate Trigger 1 to Simulate Low CST Level

9. Respond to ANN: N/A HPCI 117, A3 CONDENSATE STORAGE TANK LO LEVEU SUCTION TRANSFER 9.a AUTOMATIC ACTIONS: Determine Automatic action HPCI pump suction did not occur and Report to transfers from CST to CRS Suppression Pool:

Valves HV-55-1 F042 AND HV-55-1 F041 open.

Valve HV-55-1 F004 closes.

CUE:

Outside EO Reports, a tornado significantly damaged the Unit 1 CST and retaining wall.

RO Reports CST Level is 2.1 feet down slow IF NEEDED:

CRS direct you to take appropriate action to ensure HPCI remain in operation for RP injection.

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 7 of 8

LLOJPM0756, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

9.b Take action to swap HPCI Open HV 1 F041 and suction to Suppression Pool verify:

HV-55-1 F042 OPEN

HV-55-1 F004 closes CUE: You have met the termination criteria for the ..IPM.

JPM Stop Time: _ __

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 8 of 8

LLOJPM0756, Revision 000 INITIAL CONDITIONS:

Reactor Scram has occurred on an inadvertent closure of all MSIVs

No Condensate pumps are available

HPCI and RCIC started on low reactor level

HPCI is in pressure control

RCIC was controlling level but recently it tripped. The trip cannot be reset.

Another Operator is controlling Reactor pressure with SRVs INITIATING CUE:

Shift Supervision directs you to transfer HPCI from pressure control mode to injection mode using S55.7. A, "Transfer of HPCI from Pressure Control Mode to Injection Mode and Back", to restore and maintain reactor level between 12.5" and 54" SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure PRIMARY CONTAINMENT N2 MAKEUP JPM Number: LLOJPM0523 Revision Number: 001 Date: _ _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

op£ns Representative Date Approved By:

Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0523, Revision 001 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to ..IPM usage, revalidate JPM using steps 9 and 12 below.

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

_.~ __ 2. Knowledge and Abilities (KIA) references are included.

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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{s) referenced by this JPM reflects the current revision:

Procedure Rev:

Procedure Procedure Rev:

Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the ..IPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 2 of 7

LLOJPM0523, Revision 001 REVISION RECORD (Summary)

1. Revision 001, Format change, no rev markers used SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to IC-17, and take out of freeze

2. Use Malfunction "MPC473, Drywell Air Leak" to reduce drywell pressure to below 0.2 psig. Then remove the malfunction.

INITIAL CONDITIONS:

1. Drywell pressure is _ psig due to normal losses

2. All prerequisites for S57.3.B are completed

3. Makeup N2 is available and lined up for low 'flow service per S57.B.A TASK STANDARD:

Establish makeup flow to drywell and monitor drywell pressure INITIATING CUES:

You are directed by Shift Supervision to raise drywell pressure to between 0.2 and 0.7 psig per S57.3.B Section 4.4.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 3 of 7

LLOJPM0523, Revision 001 JPM

SUMMARY

Operator's Name:._ _ _ _ _ _ _ _ _ _ _Job

Title:

O SED 0 SM OSRO ORO o STAliA 0 OTHER JPM

Title:

PRIMARY CONTAINMENT N2 MAKEUP JPM Number: LLOJPM0523 Revision Number: 001 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 223001 A4.10 3.2/3.2 Suggested Testing Environment: Simulator Alternate Path: OYes L8lNo SRO Only: OYes L8lNo Time Critical: OYes L8lNo Reference(s): Procedure S57.3.8 Rev: 44 Actual Testing Environment: L8l Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate L8l Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? OYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature:_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 4 of 7

LLOJPM0523, Revision 001 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain a copy of S57.3.B. S57.3.B Obtained

2. REFER TO S57.8.A, Placing IF A 1722710 is not yet or removing Liquid resolved, Direct EO to OPEN N2Vaporizing System In X-25 to two turns open (From) Service and Changing Flow Modes, AND ENSURE Make-up N2 available AND N2 Supply lined up for low flow service.

IF A1722710 is not yet resolved, THEN OPEN X 25 to two turns open Cue: IF A1722710 is not yet resolved, Report:

EO Reports X-25 has been opened 2 turns

3. PLACE FIC-57-119, FIC-57-119, "Nitrogen Flow "Nitrogen Flow Controller" Controller" (FL), in (FL), in "MANUAL" AND SET "MANUAL" AND SET to zero.

to zero.

4. ENSURE HSS-57-196, 10S205," in "STANDBY "H 2/0 2 Analyzer 10S206," in "STANDBY."

5. ENSURE HSS-57-126, 10S205," in "STANDBY "H 2/0 2 Analyzer 10S205," in "STANDBY."

6. PLACE HS-57-153 to HS-57-153 closed "CLOSE."

7. PLACE HS-57-187 to HS-57-187 closed "CLOSE."

INSTRUCTOR NOTE:

Activate Remote Function RPC044, Manual Stop Valve 57-1088 to close 57-1088 after being requested in the next step SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 5 of 7

LLOJPM0523, Revision 001 ELEMENT STANDARD SAT UNSAT Comment Number

8. CLOSE 57-1088, "N2 Makeup EO directed to close 57-1088

& Atm Samp Return To Supp or perform S57.3.8 Step Pool Line Maint." -

CUE: Report as EO (as appropriate)

"57 -1088 is closed" OR

"S57.3.8 Step _ _

is complete"

9. Slowly throttle OPEN HV HV-57-116 throttled open and 116, N2 MAKE-UP for 5 stopped after approximately 5 seconds AND PLACE in seconds "PULL TO STOP" position.

10. VERIFY N2 flow using XR XR-57 -119 red pen indicates 119, NITROGEN PURGE, flow (red pen).

11. THROTTLE HV-57-116 for HV-57-116 throttled open desired flow rate. with flow indicating on XR-57 119

12. RECORD start time AND NA Drywell pressure in RO's Unified Log, using term "N2" contained in entry for System Manager's search.

Note: The Unified Log is not simulated.

CUE: Unified Log entry has been made SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 6 of 7

LLOJPM0523, Revision 001

13. MONITOR PI-57-121, Drywell pressure monitored (PX(NR>> on one or more of the OR PMS 057 DRYWELL following PRESSURE

PI-57-121, (PX(NR>>

OR PMS 075 OW/POOL OR PRESS VALIDATION PI-57

PMS 057 DRYWELL 121 (narrow range).

PRESSURE PMS 075 OW/POOL PRESS VALIDATION PI-57-121 (narrow range).

CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time: _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 7 of 7

INITIAL CONDITIONS:

Drywell pressure is _ psig due to normal losses

All prerequisites for S57.3.B are completed

Makeup N2 is available and lined lip for low flow service per S57.S.A INI1"IATING CUES:

You are directed by Shift Supervision to raise drywell pressure to between 0.2 and 0.7 psig per S57.3.B Section 4.4.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Transfer D13 From 101 to 201 (Alternate Path)

JPM Number: LLOJPM0519 Revision Number: 003 Date: 11/02/2009 Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0519, Revision 004 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the J PM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

I Page 2 of 9

LLOJPM0519, Revision 004 REVISION RECORD (Summary)

1. Revision 004, updated to correct typos and add additional simulator setup items SIMULATOR SETUP INSTRUCTIONS

1. Place RED004, Safeguard Bus 201 Tap Changer Mode Switch, to MANUAL

2. Start and Load to 2000 kw D13 DIG per S92.1.0, Local And Remote Manual Startup of a Diesel Generator

3. Change Placards for 11-1010 and 11-2010 to green

4. Insert the following malfunctions and overrides:

5. Insert the following trigger SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

I Page 3 of 9

LLOJPM0519, Revision 004 INITIAL CONDITIONS:

1. All prerequisites for 4 KV transfer are completed

2. TS 3.8.1.1 requirements are met for Unit 1 AND Unit 2

3. S92.1.N, Diesel Generator Set Up for Automatic Operations and S92.9.N Routine Inspection of the Diesel Generators have been completed for D13 Diesel Generator

4. D13 has been Started, Synchronized and Loaded to 2000 kW per S92.1.0, Local and remote manual Startup of a Diesel Generator

5. ESW is Aligned to Support Diesel Generator operation

6. An EO is standing by at the D13 Diesel Generator TASK STANDARD:

4KV bus transferred from 101 Safeguard Bus Feed to the 201 Safeguard bus feed, and Diesel Generator secured due to Lube Oil High Temperatrue.

INITIATING CUE:

You are directed by Shift Supervision to transfer 4KV Safeguard Bus from 101 Safeguard Bus Feed to the 201 Safeguard bus feed using D13 Diesel Generator per S92.6.A.

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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. marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

I Page 4 of 9

LLOJPM0519, Revision 004 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _,Job

Title:

O SED 0 SM OSRO 0 RO o STAIIA 0 OTHER JPM

Title:

Transfer D13 From 101 to 201 (Alternate Path)

JPM Number: LLOJPM0519 Revision Number: 003 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 264000 A4.04 3.7/3.7 Suggested Testing Environment: Simulator Alternate Path: [glYes ONo SRO Only: OYes [glNo Time Critical: OYes [glNo Reference(s):

Procedure S92.6.A, Transfer of a 4KV Safeguard Bus from 101 Safeguard Feed to 201 Safeguard Feed and Vice Versa Rev: 18 Actual Testing Environment: [gl Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate [gl Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? OYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

I Page 5 of 9

LLOJPM0519, Revision 004 I JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain a copy of S92.6.A Student obtains a copy of S92.6A

2. VERIFY all prerequisites "all prerequisites satisfied" satisfied. provided in Initial Conditions

3. VERIFY procedure being Verified on D13.

performed on correct unit/train.

4. MAINTAIN applicable Safeguard Transformer Safeguard Transformer Feeder Feeder Ammeter Close to Ammeter as close to zero as Zero, DIG Output breaker possible without tripping Diesel does not trip.

Generator Output breaker by adjusting 165A(B,C,D)G501/CS, "Diesel Generator Speed Governor Control Switch" (SPEED GOVERNOR)

AND 170A(B,C,D)6502 "Diesel Generator Voltage Regulator" (VOLTAGE REGULATOR).

5. OPEN 101 Feeder Breaker (101 101 Feeder Breaker SAFEGUARDS) to appropriate indicates OPEN and diese~

4kV Safeguard Bus. generator maintains proper Frequency and Voltage

6. PLACE 143-AX103 "Tap 143-AX103 "Tap Changer" Changer" (SELECT) in "AUTO" (SELECT) in "AUTO at panel 1A-C661 .

SRRS: 3D.105 (when utilized for operator initial or continuing training)

I Page 6 of 9

LLOJPM0519, Revision 004 ELEMENT STANDARD SAT UNSAT Comment Number

7. Placing 143-BX103 "Tap N/A Changer" (SELECT) in "MANUAL" makes the 20 bus TS 3.8.1.1 requirements are offsite source INOPERABLE.

met for Unit 1 AND Unit 2.

ENSURE TS 3.8.1.1 was provided in Initial requirements are met for Unit 1 Conditions AND Unit 2.

8. PLACE 143-BX103 "Tap N/A Changer" (SELECT) in "MANUAL" at panel 2D-C661.

Que: 143-BX103 "Tap Changer" (SELECT) is in "MANUAL"

9. INSERT Synchroscope Switch Synchroscope Switch handle into synchroscope switch (SYNC) for D13 201 4kV (SYNC) for appropriate 201 4kV Bus Feeder breaker "ON."

Bus Feeder breaker AND PLACE to "ON."

10. OBSERVE proper operation of N/A appropriate synchroscope (SYSTEM) by verifying the following: .

10a. Synchroscope rotating. Synchroscope rotating 1Ob. WHEN synchroscope is at 180 At 180 degrees both lights degrees, THEN both lights are are fully bright fully bright.

10c. WHEN syncrlroscope is at 0 At 0 degrees both lights are degrees, THEN both lights are off off.

11. ADJUST engine speed using Synchroscope is rotating 165-A(B,C,D)G501/CS, "Diesel slowly in the SLOW Generator Speed Governor direction (counterclockwise)

Control Switch" (SPEED GOVERNOR) until synchroscope is rotating slowly in the SLOW direction (cou nterclockwise).

SRRS: 30.105 (when utilized for operator initial or continuing training)

I Page 7 of 9

LLOJPM0519, Revision 004 ELEMENT STANDARD SAT UNSAT Comment Number

12. ADJUST diesel generator Synchronizing Running voltage using 170 Voltmeter RUNNING is A(B,C,D)G502/CS, "Diesel slightly higher (1-5 Volts)

Generator Voltage Regulator than Synchronizing Switch" (VOLTAGE Incoming Voltmeter REGULATOR) until INCOMING "Synchronizing Running Voltmeter," RUNNING is slightly higher than "Synchronizing Incoming Voltmeter," INCOMING

13 WHEN synchroscope 201 Feeder Breaker (201 (SYSTEM) is within 3 degrees Safeguards) closed to before 12 O'clock, THEN appropriate 4kV Safeguard CLOSE 201 Feeder Breaker Bus (201 Safeguards) to appropriate 4kV Safeguard Bus

14. TURN synchronizing switch to Synchronizing switch is "OFF" "OFF" Alternate Path Starts Now:

The 013 D-G Trouble alarm will annunciate shortly after the 013-201 Breaker is closed.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

I Page 8 of 9

LLOJPM0519, Revision 004 ELEMENT STANDARD SAT UNSAT Comment Number

15. Respond to the D 13 D-G Dispatch an EO to Trouble Alarm investigate Trouble Alarm Cue: The EO at D13 DIG reports:

The alarm is due to a generator lube oil high temperature. It is reading 205 degrees F and rising slowly.

The local ARC, (1CC514 C-1), states: consider tripping engine to avoid possible serious damage NOTE: Provide the following Cue ONLY if candidate requests direction from SSVN Cue: The CRS directs you to place the D13 DIG in a safe condition.

EVALUATOR NOTE The following steps are from S92.2.N, Step 4.2, Rapid Shutdown Due To Alarm Or Abnormal Condition

16. PLACE Diesel Generator Diesel Generator Breaker Breaker to "TRIP" control switch taken to "TRIP" 16.a AND "PULL TO LOCK" Diesel Generator Breaker control switch taken to "PULL TO LOCK"

17. PLACE 101-CG501/CS, 101-CG501/CS, "Diesel "Diesel Generator Control," to Generator Control," switch "STOP". taken to "STOP" 17.a AND "PULL TO LOCK". 101-CG501/CS, "Diesel Generator Control," switch taken to "PULL TO LOCK".

CUE: You have met the termination criteria for this JPM JPM Stop Time _ _ _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 9 of 9

LLOJPM0519, Revision 004 INITIAL CONDITIONS:

7. All prerequisites for 4 KV transfer are completed

8. TS 3.8.1.1 requirements are met for Unit 1 AND Unit 2

9. S92.1.N, Diesel Generator Set Up for Automatic Operations and S92.9.N Routine Inspection of the Diesel Generators have been completed for D13 Diesel Generator

10. D13 has been Started, Synchronized and Loaded to 2000 kW per S92.1.0, Local and remote manual Startup of a Diesel Generator

11. ESW is Aligned to Support Diesel Generator operation 12.An EO is standing by at the D13 Diesel Generator INITIATING CUE:

You are directed by Shift Supervision to transfer 4KV Safeguard Bus from 101 Safeguard Bus Feed to the 201 Safeguard bus feed using D13 Diesel Generator per S92.6.A.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Control Rod Exercise Test (ST-6-107-760-1)

JPM Number: LLO"IPM0107 Revision Number: 002 Date: _ _ _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLO..IPM0107, Revision 002 JOB PERFORMANCE MEASURE VALIDA-nON CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 and 12 below.

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

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

3. Performance location speci'fied. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure _ _ _ _ _ _ _ __ Rev: --

Procedure Rev: - - -

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 2 of 8

LLOJPM0107, Revision 002 REVISION RECORD (Summary)

1. Revision 2, Format changed (no rev markers used), No longer identified as Alternate path (based on procedure revisions)

SIMULATOR SETUP INSTRUCTIONS

1. Provide Copy of ST-6-107-760-1, AND Control Rod Position Report

2. Reset Simulator to IC that supports test

3. Ensure Rod Pattern supports Control Rod 14-55 at position 48

4. Insert The following:

INITIAL CONDITIONS:

1. Control Rod Exercise Test ST-6-107-760-1 is required for rod 14-55

2. No fuel defects exist

3. Reactor Engineering has determined that inadvertent double notching of rod 14-55 is acceptable and a power reduction is not required.

4. All prerequisites are satisfied for ST-6-1 07-760-1, and S73.1.A TASK STANDARD(S):

Control Rod 14-55 is inserted at least one notch and returned to position 48 in accordance with ST 107 -760-1 .

INITIATING CUE:

Shift Supervision directs you to perform Control Rod Exercise Test ST-6-1 07-760-1, step __

for control rod 14-55.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 3 of 8

LLO..JPM0107, Revision 002 Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 4 of 8

LLOJPM0107, Revision 002 JPM

SUMMARY

Operator's Name:,_ _ _ _ _ _ _ _ _ _ _J,ob

Title:

O SED 0 SM OSRO ORO o STAIIA 0 OTHER JPM

Title:

Control Rod Exercise Test (ST-6-107-760-1 JPM Number: LLOJPM0107 Revision Number: 002 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 201003 A2.01 3.4/3.6 Suggested Testing Environment: Simulator Alternate Path: OYes [8JNo SRO Only: OYes [8JNo Time Critical: OYes [8JNo Reference(s): Procedure ST-6-107-760-1 Control Rod Exercise Test Rev: 66 Actual Testing Environment: [8J Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate [8J Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? OYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 5 of 8

LLOJPM0107, Revision 002 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Provide a current copy of ST- N/A 6-107-760-1 , Control Rod Exercise marked up as Partial Procedure

2. PERFORM the following: Control Rod 14-55 is at position VERIFY on the 4 Rod Display 48 that the selected Rod indicates position 48.

3 IF 48 is not being indicated on N/A the Four Rod Display, THEN VERIFY full-out indication is present on the Full Core Display AND PMS.

4 INSERT the control rod one Insert pushbutton depressed notch.

5. VERIFY on the Four Rod Operator recognizes that rod Display that the selected Rod indicated position 46 indicates position 46

6. IF any control rod begins to Operator recognizes that rod insert AND settles back to moved to position 46 and position 48 THEN PERFORM then returned to, and settled the following. position 48.

Driver Note: after first control rod insertion is attempted reload scenario file (this reloads CR stuck after 2 seconds, rod will not reach position 46)

7 ATTEMPT another single Insert pushbutton depressed notch insert to position 46. I 8 !E.successful THEN GO TO Operator recognizes that rod step moved to position 46 and then returned to position 48.

9. IF not successful THEN N/A I

PERFORM the following:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 6 of 8

LLOJPM0107, Revision 002 ELEMENT STANDARD SAT UNSAT Comment Number 9a. IF control rod does not Covered in initial conditions.

indicate notch position 46 due to insufficient control rod movement, THEN REVIEW evaluation provided by Reactor Engineering per step 2.8 to determine if it is acceptable to insert the rod to position 44 due to an inadvertent double-notching without a power reduction.

If candidate wishes to verify then:

CUE: RE has determined that inadvertent double-notching acceptable 9b. IF a power reduction is Covered in initial conditions required, THEN REDUCE core power in accordance with GP-5 Appendix 2, Section 3.1, using core flow per Reactor Maneuvering Shutdown Instructions (RMSI) to required power level. AND GO TO step 4.4.1.1.e.4.

If candidate wishes to verify then CUE: RE has determined that power reduction is not required

10. RAISE CRD System Drive CRD System drive pressure pressure by 25 psid, not to is elevated by ~25 psid not to exceed 350 psid. exceed 350 psid

11. ATTEMPT a single notch Insert pushbutton depressed insert.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 7 of 8

LLO"IPM0107, Revision 002 ELEMENT STANDARD SAT UNSAT Comment Number

12. IF the rod double notches to The control rod either latches position 44, THEN at position 46 or double WITHDRAW the rod to notches to position 44 and position 48 then is withdrawn to position 48 CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time: _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 8 of 8

INITIAL CONDITIONS:

Control Rod Exercise Test ST-6-107-760-1 is required for rod 14-55

No fuel defects exist

Reactor Engineering has determined that inadvertent double notching of rod 14-55 is acceptable and a power reduction is not required.

All prerequisites are satisfied for ST-6-107-760-1, and S73.1 .A INI1"IATING CUE:

Shift Supervision di rects you to perform Control Rod Exercise Test ST-6-107-760-1, step for control rod 14-55.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Align RECW For Drywell Cooling (ALTERNATE PATH)

JPM Number: LLOJPM0757 Revision Number: 000 Date: _______

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0756, Revision 000 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 9 and 12 below.

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

2. Knowledge and Abilities (1</A) references are included.

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure _ _ _ _ _ _ _ __ Rev:

Procedure __________

Rev: -

9.

Procedure Verify cues both verbal and visual are free of conflict.

Rev: - -

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the J PM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 2 of 10

LLOJPM0756, Revision 000 REVISION RECORD (Summary)

1. N/A, Develop from 2008 ILT NRC JPM SIMULATOR SETUP INSTRUCTIONS Hang information tags on the following valves with the noted information:

HV-51-1 F080A, RHR Sample Line Downstream Isolation (SAMPLE OUTBOARD) ISO CLOSED

HV-51-1 F080B, RHR Sample Line Downstream Isolation (SAMPLE OUTBOARD) ISO CLOSED

HV-41-1F085, Main Steam Line Outboard Sample (DRAIN SAMPLE OUTBOARD) ISO CLOSED

HV-43-1 F020, Recirc Sample Line Outboard Isolation (SAMPLE) ISO CLOSED

1. Reset the Simulator to IC-17

2. Scram the reactor

3. Trip Both Recirc Pumps

4. A"ow FWLC to transfer to startup level control

5. Shutdown RWCU per S44.2.A

6. Setup the following:

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 3 of 10

LLOJPM0756, Revision 000 INITIAL CONDITIONS:

Unit 1 is in OPCON 4.

OW Chilled Water has been lost due to trips on both Orywell Chiller Units

OW temperature is 150°F and rising.

The CRS has entered OT-101, and T-102

RWCU has been shutdown per S.44.2.A, Reactor Water Cleanup Shutdown.

Administrative Clearances have been applied for valves in section 4.2.4 TASK STANDARD:

Leaking OW Loop A is isolated from RECW. RECW is aligned to cool the drywell using OW Loop B.

INITIATING CUE:

You are directed by Shift Supervision to align RECW operation to cool the drywell, using A Loop first per S13.6.0.

Locked Valve Log entries have been authorized for required beaker closures SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 4 of 10

LLO..IPM0756. Revision 000 Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed 'from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 5 of 10

LLOJPM0756, Revision 000 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _Job

Title:

O SED 0 SM OSRO 0 RO o STAliA 0 OTHER JPM

Title:

Align RECW for Drywell Cooling JPM Number: LLOJPM0757 Revision Number: 000 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 400000 K1.02 3.213.4 Suggested Testing Environment: Simulator Alternate Path: ~Yes ONo SRO Only: DYes ~No Time Critical: DYes ~No Reference(s):

Procedure: 813.6.0, RECW Operation with Loss of Orywell Chilled Water Rev. 14 Rev 00 Actual Testing Environment: ~ Simulator 0 Control Room 0 In-Plant o Other Testing Method: 0 Simulate ~ Perform Estimated Time to Complete: 15 minutes Actual Time Used: _ _ minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes DNo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 6 of 10

LLOJPM0756, Revision 000 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain a current revision of Current revision of S13.6.D, RECW Operation With S13.6.D. Obtained Loss of Drywell Chilled Water

2. CLOSE HV-13-*02, Cooling HV 102 closed Water to Reactor Building Isolation (SUPPLY ISOL).

3. IF loss of instrument air prohibits N/A closure of HV-13-*02, SUPPLY ISOL,THEN CLOSE 13-*039, RECW Header Valve to RWCU Non-Regen Heat Exchanger.

4. Block CLOSE the following Place Information tags sample pOint isolation valves on

HV 51 *FOBOA

HV 51 1FOBOA

HV 51 *FOBOB

HV 51 1FOBOB

HV 41 *FOB5

HV 41 1FOB5

HV 43 *F020

HV 431F020

023-1246 Directs EO to block:

CUE: After 1 minute report:

EO reports 023-1246 is closed

023-1246 Activate Trigger 1 to simulate closing D114 breakers

5. CLOSE the following breakers: Directs EO to close following breakers:

D*14-R-C-15 (124A)

D114-R-C-15

D*14-R-C-19 (124B)

D114-R-C-19

D*14-R-C-16 (125A)

D114-R-C-16

D*14-R-C-20 (1258)

D114-R-C-20 CUE: After 1 minute report:

EO reports:

D114-R-C-15

D114-R-C-19

D114-R-C-16

D114-R-C-20 SRRS: 3D.1 05 (when utIlized for operator InItIal or contInUIng tralnrng)

Page 7 of 10

LLOJPM0756, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

6. IF required THEN BYPASS N/A isolations per GP-8.5.

7. PLACE HSS-87-*21A(B), Loop HSS-87-121A in RE CLG Drywell Water Source Mode WTR placed position for Switch (LOOP), in liRE CLG LOOP A.

WTR" for loop to be supplied by Valves indicate flow path RECW AND VERIFY the open from RECW and following:

closed from Chill Water

Red indicating lights RECW IN verified.

AND RECW OUT Lit

Green indicating lights CHLD WTR IN AND CHLD WTR OUT Lit Valves verified open:

8. VERIFY Drywellisolation Loop A(B) (LOOP) red indicating lights

LOOP A HS-87-128 DRYWELL INLET AND

LOOP B HS-87-122 DRYWELL OUTLET Lit for loop to be supplied by RECW.

LOOP A HS-87-*28

LOOP B HS-87-*22 N/A

9. IF RECW flow is insufficient for adequate cooling, THEN PLACE standby RECW Heat Exchanger in service AND ALTERNATE PATH BEGINS HERE Activate Trigger 2 to Simulate RECW leak

10. Responds to RECW Head Tank Refer to ARC for Alarm level alarm. Panel 118 Window H-5, REAC ENCL COOLING WATER HEAD TANK HI/LO LEVEL.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 8 of 10

LLOJPM0756, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number Direct EO to check level 10.a Verify RECW Head Tank locally.

10T201 level locally using LG 13-101.

QUE: Report back as EO after 1 minutes

RECW Head Tank level is 35 inches and lowering approximately 1 inch per minute.

If asked, report that demin water supply valve LV-13-101 is fully opened.

When HSS-87-121 A is placed in the DWCW position, perform the following:

Restore P113-108 (RECW Header pressure indication) to normal over 2 minutes After 1 minute:

Toggle ANN 118 H5 (W Cooler Drain Flow) to OFF

Toggle ANN 115 85 (RECW Head tank level) to OFF

11. Recognizes likely leak location Isolate the leak from is on Loop A of Drywell Cooling RECW by placing HSS-and isolates Loop A Drywell 87-121A in the DWCW Cooling Loop from RECW. position.

Cue:

If necessary, CRS should ask applicant to identify the location of the leak and take necessary actions to isolate and to maintain the RECW system.

Cue: Report back as EO after 1 minutes

RECW Head Tank level is 36 inches going up slow.

Cue:

If necessary, direct applicant to continue with the procedure to establish drywell cooling.

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 9 of 10

LLOJPM0756, Revision 000 ELEMENT STANDARD SAT UNSAT Comment Number

12. IF other Drywell Chilled Water HSS-87-121B, Loop loop is needed, THEN PLACE Drywell Water Source HSS-87-*21 B(A), Loop Drywell Mode Switch (LOOP)

Water Source Mode Switch Placed in RE CLG WTR (LOOP), in RE CLG WTR AND position VERIFY the following:

Proper indicating lights

Red indicating lights verified RECW IN AND RECW OUT Lit.

Green indicating lights CHLD WTR IN AND CHLD WTR OUT Lit.

Dryweilisolation Loop B(A) (LOOP) red indicating lights DRYWELL INLET AND DRYWELL OUTLET Lit.

- LOOP A HS-87-*28

- LOOP B HS-87-*22 CUE: You have met the termination criteria for the JPM.

JPM Stop Time: _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 10 of 10

INITIAL CONOrnONS:

Unit 1 is in OPCON 4.

DW Chilled Water has been lost due to trips on both Drywell Chiller Units

DW temperature is 150°F and rising.

The CRS has entered OT-101, and T-102

RWCU has been shutdown per S.44.2.A, Reactor Water Cleanup Shutdown.

Administrative Clearances have been applied for valves in section 4.2.4 INITIATING CUE:

You are directed by Shift Supervision to align RECW operation to cool the drywell, using A Loop first per S13.6.D.

Locked Valve Log entries have been authorized for required beaker closures SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure MANUALLY ISOLATE THE REACTOR ENCLOSURE JPM Number: 0022 Revision Number: 003 Date:_I_I_

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

LLOJPM0022, Rev 003 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 9 and 12 below.

1. Task description and number, JPM description and number are identi'fied.

2. Knowledge and Abilities (K/A) references are included.

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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{s) referenced by this JPM reflects the current revision:

Procedure S76.8.8 Rev: 30 Procedure S76.9.A Rev: 21 Procedure GP-8.2 Rev: --=

8

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME !Instructor Date SME !Instructor Date SME !Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 Page 2 of 8

LLOJPM0022, Rev 003 REVISION RECORD (Summary)

1. Revision 003, reformatted, no rev markers used SIMULATOR SETUP INSTRUCTIONS

1. Reset simulator to IC 17

2. Verify the following INITIAL CONDITIONS:

Unit 1 is in OPCON1

Unit 1 Reactor Enclosure HVAC is tripped and cannot be restarted

RERS and SGTS are lined up for automatic initiation as per S76.1.C, SGTS and RERS Setup for Automatic Initiation

SGD-076-206-1, Unit 1 Rx Encl-SGTS Slide Gate Damper, (602-R12-313) is OPEN

Reactor Enclosure Secondary Containment is not extended to the Refuel Floor (HS-76 151 AlB and 152A1B, at 10C622 and 10C623 are in "NORMAL")

Reactor Enclosure temperature monitoring per S76.0.C, will be performed by an Equipment Operator

RERS and SGTS run times will be recorded by the PRO INITIATING CUES:

SSVN has directed a manual Rea eI . -be'~n Unit 1 from the MCR using the manual isolation pushbuttons per S76.8.~_se~~

TASK STANDARD: c'

Manual Reactor Enclosure Isolation initiated and Instrument Gas Isolation reset SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 Page30f8

LLOJPM0022, Rev 003 Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 Page 4 of8

LLOJPM0022, Rev 003 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ __

Job

Title:

0 SED OSM OSRO ORO o STAIIA o OTHER JPM

Title:

Manua.lly Isolate the Reactor Enclosure JPM Number: LLOJPM0022 Revision Number: 003 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 223002 A4.02 3.9/3.8 288000 A3.01 3.8/3.8 Suggested Testing Environment: Simulator Alternate Path: OYes IZ/No SRO Only: OYes IZ/No Time Critical: OYes IZ/No Reference(s): S76.S.8 Rev: 30 S76.9.A Rev: 21 GP-S.2 Rev: OS Actual Testing Environment: IZ/ Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate IZ/ Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? OYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature:,_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 PageS of8

LLOJPM0022, Rev 003 JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain current revision of Current revision of S76.8.8 S76.8.8, Initiation of Reactor obtained Enclosure or Refueling Floor Secondary Containment:

2. If desired, refer to S76.2.8, N/A Shutdown of Reactor Enclosure HVAC CUE: Reactor Enclosure HVAC is secured

3. PLACE HS-76-178A HVAC HS-76-178A HVAC ISOLATION A to "ISOLATION" ISOLATION A placed to "ISOLATION"

3a. PLACE HS-76-1788 HVAC HS-76-1788 HVAC ISOLATION 8 to "ISOLATION" ISOLATION 8 placed to "ISOLATION" 3b. Acknowledge annunciators N/A Cue: Annunciator response will be completed by the PRO

3c. DEPRESS and RELEASE Pushbuttons at 10C681 panel pushbuttons at 10C681 depressed and released 3d. Acknowledge annunciators N/A Cue: Annunciator response will be completed by the PRO

4. Record SGTS and RERS run N/A times in MCR Log Cue: The PRO will record SGTS I RERS run times EVALUATOR NOTE:

Direct Operator to reset PCIG without resetting RE HVAC per "GP-S.2 Manual Isolations"

5. Obtain current revision of GP- GP-8.2 obtained 8.2, Manual Isolations SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 Page 6 of8

LLOJPM0022, Rev 003 ELEMENT STANDARD SAT UNSAT Comment Number

6. PLACE white handled Any white handled handswitch on 10C601 to handswitch on 10C601 panel "OPEN" to "OPEN"

7a. PLACE HS-76-179A on HS-76-179A on 10C681 10C681 to "RESET" placed to "RESET"

7b. PLACE HV-59-129A to HV-59-129A placed to "CLOSE" "CLOSE"

7c. RETURN HS-76-179A to HS-76-179A returned to "AUTO" "AUTO"

7d. RETURN white handled White handled handswitch handswitch to its initial position returned to its initial position

7e. POSITION PCIG valves as HV-59 129A and HV-59 101 desired "OPEN" placed to "OPEN" HV-59-101 HV-59-129A Note: Listed PCIG valves may be opened when both "A" and "8" logics are reset

8. PLACE HV-57-104 OR HV HV-57-104 OR HV-57-114 114 to "OPEN" placed to "OPEN"

8a. PLACE HS-76-1798 on HS-76-1798 on 10C681 10C681 to "RESET" placed to "RESET"

8b. PLACE handswitches for the Handswitches for the following valves to "CLOSE following valves placed to HV-59-102 "CLOSE HV-59-1298 HV-59-102 HV-59-135 HV-59-1298 HV-59-131 HV-59-135 HV-59-131

8c. RETURN HS-76-1798 to HS-76-1798 returned to "AUTO" "AUTO"

8d. RETURN HV-57-104 OR HV- HV-57-104 OR HV-57-114 57-114 to its initial position returned to its initial position 8e. POSITION PCIG valves as desired SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 Page 70'8

LLOJPM0022, Rev 003 ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE:

Notify operator It is desired to perform the required valve alignment to place Instrument Gas in Service

9. To perform a PCIG restoration Operator opens the listed "OPEN" the following: PCIG valves HV-59-102 HV-59-131 HV-59-1298 HV-59-135 CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time: _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0022 Rev003 Page 8 0'8

LLOJPM0022, Rev 003 INITIAL CONDITIONS:

Unit 1 is in OPCON1

Unit 1 Reactor Enclosure HVAC is tripped and cannot be restarted

RERS and SGTS are lined up for automatic initiation as per S76.1.C, SGTS and RERS Setup for Automatic Initiation

SGD-076-206-1, Unit 1 Rx Encl-SGTS Slide Gate Damper, (602-R12-313) is OPEN

Reactor Enclosure Secondary Containment is not extended to the Refuel Floor (HS-76-151 AlB and 152A1B, at 10C622 and 10C623 are in "NORMAL")

Reactor Enclosure temperature monitoring per S76.0.C, will be performed by an Equipment Operator

RERS and SGTS run times will be recorded by the PRO INITIATING CUES:

SSVN has directed a manual Reactor Enclosure Isolation be initiated on Unit 1 from the MeR using the manual isolation pushbuttons per S76.8.B, section 4.4 SRRS: 30.105 (when utilized for operator initial or continuing training)

Limerick Generating Station Job Performance Measure BYPASSING AND REMOVING THE *A RPS AND UPS STATIC INVERTER FROM SERVICE JPM Number: 0203 Revision Number: 008 Date:

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0203, RevOOB 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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure Rev: --

Procedure _ _ _ _ _ _ _ __ Rev:

Procedure _ _ _ _ _ _ _ __

Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0203 RevOOB Page 2 of 10

LLOJPM0203, RevOOB REVISION RECORD (Summary)

Revision 008, minor non-technical correction SIMULATOR SETUP INSTRUCTIONS In-plant INITIAL CONDITIONS:

A RPS and UPS Static Inverter is in Service TASK STANDARD(S):

The *A RPS/UPS static inverter is bypassed and removed from service.

INITIATING CUE:

You are directed by Shift Supervision to bypass the __A RPS/USP static inverter and remove it from service per S94.2.A Briefing has been performed SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0203 RevOOB Page 3 of 10

LLOJPM0203, Rev008 Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this ...IPM. 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0203 RevOOB Page 4 of 10

LLOJPM0203, Rev008 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ __

Job

Title:

o SED o SM OSRO 0 RO 0 STAll A o OTHER JPM

Title:

BYPASSING AND REMOVING THE *A RPS AND UPS STATIC INVERTER FROM SERVICE JPM Number: LLO..IPM0203 Revision Number: 007 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 262002 K4.01 3.1 I 3.4 Suggested Testing Environment: In-Plant Alternate Path: OYes jgJNo SRO Only: DYes jgJNo Time Critical: DYes rgjNo Reference(s): Procedure S94.2.A By-Passing And Removing The *A Rps Ups Static Inverter From Service Rev: -1..Q Actual Testing Environment: 0 Simulator 0 Control Room jgJ In-Plant D Other Testing Method: jgJ Simulate D Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0203 Rev008 PageS of 10

LLOJPM0203, RevOOB JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain current revision of Current revision of S94.2.A.

S94.2.A. obtained.

2. VERIFY procedure being Verified on correct unit/train performed on correct unit/train.

3. VERIFY ALT. AVAIL. yellow ALT. AVAIL. yellow indicating indicating light Lit. light Lit.

(CUE: "ALT. AVAIL. yellow indicating light Lit..")

4. VERIFY SYNC REF. AVAIL. SYNC REF. AVAIL. yellow yellow indicating light Lit. indicating light Lit.

(CUE: "SYNC REF. AVAIL. yellow indicating light Lit.")

5. VERIFY SYNC FAIL SYNC SYNC FAIL SYNC MONITOR MONITOR red alarm light not red alarm light not Lit Lit.

(CUE: "SYNC FAIL SYNC MONITOR red alarm light not Lit.")

6. PLACE TEST TRANSFER TEST TRANSFER switch in switch to "MAN" "MAN" (CUE: "TEST TRAI\ISFER switch in "MAN"

7. VERIFY the following: N/A 7.a. 01\1 ALTERNATE red ON ALTERNATE red indicating light comes on indicating light on (CUE: "ON ALTERNATE red indicating light on.")

7.b. ON INVERTER green ON INVERTER green indicating light goes off indicating light off (CUE: "ON INVERTER green indicating light off.")

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0203 RevOOB Page 60f 10

LLOJPM0203, Rev008 ELEMENT STANDARD SAT UNSAT Comment Number 7.c. DC AMPS ammeter DC AMPS ammeter decreases to approximately 5 approximately 5 amps amps (CUE: "DC AMPS ammeter approximately 5 amps.")

8. PLACE BYPASS SWITCH to BYPASS SWITCH in BYPASS position at BYPASS

ONAD160 (CUE: "BYPASS SWITCH in BYPASS.")

9. VERIFY ATS BYPASSED red ATS BYPASSED red light on light comes on (CUE: "ATS BYPASSED red light on.")

1O. PLACE TEST TRANSFER TEST TRANSFER SWITCH SWITCH to "AUTO" to transfer in "AUTO" Static Switch from Alternate Source to Inverter (CUE: "TEST TRANSFER SWITCH in "AUTO".")

11. VERIFY the following steps N/A occur:

11.a. ON INVERTER green ON INVERTER green indicating light comes on indicating light on (CUE: "ON INVERTER green indicating light on.")

11.b. ON ALTERNATE red ON ALTERNATE red indicating light goes off indicating light off (CUE: "ON ALTERNATE red indicating light off.")

12. PLACE ISOLATION SWITCH ISOLATION SWITCH in to "OPEN" position at "OPEN" position

ONAD160, (CUE: "ISOLATION SWITCH in "OPEN" position.")

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0203 Rev008 Page 7 of 10

LLOJPM0203, Rev008 ELEMENT STANDARD SAT UNSAT Comment Number

13. VERIFY the following: N/A 13.a. ALT. AVAIL. yellow ALT. AVAIL. yellow indicating indicating light goes off light off (CUE: "ALT. AVAIL. yellow indicating light off.")

13.b. ALT. LOW VOLTS red alarm ALT. LOW VOLTS red alarm light comes on light on (CUE: "ALT. LOW VOLTS red alarm light on.")

13.c. SYNC. REF. AVAIL. yellow SYNC. REF. AVAIL. yellow indicating light goes off indicating light off (CUE: "SYNC. REF. AVAIL. yellow indicating light off.")

13.d. SYNC FAIL SYNC SYNC FAIL SYNC MONITOR MONITOR red alarm light red alarm light on comes on (CUE: "SYNC FAIL SYNC MONITOR red alarm light on.")

13.e. ALT. VOLTS voltmeter goes ALT. VOLTS voltmeter at 0 to 0 volts volts (CUE: "ALT. VOLTS voltmeter at 0 volts.")

14. DEPRESS INVERTER STOP red AND RELEASE INVERTER pushbutton Depressed and STOP red pushbutton Released (CUE: "INVERTER STOP red pushbutton Depressed and Released.")

15. VERIFY the following: N/A 15.a. INV. VOLTS meter goes to 0 INV. VOLTS meter 0 volts volts (CUE: "INV. VOLTS meter 0 volts.")

15.b. INV. FREQUENCY meter INV. FREQUENCY meter at drops to far left far left (CUE: "INV. FREQUENCY meter at far left.")

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0203 Rev008 Page 8 of 10

LLOJPM0203, Rev008 ELEMENT STANDARD SAT UNSAT Comment Number 15.c. Inverter cooling fans shut off Inverter cooling fans off as indicated by FAN FAIL red alarm light on AND no air flow from top rear of inverter (CUE: "Inverter cooling fans off.")

15.d. SYNC FAIL SYNC SYNC FAIL SYNC MONITOR MONITOR red alarm light red alarm light off goes off (CUE: "SYNC FAIL SYNC MONITOR red alarm light off.")

15.e. OUTPUT LOW VOLTS red OUTPUT LOW VOLTS red alarm light comes on after alarm light comes on approximately 10 seconds (CUE: "OUTPUT LOW VOLTS red alarm light comes on")

16. OPEN Inverter DC INPUT Inverter DC INPUT breaker breaker Open (CUE: "Inverter DC INPUT breaker Open.")

17. PLACE PRECHARGEI PLACE PRECHARGEI DISCHARGE toggle switch to DISCHARGE toggle switch in "DISCHARGE" "DISCHARGE" position (CUE: "PLACE PRECHARGEI DISCHARGE toggle switch in "DISCHARGE".")

18. VERIFY the following: N/A 18.a. CHARGED green indicating CHARGED green indicating light goes off light off (CUE: "CHARGED green indicating light off.")

18.b. DC VOLTS meter decreases DC VOLTS meter at 0 volts to 0 volts (CUE: "DC VOLTS meter at 0 volts.")

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0203 Rev008 Page 90f 10

LLOJPM0203, RevOOB ELEMENT STANDARD SAT UNSAT Comment Number 18.c. DC AMPS meter decreases DC AMPS meter decreases to 0 amps to 0 amps (CUE: "DC AMPS meter decreases to 0 amps")

18.d. All remaining indicating lights All remaining indicating tights go off. off.

(CUE: "All remaining indicating lights off.")

19. OPEN breaker 72-20120 (*DA- Breaker 72-20120 (*DA-20),

20), at 250 VDC MCC *OD201 at 250 VDC MCC *OD201

(*DA) (304-R11-217 for Unit 1. (*DA) (304-R11-217 for Unit 370-R18-217 for Unit 2), to 1, 370-R18-217 for Unit 2) remove voltage to Inverter DC OPEN INPUT breaker (CUE: "Breaker 72-20120 (*DA 20). at 250 VDC MCC

OD201 (*DA) (304-R11-217 for Unit 1, 370-R18-217 for Unit 2) OPEN.")

CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time: _ _

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0203 RevOOB Page 10 of 10

INITIAL CONDITIONS:

__A RPS and UPS Static Inverter is in Service.

INITIATING CUE:

You are directed by Shift Supervision to bypass the _A RPS/USP static inverter and remove it from service per S94.2.A Briefing has been performed SRRS: 30.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure ALIGNMENT OF EQUIPMENT FOR SHUTDOWN COOLING

..'PM Number: LLOJPM0758 Revision Number: 000 Date: _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

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 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure Rev: _ _

Procedure _ _ _ _ _ _ _ __

Procedure Rev:

Rev:

9.

Verify cues both verbal and visual are free of conflict.

~-

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the J PM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 2 of 8

REVISION RECORD (Summary)

1. Revision 000 SIMULATOR SETUP INSTRUCTIONS

1. NtA for in-plant INITIAL CONDITIONS:

1. LGS Unit 1 has been scrammed and safe shutdown procedures are in progress.

2. Fire is reported in Unit 1 CRD Hydraulic Equipment Area (EI. 253').

3. The "1 B" RHR Pump is running from the Main Control Room.

4. The following valves can NOT be positioned normally and need to be positioned:

HV-051-1F015B "1B RHR SHUTDOWN CLG INJECTION PCIV (OUTBOARD)"

HV-C-051-1F048B "1B RHR HTX. SHELL SIDE BYPASS VLV. (HEAT EXCH BYPASS)"

HV-051-1F014B "1B RHR HTX. S.W.INLETVLV. (1B)."

5. Another operator has been assigned to manually position the valves as needed.

TASK STANDARD(S):

Breakers for listed valves in noted position INITIATING CUES:

You are directed by Shift Supervision to perform Alignment of Equipment for Shutdown Cooling operation per step 3.4 of 1FSSG-3045E (Unit 1).

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 3 of 8

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 4 of 8

The JPM Start Time clock starts when the candidate acknowledges the initiating cue JPM

SUMMARY

Operator's Name:,_ _ _~_ _ _ _ _ _ _Job

Title:

D SED D SM DSRO D RO D STAll A D OTHER JPM

Title:

ALIGNMENT OF EQUIPMENT FOR SHUTDOWN COOLING JPM Number: LLOJPM0758 Revision Number: 000 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance:

600000 AA2.16 3.0/3.5 600000 AA2.17 3.1/3.6 Suggested Testing Environment: In-Plant Alternate Path: DYes I:8jNo SRO Only: DYes I:8jNo Time Critical: DYes I:8jNo Reference(s):

Procedure: 1FSSG-3045E Rev. 15 Actual Testing Environment: D Simulator D Control Room I:8j In-Plant 0 Other Testing Method: I:8j Simulate D Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes DNo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: ___________________ (Print)

Evaluator's Signature: ____~____________ Date: _ _ _ __

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 5 of 8

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain current revision of Current revision of 1FSSG 1FSSG-3045E Procedure. 3045E obtained

. 2. IF any of the following N/A valves can NOT be positioned normally, THEN POSITION valve from 10-C601-X1, 1B RHR Emergency Local Valve Control Panel, using Transfer Switches (12-217-304)

CUE: HV-051-1 F015B and HV C-051-1 F0488 cannot be j:!ositioned normally 2.a. HV-051-1F015B "1B RHR HSS51-115BX in EMER SHUTDOWN CLG INJECTION PCIV (OUTBOARD)" HSS51 1158X in EMER CUE: "HSS51-115BX is in EMER"

2.b. HV-C-051-1F048B "1B HSS51-11488X in EMER RHR HTX. SHELL SIDE BYPASS VLV. (HEAT EXCH BYPASS)" HSS51 148BX in EMER CUE: "HSS51-148BX is in EMER"

3. IF HV -051-1 F003B, "1 B N/A RHR HTX. SHELL SIDE OUTLETVLV.

(OUTLET)", can NOT be opened normally, 3.a. THEN OPEN breaker D124-R-G-01, "1B RHR HTX. SHELL SIDE OUTLET HV-51-1 F0038" (12-217-304).

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 6 of 8

ELEMENT STANDARD SAT UNSAT Comment Number CUE: HV-051-1 F003B can normally be positioned

4. IF HV-051-1F014B, "1B RHR HTX. S.W. INLET VLV. (1 B)"

can NOT be opened normally, THEN OPEN breaker D124-R G-32, "1 B RHR HTX. S.W.

INLET VLV. HV-51-1 F014B" (12-217-304).

CUE: HV-051-1F014B can NOT normally be positioned.

CUE: Breaker D124-R-G-32, "1 B RHR HTX. S.W.INLETVLV. HV 51-1 F014B" is in the open position.

Cue: You can stop here, you have met the termination criteria for this JPM JPM Stop Time: _________

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 7 of 8

INITIAL CONDITIONS:

1. LGS Unit 1 has been scrammed and safe shutdown procedures are in progress.

2. Fire is reported in Unit 1 CRD Hydraulic Equipment Area (EI. 253').

3. The "1 B" RHR Pump is running from the Main Control Room.

4. The following valves can NOT be positioned normally and need to be positioned:

HV-051-1F015B "1B RHR SHUTDOWN CLG INJECTION PCIV (OUTBOARD)"

HV-C-051-1F048B "1B RHR HTX. SHELL SIDE BYPASS VLV. (HEAT EXCH BYPASS)"

HV-051-1F014B "1B RHR HTX. S.W.INLETVLV. (1B)."

5. Another operator has been assigned to manually position the valves as needed.

INITIATING CUES:

You are directed by Shift Supervision to perform Alignment of Equipment for Shutdown Cooling operation per step 3.4 of 1FSSG-3045E (Unit 1).

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure INITIATE REACTOR SCRAM AND MSIV CLOSURE FROM AER USING SE-1 (ALTERNATE PATH)

JPM Number: 0261 Revision Number: 008 Date: _ I 1_

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev 008 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to ..IPM usage, revalidate JPM using steps 9 and 12 below.

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

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

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

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) 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(s) referenced by this JPM reflects the current revision:

Procedure __________ Rev: - -

Procedure Rev:

9. Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the JPM.

12. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SIVIE I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page2of8

LLOJPM0261 Rev 008 REVISION RECORD (Summary)

1. Revision 007 Change of format" updated to reflect current procedures no revision marks SIMULATOR SETUP INSTRUCTIONS

1. NtA for in-plant INITIAL CONDITIONS:

1. The MCR has been evacuated due to a fire.

2. Operators were unable to take any actions for Unit _ prior to leaving the MCR.

TASK STANDARD(S):

Actions taken to open noted fuse and "RPS" circuit Breakers INITIATING CUE:

Shift Supervision directs you to initiate a reactor scram and MSIV isolation on Unit _ per SE-1, step __, in order of preference.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page 30f8

LLOJPM0261 Rev 008 Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. 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, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside 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 JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page 4 of8

LLOJPM0261 Rev 008 JPM

SUMMARY

Operator's Name:_ _ _ _ _ _ _ _ _ _ _ _ _ __

Job Title :0 SED ORO OSRO o STAIIA o OTHER JPM

Title:

INITIATE REACTOR SCRAM AND MSIV CLOSURE FROM AER USING SE-1 (ALTERNATE PATH)

JPM Number: LLOJPM0261 Revision Number: 008 Task Number and

Title:

Per Licensed Operator Vision Task Matrix KIA Number and Importance: 295016 3.8/3.9 Suggested Testing Environment: In-Plant Alternate Path: ISlYes ONo SRO Only: DYes ISlNo Time Critical: DYes [8jNo Reference(s): Procedure SE-1 Rev: 63 Actual Testing Environment: 0 Simulator 0 Control Room ISlln-Plant 0 Other Testing Method: [8j Simulate 0 Perform Estimated Time to Complete: 30 minutes Actual Time: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature:_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page50f8

LLOJPM0261 Rev 008 JPM Start Time: _.__

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain current revision of SE- Current revision of SE-1

1. obtained.

(CUE: Once the trainee demonstrates the ability to locate the current revision of the procedure, provide him/her a copy.)

2. Obtain fuse pullers. Fuse pullers obtained.

EVALUATOR NOTE Immediately prior to student entering Panel *OC611 Bay B, the evaluator must cue student that panel door handle spins free and door will not open.

3. IF SCRAM OR MSIV closure N/A was not accomplished, THEN PERFORM one of following:

4. PERFORM one of the N/A following in Auxiliary Equipment Room:

5. REMOVE the following fuses:

S.a. REMOVE fuse C71A-F14A in Fuse removed.

OC609 Bay B.

(CUE: Fuse removed.)

S.b. REMOVE fuse B21 H-F6A in Fuse removed.

OC609 Bay B.

(CUE: Fuse removed.)

S.c. REMOVE fuse C71 A-F14B in N/A

OC611 Bay B.

(CUE: Door handle spins free and door will not open.)

S.d. REMOVE fuse B21 H-F6B in N/A

OC611 Bay B.

(CUE: Door handle spins free and door will not open.)

EVALUATOR NOTE Steps 5e through 5g are included in case the trainee moves on to these steps. They may move on to step 6 or 7, in which case steps 5e through 5g are NJA SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page 6 0'8

LLOJPM0261 Rev 008 ELEMENT STANDARD SAT UNSAT Comment Number

5.e. REMOVE fuse C71A-F14C Fuse removed.

in *OC609 Bay C.

(CUE: Fuse removed.)

5.t. REMOVE fuse B21 H-F6C in Fuse removed.

OC609 Bay C.

(CUE: Fuse removed.)

5.g. REMOVE fuse C71 A-F14D N/A.

in *OC611 Bay C.

(CUE: Fuse will not come out of the clip.)

5.h. REMOVE fuse B21H-F6D in N/A.

OC611 Bay C.

(CUE: Fuse will not come out of the clip.)

EVALUATORS NOTE The student will either perform step 6 (a and b) OR step 7 (a-d). Step not performed will be N/A.

6. OPEN the following circuit N/A breakers:

6.a. OPEN Circuit Breaker 13, Panel *AY160 Circuit Breaker nRPS TRIP SYSTEM A 13 switch in OPEN position.

VERTICAL BOARD"

(*AY160)

(CUE: *AY160 Circuit Breaker 13 indicates open.)

6.b. OPEN Circuit Breaker 13, Panel *BY160 Circuit Breaker nRPS TRIP SYSTEM B 13 switch in OPEN position.

VERTICAL BOARD"

(*BY160)

(CUE: *BY160 Circuit Breaker 13 indicates open.)

7a. OPEN the following breakers 52-AY24801, nRPS Breaker" in Unit* Inverter Rooom (452- (*AC248) in OPEN position A8-254/453-A8-254) :

52-AY24801, nRPS Breaker"

(*AC248)

(CUE: Circuit Breaker 52 A Y24801 indicates open.)

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page 70f8

LLOJPM0261 Rev 008 ELEMENT STANDARD SAT UNSAT Comment Number

7b. 52-CY24801, "RPS Breaker" 52-CY24801, "RPS Breaker"

(*AC248) (*AC248) in OPEN position (CUE: Circuit Breaker 52 AY24801 indicates open.)

7c. 52-BY24801, "RPS Breaker 52-BY24801, "RPS Breaker"

"(*BC248) (*BC248) in OPEN position (CUE: Circuit Breaker 52 AY24801 indicates open.)

7d. 52-DY24801, "RPS Breaker 52-DY24801, "RPS Breaker"

"(*BC248) (*BC248) in OPEN position (CUE: Circuit Breaker 52 AY24801 indicates open.)

CUE: You have met the termination criteria for the JPM. You may stop here JPM Stop Time: _ __

SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0261 Rev008 Page8of8

INITIAL CONDITIONS:

1. The MCR has been evacuated due to a fire.

2. Operators were unable to take any actions for Unit _ prior to leaving the MCR.

INITIATING CUE:

Shift Supervision directs you to initiate a reactor scram and MSIV isolation on Unit _

per SE-1, step __, in order of preference.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Appendix 0 Required Operator Actions Form ES-O-2 Event Malt. No. Event Event No.

N/A N-BOP Swap EHC pumps 2 N/A N-SRO Pull control rods per GP-2 in support of plant startup.

R-RO 3 MPROO4B TS,I-SRO APRM Fails Inoperable I-RO 4 C-BOP MED282C Loss of Div III DC TS,C-SRO 5 MRR442B C-SRO MRR443B C-RO C-BOP 6 MRP029D ATWS MRP407C MSL197 7 MRD024 C-RO Rod Drive Control System Failure 8 MEH108 C-BOP Turbine Bypass valves fail C-SRO C-RO NRC Scenario #2 - 2010 Limerick Operating Test Page 2 of 18

Appendix 0 Required Operator Actions Form ES-O-2 SCENARIO

SUMMARY

Event 1: The crew will be directed to Swap EHC pumps from 1A to 1B per S31.6.C Objective: Evaluate the crew's ability to perform S31.6.C Event 2: The crew will be directed to continue with GP-2 activities in support of plant startup.

Objective: Evaluate the crew's ability to withdraw Control Rods to raise reactor power.

Event 3: During the startup, APRM Channel 1 Failure: Inoperative will occur.

Objective: Evaluate the crew's ability to respond to the inoperable APRM, and reference T.S. 3.3.1.

Event 4: Once action for drifting rod is complete, a loss of Division III DC will occur.

Objective: Evaluate the crew's ability to respond to a loss of Div III DC.

Including actions lAW E-1 FC. The CRS will address Tech Specs 3.5.1.a, 3.5.1.b, 3.8.2.1, and 3.8.3.1.

Event 5: Once action loss of Division III DC are complete, and T.S. have been referenced, 1A and 1B Recirc Pumps will trip due to a trip of the RPT breakers..

Objective: Evaluate the crew's ability to execute OT-112, Recirculation Pump Trip, scram the reactor and execute T -101 .

NRC Scenario #2 - 2010 Limerick Operating Test Page 3 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Event 6: When Reactor Scram is attempted, one channel of RPS fails to deenergize and subsequently, ARI fails to initiate resulting in an ATWS.

Complicating the event, SLC squib valves fail to fire.

Objective: Evaluate the crew's ability to execute T-101, T-102 and T-117.

Manually insert control rods, stabilize RPV pressure, and deliberately lower and control Reactor level.

Event 7: When initial scram actions are complete an ROCS failure results in the inability to drive control rod.

Objective: Evaluate the crew's response to a failure to drive rods. The crew is expected to reset ROSC and continue to drive rods.

Event 8: When Level has been intentionally lowered per T-117, Main Turbine bypass valves will fail closed.

Objective: Evaluate the crew's response to the failure of Bypass valves. The crew is expected to take control of pressure with SRVs, and place suppression pool cooling in service. Complicating the event will be a failure of the A RHR Suppression Pool Cooling Valve HV51 1 F024A.

Termination Point: The scenario may be terminated when all control rods are inserted, reactor level is stabilized.

NRC Scenario #2 - 2010 Limerick Operating Test Page 4 of 18

Appendix 0 Required Operator Actions Form ES-O-2 CRITICAL TASKS

1. T-101.5 Implement T-215 to insert control rods.

Standard: Direct the performance of T-215 to operations personnel locate outside the control room.

SAT/UNSAT

2. T-117.7 Terminate and prevent injection into the RPV.

Standard: RPV level lowered below -50" by Terminating and Preventing injection into the RPV per T-270.

SAT/UNSAT NRC Scenario #2 - 2010 Limerick Operating Test Page 5 of 18

Appendix 0 Required Operator Actions Form ES-O-2 INITIAL SIMULATOR SETUP ITEM I MALFUNCTION I REMOTE FUNC"rlON I CONDITION

Ensure materials for applicants:

- Rod Pull Sheet with all applicable completed steps signed off

- GP-2 with all applicable completed steps signed off

- GP-2, App. 3 with all applicable completed steps signed off

- S73.1.A

Reset simulator to Preloaded Exam Ie OR Reset to IC# 10 and perform the following:

Load Scenario File OR Reset to IC# 10 AND Load items listed below:

Ensure the following malfunctions are loaded:

Ensure the following overrides are loaded:

N/A NRC Scenario #2*2010 Limerick Operating Test Page 6 of 18

Appendix 0 Required Operator Actions Form ES-O-2 rrEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

Ensure the following triggers are built:

4 5

6 l 7 ZAPS1SDN 8 : RRLINX13A <=

PRIOR TO START OF SCENARIO:

RESET APRM MEMORY

1. Select TRIP STATUS

2. RESET MEMORY

ENSURE: "8" Control Enclosure Chiller, and Chilled Water Loop in Service "A" Control Enclosure Chiller in Standby

ENSURE: Generator output breakers, 535 and 635, are green flagged

Reset any annunciators that should not be present NRC Scenario #2 - 2010 Limerick Operating Test Page 7 of 18

Appendix 0 Required Operator Actions Form ES-O-2 INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Swap EHC pumps

./ MALFUNCTION I REMOTE FUNCTION I REPORT

When Contacted Report:

-Pre-start checks are complete, 18 EHC pump is ready for start

After pump start, when contacted Report:

- EHC pressure on PI-M2-*808(A) is 1600 psig and steady

- There is no abnormal noise or vibration

Respond to request for assistance as appropriate per S31.6.C EVENT 2: Pull control rods per GP-2 in support of plant startup_

MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate.

EVENT 3: APRM Fails Inoperable

./ MALFUNCTION I REMOTE FUNCTION I REPORT

When contacted, Report - A Reactor Engineer is on the way to assist with troubleshooting and restoration activities.

-APRM 5 minutes after contacted Report:

1 indicating INOP, The Trip light is Lit

Respond to request for assistance as appropriate.

EVENT 4: Loss of Div III DC

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 4

main If asked to investigate loss of Div III DC, wait 5 minutes and report the bus fuse has blown. Electrical Maintenance is continuing to investigate.

Respond to request for assistance as appropriate.

NRC Scenario #2 - 2010 Limerick Operating Test Page 8 of 18

Appendix D Required Operator Actions Form ES-D-2 EVENT 5: Recirc Pump 1A, and 1 B RPT Breaker Trip

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger # 5

Respond to request for assistance as appropriate.

EVENT 6: ATWS

./ MALFUNCTION I REMOTE FUNCTION I REPORT

- T-214 T-214, 5 minutes, Toggle RTR10 and 11 on page T200, Report is complete.

T-215, When contacted Report:

- The door to 10C611 Bay "8" will not open. We've sent somebody out to obtain tools to take the door off. We'll call back when we're ready to pull the fuse.

(NOTE: T-215 will be completed at end of scenario)

- T-216 T-216, 7 minutes, Report:

has been unsuccessful due to a stuck valve. We are looking for another vent path.

T-251 , 6 minutes, Report:

- Verify HV-55-1 F006 is closed then Toggle Remote Function RTR309 to OPEN

- Electrical SLC Failure, 7 minutes, Report:

maintenance is troubleshooting the squib valves failure to fire.

T-270, 7 Minutes OR Immediately if pre-staged,

-Toggle RTR-220 thru 227.

OR

- Load T-270 scenario file.

Report:

- T-270 is complete in Aux Equip. room

- T-212 T-212, When contacted, Report:

will take 30 minutes to complete.

- T-212 T-212, When contacted, Report:

will take 30 minutes to complete.

NRC Scenario #2 - 2010 Limerick Operating Test Page 9 of 18

Appendix 0 Required Operator Actions Form ES-O-2

./ MALFUNCTION I REMOTE FUNCTION I REPORT

T -215, When Rx level lowered to -50" per T-117 AT DIRECTION OF LEAD EVALUATOR Report:

- Ready to pull scram solenoid fuses per T-215, expect rod motion.

DELETE MRP029D, Report:

- T-215 is complete

~

EVENT 7: Rod Drive Control System Failure

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Ensure Activation of Trigger 7 (Mode switch to Shutdown)

When T-270, Terminate and Prevent is complete, DELETE malfunction MRD024, Report:

-RDeS has been reset in the AER.

Respond to request for assistance as appropriate.

EVENT 8: Turbine Bypass valves fail

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Ensure Activation of Trigger 8 (RX water level -25")

Respond to request for assistance as appropriate.

i

\

NRC Scenario #2 - 2010 Limerick Operating Test Page 10 of 18

Appendix 0 Required Operator Actions Form E5-0-2 Op-Test No. ILT09-1 Scenario No. 2 Event No.: 1 Event

Description:

Swag EHC gumgs Time Position Applicant's Actions or Behavior BOP Obtain a copy of S31.6.C, SWAPPING OPERATING EHC PUMPS BOP Contact EO to perform EHC pump start preparations BOP PLACE the control switch for the standby EHC pump *B(A)

P113 to "RUN."

BOP VERIFY the following:

-EHC pressure on PI-M2-*80B(A) 1500 to 1700 psig

-No abnormal noise or vibration BOP WHEN on-coming pump has been running for 3 minutes, AND EHC pump operation is stable THEN PLACE the off-going *A(B)-P113 Control switch to "STOP" AND ALLOW to spring return to "AUTO",

BOP Direct EO to return PDI-031-*01 B to service BOP VERIFY "EHC System Standby Pump Running" AND "EHC System Standby Pump Not In Auto" alarms clear on *05 MAIN TURB, NRC Scenario #2 - 2010 Limerick Operating Test Page 11 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. 2 Event No.: g Event

Description:

Pull control rods Qer GP-2 in sUQQort of Qlant startuQ Time Position Applicant's Actions or Behavior SRO Direct RO to continue rod pulls RO Continue Rod Pulls, Step #23, rod 10-11 at 00 and going to position 12 Op-Test No. ILT09-1 Scenario No. g Event No.: ~

Event

Description:

APRM Fails InoQerable II ..,...

Position Applicant's Actions or Behavior RO Recognize #1 APRM INOP RO Reference appropriate ARCs:

108 REACTOR B-3, APRM Upscale Trip Iinop

108 REACTOR F-3, Rod Out Block RO Dispatch personnel to investigate SRO Direct RO to Bypass APRM # 1 RO Bypass APRM # 1 SRO Reference T.S. 3.3.6, and 3.3.7.5 Determine required number of APRMs remain operable NRC Scenario #2 - 2010 Limerick Operating Test Page 12 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Op~Test No. ILT09~1 Scenario No. g Event No.: ~

Event

Description:

Loss of Div III DC Time Position Applicant's Actions or Behavior RO Report Q/UP SRO Acknowledge Div III DC related alarms, and diagnose cause RO is Loss of Div " DC BOP SRO Enter E-1 FC, Loss Of Division III Safeguard 125 VDC Bus 1FC BOP Reference appropriate ARCs:

004 VENT B-3, REAC ENCL LOW DELTA P/ LOSS OF POWER/INOP

121 013 G-2, 1PPC1/1 PPC3 125V VDC DIST PANELS UNDERVOLTAGE

121 013 G3, 1PPC2125V DC DIST PANEL UNDERVOLTAGE BOP Manually INITIATE Main Control Room Chlorine Isolation in accordance with S78.8.A, Manual Initiations Of Control Room Radition Or ChlorineiToxic Chemical Isolation.

SRO REFER TO GP-8, Primary and Secondary Containment Isolation Verification and Reset (Green Reset AND RESET I MSIV Isolation Logic, as required.

L BOP , Dispatch personnel to Investigate loss of power BOP , Identify Loss of RWCU BOP Contact Chemistry to perform compensatory sampling of Reactor coolant conductivity SRO Identify The following can not be started OR tripped from I MCR:

NRC Scenario #2 - 2010 Limerick Operating Test Page 13 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. g Event No.: ~

Event

Description:

Loss of Div III DC Time Position Applicant's Actions or Behavior

OA MCA Chiller

1A DIW Chiller

1ACAD

1CAHA

1C Core Spray Pp SAO Aefer to Tech Specs. Identifies following affected LCOs:

3.3.2 Table 3.3.2-1

3.3.3.c

3.S.1.a

3.S.1.b

3.8.3.1

TAM 3.4.4 NRC Scenario #2 - 2010 Limerick Operating Test Page 14 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. g Event No.: § Event

Description:

Recirc PumQ 1AI and 1B RPT Breaker TriQ Time Position Applicant's Actions or Behavior RO Report Q/UP RO Recognize trip of 1A and 1B Recirc Pumps BOP SRO Enter OT-112 SRO Recognize Scram is required due to trip of both Recirc Pumps trip.

RO BOP RO Place Mode Switch in SHUTDOWN RO Insert SRM's and IRM's SRO Enter T-101 NRC Scenario #2 - 2010 Limerick Operating Test Page 15 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. g Event No.: .§ Event

Description:

ATWS I Time Position Applicant's Actions or Behavior RO Recognize rods failed to insert (B RPS) with scram valves closed RO Manually initiate RRCS RO Recognize ARI failure SRO Implement TAR SRO Direct T-213 SRO Direct T-215 SRO Direct T-216 BOP Inhibit Auto ADS RO Recognize SLC failure to inject to RPV RO Secure SLC Pumps SRO Direct T-212 SRO Direct T-221 SRO Enter T-117 BOP Perform T-270 in the MCR RO BOP Direct T -270 in AER

/ t?

RO Lower RPV level to < -50" /-tow ,f

.,)

RO Maintain RPV level above TAF NRC Scenario #2 - 2010 Limerick Operating Test Page 16 of 18

Appendix 0 Required Operator Actions Form ES~D-2 Op-Test No. ILT09-1 Scenario No. g Event No.: § Event

Description:

ATWS Time Position Applicant's Actions or Behavior SRO Enter T -102 on High Suppression Pool temperature BOP Place RHR in Suppression Pool Cooling RO Recognize T-215 successful and all rods in SRO Exit T -117 and Re-Enter T -101 Level Control Leg SRO Direct Restoration of Reactor level to 12.5" to 54" RO Restore Level to Normal Band SRO Direct Controlled Cooldown BOP Commence Controlled Cooldown Op-Test 1\10. ILT09-1 Scenario No. g Event No.: Z Event

Description:

Rod Drive Control System Failure lillie Position Applicant's Actions or Behavior RO Recognize inability to drive rods RO Reference ARC: 108 REACTOR, E-4 RDCS Inoperative RO Recognize failure of RDCS RO Dispatch operator to reset RDCS RO Recognize reset of RDCS and continue rod insertion NRC Scenario #2 - 2010 Limerick Operating Test Page 17 of 18

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. g Event No.: § Event

Description:

Turbine BYJlass valves fail r __*** _.1 Applicant's Actions or Behavior SRO Recognize EHC not contrOlling pressure RO BOP SRO Direct BOP to control Reactor pressure with SRVs BOP Stabilize Reactor pressure with SRV's RO Control Feedwater injection to maintain level <-50" TERMINATE THE SCENARIO ALL THE FOLLOWING ARE MET:

All control rods are inserted

Reactor water level is stabilized.

NRC Scenario #2 - 2010 Limerick Operating Test Page 18 of 18

PREBRIEF INSTRUCTIONS Reactor Power is 19%, Unit 2 100% power Turnover:

Unit 1 is in OPCON 1, Reactor Power is approximately 19%

GP-2, Normal Plant Startup is in progress and complete through step 3.4.25.

Rod Move Sheet sequence step #22, Group 5 is complete, Step

23 is in progress, with rod 10-11 at 00 and going to position 12

GP-2, App. 3, Startup of the Main Turbine is in progress and complete through step 3.3.7

All MeR annunciators in alarm are understood and expected due to present plant condition.

"1 B" RFP is in AUTO through the 108B

Both recirc pumps are operating at 28% speed

"1 An and "1 B" Condensate pumps are in service

"1 B" and "1 C" Circ water pumps are in service

RWCU is in service with "1A" pump and both F/Ds

"1 B" OW Chiller in service

All ECCS are operable

All available Deep Bed Demins are in service

4 Condensate Filter Demins are in service Inoperable/Out of Service Equipment and ETR

1A EHC pump needs to be removed from service before Startup continues Planned Evolutions:

Swap EHC pumps from 1A to 1B per S31.6.C, Swapping operating EHC Pumps, prior to continuing control rod withdrawal.

Continue with GP-2, and GP-2, App. 3 activities in support of plant startup.

Regulatory Action Log has been reviewed and no equipment is known to be INOP which would affect continuing the startup.

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: 4 Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

Unit 1 at 75% power. Unit 2 is at 100% power.

Turnover:

Inoperable/Out of Service Equipment and ETR

Inboard MSIV HV-41-1 F022A inadvertently closed due to an Electrical Fault

Repairs complete on HV-41-1 F022A

RCIC is Out of Service for repairs to the RCIC Trip Throttle Valve, HV-50-112.

Repairs are expected to take 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Planned Evolutions:

Open the MSIV HV-41-1 F022A per S41.3.B

Raise power to 100% power per GP-5, Attachment 1. The RE is not in the control room.

Event Malt. No. Event Type* Event No. ~

~"

Description 1 N/A N-SRO N-BOP o;,n Inboa~d ~SIV HV-41-;/(o22A "')

Ra~0100% ~

R-RO 2 N/A N-SRO C-RO 3 MRR504B C-BOP Reactor Recirc Pump 1B Shaft Shear TS,C-SRO MCW484A C-BOP 4 TECW pump A Trip, B TECW fails to auto start MCW486B C-SRO VIM123A01 C-BOP 5 RWCU A pump vibration, and Low Flow TS,C-SRO MRP445 M 6 HPCI Steam leak MHP446A MHP446B MRP029C I-RO 7 RPS Failure MFW244B C-RO 8 "A" RFP Steam Supply Valve Fails MAD141D C-BOP 9 E SRV fails closed C-SRO

. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario #4 - 2010 Limerick Operating Test Page 1 of 19

Appendix D Required Operator Actions Form ES-D-2 SCENARIO

SUMMARY

Event 1: Shift orders are to open Outboard MSIV HV-41-1 F028A Objective: Evaluate the crew's ability to open Outboard MSIV HV-41 1F028A Event 2: Once HV-41-1 F028A is open the crew is expected to raise power to 100% to perform turbine valve testing. The RO will raise reactor power using recirc flow.

Objective: Evaluate the crew's ability to raise reactor power Event 3: Shortly after the crew assumes responsibility, the 1B Reactor Recirc Pump shaft shears.

Objective: Evaluate the crew's ability to diagnose the Recirc Pump shaft shear and take action to shutdown the pump and stabilize power outside of the exclusion region lAW OT-112, Recirculation Pump Trip.

Event 4: After the crew responds to Recirculation Pump Trip and T.S. is referenced, the "1 A" TECW pump will trip. The crew is expected to enter ON-117, and start the "1 B" TECW pump.

Objective: Evaluate the crew's ability to mitigate the loss of TECW including monitoring temperatures, and restoring TECW.

Event 5: After the 1B TECW pump is started, the "1 A" RWCU pump suction will clog resulting in low flow condition coupled with hi vibrations, resulting in the need to trip the pump.

Objective Evaluate the crew's ability to recognize low flow and track vibration levels on the RWCU pump, identify that a pump trip should have occurred and trip the pump, contact chemistry to perform compensatory sampling and reference T.R.M 3.4.4.

!\IRC Scenario #4 - 2010 Limerick Operating Test Page 2 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Event 6: Once the "1 A" RWCU pump has been tripped, an unisolable steam leak will occur in the HPCI Room which will eventually result in the need to perform a T-103 shutdown, and 2 areas exceeding MSO and a T -112 Emergency Slowdown. Complicating the event will be a failure of RPS to Scram the Reactor, requiring use of ARlo Objective: Evaluate the crew's response to take actions per T-1 03, Secondary Containment Control, due to the elevated room temperatures, T -101 RPV Control, and T -112 Emergency Slowdown.

Event 7: Once the crew attempts to perform a T -103 shutdown, a failure of RPS to Scram the Reactor will occur.

Objective: Evaluate the crew's response to a failure of RPS to Scram the Reactor, and take actions to scram using ARlo Additionally, the crew will have to take manual control of Feedwater, as Scram profile will not activate due to the failure of RPS.

Event 8: During the Scram the "A" RFP Steam Supply Valve will fail to operate on HP steam (when the Main Turbine is tripped). This malfunction will result in the crew having to control RPV level without Startup Level Contro/.

Objective: Evaluate the crew's response to take actions for controlling level without the use of Startup Level Control.

Event 9: During the blowdown the "E" SRV will fail closed requiring the crew to open non-ADS SRV.

Objective: Evaluate the crew's response to take actions for successful completion of T -112 Emergency Slowdown Termination Point: The scenario may be terminated when 5 SRVs are opened, and reactor water level is stabilized.

NRC Scenario #4 - 2010 Limerick Operating Test Page 3 of 19

Appendix 0 Required Operator Actions Form ES-O-2 CRITICAL TASKS

1. T-103.1 Direct performance of T-290 Standard: Direct performance of T-290 to operations personnel located outside the control room.

SAT/UNSAT

2. T-103.2 Manually scram the reactor Standard: After it is determined that one are in Table SCC-2 has exceeded max safe op value, manually scram the reactor SAT/UNSAT

3. T-103.3 Perform Emergency Slowdown per T-112 Standard: After it is determined that two areas in Table SCC-2 have exceeded Max Safe Operating values and a primary system is still discharging into secondary containment, open 5 ADS valves.

SAT/UNSAT NRC Scenario #4 - 2010 Limerick Operating Test Page 4 of 19

Appendix 0 Required Operator Actions Form ES-D-2 INITIAL SIMULATOR SETUP ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

Ensure materials for applicants:

REMA to support:

Withdrawal of Control Rod 30-31, and direction to increase power to 100%

ST-6-107-730-1 , Control Rod Coupling Check

Reset simulator to Scenario IC or IC-17 and perform the following:

- Lower power to 75% using Recirc, and INSERT control rod 30-31 to 00

- Ensure the following RCIC valves are closed with INFO Tags:

RCIC Outboard Steam Supply Valve HV49-1 F008 (close with key)

RCIC Steam Line Warm-up Bypass Valve HV49-1 F076 RC~C Turbine Steam Valve HV49-1 F045 RCIC Turbine TriplThrottle Valve HV49-112 RCIC Turbine Exhaust Valve HV49-1 F060 (close with key)

- Hang, info tag on HV49-1 F060

- Place RCIC Flow Controller MIA Station in MANUAL and close

-Close the Inboard MSIV HV 1 F022A

Ensure the following malfunctions are loaded:

Ensure the following remote functions are loaded:

N/A NRC Scenario #4 - 2010 Limerick Operating Test Page 5 of 19

Appendix 0 Required Operator Actions Form ES-O-2 ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

Ensure the following overrides are loaded:

Ensure the following triggers are built:

N/A (all trigger a manual)

Take out of FREEZE and ensure the following:

Reactor Power is 75%

Reset any annunciators that should not be present NRC Scenario #4 - 2010 Limerick Operating Test Page 6 of 19

Appendix D Required Operator Actions Form ES-D-2 INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1 Open Outboard MSIV HV-41-1 F028A MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate.

EVENT 2: Raise Reactor power to 100%

MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate.

EVENT 3: 1B Reactor Recirc Pump Shaft Shear v" MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 3

Respond to request for assistance as appropriate.

EVENT 4: 1 A TECW Pump Trip v" MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 4

- The 3 minutes, Report:

molded-case breaker for the "1 A" TECW Pump has tripped. There is no apparent cause for the "18" TECW Pump failure to auto start.

Electrical maintenance has been called on both issues.

-"18"18TECW TECW Pump Start preparations, 3 minutes, Report:

pump is ready for start

Respond to request for assistance as appropriate.

NRC Scenario #4 - 2010 Limerick Operating Test Page 7 of 19

Appendix 0 Required Operator Actions Form ES-O-2 EVENT 5: RWCU pump low flow and vibration

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 5

- When RWCU pump is tripped, DELETE:

MALF VIM123A01

Override on RWCU flow indication

ANN 112, H1

Respond to request for assistance as appropriate.

EVENT 6: Unisolable Steam Leak in the HPCI Room

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 6

-ThisFireis the Alarm, when dispatched, Report:

Fire Brigade Leader and I am responding to the fire alarm code."

INSTRUCTOR NOTE: Use OCOEE IS display for all temperature and steam flooding damper panel reports.

- HPCI 1BC208 RE HVAC TROUBLE, 5 minutes, Report:

room temperature indications is C F and both unit coolers are running Note: Must be above 120°F and no higher than 160°F (top of scale).

T-290, 6 minutes, Report:

-Give T-290 readings as requested from OCOEE T-103 Temperature

~

values from instructor terminal.

-Subsequent reports will be per the instructions of the CRS.

- The Fire Brigade, 6 minutes, But after T-290 call out, Report:

HPCI room door is hot and it sounds like there is a steam leak in the room.

- Steam 10C234 Stm Flood Damper Panel, 5 minutes, Report:

Flooding dampers on 10C234 indicate closed.

- WeHPCIareIsolation Valves, 10 minutes, Report:

unable to close the valves from the MCG breakers. Electrical maintenance has been contacted for troubleshooting.

Respond to request for assistance as appropriate NRC Scenario #4 - 2010 Limerick Operating Test Page 8 of 19

Appendix 0 Required Operator Actions Form ES-O-2 EVENT 7: RPS Failure "A" RFP Steam Supply Valve Fails MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate EVENT 8: "A" RFP Steam Supply Valve Fails MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate EVENT 9: "E" SRV fails closed MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate NRC Scenario #4 - 2010 Limerick Operating Test Page 9 of 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _4_ Event No.: _1_

Event

Description:

O Q e MSIV HV-41~ 2,-7--A 1, l illie Position Applicant's Actions or Behavior INFORM HP that the valves listed in step 4.3.2 will be operated BOP AND another steam flow path is being established.

ENSURE alignment of the following Main Steam System valves at pane110C601:

BOP

HV-C-41-1F020, OPEN

HV-41-142, OPEN

HV-41-143, OPEN ALIGN the following Main Steam System valves to drain condensate from upstream AND downstream piping around outboard MSIV at panel 1OC601 :

BOP

HV-41-1F016, OPEN

HV-41-1F019, OPEN

HV-41-1 F021 , OPEN OPEN HV-01-*04, "Main Steam Line Startup Drain" (STARTUP DRAIN), at panel 10C653.

BOP NOTE: Evaluator may prompt operator that:

. Ten minutes have passed DEPRESS white "Single" pushbutton on LlC M1 *R600, "Reactor RO Level Controller" (MASTER, LV), at panel10C603 to place DFWLC I Single-Element Control VERIFY white "Single" pushbutton is lit on LlC M1 *R600, RO i "Reactor Level Controller" (MASTER, LV), at panel *OC603 BOP Mark steps associated with MSIV Test Mode N/A

~

BOP OPEN HV-41-(022A)"lnboard MSIV," at pane110C601.

NRC Scenario #4 - 2010 Limerick Operating Test Page 10 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _4_ ~ ( Event No.: _1_

/1/ .

Event

Description:

Open Outboard MSIV HV-41 ~

I Time Position Applicant's Actions or Behavior ALIGN THE FOLLOWING MAIN STEAM SYSTEM DRAIN VALVES, AT PANEL 10C601:

BOP

HV-41-*F016, closed

HV-41-*F019, closed

HV-41-*F021, closed CLOSE HV-01-104, "Main Steam Line Startup Drain" (STARTUP BOP DRAIN), at panel 10C653.

DEPRESS white "Three" pushbutton on L1C M1 *R600, "Reactor BOP Level Controller" (MASTER, LV), at panel10C603 to return DFWLC to Three-Element Control VERIFY white "Three" pushbutton is lit on L1C M1 *R600, BOP "Reactor Level Controller" (MASTER, LV), at panel *OC603.

NRC Scenario #4 - 2010 Limerick Operating Test Page 11 of 19

Appendix D Required Operator Actions Form E5-D-2 Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _2_

Event

Description:

Raise gower to 100%

Time Position Applicant's Actions or Behavior Direct Power to raise power to 100% lAW REMA:

SRO

Withdrawal Control Rod 30-31

Raise power to 100%

Evaluator NOTE:

IF RBM Upscale Alarm is received: 108 Reactor 0-3, RBM UPSCALEINOPERATIVE Report the following:

Reactor Engineering directs taking Rod Select Key to "NO ROD SELECTED" to reset RBM RO Withdrawal Control Rod 30-31, and perform Coupling Check Inform PSD and Reactor Engineering of planned load increase to BOP 100% power. Obtain RE support for Rx power ascension to desired power level.

REQUEST a P-1 edit AND VERIFY the following for the SRO applicable Recirc loop operation configuration.

SRO COMPARE Core Megawatts Thermal (CMWT), Generator Mwe, BOP AND Main Turbine first stage pressure to ensure values provide i RO consistent indications of Rx power.

RO MAINTAIN Recirc Pump *A(B)P201 speed:s 1650 rpm].

SRO LIMIT subsequent rises in Rx power to a maximum increment of BOP 50 MWe AND MAINTAIN FRP < 0.95 for two Recirc loop RO operation.

NRC Scenario #4 - 2010 Limerick Operating Test Page 12 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _3_

Event

Description:

Reactor Recirc PumQ 1B Shaft Shear Time Position Applicant's Actions or Behavior RO Report Q\L\P, Observe power drop RO Observe RPV level swell SRO Enter OT-110 and OT-104 Observe Loop B jet pump flow decrease to zero and then BOP increase on reverse flow. 1B RRP indicated speed will increase to 100% and then return to the initial speed value.

BOP Determine that RRP 1B is not pumping.

SRO Directs shutdown of 1B RRP.

BOP TRIP M-G Set Drive Motor breaker.

SRO Enter OT-112, Recirculation Pump Trip CLOSE HV-043-*F031B, n*B Recirc Pump Disch Vlv" BOP (DISCHARGE OR HV-43-*F023B, "B Recirc Pump Suction Vlv" (SUCTION), for tripped Recirc Pump.

Per OT-112, Recirculation Pump Trip: Identify correct Power/Flow Map for given plant conditions. (ATTACHMENT 1 SRO

,All Feedwater Heaters In Service), and determine operating in the restricted region.

Direct RO to drive Rod<)to exit RESTRICTED REGION of .,-"

~

SRO I

Power/Flow Map RO Drive RO{to exit RESTRICTED REGION of Power/Flow Map SRO Reference T.S. 3.4.1.1 After 5 minutes has elapsed OPEN HV-043-*F031), "B Recirc BOP Pump Disch Vlv" (DISCHARGE B) OR HV-43-*F023B, "*B Recirc Pump Suction Vlv" (SUCTION B), for tripped Recirc Pump.

BOP Dispatch personnel to INVESTIGATE cause of Recirc Pump trip.

NRC Scenario #4 - 2010 Limerick Operating Test Page 13 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. 4 Event No.: 4 Event

Description:

1A TECW PumQ TriQ Ti mp I n .ition Applicant's Actions or Behavior I

I BOP Recognize trip of 1A TECW pump BOP Reference appropriate ARCs:

118 G-1, 1A Turb Encl Cooling Water Pump Ovid Trip

118 G-3, Turb Encl Cooling Water Htx Out Lo Press

118 AlB/C-1 ,

Air Compressor Trouble

118 AlB/C-3,

Air Compressor Aftercooler Hi Temp SRO Enter ON-117 BOP Dispatch Personnel to monitor Air Compressor temperatures BOP Recognize Failure of 1B TECW pump to auto start BOP Start 1B TECW pump BOP After starting 1B TECW pump, follow up with S14.6.A Placing Alternate TECW Pump in Service BOP Dispatch personnel to investigate Trip of 1A TECW pump BOP Dispatch personnel to investigate failure of 1B TECW pump to auto start NRC Scenario #4 - 2010 Limerick Operating Test Page 14 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. 4 Event No.: § Event

Description:

RWCU QumQ low flow and vibration Time Position Applicant's Actions or Behavior BOP Reference appropriate ARC's

107 C3, VIBRATION ALARM ALERT

10713, VIBRATION ALARM DANGER

112 H1, RWCU PUMP SUCTION LO FLOW

112 G 1, RWCU DISCHARGE HilLa PRESS BOP Recognize "1 A" RWCU pump Low Flow should have resulted in a pump trip BOP Trip "1 A" RWCU pump SRO Direct shutdown of RWCU BOP Notify Chemistry to conduct alternate sampling of coolant activity SRO Reference T.R.M. 3.4.4 NRC Scenario #4 - 2010 Limerick Operating Test Page 15 of 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. ~ Event No.: § Event

Description:

Unisolable Steam Leak in the HPCI Aoom Time Position Applicant's Actions or Behavior BOP Enter SE-8 and dispatch Fire Brigade Leader BOP Aeference appropriate AAC's 004 A3 B Aeac Encl HVAC PNL 1BC208 Trouble 117 A 1 HPCI OUT of Service 107 GS Div 2 Steam Leak Det Sys Hi Temp / Trouble SAO Enter T-103 SAO Direct use of PAMS, FZ and EQ PMS only SAO Direct performance of T -290 BOP Perform T-291 BOP Evacuate personnel from affected areas per SE-8, or SE-24 BOP Investigate 1BC208 Trouble alarm BOP Inform Fire Brigade of possible steam leak in HPCI Aoom BOP Attempt to isolate HPCI per T-2S0 BOP Dispatch Personnel to attempt to isolate HPCI isolation valves remotely from the MCC SAO Aecognize HPCI temperature cannot be maintained below MSO SAO Perform T-103 Shutdown AO BOP BOP Transfer House Loads I

NRC Scenario #4 - 2010 Limerick Operating Test Page 16 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. 4 Event No.: 6 7 Event

Description:

Unisolable Steam Leak in the HPCI Room Time Position Applicant's Actions or Behavior BPO Runback Recirc to minimum RO Scram the Reactor RO Place mode switch in SHUTDOWN

~

RO Recognize Failure of "An RPS (see event .s) 1 RO Recognize Scram Profile and automatic transfer to Startup Level control will not occur RO Recognize Failure of A RFP and control Level Manually using RFPs and Condensate SRO Implement TAR SRO Enter and execute T-101 RO Insert SRMsIIRMs RO Ensure Turbine Trip/Generator Lockout RO Reduce RPV pressure within allowable C/O rate BOP BPO Investigate 10C234 Steam Flooding Damper Alarm SRO Re-enter T -103 as required SRO Re-direct T-290 and T-291 as required SRO Recognize 2nd Area (309 room) temperature at MNO and i track to MSO SRO Direct T-112 Blowdown when MSO Temperature is exceeded in two areas

(.

('

BOP Open 5 ADS Valve(

9 Cv~

..l.. n rl)..-. /'I ...-!:--

fr:"'~l/\ ~/L-~~_

~ '-( ,Q~

NRC ScenariO #4 - 2010 Limerick Operating Test Page 17 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario 1\10. 4 Event No.: § f ~ 7(

Event

Description:

Unisolable Steam Leak in the HPCI Room

....., n ..

Applicant's Actions or Behavior Op-Test No. ILT09-1 Scenario No. ~ Event No.: 1 Event Description RPS Failure I Time Position Applicant's Actions or Behavior RO I Recognize Failure of "A" RPS RO Initiate RRCS RO Recognize ARI was successful

....J Op-Test No. ILT09-1 Scenario No. 4 Event No.: §.

Event

Description:

"A" RFP Steam SUQl:;~I~ Valve Fails

~ ..

Time Applicant's Actions or Behavior RO Recognize failure of "A" RFP HP Steam Supply Valve to open RO Take manual control of "B" or "C" RFP to control Level NRC Scenario #4 - 2010 Limerick Operating Test Page 18 of 19

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. 1 Event No.: ~

Event

Description:

"E" SRV fails closed

, lillie Position Applicant's Actions or Behavior BOP Recognize failure of "E" SRV to open, and report fail~

CRS v'~

SRO Direct BOP to open a non-ADS SRV I~

BOP Open a non-ADS SRV

- ~( JI ~Cfi TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:

5 SRVs are opened AND r-

Reactor Water level is stabilized .

r:~

I (

NRC Scenario #4 - 2010 Limerick Operating Test Page 19 of 19

PREBRIEF INSTRUCTIONS Initial Conditions:

Unit 1 at 79% power. Unit 2 is at 100% power.

Turnover:

Inoperable/Out of Service Equipment and ETR

Inboard MSIV HV-41-1 F022A inadvertently closed due to an Electrical Fault

Repairs complete on HV-41-1 F022A

RCIC is Out of Service for repairs to the RCIC Trip Throttle Valve, HV-50-112.

Repairs are expected to take 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Planned Evolutions:

Open the MSIV HV-41-1 F022A per S41 .3. B

Raise power to 100% power per GP-5, Attachment 1. The RE is not in the control room.

Appendix 0 Scenario Outline Form ES-O-1 Facility: Limerick 1 & 2 Scenario No.: 5 Op-Test No.: 1 Examiners: --- Operators: --------

Initial Conditions:

Reactor Power is 58%, Unit 2 100% power Turnover:

Inoperable/Out of Service Equipment and ETR None Planned Evolutions:

Maintain 100% power

Place HPCI in Full Flow Test, using the Manual Quick Start Method per S55.1.0 for oil sampling .

Completion of oil sampling is expected to take 15 minutes.

HPCI will be shutdown when sampling is complete

1A RHR is in Suppression Pool cooling to support HPCI operation Event Malt. No. Event Event No. Type* Description N/A N-BOP 1 Start HPCI using Manual Quick Start Method N-SRO MHP448B C-BOP

.2 HPCI Flow controller failure TS, C-SRO MFH564A C-SRO 3 2A Feedwater Heater Isolation R-RO MVI231A C-BOP 4 Oiv 1 LOCA Signal. 011 fails to start MOG420A TS, C-SRO C-RO MCU575 M 5 Unisolable Steam leak will occur in RWCU Regen Heat MCU195A Exchanger Room.

MCU195B MCU195C MRR440A M 6 LOCA via "1 An Recirc MMS067 MRH172C C-BOP 7 "C" RHR pump and liB" Core Spay pump fail to auto start.

MCS183B MRH171B C-BOP 8 Failure of B RHR pump and "A" RHR drywell Spray valves,.,.

MRH528C C-SRO C-RO

(N}ormal, (R)eactivity. (I)nslrument. (C)omponent. (M)ajor NRC Scenario # - 2010 Limerick Operating Test Page 1 of 20

Appendix D Required Operator Actions Form ES-D-2 SCENARIO

SUMMARY

Event 1: The crew is directed to perform a quick start of HPCI per S55.1.D Objective: Evaluate the crew's ability to start HPCI and place in Full Flow test Event 2: When HPCI is in Full Flow test, it will experience a flow controller failure.

Objective: Evaluate the crew's ability to secure HPIC due to a malfunction and place it in a safe configuration. In addition, Tech Spec's should be referenced in order to determine the applicable LCO.

Event 3: Once Tech Specs have been referenced and the appropriate action determined for HPCI, an isolation of the 1C FW Heater string results in Feedwater temperature excursion and power rise ..

Objective: Evaluate the crew's response to the feedwater heater string isolation and implementation of OT-104.

Event 4: When actions for the abnormal event are complete and power is being reduced, Excess Flow check valve fails resulting in an inadvertent Div 1 LOCA Signal.

Objective: Determine the crew's ability to diagnose and respond to an inadvertent LOCA signal. Complicating the event will be a failure of 011 EDG to auto start.

Event 5: When actions for LOCA signal are complete, an unisolable leak will occur in RWCU Regen Heat Exchanger Room.

Objective: To determine the crews ability to take appropriate actions per T-103 and SE-S. Track and trend RWCU room temperatures and attempt to isolate the leak and perform a T-103 Rx Shutdown.

NRC Scenario # - 2010 Limerick Operating Test Page 2 of 20

Appendix 0 Required Operator Actions Form ES-O-2 Event 6: When actions for T -103 are complete and the Rx has been SID and stabilized, a leak will develop in the Drywell progressing to a 3% LOCA. Complicating the event will be a failure of the A RHR pump and B RHR spray valves.

Objective: To determine the crew's ability to take appropriate actions per OT-101, T-101, and T-102. Track Containment parameters and perform an Emergency Blowdown per T -112 due to PSP.

Event 7: After the shutdown the, "C" RHR pump and "B" Core Spay pump will fail to auto start.

Objective: To determine the crews ability to respond to a failure of Emergency Core Cooling System pumps to start during a LOCA, and take action to manually start the pumps.

Event 8: When the LOCA has occured, HV-51-1F021A Drywell Spray Valve fails closed and "1 B" RHR pump will trip.

Objective: To determine the crew's ability to take appropriate actions to spray the drywell with RHRSW.

Termination Point: The scenario may be terminated when a T-103, Rx Shutdown has been accomplished, An Emergency Blowdown is complete, and Containment Spray is in service.

NRC Scenario # - 2010 Limerick Operating Test Page 3 of 20

Appendix 0 Required Operator Actions Form ES-D-2 CRITICAL TASKS

1. T-103.2 Manually scram the reactor.

Standard: After it is determined that one area in Table SCC-2 has exceeded max safe op value, manually scram the reactor.

SAT/UNSAT

2. T-102.2 Perform emergency blowdown per T-112.

Standard: When Suppression Pool Pressure cannot be maintained below the Pressure Suppression Pressure (PC/P-3) curve and before Drywell pressure exceeds 55 psig, open 5 SRV's SAT/UNSAT

3. T-102.1 Spray the Drywell per T-225.

Standard: When Drywell temperature and pressure are on the SAFE side of curve PC/P-2, spray the Drywell before exceeding 340°F or 55 psig.

SAT/UNSAT NRC Scenario # - 2010 Limerick Operating Test Page 4 of 20

Appendix 0 Required Operator Actions Form E5-0-2 INITIAL SIMULATOR SETUP ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

Ensure materials for applicants:

Provide crew with working copy of S49.1.0

Reset simulator to Scenario IC or and perform the following:

100% Power Place "1 A" RHR is Suppression Pool Cooling AND Load scenario OR Perform the following:

Ensure the following malfunctions are loaded:

,2 TI""

RWCU I_Valve HV44*1F004 Foi,A!*i< True

,RWCU Isolation Valve HV44-1F040Eai,As';' T,ue

'RocfcUation loop ARuoM> 1

FeedwllterH"""" 12t>l.....tSen,;,glineF;,iI,High T,ue Imlrumem line eleai< D""""beam oIXII42*1F045A T,ue Dio,eI Gen 011 Faib 10 Auto Slat To,,,;

FlHflfu.P1C F.;i$ioAutoSIoll

CoroSI".y""",,, 18 FoiSt~AutoS~1

RHA Ptm'Ip 18 Iri!>'

RHA Ccnlainmenl

Ensure the following remote functions are loaded:

N/A

Ensure the following overrides are loaded:

N/A NRC Scenario # - 2010 Limerick Operating Test Page 5 of 20

Appendix 0 Required Operator Actions ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

Ensure the following triggers are built:

Reset any annunciators that should not be present NRC Scenario # - 2010 Limerick Operating Test Page 6 of 20

Appendix D Required Operator Actions Form ES-D-2 INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Start HPCI using Manual Quick Start Method MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate.

EVENT 2: HPCI Flow Controller

./ MALFUNC"rlON I REMO"rE FUNCTION I REPORT

Activate Trigger 2.

After 5 minutes, Report:

- I&C will bring a TRT to MCR for approval to troubleshoot the controller

Respond to request for assistance as appropriate.

EVENT 3: 2A Feedwater Heater Isolation

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 2.

-"I amIf requested:

getting a brief from HP before I can enter the condenser bay."

-"Actual If requested, 15 minutes after last report:

level appears low, request I&C investigate"

Respond to request for assistance as appropriate.

NRC Scenario # - 2010 Limerick Operating Test Page 7 of 20

Appendix D Required Operator Actions Form ES-D-2 EVENT 4: Div 1 LOCA Signal

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 3.

- XV1OC218 Panel, 5 minutes Report:

42-1 F045A indicates closed When requested to reset Div I Shunt trips, After 5 Minutes Toggle:

RED107, Div I shunt trip to RESET

RED108, Div I shunt trip to RESET Then Report:

-Div I Shunt trips have been reset

Respond to request for assistance as appropriate ..

EVENT 5: Leak in RWCU Regen HX Room

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 4

-GiveT-290 5 minutes, Report:

T-290 readings as requested from OCOEE T-103 Temperature values from instructor terminal

- There Fire Brigade, 6 minutes after T-290 call out Report:

is no evidence of fire in the Reactor Enclosure. It's extremely hot and humid and the sound of blowing steam can be heard on Rx 283' elevation.

Isolate RWCU leak from outside MCR, If directed, 4 minutes after Reactor Scram:

-Remove MCU195A and verify valve closed Then Report:

- RWCU isolation valve HV-44-1 F001 has been closed from the MCC.

Respond to request for assistance as appropriate.

NRC Scenario # - 2010 Limerick Operating Test Page 8 of 20

Appendix D Required Operator Actions Form ES-D-2 EVENT 6: LOCA via "1 A" Recirc

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 5

SE-10 Floor Actions, 10 minutes:

-Load All SE-10 Floor Actions with ,Time Delays Scenario

-Report the status of individual resets as requested or when all resets are timed out report "All SE-10 Floor Actions are complete."

Respond to request for assistance as appropriate.

EVENT 7: IIC" RHR pump and liB" Core Spay pump fail to start automatically MALFUNCTION I REMOTE FUNCTION I REPORT

Respond to request for assistance as appropriate.

EVENT 8: Failure of B RHR pump and"A" RHR drywell Spray valve

./ MALFUNCTION I REMOTE FUNCTION I REPORT

HV-15-1 F021A Drywell Spray Valve, 8 minutes, Report :

- HV55-1 F021A (Drywell Spray Valve) valve would not operate from the MGG when attempted.

When Requested to close 051-1 F048, WAIT 4 MINUTES, but only AFTER SLOWDOWN, Report:

- 051-1 F048 is closed

Respond to request for assistance as appropriate. i NRC Scenario # - 2010 Limerick Operating Test Page 9 of 20

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. § Event No.: 1 Event

Description:

Start HPCI using Manual Quick Start Method Time Position Applicant's Actions or Behavior SRO Give permission to start HPCI BOP Obtain a copy of S55.1.D HPCI SYSTEM FULL FLOW FUNCTIONAL TEST BOP ENSURE the following valves aligned as indicated(

CLOSED):

HV-55-1 F071 HV-55-1 F008 HV-55-1 F011 HV 1 F022 BOP OPEN HV-55-F011, CONDENSATE RETURN BOP START 10P216, "Barometric Condenser Vacuum Pump" (VACUUM PUMP).

BOP MONITOR Suppression Pool temperature per ST-6-060-390-1 , Suppression Pool Temperature Check.

Que Canidate:

-Another operator is monitoring Suppression Pool temperature BOP INFORM HP of changing radiological conditions due to HPCI system start.

MANUAL QUICK START BOP ENSURE FC 55 *R600, "HPCI Pump Discharge Flow Controller" (FL), set to 5,600 gpm in "AUTO."

NRC Scenario # - 2010 Limerick Operating Test Page 10 of 20

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. §. Event No.: 1 Event

Description:

Start HPCI using Manual Quick Start Method Time Position Applicant's Actions or Behavior BOP Simultaneously OPEN HV-55-1 F001, "HPCI Steam Supply" AND START *OP213, "Auxiliary Oil Pump" (AUX OIL PUMP).

BOP WHEN SI 56 *61, "Turbine Speed" (S), starts to go up, THEN Immediately THROTTLE open HV 55 *F008, "HPCI Test Loop Shutoff" (TEST ISOL), until desired 'flow is obtained, while maintaining turbine speed greater than 2,200 rpm.

BOP VERIFY FV-56-112 "Turbine Stop Valve" OPEN BOP VERIFY FV-56-111 "Turbine Control Valve" OPEN BOP WHEN FV-56-112 , "Turbine Stop Valve" opens, THEN VERIFY HV-56-F059, "HPCI Lube Oil Cooling Water Valve,"

opens.

NRC Scenario # - 2010 Limerick Operating Test Page 11 of 20

Appendix 0 Required Operator Actions Form E5-0-2 Op-Test No. ILT09-1 Scenario No. §. Event No.: g Event

Description:

HPCI Flow Controller Time Position Applicant's Actions or Behavior RO Report Q / L / P BOP Reference appropriate ARC:

107 REACTOR 1-2, Vibration Alarm Alert

107 REACTOR 1-3, Vibration Alarm Danger BOP Recognize HPCI Controller Failed Low BOP Take HPCI Flow Controller to MANUAL and raise HPCI Turbine Speed to > 2200 rpm AND/OR Trip HPCI BOP Dispatch personnel to investigate HPCI SRO Reference Tech Spec 3.5.1 NRC Scenario # - 2010 Limerick Operating Test Page 12 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. §. Event No.: Q Event

Description:

FW Heater Isolation I III _

'"' Applicant's Actions or Behavior RO Report Q / L / P BOP Reference ARC:

102-G4 1A & 2A FW Heater Isolation BOP Recognize isolation of "An FW Heater String in progress BOP Attempt Alarm reset per ARC Action RO Recognize Rx Power Rise SRO Enter OT-104 RO Restore power to below pre-transient levels I

SRO Verify plant operating in a valid region of power/flow map / FW Operating region per attachment 1 RO Demand control rod position report BOP Verify FW inlet temperature RO Reduce power to <85% per the RMSI BOP Investigate cause of FW heater isolation NRC Scenario # - 2010 Limerick Operating Test Page 13 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. § Event No.: 1 Event

Description:

Inadvertent Div 1 LOCA signal

. Time Position Applicant's Actions or Behavior RO Report QIUP SRO Recognize Inadvertent Div 1 LOCA signal BOP RO BOP Reference appropriate ARCs

112 E5, EXCESS FLOW CHECK VALVE OPERATED PANEL C218

110 B3, ADS HIGH DRYWELL BYPASS TIMER INITIATED BOP Dispatch EO to 10C218 Panel BOP Execute SE-1 0 for Div I only BOP ecognize and report RCIC running and injecting BOP Secure RCIC Injection BOP Recognize that the D11 DIG did not AUTO start and manually start ,-~-- .....--.. c_---*--~*-~

BOP Recognize SJAE 1st stage air valves going closed and re BOP Track Main Condenser Vacuum SRO I If vacuum drops, enter OT-116 BOP ecure "1 A" CS pump BOP Secure "1A" RHR pump or Restore to Suppression Pool Cooling BOP Inhibit Div 1 Auto ADS NRC Scenario # - 2010 Limerick Operating Test Page 14 of 20

Appendix D Required Operator Actions Form E5-D-2 Op-Test No. ILT09-1 Scenario No. §. Event No.: 1 Event

Description:

Inadvertent Div 1 LOCA signal Time Position Applicant's Actions or Behavior BOP Call out for SE-1 0 Div 1 floor actions BOP Verify ESW pump running on diesel start BOP Restore Drywell Cooling SRO Reference TS:

3.3.3 - Div 1 ADS INOP

3.5.1 ECCS

3.6.3 - XV42-1 F045A actuation / Bypass of PCIVs

3.8.1.1 - 011 failed to Auto start BOP Contact Work Week Manager for troubleshooting and support NRC Scenario # - 2010 Limerick Operating Test Page 15 of 20

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. § Event No.: § Event

Description:

Leak in RWCU Regen HX Room Time Position Applicant's Actions or Behavior Report OIUP RO Reference ARCs

107 F5, DIV 1 Steam Leak DET SYS HI TemplTrouble

107 15, DIV 4 Steam Leak DET SYS HI TemplTrouble SRO Enter SE-8 on Fire alarms BOP Dispatch Fire Brigade BOP Evacuate RE per SE-24 SRO Enter and execute T -103 on Div I and Div IV Steam Leak Detection Alarms SRO Direct crew to use PAMSI FZ lEa PMS only SRO Direct T-290 SRO Direct and attempt to isolate RWCU per T-250 BOP Recognize and report failure of RWCU isolation valves BOP Direct personnel Outside MCR to close RWCU isolation valves SRO Direct T-103 Rx Shutdown BOP Transfer House Loads BOP Runback Recirc to Minimum.

RO Manually Scram At 60% core flow RO Mode Switch to SID NRC Scenario # - 2010 Limerick Operating Test Page 16 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. Q Event No.: Q Event

Description:

Leak in RWCU Regen HX Room Time po",itinr'\ Applicant's Actions or Behavior SRO Enter T-101 on <+12.5" RO Verify all rods in BOP Trip the MT and ensure generator lockout RO Stabilize a~i.!!, RPV level 12.5" and 54" SRO Implemerlt!~ S SRO Reduce RPV pressure wlo exceeding CID rate limit BOP Recognize and report RWCU is isolated NRC Scenario # - 2010 Limerick Operating Test Page 17 of 20

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No. ILT09-1 Scenario No. § Event No.: 2 Event

Description:

LOCA via "1 A" Recirc I Po~ition Applicant's Actions or Behavior RO Recognize, report and track rising DW pressure BOP BOP Perform OT -101 Immediate Operator Actions:

-Determine Drywell cooling is maximized.

-Determine Containment Inerting is not in progress SRO Enter and direct follow-up actions of OT-101 SRO Enter T-102 when Drywell pressure exceeds 1.68 psig.

SRO Re-enter T-1 01 > 1.68#

BOP Take Action to control HPCI on Drywell Pressure 1.68# start BOP Place a Loop of RHR in suppression pool spray per T-225 i BOP Start RHRSW to support SP Spray BOP Bypass and restore Drywell cooling SRO Re-enter T -102 when Drywell temperature exceeds 145 deg.

SRO Enter T -112 when safe side of T -102 curve PC/P-3 cannot be maintained.

BOP Open all 5 ADS valves.

BOP Perform SE-10 when the LOCA signal occurs.

BOP Direct SE-1 0 actions to personnel outside MCR BOP Prevent injection not needed for core cooling RO NRC Scenario # - 2010 Limerick Operating Test Page 18 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. § Event No.: Z

~tl j (l-Event

Description:

"C" RHR QumQ and "B" Core SQay QumQ will fail to auto s art. ~

fl?~ ~

I II lit:: Position Applicant's Actions or Behavior t~

BOP Recognize that the "1 Bf! CS Pump did not AUTO start and manually start BOP Recognize that the "1 C" RHR Pump did not AUTO start and manually start.

Op-Test No. ILT09-1, Scenario No. § Event NO':!t

~..£ ".1(' !) t-J 5(Z~ til' V ~--,,~f -t ...--:>

Event

Description:

Failure of B RHR QumQ and "A RHR drvwell SQray valveEb lime t-'osition Applicant's Actions or Behavior SRO Direct Drywell Spray BOP Recognize HV-51-1 F021 A Drywell Spray Valve fails to open BOP Recognize "1 B" RHR Pump Trip SRO DIRECT Drywell Spray using RHRSW INITIATING DRYWELL SPRAY USING RHR SERVICE WATER BOP ENSURE 1BP202, "RHR Pump" not running.

BOP PLACE RHR Service Water Loop B OR D in service BOP Dispatch personnel to close 051-1 F048 NRC Scenario # - 2010 Limerick Operating Test Page 19 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No. ILT09-1 Scenario No. 5 Event No.: ~

Event

Description:

Failure of B RHR QlJmQ and "An RHR dtYwell SQra~ valves Time Position Applicant's Actions or Behavior BOP OPEN the following RHR Service Water/RHR Emergency Crosstie Valves at 10C601

HV 51 1F073, "RHR Service Water Crosstie"

HV 51 1F075, "RHR Service Water Crosstie" NIA Simultaneously PERFORM the following to maintain RHR Service Water discharge pressure 75 to 120 psig as indicated on PI-12-001 B-1 "Pump BID Disch" (Px), at 00C667 (Main Control Room):

RO Throttle Fully CLOSED HV-51-1 F068B, "1 B RHR Htx SW Outlet Vlv" (1 B) at 00C667 (Main Control Room).

BOP Throttle Fully OPEN HV 51 1F016B, "1 B RHR Cntmt Spray Line Outboard PC IV" (OUTBOARD) to initiate spray AND MAXIMIZE flowrate as indicated on FI51 1 R603B, FL.

TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:

RPV Pressure < 300 PSIG RPV water level is restored to normal band Drywell Spray is in service using RHRSW NRC Scenario #*2010 Limerick Operating Test Page 20 of 20

PREBRIEF INSTRUCTIONS Unit 1 Reactor Power is 100%, Unit 2 100% power Inoperable/Out of Service Equipment and ETRs

None Planned Evolutions:

Maintain 100% power Place HPCI in Full Flow Test, using the Manual Quick Start Method per S55.1.D for oil sampling.

Completion of oil sampling is expected to take 15 minutes.

HPCI will be shutdown when sampling is complete

1A RHR is in Suppression Pool cooling to support HPCI operation

v t e Letter Sequence Draft Other
TAC:U01767, (Open)
Initiation Acceptance Administration Questions Answers Results Approval... Other: ML102920667, ML102920673, ML102920676, ML103080887
MONTHYEAR2010-08-20 [Table View]

ML102920658

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