Text

Draft Operating Exam (Sections a, B, C) (Folder 2)
	ML12072A353
Person / Time
Site:	FitzPatrick
Issue date:	01/11/2012
From:	; Entergy Nuclear Generation Co
To:	Peter Presby; Operations Branch I
	Jackson D
Shared Package
ML113070677	List: IR 05000333/2012301; ML113330864; ML120610564; ML12072A344; ML12072A351; ML12072A353; ML12072A356; ML12116A225; ML12116A242; ML12116A252; ML12116A259; ML12116A275; ML12116A290;
References
	TAC U01843
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{{#Wiki_filter:-------------------- NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO L8J RO D NLO D ALTERNATE SUCCESS PATH TITLE: Verify Fuel Movement Sheets OPERATOR: DATE: EVALUATOR: EVALUATOR SIGNATURE: CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 20 Actual Time (min): JPM RESUL TS*: SAT UNSAT (Circle one) COMMENT SHEET ATTACHED: Yes f No (circle one) SYNOPSIS: Fuel movement sheets are reviewed to see if there are errors in orientation or placement of fuel. TASK STANDARD: Correctly identifies the fuel movement errors. EVALUATION METHOD: EVALUATION LOCATION: ~ Perform Plant r------i L-=:J Simulate Simulator f---------j Control Room f---------j 2S Classroom (Admin) Prepared: Date: Reviewed: Date: I 7 Approved: Date: r/trjl-e-E~TERGY :-ILCLEAR Page I ofl3 E-DOC TITLE: Verify Fuel Movement Sheets E-DOCNO. REVISION NO. NRC 2012 Admin 1 0 I

REVISION LOG Revision Number: 0 Date Originated: Pages Affected:

== Description:== i I ENTERGY NUCLEAR Page 2 of13 E-DOC TITLE: Verify Fuel Movement Sheets E-DOC NO. REVISION NO. NRC 2012 Admin 1 I 0

TASK

Title:

Task Number K&ASYSTEM: K&A RATING: 2.1.35 SRO

3.9 REFERENCES

OSP-66.001 SIMULATOR CONDITIONS: N/A.

GENERAL TOOLS AND EQUIPMENT: OSP-66.001 CRITICAL TASKS: Identified with a

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. State the following:

Today is October 2,2012.

Refuel outage R20 is underway.

A refueling error occurred last night and fuel movement was halted.

You are the oncoming Refuel Bridge SRO

3. Solicit and answer any questions the operator may have.

INITIATING CUE: State the following: The Shift Manager directs you to verify the previous shifts in-core placement of components, steps 1 19, from the leA Fuel Movement Sheets. ENTERGY NUCLEAR Page 3 ofJ3 E-DOC TITLE: Verify Fuel Movement Sheets E-DOC NO. REVISION NO. NRC 2012 Admin 1 i 0

i PERFORMANCE: Notes START TIME:

1.

Procedure Step: Standard Cue Notes EVALUATOR: Provide the candidate with the attached handouts (Fuel movement sheets and pictures of the core cells). Provide OP-66.001 if requested. IF the operator asks about Spent Fuel Pool verification, THEN tell the operator he is only responsible for in-core verifications. Verify correct loading of Control Cell 38-35. Operator determines that the following bundles are in the correct location and orientation:

JLV675
JLV682 JLK804
JLK817 Results I SAT UNSAT D

D

2.

Determine the INCORRECT loading of Control Cell 14-35. Procedure Step: Standard Operator determines two Control Cell 14-35 bundles are the correct bundles but in the INCORRECT orientation:

JLV678 I

~ILV670 Cue I Notes I Bundles JLV678 and JLV670 are 180 0 out. Results SAT Critical Step UNSATCI I~ E:NTERGY NUCLEAR Page 4 of 13 I E-DOC TITLE: Verify Fuel Movement Sheets E-DOCNO. REVISION NO. I NRC 2012 Admin 1 o

3.

Procedure Step: Standard Cue i Notes I

4.

Procedure Step: Standard Cue Notes Results

5.

Procedure Step: Standard I Cue I Notes Results I Verify the correct loading of Control Cell 14-35. I Operator determines two Control Cell 14-35 bundles are the correct bundles . and in the correct orientation:

JLK805
JLK812 i
SAT i

I I I I I I I Determine the INCORRECT loading of Control Cell 38-15. Operator determines one Control Cell 38-15 bundle is in the correct orientation but is the INCORRECT bundle

JLV668 i

i The correct bundle should be JL V698. SAT Critical Step UNSATI I I D I Verify the correct loading of Control Cell 38-15. Operator determines three Control Cell 38-15 bundles are the correct . bundles and in the correct orientation:

JLV674
JLK807
JLK820 I

SAT UNSAT D D I ENTERGY NUCLEAR Pa e 5 of 13 E-DOC TITLE: Verify Fuel Movement Sheets E-DOCNO. REVISION NO.

NRC 2012 Admin 1
6.

Determine the INCORRECT loading of Control Cell 14-15. Procedure Step: Standard Operator determines that the two single blade guides are in the wrong orientation. I I Cue i I Notes IThe single blades are 180 0 out. The blade guide channel spacers should be ! turned towards the control rod. I i Results I SAT D Critical Step UNSATC Terminating Cue: This completes this JPM. STOP TIME: ENTERGY NUCLEAR Page 6 of 13 E-DOC TITLE: Verify Fuel Movement Sheets E-DOC NO. REVISION NO. NRC 2012 Admin 1 0

HANDOUT Today is October 2.2012. Refuel outage R20 is underway. A refueling error occurred last night and fuel movement was halted. You are the oncoming Refuel Bridge SRO The Shift Manager directs you to verify the previous shifts in-core placement of components. steps 1

19. from the leA Fuel Movement Sheets.

ENTERGY NUCLEAR Pa~e 7of13 IE-DOC TITLE: E-DOC NO. REVISION NO. NRC 2012 Admin-l I 0

HANDOUT ATTACHMENT 9.1 ITEM CONTROL AREA TRANSFER FORM (1) (2) (3) (4) (4a) (4b) (10) .!:!:.-""""~",,--.-,-/-,,,S,-,,-*.",ewwI.in=""'______ Lines _1-12 thru Date Oct 1, 2012 Line Description Serial No. From To Performed Datc/Timc Verified No. or Mat.:rial Eqllipment ID le/\\ Coord. le/\\ Coord. hy Executed by (5)

15)

(6) t7) (8) (9) (IJ) (12) (13) FUEL BUNDLE JLV675 SFP 26-BB-2 CORE 39-34 a!ll WI02112 03lJO eo \\ FUEL BUNDLE JLV682 SFP 26-CC-2 CORE 37-36 a!ll TOI02112 031() eo

2 DOUBLE BLADE GUIDE N/A CORE 39-36 37-SFP 26-EE-2 a!ll 10/02/12 0320 eo 3

34 26-DD-l FUEL BlJNDLE JLK804 SFP 26-DD-2 CORE 37-34 a!ll 10102112 0330 eo <1 FUEL BUNDLE JLKS!7 SFP 26-EE-2 CORE 39-36 a!ll 10102/12 0340 (>.:V 5 FUEL BUNDLE JLV678 SFP 26-FF-2 CORE 15-34 a!ll 1()102112 0350 eo 6 7 FUEL BUNDLE JLV670 SFP 26-W-3 CORE \\3-36 a!ll 10/02/12 0400 C:v 8 DOUBLE BLADE GUIDE N/A CORE 15-36 13-SFP 26-DD-2 a!ll W/02/12 04W e:v 34 26-CC-\\ FUEL BUNDLE JLK805 SFP 26-X-3 CORE 13-34 a!ll 10/02/12 0420 C:v 9 l(l FUEL BUNDLE JLK812 SFP 26-Y-3 CORE \\5-36 a!ll W102/12 043lJ C:v FUEL BUNDLE JLV698 SFP 26-Z-3 CORE 39-14 a!ll W/lJ2112 0440 e:v II FUEL BUNDLE JLV674 srp 26-AA-3 CORE 37-16 a!ll 10102/12 0450 C:v 12 NOTES/COMMENTS Line #: Line #: Line #: Line #: (14) SNM Records Updated by: ____________ Lines Thru Date (15) Verified by: _....____________ Lines Thru Date ENTERGY Nl'CLEAR Pa2c80f13 E-DOC TITLE: E-DOCNO. REVISION NO. NRC 2012 Admin-l 0

HANDOUT ATTACHMENT 9.1 ITEM CONTROL AREA TRANSFER FORM (1) Number: R20-000 1 (2) Issued (Date): ~O~ct.:....l,,-,",--=2,-,<0..!..:12,,----c-:--:-:--:-:--:_-:--:__ (3) Reason for Transfer: __Cycle 20 Refueling Ouage (4) Prepared By: ___ih~!Q[!.!..lL~~~!___..... ___________________ (4a) ReviewedBY: __e~~~~~~~~~_______________________ (4b) Additional Approvals By: (10) SNMC Approval: S. Carolin!,.L/-""S"-,,0.vwtin""",,~',t;______ Lines _13-19 thru Date Oct 1, 2012 j~il1e No. Description of Malt:rial (5) Seri~1 No. Equipment (5) I ID ICA (6) From

Coord, (7)

ICA (8) To

Coord, (9)

Performed by (11) Daterrime Executed (12) Y<:rified by (13) 13 14 15 16 17 18 19 20 21 22 ~ DOUBLE BLADE GUIDE FUEL BUNDLE FUEL BUNDLE SINGLE BLADE GUIDE SINGLE BLADE GUIDE I FUEL BUNDLE FUEL BUNDLE N/A N/A N/A N/A N/A N/A JLK807 JLK820 N/A N/A JLynO JLyn5 CORE SFP SFP SFP SFP CORE CORE 39-11 37 14 26-88-1 26-CC-I 25-FF-II 25-FF-I 13-14 15-16 I SFP CORE CORE CORE CORE SFP SFP 26-CC-2 26-8B-I 37-14 39-16 13-16 15-14 35-N-7 35-N-6 a9J a9J a9J a9J a9J a9J a9J 1O/()2/12 ()S()() 1()/()2/12 ()SI() to/021t2 0520 10102/12 ()53() 10102/12 ()S4() 10/02/12 0550 10102/12 0600 e!lJ e!lJ e:o e:o e!lJ e:t> e!lJ NOTES/COMMENTS Line #: Line #: Line#: ____ (14) SNM Records Updated by: ___________ Lines Thru Date (15) Verified by: ____________ Lines Thru Date E-DOC TITLE: ENTERGY NUCLEAR E-DOC NO. NRC 2012 Admin-l Page90fl3 REVISION NO. 0 I I

HANDOUT S N 0 0 U T H H \\VEST CONTROL CELL 38-35 ENTERGY NUCLEAR Page 10 of 13 I E-DOC TITLE: E-DOCNO. REVISION NO. NRC 2012 Admin-l I 0 I

HANDOUT N 0 R I H IE-DOC TITLE: EAST '"VEST CONTROL CELL 14-35 ENTERGY NUCLEAR E-DOCNO. NRC 2012 Admin-l S 0 U rI-H Pa~e II of 13 REVISION NO. o I

HANDOUT E,.L\\ST S N 0 o 1J 'Ii. l T H II CONTROL CELL 38-15 E~TERGY NUCLEAR Pal1;e 12 of 13 E-DOC TITLE: E-DOCNO. REVISION NO. NRC 2012 Admin-l 0 i

N o f H IE-DOC TITLE: HANDOUT EAST \\VEST CONTROL CELL 14-15 ENTERGY NUCLEAR E-DOC NO. NRC 2012 Admin-1 s o U T H Page 13 of 13 REVISION NO. 0 I

NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO~ ROO NLOO ALTERNATE SUCCESS PATH 0 TITLE: IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING OPERATOR: DATE: EVALUATOR: EVALUATOR SIGNATURE: __________ CRITICAL TIME FRAME: Required Time (min): I N/A Actual Time (min): N/A I PERFORMANCE TIME: Average Time (min): I 15

Actual Time (min):

I JPM RESUL TS*: SAT UNSAT (Circle one) COMMENT SHEET ATTACHED: Yes / No (circle one) SYNOPSIS: Using Tech Specs and NMM Operations Procedures, the candidate makes a determination on the adequacy of plant staffing. TASK The task will be complete when the candidate has identified the plant only needs 1 STANDARD: more RO and1 more NPO. EVALUATION METHOD: EVALUATION LOCATION: Perform Plant 1------1 I------i Simulate Simulator 1------1 Control Room I-------j Classroom (Admin) Prepared: Date: Date: Approve' Date: I I Superintenden, Operations Training (or Designee) I I ENTERGY NUCLEAR Page 1 of7 I E-DOC TITLE: E-DOC NO. REVISION NO. . IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING 2012 NRC SRO A-2 0

REVISION LOG I Revision Number: 0 . Date Originated: I Pages Affected:

== Description:== I r ENTERGY NUCLEAR Pa~e 2 of7 . E-DOC TITLE: E-DOC NO. REVISION NO. ! IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING 2012 NRC SRO A-2 0

TASK

Title:

Task Number K&ASYSTEM: K&ARATING: 2.1.5 2.9/

3.9 REFERENCES

EN-OP-115 Tech Specs SIMULATOR CONDITIONS: N/A. GENERAL TOOLS AND EQUIPMENT: N/A CRITICAL TASKS: Identified with a

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. State the following two paragraphs:

a) "The task conditions are as follows: Plant status is: ? Reactor scrammed y All rods in ? Rx Press - 900 psig )- Night Shift has just started ENTERGY NUCLEAR Page 3 of7 ~E-DOC TITLE: E-DOC NO. REVISION NO.

IDENTIFY ADEQUATEIINADEQUATE SHIFT STAFFING 2012 NRC SRO A-2 0

Current shift staffing includes the following 1 - Shift Manager (SM) (SRO) 1 - Control Room Supervisor (CRS) (SRO) 1 - Field Support Supervisor (FSS) I Shift Technical Advisor (STA) (Non-Licensed) 1 - At The Controls Operator (ATC) (RO) 1 - Senior Nuclear Operator (SNO) (RO) 4 - Nuclear Power Operators (NPO) (Non-Licensed) 0 - Health Physics Tech (HP) (Non-Licensed)

3. Solicit and answer any questions the operator may have.

INITIATING CUE: State the following: ConSidering only the above positions, utilize: Tech Specs Nuclear Management Manual (NMM) Operations Procedures to determine if required shift staffing is met and, if not met: Any required actions Any required time limits I E~TERGY ~UCLEAR Page 4 of7 ! E-DOC TITLE: E-DOC NO. I REVISION NO. i IDENTIFY ADEQUATEIINADEQUATE SHIFT STAFFING 2012 NRC SRO A-2 0

PERFORMANCE: Notes The use/research of procedures may occur in any order. START TIME:

1.

Determine required staffing and required action/time limit. i Procedure Step: Standard Candidate determines that: An HP is required

Replace within 2 hours Cue Notes This step is from Tech Specs 5.2.2.c Results SAT Critical Step UNSATD I

I I I

2.

Determine required staffing and required action/time limit. Procedure Step: Standard Candidate determines that

One more RO or SRO is required
Replace within 2 hours Cue Notes This step is from EN-OP-115 "Conduct of Operations", Attachment 9.5. The candidate must determine the plant is in Mode 3 and that AOP-43 is applicable in Mode 3. Therefore, the Safe Shutdown/Fire Brigade Staffing is i

not met. i Results SAT Critical Step UNSATI D I I

3.

Determine required staffing and required action/time limit. Procedure Step: Standard Candidate determines that:

One more NPO is required
Replace within 2 hours Cue Notes This step is from EN-OP-115 "Conduct of Operations", Attachment 9.5. The candidate must determine the plant is in Mode 3 and that AOP-43 is applicable in Mode 3. Therefore, the Safe Shutdown/Fire Brigade Staffing is
not met.

Results SAT Critical Step UNSATD D ENTERGY NUCLEAR Paee 5 of7 E-DOC TITLE: E-DOC NO. REVISION NO. IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING 2012 NRC SRO A-2 0 I

4.

Determine that other positions meet staffing requirements. i Procedure Step: Standard After reviewing Tech Specs and Operations Procedure, candidate does NOT identify other positions as being understaffed. Cue i Notes Results SAT UNSAT D D Terminating Cue: When candidate has identified the missing positions, inform the candidate "This completes the JPM". STOP TIME: ENTERGY NUCI.EAR Page 6 of7 IE-DOC TITLE: E-DOC NO. REVISION NO. I . IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING 2012 NRC SRO A-2 0 I

HANDOUT Plant status is: y Reactor scrammed y All rods in Rx Press - 900 psig y Night Shift has just started Current shift staffing includes the following y 1 - Shift Manager (SM) (SRO) y 1 - Control Room Supervisor (CRS) (SRO) y 1 - Field Support Supervisor (FSS) (Non-Licensed) y 1 - Shift Technical Advisor (STA) (Non-Licensed) y 1 - At The Controls Operator (ATC) (RO) y 1 - Senior Nuclear Operator (SNO) (RO) y 4 - Nuclear Power Operators (NPO) (Non-Licensed) y a Health Physics Tech (HP) (Non-Licensed) Considering only the above positions, utilize: Tech Specs Nuclear Management Manual (NMM) Operations Procedures to determine if required shift staffing is met and, if not met:

Any required actions
Any required time limits

NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO [8] RO D NLO D ALTERNATE SUCCESS PATH D TITLE: ST-26K Recirc Loop Startup Differential Temperature SRO Review OPERATOR: DATE: EVALUATOR: EVALUATOR SIGNATURE: CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): I N/A

PERFORMANCE TIME:

Average Time (min): 15 Actual Time (min): i I I \\ JPM RESUL TS*: SAT UNSAT (Circle one) COMMENT SHEET ATTACHED: Yes I No (circle one) SYNOPSIS: Using ST-26k, candidate determines that Recirc surveillance failed its Level 1 acceptance criteria. TASK STANDARD: Complete section 11.2 of ST-26K correctly. EVALUATION METHOD: EVALUATION LOCATION: Perform Plant '-------{ '-------{ Simulate Simulator c------{ Control Room 1----:-:-,---1 Classroom (Admin) l ___----' Prepared: Date: Reviewed: Date: Approved: Date: ENTERGY Nl;CLEAR Pa~e 1 of8 IE-DOC TITLE: ST-26K Recirc Loop Startup Differential E-DOCNO. REVISION NO. [ Temperature SRO Review 2012 NRC Admin 3 o I

I REVISION LOG I Revision Number: 0 Date Originated: J Pages Affected:

== Description:== ENTERGY NUCLEAR Page 2 of8 E-DOC TITLE: ST -26K Recirc Loop Startup Differential E-DOC NO. REVISION NO. Temperature SRO Review 2012 NRC Admin 3 i 0

TASK

Title:

Task Number K&ASYSTEM: K&ARATING: 2.2.12 3.7/

4.1 REFERENCES

ST-26K SIMULATOR CONDITIONS: N/A. GENERAL TOOLS AND EQUIPMENT: A completed ST-26K (with the exception of section 11.2). CRITICAL TASKS: Identified with a

OPERATOR BRIEF:

1. State the following paragraph IE this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin". ENTERGY NUCLEAR Page 3 of8 I E-DOC TITLE: ST-26K Recirc Loop Startup Differential E-DOCNO. REVISION NO. I Temperature SRO Review 2012 NRC Admin 3 I 0

2. State the following:

"The task conditions are as follows: Plant status is: >> Reactor scrammed );> All rods in );> Rx Press - 370 psig (06PI-90A) RWCU is in service with flow through the reactor vessel bottom head drain line. );> Rx Vessel Temp (02-3TR-89) point 7, Vessel Bottom Drain Temp - 320 deg F '>> RWR Pump "A" (a) Shutdown (b) RWR Loop "An Inlet Temp (i) 360 deg F (EPIC-A-425) (ii) 360 deg F (EPIC-A-426) (iii) 340 deg F (02TR-165) '>> RWR Pump "B" (a) started 40 minutes ago, (b) Flow (i) 13,500 gpm (02FI-159B) (ii) 5.2 mlbm/hr (EPIC-A420) (c) Shift Manager and Reactor Engineering have determined it is not feasible to increase "B" loop flow greater than 13,500 gpm. (d) RWR Loop "B" Inlet Temp (i) 410 deg F (EPIC-A-430) (ii) 410 deg F (EPIC-A-431) (iii) 400 deg F (02TR-165) );;> ST-26K, Recirc Loop Startup Differential Temperature Check, has been completed.

3. Solicit and answer any questions the operator may have.

INITIATING CUE: State the following: "The Shift Manager has directed you to complete and sign ST-26K, Recirc Loop Startup Differential Temperature Check, Section 11.2, Management SRO Review. Any problems or concerns found are to be documented in section 11.3, remarks." E-DOC TITLE: ST-26K Recirc Loop Startup Differential E-DOC NO. REVISION NO. i Temperature SRO Review I 2012 NRC Admin 3 0

PERFORMANCE: Notes A completed ST-26K (with the exception of section 11.2) and the attached handout. If the candidate asks for other temperature indications, inform the candidate that all operable indications have been provided in the plant status brief. START TIME:

1 Procedure Step:

11.2.1 Verify data is within required tolerances. Standard Determines that step 8.4.7 is out of tolerance. Cue Notes I Results SAT Critical Step UNSATD D 2 Procedure Step: 11.2.2 Verify data attachments, such as recorder printouts and calibration sheets are included as required. Standard Determines that this step is not applicable. Cue Notes Results SAT UI\\JSAT I D I

3 Procedure Step:

11.2.3 Verify required initials and signatures have been entered. Standard Determines that step 8.4.4.C.2 is missing a signature. Cue Notes Results I SAT Critical Step UNSATD I D ENTERGY NUCLEAR Paj!e 5 of8 E-DOC TITLE: ST-26K Recirc Loop Startup Differential E-DOCNO. REVISION NO. I Temperature SRO Review 2012 NRC Admin 3 0 I

4

\\ Procedure Step: 11.2.3 Verify required initials and signatures have been entered. i i Standard Determines that step 8.4.5 is missing initials. Cue Notes LE__ Re_s_ul_ts--,I_S_A_T__ 1 __I ___c_r_'t,_ca_I_S_te_p___U_N_SA_T_I___ 1 ___--' 5 Procedure Step: Documents in the remarks section problems found i Standard Indicates in remarks section: i step 8.4.7 is out of tolerance step 8.4.4.C.2 is missing a signature step 8.4.5 is missing initials. I i Cue Notes Results ' SAT UNSAT D

6 Procedure Step: 11.2.4 Review test to determine if test results satisfy acceptance criteria:

C) Satisfactory U Satisfactory with corrective actions ( J Unsatisfactory Standard Determines test is "Unsatisfactory" Cue Notes I Results SAT Critical Step UNSAT\\ I D J

7 Procedure Step: 11.2.5 IF Level 1 acceptance criteria is not satisfied, THEN immediately notify Operations Manager or alternate. Record name of I

I person notified. i I I Standard Notifies Operations Manger or alternate. I Cue When candidate indicates a call to the Operations Manager, tell the candidate Chris Adner has been notified. i Notes Results SAT Critical Step UNSATD I D I I ENTERGY NUCLEAR Page 6 of8 , E-DOC TITLE: ST-26K Recirc Loop Startup Differential E-DOCNO. REVISION NO. i Temperature SRO Review 2012 NRC Admin 3 0 I

8 Procedure Step: ~ 11.2.6 Initiate required corrective and compensatory actions. L) Not required U Required Standard Marks required. I Cue Notes Results i Step 11.1.3 requires a CR if level 1 acceptance criteria was not met. SAT D UNSAT D 9 Procedure Step:. 11.2.7 Sign and record date and time. Management SRO Date/Time i Standard Candidate will sign, date and time the surveillance test I Cue ~ Notes ~___R_es_ul_ts~I_SA_T__I____ 1 _____________U_NS_A_T_I____ I ______~ Terminating Cue: When the candidate signs and dates the surveillence, tell the candidate "This completes the JPM" STOP TIME: ENTERGY NLCLEAR Page 7 of8 E-DOC TITLE: ST-26K Recirc loop Startup Differential E-DOC NO. REVISION NO. Temperature SRO Review 2012 NRC Admin 3 o I

HANDOUT

Plant status is:

);- Reactor scrammed .~ All rods in );- Rx Press - 370 psig (06PI-90A) );- RWCU is in service with flow through the reactor vessel bottom head drain line.

~ Rx Vessel Temp (02-3TR-89) point 7, Vessel 80ttom Drain Temp 320 deg F

.~ RWR Pump "A" (a) Shutdown (b) RWR Loop "A" Inlet Temp (i) 360 deg F (EPIC-A-425) (ii) 360 deg F (EPIC-A-426) (iii) 340 deg F (02TR-165) ); RWR Pump "8" (a) started 40 minutes ago, (b) Flow (i) 13,500 gpm (02FI-1598) (ii) 5.2 mlbm/hr (EPIC-A420) (c) Shift Manager and Reactor Engineering have determined it is not feasible to increase "8" loop flow greater than 13,500 gpm. (d) RWR Loop "8" Inlet Temp (i) 410 deg F (EPIC-A-430) (ii) 410 deg F (EPIC-A-431) (iii) 400 deg F (02TR-165) );- Section 4.0 of ST-26K, Recirc Loop Startup Differential Temperature Check, has been completed. "The Shift Manager has directed you to complete and sign ST-26K, Recirc Loop Startup Differential Temperature Check, Section 11.2, Management SRO Review. Any problems or concerns found are to be documented in section 11.3, remarks."

NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO I2?J RO D NLO ALTERNATE SUCCESS PATH TITLE: Determine Requirements for Drywell Entry and Tech Spec LCO OPERATOR: DATE: EVALUATOR: EVALUATOR SIGNATURE: CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 35 Actual Time (min): I JPM RESLIL TS*: SAT UNSAT (Circle one) COMMENT SHEET ATTACHED: Yes 1No (circle one) SYNOPSI~: Reviews AP 12.02 for drywell entry requirements and T.S. for inoperable airlock doors. TASK STANDARD: Determines that there are additional requirements for drywell entry and an LCO for the drywell interlock mechanism. EVALUATION METHOD: EVALUATION LOCATION: Perform Plant 1---- f--------j Simulate Simulator f--------j Control Room 1---:-:-----1 ~ Classroom (Admin) Prepared: Date: 12/29/2011 Reviewed: Date: I/;//;L /1 Approved: Date: Superintend nt, Operations Training (or Designee) ENTERGY NUCLEAR PaRe 1 of9 E-DOC TITLE: Determine Requirements for Drywell E-DOCNO. REVISION NO. Entry and Tech Spec LCO 2012 NRC Admin 4 0

I REVISION LOG Revision Number: 0

Date Originated:

Pages Affected:

== Description:== ENTERGY NlJCLEAR Page 2of9 E-DOC TITLE: Determine Requirements for Drywell E-DOCNO. REVISION NO. Entry and Tech Spec LeO 2012 NRC Admin I 4 0 I

TASK

Title:

Task Number K&ASYSTEM: K&A RATING: 2.3.12

3.7 REFERENCES

AP-12.02 & Tech Specs SIMULATOR CONDITIONS:

N/A. GENERAL TOOLS AND EQUIPMENT: AP-12.02, Tech Specs, ODCM & TRM. CRITICAL TASKS: Identified with a

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. State the following: (give attached handout)

Power has been reduced from 100% to 14% power to investigate unidentified drywel1leakage.
Dryvvell cooling is in normal 100% power configuration.
Initial drywell entry has been made by RP in preparation for NPO entry o Drywell oxygen concentration is 19.4%

o Emergency escape airlock oxygen concentration is 19.6% o Emergency escape airlock strongback has been removed from the inner door. o Emergency Drywell Exit Kit is staged near the Personnel Airlock o RPs reported that the drywell inner and outer air lock door interlock is not working. Both doors had momentarily been opened at the same time. A Condition Report has been generated. o RP drywell surveys are not completed o RPs have left the drywell for a break. Both Personnel Airlock Doors are closed. ENTERGY NUCLEAR Pa2e30f9 E-DOC TITLE: Determine Requirements for Drywell E-DOC NO. REVISION NO. Entry and Tech Spec LCO 2012 NRC Admin 4 0

Rx Engineering plans a rod shuffle for this shift: 4 rods are to be withdrawn two notches and 4 rods are to be inserted two notches. Steady state reactor power is expected to remain at 14%.
Two NPOs are to be sent into the drywell to investigate an increase in unidentified leakage. The NPOs:

o Had a pre-job briefby the CRS concerning the drywell entry o Have been told to stay below the 292' elevation o Had a heat Stress Evaluation per EN-IS-1 08 o Signed onto OPS General RWP 20120008-21 "Surveillance Testing/Inspections" o Have current dosimetry o Are ready to enter the drywell

3. Solicit and answer any questions the operator may have.

INITIATING CUE: State the following: You are the Shift Manager. Determine what, if any,

1. Additional requirements are needed for NPO entry into the drywel1

2. Tech Spec, TRM or ODCM actions that may be required ENTERGY NUCLEAR Pa~e4 of9 E-DOC TITLE: Determine Requirements for Drywell E-DOC NO.

REVISION NO. Entry and Tech Spec LCO 2012 NRC Admin 4 0

PERFORMANCE: Notes If the candidate states that drywell entry would not be allowed (and stops), prompt candidate to identify all problems that must be resolved to allow entry. START TIME:

1.

Ensure reactor power level is not raised during drywell entries. Procedure Step: i i I Standard Determines that withdrawing control rods for the rod shuffle is not permitted when personnel are in the drywell. i Cue* Notes AP-12.02, 6.6.1 and 8.2.1.A.1 Results SAT Critical Step UNSATD D

2.

The following are required for drywell entries while primary containment is in Procedure Step: effect: Specific RWP per AP-07.01. Standard Determines that a specific RWP is required. Cue Notes AP-12.02,7.8 Results SAT Critical Step UNSATD i I D I I

3.

Procedure Step:. The following are required for drywell entries while primary containment is in effect: ALARA Review per RP-ALARA-01.01. i I Standard Cue Notes I AP-12.02, 7.8 Results. SAT D Critical Step UNSATD I I ENTERGY NUCLEAR Palle 50(9 E-DOC TITLE: Determine Requirements for Drywell E-DOCNO. REVISION NO. Entry and Tech Spec LCO 2012 NRC Admin 4 0 I

4.

Procedure Step: Standard Cue The drywell atmosphere is between 19.5 and 23,5% oxygen following an initial entry and verification Determines oxygen concentration is to low for entry OR that a confined space entry permit is required. I Notes Results AP-12.02,8.2.1.8 SAT D Critical Step UNSATD

5.

Procedure Step: Workers performing inspections shall remain with the Radiation Protection Technician until radiological conditions are determined. Standard Determine NPOs must have RP coverage OR that the RP surveys must be completed prior to entry. I Cue

Notes AP-12.02,8.2.2 Results SAT I

I Critical Step UNSATD

6. I Procedure Step:

Standard Two primary containment air locks shall be operable. Modes 1,2,3. One or more primary containment air locks with primary containment air lock interlock mechanism inoperable. Determines that one airlock door must be verified closed within one hour and locked closed within 24 hours OR that entry/exit is allowed under the control of a dedicated individual. Cue. Notes Tech Specs 3.6.1.2.8 Results SAT D Critical Step UNSATD i I Terminating Cue: This completes this JPM. STOP TIME: I ENTERGY NUCLEAR Page 6 of9 ! E-DOC TITLE: Determine Requirements for Drywell E-DOC NO. REVISION NO. I Entry and Tech Spec LeO 2012 NRC Admin 4 o

HANDOUT

Power has been reduced from 100% tol4% power to investigate unidentified drywellieakage.
Drywell cooling is in normal 100% power configuration.
Initial drywell entry has been made by RP in preparation for NPO entry o Drywell oxygen concentration is 19.4%

o Emergency escape airlock oxygen concentration is 19.6% o Emergency escape airlock strongback has been removed from the inner door. o Emergency Drywell Exit Kit is staged near the Personnel Airlock o RPs reported that the dryweU inner and outer air lock door interlock is not working. Both doors had momentarily been opened at the same time. A Condition Report has been generated. o RP drywell surveys are not completed o RPs have left the drywell for a break. Both Personnel Airlock Doors are closed.

Rx Engineering plans a rod shuffle for this shift: 4 rods are to be withdrawn two notches and 4 rods are to be inserted two notches. Steady state reactor power is expected to remain at 14%.
Two NPOs are to be sent into the drywell to investigate an increase in unidentified leakage. The NPOs:

o Had a pre-job brief by the CRS concerning the drywell entry o Have been told to stay below the 292' elevation o Had a heat Stress Evaluation per EN-IS-108 o Signed onto OPS General RWP 20120008-21 "Surveillance Testing/Inspections" o Have current dosimetry o Are ready to enter the drywell You are the Shift Manager. Determine what, if any,

1. Additional requirements are needed for NPO entry into the drywell

2. Tech Spec, TRM or ODCMactions that may be required ENTERGY NUCLEAR Page 7 of9 E-DOC TITLE:

E-DOC NO. REVISION NO. 2012 NRC Admin 4 0 I

HANDOUT ENTERGY NUCLEAR OPERATIONS. INC. '!'I'i:;'~~":!,. JAMES A. FITZPATRICK NUCLEAR POWER PLANT '~'Elltergy TKf. POWER OF PEOPlr RADIOLOGICAL WORK PERMIT RWP

Title:

OPERATlONS I~Ol;T1NF. ACTIVITJF:S BWPNo.: 20120008 Rev. 00 Comments:

20120008 *

~Tl'I'I': GENERAL RWP Status: B!:l:in Date: 1Close 011 Date: ACTIVE 12/06/2011 1213112012 l'r~l'liIrC'd Ih': JQb Suuervisor: h.Il!lli't"d j)U'l"r Ac!ual Dose: Actual Huurs: Ir'!i.It;II!:d I~~~~~ J 3,200 mrem 2.352.7 mrclll 32.239...19

I:' ':'. t.lIt';,il(1I1'1,:,.. )

ii r----:---:-

'h'ihHIIl:..~ I Ut, :U I.m ~ l{",inJol NiA i ~luJinl(l~i~1 ('o~lyhi(lnll Dcserilltion ',1411", } Unit N/A I I I:: I::: I::: l'u,k.,':': :, ~..- Task rU,"'.ni Jli.. n ':1l!J.t." 12 REACTOR BUILDING ROUNDS Active 13 TURBINE BUILDING/OUTSIDE ROUNDS Active 14 NO HRA RADWASTE ROUNDS Active 21 SURVEILLANCE TESTING/INSPECTIONS Active .11 PTR /VALVE LINEUPS Active .)~ WALKDOWNS FOR TRAINING Active ii*: Rl!quirlilllt!'nlii.' I::' Requirement Croups I Requirement Descriptiolls NiA I Page 1 of 2

HANDOUT ENTERGY NUCLEAR OPERATIONS. INC. c,f~:l,ii~ JAMES A. FITZPATRICK NUCLEAR POWER PLANT .~~Entergy. ,~ Tttt:: poweR Of' PEOPL" RADIOLOGICAL WORK PERMIT RWP No,: Task Number: 21 20120008 !lev,; 00 Task

Description:

SURVEILLANCE TESTlNG/lNSPECTJONS Task Status: Active Estim;Ue Dose: 800m) E!tiroat( Houri: 9.200.00 Radiological Waste Control: lustruction 3: Worker Instructions: Instruction 4: Otber Instructions: Addditi{)nallll:;tru~tjol1s: I) Sil1glePC's with car> for work in Contaminated Arca's.

2) Single PC's wilh Hood when cal'ryingmllterial on shoulders or working ill overhead or whell contaminated material will be near head and nICC.

3) D,mblc PC's with Hood in Highly COllmminatcd Area's.

4) Plastics or Equivalent for Wet work.Additional Instructions:

Page 4 of6

NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO LZJ RO 0 NLO 0 ALTERNATE SUCCESS PATH 0 TITLE: Determine Protective Action Recommendations and Complete Event Notification Form OPERATOR: DATE: EVALUATOR: EVALUATOR SIGNATURE: I CRITICAL TIME FRAME: Required Time (min): 15 Actual Time (min): I PERFORMANCE TIME: Estimated Time 14 Actual Time (min): i (min): i JPM RESUL TS*: SAT UNSAT (Circle one) COMMENT SHEET ATTACHED: Yes / No (circle one) SYNOPSIS: Plant conditions are evaluated to recommend the correct protective actions TASK STANDARD: Complete the upgrade offsite notification message fonn, including correct PARs. EVALUATION METHOD: EVALUATION LOCATION: Perform Plant r----.----< Simulate Simulator !--- Control Room !---- Classroom (Admin) Prepared: Date: I Ilf II}- Reviewed: Date: Approved: Date: Superintende t, Operations Training (or Designee) ENTERGY NUCLEAR Page I ofl2 I E-DOC TITLE: Determine Protective Action E-DOCNO. REVISION NO. Recommendations and Complete Event Notification 2012 NRC I Form Admin 5 0

i REVISION LOG Revision Number: 0 Date Originated: Pages Affected:

== Description:== i ENTERGY NUCLEAR E-DOC TITLE: Determine Protective Action E-DOC NO. Page 2 of 12 REVISION NO.

Recommendations and Complete Event Notification

, Form 2012 NRC I Admin 5 0 I

TASK

Title:

Task Number Detennine Protective Action Recommendations and Complete Event Notification Fonn

REFERENCES:

IAP-2, Classification of Emergency Conditions
EAP-I.I, Offsite Notifications
lAP-I, Emergency Plan Implementation Checklist
EAP-4.1, Release Rate Detennination
EAP-4, Dose Assessment Calculations
EAP-42, Obtaining Meteorological Data SIMULATOR CONDITIONS:

N/A. GENERAL TOOLS AND EQUIPMENT:

1. Hand out the following materials:

Calculator Blank EAP-I.l Attachment 1 Notification Fonn Legible EAL Flowchart Legible EAP-4 Attachment 1 Flowchart

2. Handout copies of following procedures:

EAP-4.1, Release Rate Detennination EAP-42, Obtaining Meteorological Data IAP-2, Classification of Emergency Conditions lAP-I, Emergency Plan Implementation Checklist EAP-I.l, Offsite Notifications

3. Have copies available of following procedure:

EAP-4, Dose Assessment Calculations ENTERGY NUCLEAR IE-DOC TITLE: Determine Protective Action

Recommendations and Complete Event Notification Form K&ASYSTEM:

K&ARATING: 4.4 2.4.38 Pa2C 3 of12 I E-DOC NO. REVISION NO. I 2012 NRC Admin 5 o I

CRITICAL TASKS: Identified with a

OPERATOR BRIEF:

1. State the following paragraph IE this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. Provide the candidate the following information (see attached handout).

At 0342 today (Feb 28, 2012), an earthquake with a magnitude ofO.08g caused a loss ofoffsite power. Plant conditions: At 0342, a large break LOCA occurred. The reactor automatically scrammed. Multiple failures in safety systems caused the operators to conduct an emergency depressurization. RPV level dropped to minus (-) 9". Drywell pressure peaked at 55 psig. Secondary containment radiation levels increased to >EOP-5 Maximum Normal values in the Reactor Building 344 foot elevation. At 0352, a Site Area Emergency was declared with a release in progress based on an unisolable MSL break outside primary containment. At 0401, the initial offsite notification message was transmitted. ERO is staffing the emergency response facilities. Neither the TSC nor the EOF has been fully activated (the earthquake caused damage to local roads). At 0412, (when you start the JPM) the following plant conditions exist:

Drywell pressure has dropped rapidly to 3 psig.
RPV level minus (-) 9", going up slowly.
You are the Emergency Director until relieved and have just declared an EAL upgrade to General Emergency at Time 0412.
EAL upgrade based on radioactivity release as indicated on effluent radiation monitors, exceeding EAL threshold for > 15 minutes.
NO other General Emergency EAL thresholds have been reached.

ENTERGY NUCLEAR Page 4 of 12 I E-DOC TITLE: Determine Protective Action E-DOC NO. REVISION NO. I Recommendations and Complete Event Notification 2012 NRC Form Admin 5 o

Stack flow rate = 12,000 cfm, with 1 SGT train and 1 stack dilution fan operating. EPIC "Rad Release" screen shows the following relating to the offsite release: HIGH RANGE CONTINUOUS OFFSITE REL RATES LOCATION RATES X CF = CIISEC STACK 11,700 MRlHR CF 2.9718E+04 TURBBLDG OMRlHR CF CIISEC EXH OMRlHR CF O.OOOOE+OO RADWBLDG CIISEC EXH O.OOOOE+OO CIISEC

Meteorological conditions are provided in the following EDAMS report:

Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System Date: 2128/12 Time (Local): 4:00:00 Elevated Ground 200' Vlind Dir From 271 (deg) 30' Wind Dir From (Main) 261 (deg) 200' Wind Speed 6.1 (mph) 30' Wind Speed (Main) 3.8 (mph) 200' Delta Temperature -1.49 (deg F) 100' Delta Temperature -.56 (deg F) Stability Class C Stability Class D 30' Air Temperature 45.6 (deg F) Precipitation (15 min) 0.00 (in) Solicit and answer any questions the operator may have. INITIATING CUE: State the following: Complete the required E-plan upgrade notification form for the current conditions. THIS IS A TIME-CRITICAL JPM. ENTERGY NUCLEAR Page 5 of 12 E-DOC TITLE: Determine Protective Action E-DOCNO. REVISION NO. Recommendations and Complete Event Notification 2012 NRC Form Admin 5 0

PERFORMANCE:

1.

Applicants review the handout sheet and ask any questions regarding the initial Procedure Step: conditions or initiatin cues. Standard A Iicants review initial conditions and initiatin cues. Cue Notes Results SAT UNSAT D D

2.

Procedure Step: Handout the references with the handout sheet and the initiating cue sheet. Standard Start the IPM. Record START Time: Cue Examiner Cue: Remind applicant the task is time critical. Notes Results SAT UNSAT D D

3.

Obtains Notification Form (Attachment 1 ofEAP-l.1, Offsite Notifications) Procedure Step: Standard Applicant completes Notification Form Item #2, circling "A, Actual Emergencv". Cue Notes Results SAT UNSAT D D

4.

Record the correct event classification. Procedure Step: i Standard i Applicant completes Notification Form Item #3, circling liD. General Emergency". I I Cue Notes i I i I Results SAT Critical Step UNSATD D i ENTERGY NUCLEAR Pae:e 6 of 12 I E-DOC TITLE: Determine Protective Action E-DOCNO. REVISION NO. Recommendations and Complete Event Notification 2012 NRC Form Admin 5 o

5.

Procedure Step: Record the correct declaration date and time. Applicant completes Notification Form Item #4, Critical Step UNSAT

6.

I Procedure Step: Standard Cue Notes Determine release rate using EAP-4 and EAP-4.1 (Step 4.1.2 or Attachment 2 from mr/hr

2.54 factor)

Applicant determines release rate is 29,718 Ci/sec. I I Critical Step UNSATO I i

7.

Procedure Step: Record the radioactive release information based on EAP-4.1 Attachment 11. Standard Applicant completes Notification Form Item #5, circling "C. Release ABOVE Critical Step UNSATO

8.

Procedure Step: Standard ! Determine and record the protective active recommendations using EAP-4, Tables 4.1.1 and 4.1.2. Applicant completes Notification Form Item #6, circling "B. EVACUATE and IMPLEMENT the KI PLAN fqr the following ERPAs and All remaining ERP As MONITOR the EMERGENCY ALERT SYSTEM" and by circling ERP As # 1,2,3,4,7,9,26,27. Cue Notes Results Examiner Note: These are 2 mile radius and 5 mile downwind ERPAs. SAT I I Critical Step UNSATO ENTERGY NCCLEAR E-DOC TITLE: Determine Protective Action Recommendations and Complete Event Notification Form E-DOCNO. 2012 NRC Admin 5 Pae:e 7 of 12 REVISION NO. 0 I

9.

appropriate EAL number and brief description. Critical Step UNSAT

10 Proc;dure Step: IRecord reactor status.

Standard

Applicant completes Notification Form Item #8, circling "B. Shutdown" and date L-i time of 02/28111 at 0342.

~I------*

Cue* l----N-o-=-te=s'----t-I--**~~=-**_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-:_-_-_-_-~~~~~~~~~~~~~: Results SAT D Critical Step UNSAT D ___L-____________ i ~ ~

11 Record appropriate wind speed Procedure Step:

Standard Records wind speed by filling in Notification Form Item #9 as "A. hl Miles/Hour I at elevation £Q.Q Feet (Elevated),. I Cue i Notes D Results SAT Critical Step 12 Procedure Step:. Record meteorological stability class as determined using provided data per EAP-42. 1 I Standard Determines Stability Class "~", based on wind direction variation and 30 to 200 foot

delta T. Records stability class by circling tIC Neutral" in Notification Form Item

11.

I Cue Notes Results SAT Critical Step UNSATD D I ENTERGY NUCLEAR Page 8 of 12 E-DOC TITLE: Determine Protective Action E-DOC NO. REVISION NO. Recommendations and Complete Event Notification 2012 NRC Form Admin 5 0 i i I i

13 Procedure Step: I Turn in notification form within required time.

Standard Applicant turns in notification form within 15 minutes of start of JPM. I Record Stop Time: I i Cue Notes Results SAT D Critical Step UNSATD Terminating Cue: This completes this JPM. ENTERGY NUCLEAR E-DOC TITLE: Determine Protective Action E-DOCNO. Page 9 of 12 REVISION NO. Recommendations and Complete Event Notification Form 2012 NRC Admin 5 o I

,-'PM ANSWER KEY 1 of

L eleV<1ted radioactivity release from main vent stack w.~ Point 0 01ll1ill'1I'9O Coumy WIl\\il".h~9 i>OMt

.h;tJtt~Al"c~ l;I"t'ilt ?_ P'lIf>f <3.;11)1 1JJjl:~J!',1~' JPM ANSWER KEY EAP-l.l AI'T.I\\CtiMENT 1 OFf'SI'TE NOTIFICATIO!JS Rev. Nc*. ".,.t:.L of Recommendations and Complete Event Notification 2012 NRC Form Admin 5 o I

HANDOUT At 0342 today (Feb 28, 2012), an earthquake with a magnitude of 0.08g caused a loss of offsite power. Plant conditions: At 0342, a large break LOCA occurred. The reactor automatically scrammed. Multiple failures in safety systems caused the operators to conduct an emergency depressurization. RPV level dropped to minus (-) 9". Drywell pressure peaked at 55 psig. Secondary containment radiation levels increased to >EOP-5 Maximum Normal values in the Reactor Building 344 foot elevation. At 0352, a Site Area Emergency was declared with a release in progress based on an unisolable MSL break outside primary containment. At 0401, the initial offsite notification message was transmitted. ERO is staffing the emergency response facilities. Neither the TSC nor the EOF has been fully activated (the earthquake caused damage to local roads). At 0412, (when you start the JPM) the following plant conditions exist: Drywell pressure has dropped rapidly to 3 psig. RPV level minus (-) 9", going up slowly. You are the Emergency Director until relieved and have just declared an EAL upgrade to General Emergency at Time 0412. EAL upgrade based on radioactivity release as indicated on effluent radiation monitors, exceeding EAL threshold for> 15 minutes. NO other General Emergency EAL thresholds have been reached. Stack flow rate 12,000 cfin, with 1 SGT train and 1 stack dilution fan operating. (continued on next page) ENTERGY NUCLEAR Pal(e 11 of 12 E-DOC NO. 2012 NRC Admin 5

HANDOUT EPIC "Rad Release" screen shows the following relating to the offsite release: IGH RANGE CONTINUOUS OFFSITE REL RATES CATION RATES X CF = CIISEC STACK 11,700 MRfHR CF 2.9718E+04 TURB BLDG 0 MRlHR CF CIISEC EXH 0 MRlHR CF O.OOOOE+OO RADW BLDG CIISEC EXH O.OOOOE+OO CIISEC Meteorological conditions are provided in the following EDAMS report: Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System Date: 2/28/12 Time (Local): 4:00:00 Elevated Ground 200' Wind Dir From 271 (deg) 30' Wind Dir From (Main) 261 (deg) 200' Wind Speed 6.1 (mph) 30' Wind Speed (Main) 3.8 (mph)

200' Delta Temperature

-1.49 (deg F) 100' Delta Temperature -.56 (deg F) Stability Class C Stability Class D 30' Air Temperature 45.6 (deg F) Precipitation (15 min) 0.00 (in) You are to complete the required E-plan upgrade notification form for the current conditions. THIS IS A TIME-CRITICAL JPM. ENTERGY NUCLEAR Paee 12 of 12 ~ E-DOC NO. 2012 NRC Admin 5 I

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC S-1 TASK TITLE: Removal of 'B' SBGT from service following an Automatic Initiation APPL. TO JPM NUMBER REV: DATE: 12/28/11 NRC KIA SYSTEM NUMBER: 261000 A4.03 3.0/3.0 JAF TASK NUMBER: 26100401 JAF QUAL STANDARD NUMBER: ESTIMATED CO~ETION TIME: 8 Minutes //1..~It////# SUBMITTED: ) h b OPERATIONS REVI~t/n,ItZ APPROVED: ~~~/U?a~~/~_______ /

~==:-------------------------------------------------------

CANDIDATE NAME: JPM Completion D Simulated [8J Performed Location: D Plant [8J Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO/NPO 2012 NRC S-1 TASK TITLE: Removal of 'B' SBGT from service following an Automatic Initiation APPL. TO JPM NUMBER Current Update: By: Date Int Outstanding Items o Technical Review o Additional Information o Questions and Answers Validation o Procedural Change Required [8J None Comments: Current Update: By: Date tnt. Previous Revision Date: -2 of 7

S/RO/NPO 2012 NRC S-1 TASK TITLE: Removal of 'B' SBGT from service following an Automatic Initiation I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-20, STANDBY GAS TREATMENT SYSTEM III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Initialize the simulator to an IC that has SBGT 'A & 'B' running following an automatic initiation (IC-121) B. Clear all SBGT initiation signals. C. Reactor Building Ventilation is isolated. V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed. C. The candidate should demonstrate proper use of HU tools such as procedure use, placekeeping and self checking. VI. TASK CONDITIONS A. SBGT's 'A &B' automatically started due to RPV level lowering to 177" in response to a scram. B. Reactor level is now recovered to greater than 177". -3 of 7

S/RO/NPO 2012 NRC S-1 TASK TITLE: Removal of 'B' SBGT from service following an Automatic Initiation

- CRITICAL STEP VII.

INITIATING CUE Inform the candidate, "The CRS directs you to shutdown the 'B' SBGT per OP-20, Attachment 4" NOTE: All actions occur at panel 09-75. STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SAT / UNSAT procedure OP-20, STANDBY of procedure OP-20.

GAS TREATMENT SYSTEM. EVALUATOR: Provide the candidate a current copy of OP-20 (Attachment 4).

2. Select the correct section to Selects Attachment 4, of OP-20.

SAT I UNSAT perform the task.

3. Ensure SBGT 'B' operation is The candidate determines that operation of SBGT "B" is not SAT I UNSAT not required.

required. EVALUATOR: If asked, inform candidate that SBGT 'B' is no longer required and the initiation signals are cleared. ~-

4.

IF SGT Train 'A' is shutdown, Candidate verifies that SBGT 'A' is not shutdown by SAT I UNSAT THEN ensure closed the observing TRAIN A FN 01-125FN-1A red light on, green following valves: light off. --~..........-.--.............-.-- -4 of 7

S/RO/NPO 2012 NRC S-1 TASK TITLE: Removal of 'B' SBGT from service following an Automatic Initiation STEP STANDARD EVALUATION I COMMENT

5. Close TRAIN 'B'INLET At panel 09-75, the candidate places the control switch for CRITICAL STEP 01-125MOV-14B 01-125MOV-14B to close.

SAT I UNSAT

6. Verify closed TRAIN 'B' INLET At panel 09-75, the candidate verifies green light on, red SAT I UNSAT 01-125MOV-14B light off, for 01-125MOV-14B.

7. Close BELOW EL 369' SUCT At panel 09-75 the candidate places the control switch for CRITICAL STEP 01-125MOV-12.

01-125MOV-12 to close. SAT I UNSAT

8. Verify closed BELOW EL 369' At panel 09-75 the candidate verifies green light on, red light SAT I UNSAT SUCT 01-125MOV-12.

off, for 01-125MOV-12. -50f7

S/RO/NPO 2012 NRC S-1 TASK TITLE: Removal of 'B' SBGT from service following an Automatic Initiation IF STEP

9. Verify the following system response:

White light AIR HTR 01-125E-5B is on. Red light for AIR HTR 01-125E-5B is off Train B CLG VLV 01-125MOV-100B is open FN DISCH 01-125MOV-15B is closed TRAIN B FN 01-125FN-1B is stopped.

10. IF SGT Train 'A' is in service THEN verify flow rate on SGT FLOW 01-125FI-106A.

RB un-isolated approx.

6000 scfm.

RB isolated approx.

5600-5800 scfm.

11. Reports to the CRS that SGT

'B' is shutdown STANDARD Observes and verifies component operation during the shutdown of 'B' SBGT. Component 01-125E-5B 01-125E-5B 01-125MOV-100B 01-125MOV-15B 01-125FN-1 B Status White light on Red light off Red light on, green light off Green light on, red light off Green light on, red light off EVALUATOR: Candidate verifies that SGT lA' is in service and f10wrate on 01-125FI-1 06A is RB isolated: approximately 5600-5800 scfm. Reports to the CRS that SGT 'B' is shutdown and the task is complete. EVALUATOR: Terminate the task at this point. -6 of 7 EVALUATION I COMMENT SAT I UNSAT SAT I UNSAT SAT I UNSAT

HANDOUT

SBGT's 'A & B' automatically started due to RPV level lowering to 177" in response to a scram.
Reactor level is now recovered to greater than 177".

The eRS directs you to shutdown the 'B' SBGT per OP-20, -7 of 7

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SIRO 2012 NRC S-2 TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 212000 A4.14 3.8/3.8 JAFTASKNUMBER: ~2~1=20~1~0~10~0~9________ JAF QUAL STANDARD NUMBER: AOP-1 ESTIMATED COMPLETION TIME: 10 Minutes n SUBMITTED: &~ ~ OPERATlONSREVIEW:~ #2 ~:~~~~~~~-------~--------------------------------------------------------- CANDIDATE NAME: JPM Completion o Simulated [gl Performed Location: o Plant [gl Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory o Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIRO APPL. TO 2012 NRC S-2 JPM NUMBER TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close Current Update: Outstanding Items Date o Technical Review Questions and Answers Procedural Change Required Comments: By: Int o [SJ Additional Information Validation None Current Update: Previous Revision Date: Date By: Int. -2 of 7

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIRO 2012 NRC S-2 TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-1, Reactor Scram, Current Revision III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Initialize the simulator to any full power IC (lC-121). B. Insert a manual scram by placing the Mode Switch to SHUTDOWN. C. Reset ARI. D. Stabilize RPV level above 177 inches. E. Manually override the blue scram lights "ON" for control rods 14-43, 30-19, 06-19,42-07. V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed. C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication. VI. TASK CONDITIONS A. The reactor was scrammed 1 hour ago due to a Feedwater malfunction. B. The scram condition has been identified and cleared. C. All Reactor scram signals are now clear with the exception of the scram discharge volume high level signal. -3 of 7

SIRO 2012 NRC S-2 TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS has directed that you reset the scram per AOP-1."

NOTE: All actions performed at Panel 09-5 STEP ~- STANDARD

1.

Obtain a controlled copy of The candidate determines where to obtain a controlled copy AOP-1, Reactor Scram. of AOP-1. (Control Room, Merlin) EVALUATOR: Provide candidate a current copy of AOP-1 1----

2. Select the correct section to The candidate selects Section F.1 of AOP-1.

perform the task. EVALUATOR; Provide candidate a copy of section F.1 IF ARI actuated, THEN reset The candidate observes that ARI is reset.

3.

ARI.

4. Verify annunciator 09-5-1-33 The candidate observes that the annunciator window for MODE SW IN SHUTDOWN annunciator 09-5-1-33 is in alarm.

TRIP BYPASSED is in alarm.

5. Place the SDIV HI LVL TRIP The candidate places the SDIV HI LVL TRIP switch in keylock switch in BYPASS.

BYPASS. (09-5-1-11 Alarm) ~.-.- ~.-.- EVALUATION I COMMENT SAT/UNSAT SAT IUNSAT SAT I UNSAT SAT/UNSAT CRITICAL STEP SAT I UNSAT -4 of 7

S/RO 2012 NRC S-2 TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close STEP STANDARD EVALUATION I COMMENT

6. Place RX SCRAM RESET The candidate places the REACTOR SCRAM RESET CRITICAL STEP switch to Group 2 & 3, then to selector switch, (SA-SS), momentarily to the GP2 and GP3 SAT / UNSAT 1 & 4, spring return to NORM.

position then back thru "NORM" to the GP1 and GP4 position then back to "NORM".

7. Verify RPS A and B SCRAM The candidate verifies the scram has been reset by SAT / UNSAT GROUPS 1, 2, 3 and 4 lights ensuring that the following lights are lit:

are on. A. RPS A Scram Groups 1, 2, 3 and 4 on Panel 09-S; B. RPS B Scram Groups 1, 2, 3 and 4 on Panel 09-S.

8.

Verify closed all scram inlet The candidate recognizes/reports that several control rod SAT/UNSAT I and outlet valves using one or scram inlet and outlet valves have failed to close by a combination of the following observing that blue scram lights are lit. I methods: Blue scram lights or local indication. EVALUATOR: If candidate asks, inform him that local I indication is consistent with the blue lights, the valves are open. -5 of 7

S/RO 2012 NRC S-2 TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close STEP STANDARD EVALUATION I COMMENT i

9. IF any scram inlet or outlet The candidate depresses the both manual scram CRITICAL STEP valve fails to close, then push buttons.

SAT IUNSAT I perform the following: A. Depress the following push buttons: MANUAL SCRAM A MANUAL SCRAM B B) Investigate cause The candidate states that they would initiate action SAT I UNSAT (condition report. work order request or discussion with supervision) to identify the cause of the scram valves failing to close. EVALUATOR: Terminate the task at this point. -6 of 7

HANDOUT

The reactor was scrammed 1 hour ago due to a Feedwater malfunction.
The scram condition has been identified and cleared.
All Reactor scram signals are now clear with the exception of the scram discharge volume high level signal.

The eRS has directed that you reset the scram per AOP*1 -7 of 7

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control & Manual Trip Required (Alternate Path). APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 206000 A4.06 4.3/4.3 JAF TASK NUMBER: 2060101005 JAF QUAL STANDARD NUMBER: _5.:....:0=2=3.:....:.1....;;.0....;...1___ ~~~~~---- ESTIMATED COMPLETION TIIVIE: 15 Minutes SUBMITTED: O~ r~ OPERATIONS REVIE APPROVED: ~~~

~---~ ~~--------------------------------------------------------

CANDIDATE NAME: SS NUMBER: JPM Completion D Simulated [gJ Performed Location: D Plant [gJ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CAI\\JDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COIVIPLETE: PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO/NPO APPL. TO 2012 NRC S-3 ..IPM NUMBER TASK TITLE: HPCI Manual Startup for RPV Pressure Control & Manual Trip Required (Alternate Path). Current Update: Date Outstanding Items D Technical Review D Questions and Answers D Procedural Change Required Comments: By: Int D D ~ Additional Information Validation None Current Update: Date By: Int. -2of11

S/RO/I\\IPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control & Manual Trip Required (Alternate Path). I. SAFETY CONSIDERATIONS None II. REFERENCES OP-15, High Pressure Coolant Injection (Current Revision), Attachment 7. III. TOOLS AND EQUIPMENT None IV. SET UP REQUIREMENTS Initialize the simulator to a 100% power IC (IC-122) Establish the following simulator conditions:

a. Rx Scrammed with MSIV's closed.

b. RPV Level> 126.5 and < greenband

c. RPV Pressure Control on SRV's at 800-1000 psig

d. RCIC running and injecting to maintain level (adjust as needed)

e. Place RHR Loop A in Torus Cooling

f. HPCI Auto Initiation Failure, MFI-HP01

g. HPCI Manually Tripped

h. SGT in service on Rx Bldg Vent.

i.

Place HPCI Turb Exh Disch Press Hi annunciator and 23PI-112 to 140 pSig on Trigger 1 NOTE: Sim Operator, at step 29, activate Trigger 1 after HPCI Turb Vib Mon switch is placed to On. V. EVALUATOR NOTES None VI. TASK CONDITIONS

Plant is in a post-scram condition with RPV level being controlled by RCIC RPV pressure is between 800 and 1000 psig and rising slowly.

Main Steam Isolation Valves are closed. 'A' and 'B' Standby Gas Treatment fan and filter train are in service RHR Loop 'A' is in Torus cooling -3 of 11

S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control &Manual Trip Required (Alternate Path).

- CRITICAL STEP INITIATING CUE Inform the candidate, "The CRS directs you to start the HPCI system for RPV pressure control lAW OP-15, Attachment 7.

Maintain RPV pressure 800 to 1000 psig." STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate obtains OP-15 Attachment 7 (located in the SAT I UNSAT procedure OP-15, Manual procedure holder on Panel 09-3).

Pressure Control Posted

2. Review the caution.

The candidate reviews caution. SAT I UNSAT

3. Verify a HPCI auto-initiation The candidate verifies Rx level is greater than 126.5" and SAT I UNSAT condition does not exist.

OW pressure less than 2.7 psig (thru use of panel meters, lack of Annunciators or EPIC computer indications).

4.

Verify RPV water level is LESS The candidate insures level is less than 222.5" on 02-3U THAN the high level trip. 283D. -4 of 11

S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control & Manual Trip Required (Alternate Path). STEP

5.

IF amber RX HI LVL SIGNAL 23A-DS65 light is on at panel 09 3, THEN reset high water level trip as follows:

6. Verify open CST SUCT VL V 23MOV-17.

7. Verify closed the following valves:

OUTBD TORUS SUCT VLV 23MOV-57 INBD TORUS SUCT VLV 23MOV-58

8. Ensure open OUTBD STM SUPP VLV 23MOV-16.

9. Verify open OUTBD STM SUPP VLV 23MOV-16

10. Throttle open TEST VLV TO CST 23MOV-21 approximately 10 secs.

STANDARD The candidate reviews step and recognizes that it is NA. The candidate verifies 23MOV-17 is open at 09-3 panel with red light on, green light off. The candidate verifies the Torus Suction Valves closed at panel 09-3 with red light off, green light on. The candidate opens 23MOV-16, at panel 09-3. The candidate verifies 23MOV-16 is open at 09-3 panel with red light on, green light off The candidate throttles open 23MOV-21 approximately 10 secs, at panel 09-3. -5 of 11 EVALUATION I COMMENT SAT IUNSAT SAT I UNSAT SAT I UNSAT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT I UNSAT

S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control &Manual Trip Required (Alternate Path). STEP

11. Verify throttled open TEST VLV TO CST 23MOV-21.

12. Open HPCI & RCIC TEST VLV TO CST 23MOV-24.

13. Verify open HPCI & RCIC TEST VL V TO CST 23MOV-24.

14. Ensure GLAND SEAL CNDSR BLOWER 23P-140 is running.

15. Ensure open TURB STM SUPP VLV 23MOV-14.

16. Verify open TURB STM SUPP VLV 23MOV-14.

17. IF annunciator 09-3-3-28 HPCI TURBINE TRIP SOLENOID ENERGIZED is in alarm, THEN depress INITIATION SIG/MAN TURBINE TRIP RESET 23A-S17 pushbutton.

STANDARD The candidate verifies 23MOV-21 is throttled at 09-3 panel with red light on, green light on. The candidate opens 23MOV-24, at panel 09-3. The candidate verifies 23MOV-24 is open at 09-3 panel with red light on, green light off. The candidate starts 23P-140, at panel 09-3, with red light on, green light off. The candidate opens 23MOV-14, at panel 09-3. The candidate verifies 23MOV-14 is open at 09-3 panel with red light on, green light off. The candidate will verify 09-3-3-28 HPCI TURBINE TRIP SOLENOID ENERGIZED is not in alarm EVALUATION I COMMENT SAT I UNSAT CRITICAL STEP SAT I UNSAT SAT I UNSAT SAT I UNSAT CRITICAL STEP SAT IUNSAT SAT / UNSAT SAT / UNSAT -6 of 11

S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control &Manual Trip Required (Alternate Path). ~-- STEP STANDARD EVALUATION I COMMENT

18. Ensure AUX OIL PMP 23P-150 is The candidate starts 23P-150, at panel 09-3.

CRITICAL STEP running. SAT/UNSAT

19. Verify HPCI flow is approximately The candidate verifies approximately 4250 gpm on SAT/UNSAT 4250 gpm.

23FI-108-1 at Panel 09-3.

20. Ensure closed the following The candidate ensures 23MOV-25, 23AOV-42 and SAT I UNSAT valves:

23AOV-43 are closed on the 09-3 and 09-4 panels with red light off, green light on.

Ensure closed MIN FLOW VLV, 23MOV-25.
STM LINE DRAIN TO RADW 23AOV-42
STM LINE DRAIN TO RADW 23AOV-43

-7of11

S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control &Manual Trip Required (Alternate Path). STEP STANDARD EVALUATION I COMMENT

21. CAUTION:

The candidate reviews caution and monitors HPCI turbine SAT IUNSAT speed on 23SPI-161. Operating HPCI at less than 2100 rpm could cause improper oil system operation, overheating of shaft driven oil pump, and insufficient exhaust flow resulting in check valve banging.

23. CAUTION:

The candidate reviews caution and monitors HPCI pump SAT I UNSAT discharge pressure on 23PI-109. Failure to closely monitor HPCI pump discharge pressure could result in exceeding HPCI piping design pressure of 1320 psig.

24. WHILE HPCI is in pressure At Panel 09-3, the candidate monitors HPCI turbine speed SAT I UNSAT control mode, maintain HPCI and throttles closed 23MOV-21 to ensure HPCI speed is >

speed GREATER THAN 2,100 2100 rpm, on 23SPI-161, except during transient rpm by throttling closed TEST operation. VL V TO CST 23MOV-21. -8 of 11

S/RO/NPO 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control & Manual Trip Required (Alternate Path). STEP STANDARD EVALUATION I COMMENT r~~-~

25. Control RPV pressure as follows:

At Panel 09-3, the candidate throttles 23MOV-21 as SAT I UNSAT necessary to maintain between 800 and 1000 psig.

Lower RPV pressure at a faster rate by throttling closed TEST VL V TO CST 23MOV 21 to raise discharge pressure and turbine steam flow.
Lower RPV pressure at a slower rate by throttling open TEST VL V TO CST 23MOV 21 to lower discharge pressure and turbine steam flow.

26.

Place RHR torus cooling per EVALUATOR: If asked, remind the operator of the initial N/A Section D of OP-13B, as soon conditions and that RHR Loop "A" is in Torus Cooling and as practicable.

that SGT "A" \\ "B" is running per OP-20.

Ensure any SGT is running.

27.

Ensure open one of the following The candidate ensures that 01-125MOV-13A OR 01-SAT I UNSAT valves: 125MOV-13B are OPEN at panel 09-75 with red light on, green light off.

HPCIGLANDSEALSUCT 01-125MOV-13A
HPCI GLAND SEAL SUCT 01-125MOV-13B

-9 of 11

HANDOUT

Plant is in a post-scram condition with RPV level being controlled by RCIC
RPV pressure is between 800 and 1000 psig and rising slowly.
Main Steam Isolation Valves are closed.
'A' and 'B' Standby Gas Treatment fan and filter train are in service
RHR Loop 'A' is in Torus cooling The CRS directs you to start the HPCI system for RPV pressure control lAW OP-15, Attachment 7.

Maintain RPV pressure 800 to 1000 psig.

11 of 11*

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/I\\lPO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED APPl. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 239001 A4.043.8/3.7 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: ESTIMATED COMPLETION TIf5L 15 Minutes SUBMITTED: OPERATIONS REVIE fh ~ ~~~~~~-----~------------------------------- CANDIDATE NAME: JPM Completion Location: D D Simulated Plant ~ Performed ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER Page 1 of 9

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED APPL. TO JPM NUMBER Current Update: By: Date Int Outstanding Items o Technical Review D Additional Information o Questions and Answers D Validation o Procedural Change Required [g] None Comments: Current Update By: Date Int Previous Revision Date: Page 2 of 9

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-9; OPENING MSIV's III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Any 100% power IC (IC-122) B. Rx Scrammed with MSIV's closed. C. RPV Level> 126.5 and < 222.5 controlling on RCIC. RPV Pressure Control on SRV's I HPCI/RCIC at 800-1000 psig OR use malfunctions A05 to control reactor pressure D. PCIS Group I isolation signals reset E. Assign to Trigger 2, ORI-TC ZAOP1 MSPA and ORI-TC ZAOP'I MSPB to 800 psig on a 5 minute ramp (this will allow DP indication across the MSIVs to equalize within 200 psid) NOTE: Reactor Pressure must be maintained 800-1000 psig for the Trigger 2 to simulate properly. Additional Simulator Instructor actions required at steps 3, 9 and 12. V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and not actually performed. B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated. VI. TASK CONDITIONS A. Plant is post scram with MSIV's closed

8.

MSIV isolation signals have been overridden as directed by the EOPs. C. Another operator has RPV pressure control on the SRV's at 800-1000 psig. D. The main condenser is to be re-established as a heat sink

- CRITICAL STEP Page 3 of 9

S/RO 201 2 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED VII. INITIATING CUE: Inform the candidate "The CRS directs you to equalize pressure and reopen the MSIV's per EP-9." STEP STANDARD EVALUATION I COMMENT

1.

SAT I UNSAT Obtain a controlled copy of procedure The candidate obtains a controlled copy of EP-9. EP-9, OPENING MSIV's Evaluator: Provide working copy.

2.

SAT / UNSAT IF differential pressure across the MSIVs is LESS THAN OR EQUAL TO Candidate uses 06PI-90A, B, and or C at panel 09-5 200 psid, THEN perform the following: and MAIN STEAM PRESS A and or B at EHC section of panel 09-5 to determine that differential pressure exceeds 200 psid. ---~ --~ Page 4 of 9

SIRO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED STEP

3.

Ensure closed the following valves: ./ MSIV 29AOV-80A-D ./ MSIV 29AOV-86A-D ./ MAIN STM DRN 29MOV-74, 77, 78 and 79 ./ MAIN STM DRN VLV 29MOV 101A-D ./ RFPT A and B HP STOP VLV HP SVA-1 and SVB-1 ./ TSV-1-4 ./ TO PCV 96MOV-S1 ./ PCV BYP 96MOV-S2 ./ 29MST-105 (SJAE MST supply 29PCV-107 outlet isol valve) (remote operated from East Electric Bay) ./ 29MST-107 (SJAE MST supply 29PCV -107 bypass strainer outlet isol valve) (remote operated from East Electric Bay) STANDARD Candidate closes and/or observes green closed light on and red open light off at the following locations: ./ MSIV 29AOV-80A-D at 09-3 and 09-4 ./ MSIV 29AOV-86A-D at 09-3 and 09-4 ./ MAIN STM DRN 29MOV-74, 77, 78 and 79 at 09-3 and 09-4 ./ MAIN STM DRN VLV 29MOV-101A-D at 09-7 ./ RFPT A and B HP STOP VLV HP SVA-1 at 09-6 ./ TSV-1-4 at 09-5 ./ TO PCV 96MOV-S1 at 09-7: depresses Close PB ./ PCV BYP 96MOV-S2 at 09-7: may depress Close ./ ***29MST -105 (SJAE MST supply 29PCV-1 07 outlet isol valve) (remote operated from East Electric Bay) by tel con to NPO*** ./ ***29MST-107 (SJAE MST supply 29PCV-107 bypass strainer outlet isol valve) (remote operated from East Electric Bay) by telcon to NPO.***

- - INSTRUCTOR NOTE***

Remote: MC31 TO 0 (to close 29MST-105/107) EVALUATION I COMMENT SAT I UNSAT Page 5 of 9

S/RO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED

4.

STEP Open the following valves: MAIN STM DRN 29MOV-74 STAi'1lDARD At panel 09-3 and 4 candidate opens 29 MOV-74 and

77.

EVALUATION I COMMENT SAT I UNSAT

CRITICAL STEP*

MAIN STM DRN 29MOV-77

5.

Verifies open the following valves: MAIN STM DRN 29MOV-74 At panel 09-3 and 4 candidate verifies open 29 MOV-74 and 77, red lights on, green lights off. SAT I UNSAT MAIN STM DRN 29MOV-77

6.

Jog open MAIN STM DRN 29MOV-79 until full open. At panel 09-4 candidate jogs opens 29 MOV-79 until full open and observes red light on, green light off SAT I UNSAT

7.

Open the following valves: MSIV 29AOV-86A At panel 09-3 candidate opens 29AOV-86 A-D. SAT I UNSAT

CRITICAL STEP*

MSIV 29AOV-86B MSIV 29AOV-86C MSIV 29AOV-86D Page 6 of 9

SIRO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED STEP STANDARD EVALUATION I COMMENT Verifies open the following valves:

8.

At panel 09-3 candidate verifies open 29AOV-86 A-D SAT / UNSAT and observes red lights on, green lights off. MSIV 29AOV-86A MSIV 29AOV-86B MSIV 29AOV-86C MSIV 29AOV-86D Open MAIN STM DRN 29MOV-78.

9.

At panel 09-4 candidate opens 29 MOV-78. SAT I UNSAT Simulator O~erator: Insert Trigger 2.

CRITICAL STEP*

Verifies open MAIN STM DRN 29MOV

10.

At panel 09-4 candidate verifies open 29 MOV-78 and SAT I UNSAT

78.

observes red light on, green light off. Close MAIN STM DRN 29MOV-79. EVALUATOR

11.

SAT I UNSAT Act as SM and waive step 5.9 At panel 09-4 candidate closes 29 MOV-79 and observes red light off, green light on. Page 7 of 9

SIRO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED STEP STANDARD EVALUATION I COMMENT WHEN differential pressure across the

12.

Candidate uses 06PI-90A, 8, and or C at panel 09-5 SAT I UNSAT MSIVs is LESS THAN OR EQUAL TO and MAIN STEAM PRESS A and or 8 at EHC section 200 psid, open the following valves: of panel 09-5 to determine differential pressure.

CRITICAL STEP*

MSIV 29AOV-80A When differential pressure is ~ 200 psid, candidate opens 29AOV-80 A-D at panel 09-4. MSIV 29AOV-80B Simulator Operator: Delete Trigger 2 overrides. MSIV 29AOV-80C MSIV 29AOV-80D Verfies open the following valves:

13.

Candidate verifies open MSIVs 29AOV-80A-D at SAT I UNSAT panel 09-4 by observing red lights on, green lights MSIV 29AOV-80A off. MSIV 29AOV-80B MSIV 29AOV-80C MSIV 29AOV-80D EVALUATOR: Terminate the task at this point. Page 8 of 9

HANDOUT Plant is post scram with MSIV's closed MSIV isolation signals have been overridden as directed by the EOPs. Another operator has RPV pressure control on the SRV's at 800-1 000 psig. The main condenser is to be re-established as a heat sink The CRS directs you to equalize pressure and reopen the MSIV's per EP-9. Page 9 of 9

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T 4 to Reserve Station Service APPL TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 262001 A4.04 3.6/3.7 JAF TASK NUMBER: 2620101001 JAF QUAL STANDARD NUMBER: OP-46A ~-...;...;....:.---- ~~--~--------- ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIE (h ~ APPROVED: M~

:-------~----------------------------------------------------

CANDIDATE NAME: JPM Completion Simulated lSI Performed Location: D Plant lSI Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIRO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service APPL. TO JPM NUMBER Current Update: By: Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers Validation D Procedural Change Required ~ None Comments: Current Update: By: Date Int. Previous Revision Date: -2 of 10

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIRO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-46A, 4160V and 600V Normal AC Power Distribution, Current Revision. III. TOOLS AND EQUIPMENT A. Synch Selector Switch key IV. SET UP REQUIREMENTS A. Initialize the simulator to an IC that has a power level of approximately 30% (IC-123). B. Place malfunction ED-19C, Bus 10300 Failure, on Trigger 1 NOTE: Simulator operator will need to insert this trigger after 10300 is on the Reserve Bus. V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed. C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication. VI. TASK CONDITIONS A. Reactor power is approximately 30% with the plant in the process of shutting down. B. The main generator is still synched to the grid. The plant is ready to transfer electrical supply must from normal station service to reserve station service. C. All prerequisites for transferring from normal to reserve station service have been met. D. The Shift Manager has given direction to transfer loads from the normal station service to the reserve station service. -3 of 10

S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, The CRS directs you to transfer loads from normal station service transformer T-4 to reserve 115kv transformers T2 and T3 per OP-46A, Section F. You are to start with the 10300 bus first. Inform the CRS when the 10300 bus has been transferred."

NOTE: All manipulations and indications are done at panel 9-8 unless otherwise indicated. STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SAT I UNSAT procedure OP-46A, 4160V of OP-46A.

and 600V Normal AC Power Distribution.

2.

Select the correct section to Selects Section F.3 of OP-46A. SAT / UNSAT perform the task. EVALUATOR: Provide candidate a copy of section F.3

3. Review precautions, notes and Reviews the precautions, notes and cautions.

SAT/UNSAT cautions associated with Section F.3.

4. WHILE performing the The candidate refers and reviews Section E.

SAT I UNSAT remainder of this subsection maintain 4KV and 600V bus voltage per Section E. ~.... -4 of 10

S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP

5.

Ensure Clark Energy Control Center notified that 10300 Bus will be transferred from normal to reserve service.

6. Station operators as follows:

One to adjust Bus voltage at LTC Control
One to operate breaker control switches
7. Place Bus 10300 FOR SYNCH switch in RES.

8. Match voltages on Non-EMERG BKRS INCOMING and RUNNING volt meters using LTC CONTROL switch.

STANDARD The candidate notifies ECC of impending transfer of bus 10300 to Transformer T3. EVALUATOR: If candidate inquires, inform candidate to call the simulator booth operator for all ECC actions. Simulator Operator: Act as ECC Dispatcher/Niagara Mohawk as necessary to simulate communications. The candidate ensures that operators are stationed at the LTC Controls and to operate breaker control switches. EVALUATOR: If candidate inquires, inform the candidate that an operator is standing by to adjust the LTC Control as directed by the candidate. Places the Bus 10300 FOR Synch Switch in RES. Observes that incoming and running voltages are matched on Non-Emerg Bkr 4KV Panel. EVALUATION I COMMENT SAT / UNSAT SAT I UNSAT CRITICAL STEP SAT / UNSAT SAT / UNSAT -5 of 10

S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T 4 to Reserve Station Service STEP STANDARD EVALUATION I COMMENT

9.

If phase angle is GREATER Observes that the phase angle is less than 17°. SAT/UNSAT THAN 17° on NON-EM ERG BKRS SYNCHROSCOPE, THEN perform the following:

1. Call ECC and Niagara Mohawk to reduce grid loads.

2. I F grid loads cannot be reduced THEN notify plant management before performing transfer.

10. WHEN incoming and running Ensures incoming and running voltages are matched and CRITICAL STEP voltages are matched AND synchroscope is approximately 12 o'clock. Operates SAT I UNSAT synchroscope is at breakers as follows:

approximately 12 o'clock, perform the following bus transfer using the same hand,

Close RSS to Bus 10300 Bkr 10312 by placing control switch to CLOSE.

without unnecessary delay, to perform each breaker operation: Open NSS to Bus 10300 Bkr 10302 by placing control

Close RSS TO BUS 10300 switch to TRIP.

BKR 10312

Open NSS TO BUS 10300 BKR 10302

-6 of 10 I

S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP

11. I Place Bus 10300 FOR SYNCH SW switch in OFF and remove handle.

12. I Recognize Loss of Bus 10300

13. I Performs AOP-16 immediate actions of:

IF 10400 Bus is energized, THEN cross-tie 10300 Bus L Gear with 10400 Bus L-Gear per Attachment 2 (sync switch required). STANDARD Restore 10300 Bus Controls and Indications to normal lineup. Remove operating handle and return handle to its normal storage location. Simulator Operator: Activate Trigger 1 at this point I Operator recognizes the loss of the 10300 bus and informs the CRS. EVALUATOR: As the CRS, direct the candidate to carry out any immediate actions for Panel 9-8. If the candidate starts to carry out AOP-8 (RWR Pump "An Trip) then inform the candidate another operator will perform that. I Refers to Attachment 2 of AOP-16. EVALUATION I COMMENT SAT/UNSAT SAT/UNSAT SAT I UNSAT -7 of 10

S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP

14. Verify closed L 14 L24 L34 L44 4KV FOR BKR 10440.

15. Cross-tie L43 with L44 as follows:

a. Open L43 600V FOR BKR 14302 and place its control switch in PULL TO LOCK.

b. Close L43-L44 TIE BKR 14304.

16. Cross-tie L33 with L34 as follows:

a. Open L33 600V FOR BKR 13302 and place its control switch in PULL TO LOCK.

b. Close L33-L34 TIE BKR 13404.

STANDARD Observes red light on, green light off for breakers:

L14 600V FOR Bkr 11402
L24 600V FOR Bkr 12402
L34 600V FOR Bkr 13402
L44 600V FOR Bkr 14402 Operator performs the following:
Places control switch for L43 600V FOR BKR 14302 to the PULL TO LOCK position
Places the L43-L44 Tie Synch SW to the ON position.
Places the L43-L44 TIE BKR 14304 to the CLOSE position.

Operator performs the following:

Places control switch for L43 600V FOR BKR 14302 to the PULL TO LOCK position
Places the L33-L34 Tie Synch SW to the ON position.
Places the L33-L34 TIE BKR 14304 to the CLOSE position.

EVALUATION I COMMENT SAT I UNSAT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT I UNSAT -8 of 10

S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP

17. Cross-tie L23 with L24 as follows:

a. Open L23 600V FOR BKR 12302 and place its control switch in PULL TO LOCK.

b. Close L23-L24 TIE BKR 12404.

18. Cross-tie L 13 with L 14 as follows:

a. Place RBC PMP A 15P-2A control switch in PULL TO LOCK.

b. Place RBC PMP C 15P-2C control switch in PULL TO LOCK.

c. Open L 13 600V FOR BKR 11302 and place its control switch in PULL TO LOCK.

d. Close L 13-U4 TIE BKR 11304.

STANDARD Operator performs the following: Places control switch for L43 600V FOR BKR 14302 to the PULL TO LOCK position

Places the L23-L24 Tie Synch SW to the ON position.

Places the L23-L34 TIE BKR 14304 to the CLOSE position. Operator performs the following:

At panel 9-6 places RBC PMP A 15P-2A control switch in PULL TO LOCK.
At panel 9-6 places RBC PMP C 15P-2C control switch in PULL TO LOCK.
Places control switch for L43 600V FOR BKR 14302 to the PULL TO LOCK position
Places the L23-L24 Tie Synch SW to the ON position.
Places the L23-L34 TIE BKR 14304 to the CLOSE position.

EVALUATION I COMMENT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT I UNSAT EVALUATOR: Terminate the task at this point. -9 of 10

HANDOUT

Reactor power is approximately 30% with the Plant in the process of shutting down.
The Main Generator is still synched to the grid.
The Plant is ready to transfer electrical supply from Normal station service to Reserve station service.
All prerequisites for transferring from Normal to Reserve station service have been met.
The Shift Manager has given direction to transfer loads from the Normal station service to the Reserve station service.

The CRS directs you to transfer loads from normal station service transformer T-4 to reserve 115kv transformers T2 and T3 per OP-46A, section F.3. You are to start with the 10300 bus first. Inform the CRS when the 10300 bus has been transferred. -10 of 10

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SIROINPO 2012 NRC S-6 TASK TITLE: "A" RHR Keep Full for Injection to the RPV APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 295031 EA1.08 3.8/3.9 JAF TASK NUMBER: 2050104048 5010.501 ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: 6b~ APPROVED: ~~~~~-=~~________________

~---------------------------------

CANDIDATE NAME: JPM Completion Location: o Simulated o Plant ~ Performed ~ Simulator DATE PERFORMED: PERFORMANCE EVALUATION: TIME TO COMPLET o Satisfactory E: Minutes 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNA TUREIPRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER 1 of 8

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC S-6 TASK TITLE: fI A fI RHR Keep Full for Injection to the RPV APPL. TO JPM NUMBER Current Update: By: Date Int Outstanding Items o Technical Review o Additional Information o Questions and Answers o Validation o Procedural Change Required IZI None Comments: Current Update By: Date Int Previous Revision Date: -2 of 8

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC S-6 TASK TITLE: nAn RHR Keep Full for Injection to the RPV APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. Comply with JAF Safety Standards and Requirements II. REFERENCES A. Primary Containment Flooding, EP-7 B. Alternate Injection Systems, EP-8 III. TOOLS AND EQUIPMENT A. Necessary tools and materials are located in the EP Support Cabinets. IV. SET UP REQUIREMENTS A. Obtain a controlled copy of EP-8 for use by the candidate. B. Setup the simulator for EOP-2 Post Emergency Depressurization with level below 0" T AF (lC-124) C. Secure all RPV injection D. Open the following RHR valves: 26A, 31 A, 38A, Close the following RHR valves: 25A, 27A V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed. VI. TASK CONDITIONS A. EOP-2 has been entered and the plant has Emergency Depressurized. B. Torus and DrYWell Sprays were in service when Adequate Core Cooling was lost C. Reactor water level can not be maintained greater than 0".

- CRITICAL STEP

-3 of 8

SRO/RO 2012 NRC S-6 TASK TITLE: "A" RHR Keep Full for Injection to the RPV. VII. INITIATING CUE Inform the candidate "The CRS directs you to Perform EP-8, Section 5.8, Condensate Transfer Keep Full for Injection into the "A" Loop of RHR." NOTE: Unless otherwise indicated, all actions are performed at Panel 09-03. STANDARD EVALUATION I COMMENT t II d f EP 8 Obtains a controlled copy of EP-8 and selects Section Obtam a con ro e copy 0 5.8 1. Evaluator: Provide working copy. SAT I UNSAT

+--------------------1 panel 09-06, verifies CST water level is GREATER i

220 inches I

2.

SAT/UNSAT 1 I At panel 09~06, ensures available condensate transtert. 'II pumps are running, red light on, green light off: I COND XFER PUMP A 33P-13A 'Ii I Ensure condensate transfer pumps are CRITICAL STEP running COND XFER PUMP B 33P-13B (starts) I ii'

3.

SAT I UNSAT I I I .._l I J -4 of 8

SRO/RO 2012 NRC S-6 TASK TITLE: "A" RHR Keep Full for Injection to the RPV. STEP STANDARD EVALUATION / COMMENT I Directs NLO to perform step A and/or B in the Line up condensate transfer to RHR Reactor Building: Loop "Au. A. Open 10RHR-274 (RHR Loop A containment spray keep-full cond xfer connection valve B. Open both of the following valves in the Drywell entrance: CRITICAL STEP 10RHR-256A (RHR Loop A LPCI cond xfer SAT I UNSAT inner isol valve)

4.

NOTE: Only Step A OR step B 1 ORHR-257 A (RHR Loop A LPCI cond xfer needs to be directed. outer isol valve) SIMULTOR OPERATOR: Insert Remote RH46 to 100%. As the Rx Bldg NLO, inform the operator the valve(s) are open. ~ __ ______________ L __________________________ L____ -5 of 8

SRO/RO 2012 NRC S-6 TASK TITLE: "An RHR Keep Full for Injection to the RPV. I STEP

1 STANDARD I

EVALUATION / COMMENT *1 I II! At panel 09-6, verifies condensate transfer pressure I i I I I I Verify condensate transfer pressure I 5 II' I is GREATER THAN RPV pressure 1 SAT I UNSAT I 1- -'I I Ensures closed at least one of the following by taking I I I I side DW Spray Valves I the control switch to the CLOSE position: 1 I I DW SPRAY OUTBD VLV 10MOV-26A i CRITICAL STEP I i

6, I

I SAT / UNSAT I I DW SPRAY INBD VLV 1 OMOV-31 A I I 1

-------+--V-e**-ri-fy-c-IO-s-e-d-a-t-Ie-a-s-t-o-n-e-o-f-t-h-e-'-'A-'-'----+ Verifies closed at least one of the following:

1 side DW Spray Valves 'I DW SPRAY OUTBD VLV 10MOV-26A

7.

SAT / UNSAT DW SPRAY INBD VLV 10MOV-31A Ensures closed TORUS SPRAY INBD VLV 10MOV Ensure closed Torus Spray Inboard 38A b k' hi' h h CLOSE V I Y ta 109 t e contro SWltc to t e CRITICAL STEP

8.

a ve position. Green light on, red light off SAT I UNSAT Verify closed Torus Spray Inboard Verifies closed TORUS SPRAY INBD VLV 10MOV

9.

Valve 38A by observing red light off, green light on. SAT / UNSAT Determine IF/THEN reset logic Determines that the IF/THEN statement regarding

10.

statement for SDC ISOL for 10MOV-the isolation signal for 1OMOV-25A for SAT I UNSAT 25A does not apply cooling does not apply -6 of 8

SRO/RO 2012 NRC S-6 TASK TITLE: "An RHR Keep Full for Injection to the RPV. I COMMENT! I Ensures open LPCI OUTBD INJ VLV 1OMOV-27A by CRITICAL STEP I

11.

SAT / UNSAT open

12.

10MOV-27A by observing red light on, green light off. SAT / UNSAT Ensure open LPCI INBD INJ VLV 10MOV-25A Ensures open U'CI INt:SU INJ VLV 1UMUV-LOA by

13.

taking the control switch to the OPEN position. SAT / UNSAT Ensures open LPCIINBD INJ VLV 10MOV-25A by 14 1OMOV-25A observing red light on, green light off. EVALUATOR: Terminate the task at this point. -7 of 8

HANDOUT

EOP-2 has been entered and the plant has Emergency Depressurized.
Torus and Drywell Sprays were in service when Adequate Core Cooling was lost
Reactor water level can not be maintained greater than OFf.

The CRS directs you to Perform EP-8, Section 5.8, Condensate Transfer Keep Full for Injection into the "A" Loop of RHR. -8 of 8

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation APPL. TO JPM NUMBER REV: DATE: ____ NRC KIA SYSTEM NUMBER: 290001 A3.01 3.9/4.0 JAF TASK NUMBER: 2000401250 5066.104 ESTIMATED COMPLETION TIM~ 10 Minutes SUBMITTED: Cb. ~~ OPERATIONS REV. EW: ~~~-~~~~~~---------~------------------------------------------------------ CANDIDATE NAME: JPM Completion o Simulated ~ Performed Location: o Plant ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: o Satisfactory o Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER C:\\Documents and Settings\\nrcexam\\Desktop\\LOI-12 NRC Exam Final\\JPMs Final\\- Sim Plant JPMs\\S7\\S7 New Restore RBHVAC.doc

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation APPl. TO JPM NUMBER Current Update: By: Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation Procedural Change Required lZl None Comments: Current Update: By: Date Int. Previous Revision Date: ~2 of 9

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIRO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. Reactor Building Ventilation and Cooling System OP-51A B. Recovery from an Isolation AOP-15 C. Standby Gas Treatment System OP-20 D. Isolationllnterlock Overrides EP-2 III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset the simulator to a 100% IC and scram the reactor (IC-124). B. Ensure level reaches the 177" low level isolation setpoint C. After level recovers, complete AOP-1 actions and AOP-15 isolation reset. D. Secure "B" SBGT. V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed. VI. TASK CONDITIONS A. A feedwater transient occurred result in a reactor scram caused by RPV water level lowering to 165". B. All automatic actions were verified. C. All Immediate and Subsequent Actions of AOP-1 are completed. D. Low RPV water level isolation has been defeated per EP-2. E. The "A" train of the Standby Gas Treatment System remains in operation for a maintenance inspection. -3 of 9

S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation

- CRITICAL STEP VII.

INITIATING CUE Inform the candidate, "The CRS has directed you to "Restore Reactor Building Ventilation to a normal line-up following the isolation on low RPV water level, using OP-51A, Section G.3." NOTE: All actions are at panel 09-75. STEP

1. Obtain a controlled copy of OP 51A, Reactor Building Ventilation and Cooling System.

2. Reviews the correct section of the procedure.

3. IF Reactor Building Ventilation isolated due to low RPV water level (177 inches) or high drywell pressure (2.7 psig) THEN either reset isolation per AOP-15 OR ensure isolation is overridden per EOPs.

STANDARD Obtains a controlled copy of OP-51 A. Evaluator: Provide working copy. Reviews Special Procedures Section of OP-51A and selects Section G.3, Restoration from isolation. Candidate remembers from initial conditions that the isolations are reset OR contacts CRS/SM. EVALUATOR: If asked in isolations are reset, inform the candidate they are. EVALUATION I COMMENT SAT I UNSAT SAT / UNSAT SAT I UNSAT -4 of 9

S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP

4. Ensures one below refuel floor exhaust fan is running and red flagged:

Below EI. 369' EXH FAN 66FN-12A
Below EI. 369' EXH FAN 66FN-12B

5.

Ensures the control switch for the shutdown below refuel floor exhaust fan (Below EI. 369' EXH FAN 66FN-12A or B) is green flagged.

6. Ensure two of the supply fans are running with switch red flagged.

Supp FN A 66FN-5A
Supp FN B 66FN-5B
Supp FN C 66FN-5C

7.

Ensure control switch for the shutdown supply fan (SUPP FN 66FN-5A, B, or C) is green flagged. STANDARD Ensures one below refuel floor exhaust fan is running with its control switch red flagged.

Below EI. 369" EXH FAN 66FN-12A
Below EI. 369' EXH FAN 66FN-12B Observes red light on, green light off for the running fan.

Ensures the control switch for the shutdown below refuel floor exhaust fan fan {Below EI. 369' EXH FAN 66FN-12A or B) is green flagged. Observes red light off, green light on. Ensures two of the supply fans are running with their associated control switches are red flagged.

Supp FN A 66FN-5A
Supp FN B 66FN-5B
Supp FN C 66FN-5C Observes red lights on, green lights off for the running fans.

Ensures shutdown supply fan (SUPP FN 66FN-5A, B, or C) switch is green flagged. Observes red light off, green light on. -5 of 9 EVALUATION I COMMENT SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT

S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP Ensure control switches for above

8.

refuel floor exhaust fans (EL 369' EXH FN 66FN-13A and 8) are as follows:

One Fan Control Switch RED Flagged.
One Fan Control Switch in PULL TO LOCK.

9. Verifies that one fan is running and one fan is not.

10. Ensure control switch for tank exhaust fan is red flagged.

11. Ensure one crescent supply fan is running with control switch red flagged.

CRESC SUPP FN 66FN-26A
CRESC SUPP FN 66FN-26B

12. Ensure control switch for the shutdown crescent supply fan is green flagged.

STANDARD Ensures the control switch for one of the below fans is in PULL TO LOCK and the other is RED FLAGGED.

66FN-13A RED FLAGGED
66FN-13B PULL TO LOCK For the running fan observes red light on, green light off and for the fan in PULL TO LOCK observes red light off, green light on.

Ensures the control switch for the tank exhaust fan 66FN-35 is red flagged. Ensure the control switch for one of the crescent supply fans is red flagged and the fan is running.

Ensures the control switch for the crescent supply fan 66FN-26A is red flagged.

Observes red light on, green light off. Ensures the control switch for the shutdown crescent area supply fan 66FN-26B is green flagged. -6 of 9 EVALUATION I COMMENT CRITICAL STEP SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT

S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP

13. Verify the shutdown crescent supply fan is not running

14. Reset Reactor Building Ventilation Isolation. Depress and Hold "RESET' AlB pushbuttons to open:
66AOV-100A INBD SUPP ISOL
66AOV-101A OUTB SUPP ISOL 66AOV-100B INBD SUPP ISOL
66AOV-101B OUTB EXH ISOL

15. Verifies the Reactor Building Ventilation Isolation is reset.

16. Verify one of the following above refuel floor fans is running:

EL 369' EXH FAN 66FN-13A
EL 369' EXH FAN 66FN-13B STANDARD Verifies the shutdown crescent area supply fan 66FN-26B is not running, red light off, green light on.

Depress and Hold "Reset" push buttons concurrently or individually until the following valves indicate open; then release the push buttons: "A" Reactor Building Ventilation:

66AOV-100A OPEN 66AOV-101A OPEN "B" Reactor Building Ventilation:
66AOV-100B OPEN 66AOV-101B OPEN Verifies 66AOV-100AlB and 66AOV-101A1B are open, observing red light on, green lights off.

Verifies that the above refuel floor exhaust fan 66FN-13A is running, red light on, green light off. EVALUATION I COMMENT SAT/UNSAT CRITICAL STEP SAT I UNSAT SAT / UNSAT SAT I UNSAT -7 of 9

S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation

17.

STEP Place the control switch for the shutdown above refuel floor exhaust fan in "NORMAL AFTER OFF" (Green Flagged). STANDARD Release PULL TO LOCK and "Green" flag the switch and verify red light off, green light on. EVALUATION / COMMENT CRITICAL STEP SAT / UNSAT EVALUATOR: Previous step (#8) had the control switch in PULL TO LOCK.

18.

Verify tank exhaust fan is running.

66FN-35 Verifies tank exhaust fan 66FN-35 started and is running.

SAT I UNSAT EVALUATOR: Terminate the task at this point. -8 of 9

HANDOUT o A feedwater transient occurred result in a reactor scram caused by RPV water level lowering to 165". o All automatic actions were verified. o All Immediate and Subsequent Actions of AOP-1 are completed. o Low RPV water level isolation has been defeated per EP-2. o The "A" train of the Standby Gas Treatment System remains in operation for a maintenance inspection. The eRS has directed you to "Restore Reactor Building Ventilation to a normal line-up following the isolation on low RPV water level, using OP-51A, Section G.3. -9 of 9

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SIROINPO 2012 NRC P-1 TASK TITLE: Venting the Scram Air Header APPL. TO JPM NUMBER REV: 0 DATE: 1/312012 NRC KIA SYSTEM NUMBER: 295037 EA 1.05 (3.9/4.0) JAF TASK NUMBER: 2000402213 JAF QUAL STANDARD NUMBER: 503c.502b ESTIMATED COMPLETION TIME: 13 Minutes SUBMITTED: Ch ~...... OPERATIONS REVIE ~~~~~~-----~--------------------------------- CANDIDATE NAME: JPM Completion Location: [gJ [gJ Simulated Plant D D Performed Simulator. DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory . D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNA TURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER -1 of 6

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC P-1 TASK TITLE: Venting the Scram Air Header APPL. TO JPM NUMBER Current Update: By: Date Int Outstanding Items D Technical Review D Additional Information D D Questions and Answers Procedural Change Required D cg) Validation None Comments: Current Update By: Date Int Previous Revision Date: -2 of 6

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC P-1 TASK TITLE: Venting the Scram Air Header APPL. TO JPM NUMBER A. Ensure proper safety equipment and safety procedures are observed. II. REFERENCES A. EOP-3, Failure to Scram B. EP-3, Backup Control Rod Insertion III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Contact Radiation Protection concerning area dose rates and contamination levels prior to performing the task. B. Current copy of EP-3, Backup Control Rod Insertion for candidate use. V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. This task is to be simulated. Inform the candidate that the conditions of each step need only be properly identified and not actually performed. VI. TASK CONDITIONS A. A Failure to Scram condition has occurred. B. Numerous control rods have failed to insert. C. EOP-2, 3 have been entered by the Shift Manager. D. Investigation has determined, from EP-3 that the first success path would be to vent the scram air header to insert the control rods.

- CRITICAL STEP

-3 of 6 I. SAFETY CONSIDERATIONS

S/RO/NLO TASK TITLE: Venting the Scram Air Header. VII. INITIATING CUE Inform the candidate, "The CRS has directed you to Vent the Scram Air Header per Section 5.3 of EP-3". STEP STANDARD EVALUATION / COMMENT

~------------------------------------+-

1.

Obtain a controlled copy of the Obtains a controlled copy of EP-3. SAT / UNSAT procedure. Evaluator: When Candidate states where one can be obtained, provide copy.

2.

Reviews the prerequisites/precautions Reviews prerequisites/precautions and notes SAT / UNSAT associated with the procedure. applicable portions.

3.

Selects the correct section of the Reviews EP-3 and indications. Selects section 5.3 of SAT I UNSAT procedure to be performed. the procedure for Venting the Scram Air Header.

4.

Ensures Open: Proceeds to the Reactor Building 272' el. Southwest SAT / UNSAT Corner, locates and ensures open the following '03CRD-2028 valves: '03CRD-2029 '03CRD-2028 (Filter 278 Outlet Isolation) '03CRD-2029 (Filter 27A Outlet Isolation) EVALUATOR NOTE: One valve will be open (the in service filter) and one valve will be closed EVALUTOR CUE: When the closed valve is turned CW, the handwheel does not move. When the open valve is turned CW, the handwheel turns. Candidate will turn valve CCW and hits a hard stop. 4

S/RO/NLO TASK TITLE: Venting the Scram Air Header. STEP

5.

Shuts the following valves: '03CRD-2030 '03CRD-2031

6.

Opens drain valve on air filters. 03F-27A (is a 8all Valve) 03F-278 (is a Petcock Valve)

7.

Verifies scram air header pressure lowers. STANDARD Shuts the following valves: '03CRD-2030 (Filter 27A Inlet Isolation) '03CRD-2031 (Filter 278 Inlet Isolation) EVALUTOR CUE: When turned CW, the handwheel turns several rotations, then hits a hard stop. Locates the drain valve on the bottom of each filter and OPENS both filter drain valves. EVALUTOR CUE: When turned CCW, the petcock \\ paddle turns then hits a hard stop. Locates pressure indication 03PI-229 and verifies that air header pressure is lowering. EVALUTOR CUE: Inform the candidate when the correct pressure indication is located that "scram air header pressure is lowering". After one minute, inform the candidate that "scram air header pressure is reading 0 psig". EVALUATION I COMMENT SAT I UNSAT CRITICAL STEP SAT I UNSAT SAT I UNSAT EVALUATOR: Inform the candidate that all control rods are fully inserted and to restore the scram air header. 5

S/RO/NLO TASK TITLE: Venting the Scram Air Header. STEP STANDARD EVALUATION I COMMENT

8.

Shuts air filter drain valves. Locates the scram air header filter drain valves and CRITICAL STEP shuts both drain valves. SAT I UNSAT EVALUTOR CUE: When turned CW, the petcock \\ paddle turns then hits a hard stop. .., 9. Opens the filter inlet isolation valves. Locates and opens the following valves: CRITICAL STEP SAT I UNSAT

03CRD-2030 (Filter 27A Inlet Isolation)
03CRD-2031 (Filter 27B Inlet Isolation)

EVALUTOR CUE: When turned CCW, the handwheel turns several rotations, and then hits a hard stop. EVALUATOR CUE: If asked, inform the candidate that pressure indication on pressure indicator 03PI-299 is rising. 6

S/RO/NLO TASK TITLE: Venting the Scram Air Header. STEP STANDARD EVALUATION I COMMENT

10.

Shuts one of the following valves: Locates and shuts one of the following valves: CRITICAL STEP SAT I UNSAT '03CRD-2028 '03CRD-2028 (Filter 278 Outlet Isolation) OR OR '03CRD-2029 '03CRD-2029 (Filter 27A Outlet Isolation) EVALUATOR CUE: If candidate contacts the Control Room for guidance, then direct the operator to shut either valve of your choice. When turned CW, the handwheel turns several rotations, and then hits a hard stop.

11.

Reports task restoration to the Reports to the Control Room that the Scram Air SAT I UNSAT Control Room. System has been restored. 7 EVALUATOR: Terminate the task at this point.

HANDOUT

A Failure to Scram condition has occurred.
Numerous control rods have failed to insert.
EOP-2, 3 have been entered by the Shift Manager.
Investigation has determined, from EP-3 that the first success path would be to vent the scram air header to insert the control rods.

The CRS has directed you to Vent the Scram Air Header per Section 5.3 of EP-3. 8

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC P-2 TASK TITLE: VENTING THE TORUS TO REDUCE APPL. TO JPM NUMBER CONTAINMENT PRESSURE REV: 0 DATE: 1/3/2012 NRC K/A SYSTEM NUMBER: 295010 AA 1.05 3.1/3.4 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIE (h~ APPROVED: CANDIDATE NAME: JPM Completion Location: rg] rg] Simulated Plant D D Performed Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (IVIANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC P-2 TASK TITLE: VENTING THE TORUS TO REDUCE APPL. TO JPM NUMBER CONTAINMENT PRESSURE Current Update: By: Date Int Outstanding Items Technical Review D Additional Information Questions and Answers D Validation Procedural Change Required ~ None Comments: Current Update By: Date Int Previous Revision Date:

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC P-2 TASK TITLE: VENTING THE TORUS TO REDUCE APPL. TO JPM NUMBER CONTAINMENT PRESSURE I. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed. II. REFERENCES A. EP-6, POST ACCIDENT CONTAINMENT VENTING AND GAS CONTROL III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Current copy of EP-6 including Attachment 1. V. EVALUATOR NOTES A. This task is to be simulated. Inform the candidate that the conditions of each step need only be properly identified and not actually performed. B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated. VI. TASK CONDITIONS A. Conditions have occurred which require venting the drywell. B. Action to preclude the failure of containment must be completed

- CRITICAL STEP

VII. INITIATING CUE Inform the candidate "You are directed by the CRS to vent the Torus using EP-6, Section 5.7 "Venting Containment". NOTE: Unless otherwise noted, all controls are located on Panel 27PCP in the Relay Room. STEP 1. Obtain a controlled copy of procedure, EP-6. Reviews prerequisites, precautions

2.

and special instructions associated with the procedure.

3.

Selects section 5.7, Venting Containment. CAUTION:

4.

PCPl is based upon the maximum pressure that primary containment vent and purge Isolation valves (AOVs and MOVs) can be operated. PCPl curve is shown on Attachment 1. STANDARD Obtains a controlled copy of procedure and proceeds to the PCP panel in the Relay Room. EVALUATOR: A controlled copy of the procedure is available at the PCP panel. Evaluator to provide working copy Reviews applicable portions. Selects the correct section of the procedure to be performed. Reviews Caution and Attachment 1, and determines whether containment conditions will allow venting. EVALUATOR CUE: When candidate locates indication of pressure and level, inform the candidate that Torus Pressure is 50 psig and Torus level is 29.0 ft. EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT

WARNINGS:

5.

While venting the primary containment, radiation dose rates will rise in the following areas: Along Primary Containment vent piping in the Reactor Building. Above underground vent piping between the Reactor Building and Stack.

In the vicinity of the Stack.
In the Standby Gas Treatment System room.

While venting the Primary Containment, the in-service SGT could rupture and cause a ground level release. Ensure only one SGT is in service per

6.

OP-20. CAUTION:

7.

Failure to close 01-125MOV-11 and 01-125MOV-12 could release primary containment atmosphere to the reactor building. Ensure each of the following valves is

8.

closed with its control switch in to-lock: ABOVE EL. 369' SUCT 01 125MOV-11 BELOW EL. 369' SUCT 01 125MOV-12 Reviews Warnings: Ensures Radiation Protection has been informed regarding the potential change in radiation levels in these areas. Ensures any operators in the vicinity of SGT are warned of the potential for rupture. EVALUATOR CUE: Acknowledge the Radiation Protection and operator warning from the candidate. Candidate either goes to, or contacts the control room to ensure the SGT is in service. EVALUATOR CUE: When candidate requests feedback, acknowledge that only one SGT is in service. Reviews Caution. Contacts the control room to ensure the valves are closed. EVALUATOR CUE: When candidate requests feedback regarding valves from the control room, acknowledge the valves are closed and in PTL. SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT

Ensure closed the following valves:

9.

For each valve, candidate locates its red/green SAT I UNSAT position lights and indicates it should be closed.

OW PURGEIINERT SUPP ISOL VLV 27AOV~111
OW SUPP ISOL VLV 27AOV-112 EVALUATOR CUE:

When candidate inquires about light status, inform the candidate the green light is

TORUS PURGE/INERT SUPP ISOL on, red light is off.

VLV 27AOV~115

TORUS SUPP ISOL VLV 27AOV 116.
TORUS EXH INNER ISOL VL V 27AOV-117.
TORUS EXH OUTER ISOL VLV 27AOV-118.
OW EXH OUTER BYP VL V 27MOV-113.
TORUS EXH INNER BYP VLV 27MOV-117.
OW EXH INNER BYP VLV 27MOV 122.
TORUS EXH OUTER BYP VLV 27MOV-123.
OW EXH INNER ISOL VLV 27AOV-113.
OW EXH OUTER ISOL VL V 27AOV-114.

Ensure the following switches are in

10.

RESET:

27 SYS DIV II ISOL VLVS at panel 09-3
27 SYS DIV I ISOL VLVS at panel 09-4 Ensure open the following valves:

11. DW/TORUS EXH TO SGT ISOL VLV 2MOV-120 DWITORUS EXH TO SGT ISOL VLV 27MOV-121 NOTE:

12.

Steps 5.7.6 and 5.7.7 may be performed and repeated in any order to alternate between torus and drywell venting. Torus venting is preferred.

13.

IF Torus will be vented THEN perform the following:

Verify torus pressure is LESS THAN PCPL
Verify primary containment water level is LESS THAN 29.5 feet.
While venting torus, frequently monitor torus pressure and primary containment water level.
IF primary containment water level reaches 29.5 feet while venting the torus, THEN vent drywell per Step 5.7.7.

Contacts the control room to ensure switches are in RESET. EVALUATOR CUE: When candidate requests feedback regarding switches from the control room, acknowledge the switches are in RESET. For each valve, candidate locates its red/green position lights and indicates it should be open. EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is off, red light is on. Reviews Note and selects step 5.7.6 to perform as directed. Verifies pressure is less than PCPL and level is less than 29.5 ft. EVALUATOR CUE: When candidate locates indication of pressure and level, inform the candidate that Torus Pressure is 50 psig and Torus Level is 29.0 ft. SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT I UNSAT

Open TORUS EXH INNER BYP 13 cont

VLV 27MOV-117.
Open TORUS EXH OUTER BYP VLV 27MOV-1
Ensure closed the following valves:

0 OW EXH OUTER BYP VLV 27MOV-113. 0 OW EXH INNER BYPASS VLV 27MOV-122. 0 OW EXH INNER ISOL VLV 27AOV-113. 0 OW EXH OUTER ISOL VLV 27AOV-114. IF primary containment water level

14.

reaches 29.5 feet while venting the torus, THEN vent drywell per Step 5.7.7. Candidate places TORUS EXH INNER BYP VLV 27MOV-117 control switch to the OPEN position EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on. Candidate places TORUS EXH OUTER BYP VLV 27MOV-123 control switch to the OPEN position. EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on. For each valve, candidate locates its red/green position lights and indicates it should be closed. EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is on, red light is off. EVALUATOR CUE: After 27MOV-117 & 123 are open, inform the candidate that the control room has called to inform the candidate that Torus Water level is 30 ft. Candidate refers to section 5.7.7 E~ALUAIOB CUE: If candidate wants direction from the control room, inform the candidate that for the purposes of this JPM, no further guidance can be given. SAT / UNSAT CRITICAL TASK SAT / UNSAT CRITICAL TASK SAT / UNSAT SAT I UNSAT

IF drywell will be vented, THEN

15.

perform the following:

Verify torus pressure is BELOW PCPL
Open OW EXH OUTER BYP VLV 27MOV-113 Open OW EXH INNER BYPASS VLV 27MOV-122.
Ensure closed the following valves:

0 TORUS EXH INNER BYP VLV 27MOV-117 Verifies pressure is less than PCPL. EVALUATOR CUE: When candidate locates indication of pressure and level, inform the candidate that Torus Pressure is 50 psig and Torus Level is 30.0 ft Candidate places OW EXH OUTER BYP VLV 27MOV 113 control switch to the OPEN position EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on. Candidate places OW EXH INNER BYPASS VLV 27MOV-122 control switch to the OPEN position EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on. Candidate places TORUS EXH INNER BYP VLV 27MOV-117 control switch to the CLOSE position. EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off. SAT / UNSAT SAT / UNSAT CRITICAL TASK SAT / UNSAT CRITICAL TASK SAT / UNSAT CRITICAL TASK

0 TORUS EXH OUTER BYP VLV 27MOV-123 0 TORUS EXH INNER ISOL VlV 27AOV-117 0 TORUS EXH OUTER ISOL VLV 27AOV-118

IF it becomes necessary to raise

16.

vent rate, AND torus pressure is LESS THAN PCPl, THEN attempt to open the following valves: 0 OW EXH INNER ISOl VlV 27AOV-113 0 OW EXH OUTER ISOL VlV 27AOV-114 Candidate places TORUS EXH OUTER BYP VLV 27MOV-123 control switch to the CLOSE position. EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off. For each valve, candidate locates its red/green position lights and indicates it should be closed. EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is on, red light is off. Contacts control room and requests direction on vent rate. EVALUATOR CUE: When candidate requests direction for vent rate, respond that current rate of pressure reduction is acceptable. SAT / UNSAT CRITICAL TASK SAT / UNSAT SAT / UNSAT

IF containment purge is not in Contacts the control room on the status of

17.

progress, THEN cycle one or more containment purge. of the following valves as necessary to control torus pressure. Verify torus pressure is EVALUATOR CUE: When candidate inquires as to lESS THAN PCPl before opening the status of containment purge, inform the candidate any valve: that it is NOT in progress. 0 OW EXH OUTER BYP VlV 27MOV-113 0 OW EXH INNER BYPASS VlV 27MOV-122 0 OW EXH INNER ISOL VLV 27AOV-113 0 OW EXH OUTER ISOL VlV 27AOV-114 EVALUATOR: Terminate the JPM at this point. SAT I UNSAT

HANDOUT

Conditions have occurred which require venting the drywell.
Action to preclude the failure of containment must be completed You are directed by the CRS to vent the torus using EP-6, Section 5.7 IIVenting Containment.

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO/NPO 2012 NRC P-3 TASK TITLE: Supplying Cooling Water to EDG's Band 0 from Fire Protection APPL. TO .JPM NUMBER REV: 0 DATE: 1/3/2012 NRC KIA SYSTEM NUMBER: 286000 K1.09 3.2/3.3 JAF TASK NUMBER: 2000402246 JAF QUAL STANDARD NUMBER: OP-22 ESTIMATED COMPLETION TIME: 12 Minutes SUBMITTED: OPERATIONS REVI APPROVED: CANDIDATE NAME: ...IPM Completion rz:I Simulated D Performed Location: rz:I Plant D Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) EVALUATOR: SIGNATURE/PRINTED CANDIDATE REVIEW: SIGNATURE REVIEWED BY: DOC. COMPLETE: PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIROINPO APPL. TO 2012 NRC P-3 ..IPM NUMBER TASK TITLE: Supplying Cooling Water to EDG's Fire Protection Band D from Current Update: Outstanding Items Date D Technical Review D Questions and Answers D Procedural Change Required Comments: By: Int D D ~ Additional Information Validation None Current Update Previous Revision Date: Date By: Int -2 of 8

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO/NPO 2012 NRC P-3 TASK TITLE: Supplying Cooling Water to EDG's Band D from Fire Protection APPL TO JPM NUMBER I. SAFETY CONSIDERATIONS A. Gloves II. REFERENCES A. OP-22, Diesel Generator Emergency Power. III. TOOLS AND EQUIPMENT A. Equipment located in cabinet 76CAB-1 on West wall of North Emergency Service Water Room. IV. SET UP REQUIREMENTS A. Obtain Shift Manager/Control Room Supervisor permission prior to performing this task. B. Obtain a current copy of OP-22 for use by the candidate prior to performing this task. V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated. B. This task is to be simulated. Inform the candidate that the conditions of each step need only be properly identified and not actually performed. C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication. VI. TASK CONDITIONS A. The plant has sustained a loss of off-site power. S. The A and C EDG's have failed to start. C. Upon initiation of the Band D EDG's, the "B" ESW System failed due to a fault in the supply breaker to the "B" ESW pump.

- CRITICAL STEP

-3 of 8

S/RO/NPO 2004246B TASK TITLE: Supplying Cooling Water to EOG's Band 0 from Fire Protection VII. INITIATING CUE the candidate, "The Shift Manager has directed you to supply cooling water to EOG's Band D from the Fire Protection System per OP-22, section G.25" STEP

1. Obtain a controlled copy of the procedure OP-22.

2. Reviews the precautions of the procedure.

3. BEFORE cross connecting safety systems, review system status to ensure failure of one system will not result in common-cause failure.

4. Verify ESW pumps not available

46P-2A
46P-2B

5. Reviews "CAUTION" pertaining to fire protection pumps and reference to screenwell forebay level.

STANDARD The candidate determines where to obtain a controlled copy of OP-22. (Control Room, Merlin, EDG room) EVALUATOR: Provide trainee a current copy of OP-22 G.25. Reviews the precautions associated with OP-22 and notes applicable sections. EVALUATOR CUE: If asked, inform the candidate that the review is complete and a single failure of one system will NOT result in common-cause failure. From initial conditions, verifies that ESW pumps 46P-2A and 46P-2B ARE NOT available. Reviews "CAUTION" and notes reference to screenwell forebay level. EVALUATOR CUE: If asked for forebay level state that forebay level is normal. -4 of 8 EVALUATION I COMMENT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT

S/RO/NPO 20042468 TASK TITLE: Supplying Cooling Water to EDG's 8 and D from Fire Protection STEP STANDARD EVALUATION I COMMENT ~~-

6. Ensures one Fire Protection pump Ensures at least one of the following pumps is running:

SAT I UNSAT running.

ELECTRIC FIRE PUMP, 76P-2
DIESEL FIRE PUMP, 76P-1
DIESEL FIRE PUMP, 76P-4 EVALUATOR CUE: Candidate may visually ensure one pump is running by using local indications or by contacting the Control Room. If necessary, respond to Control Room communication and report to the candidate that Diesel Fire Pumps P1 and P4 are running.

7. Verify closed at least one of the Verify closed at least one of the following valves:

SAT IUNSAT following:

46ESW-2A, ESW Loop "A" supply to EDG cross-tie 46ESW-2A isolation valves
46ESW-28
46ESW-28, ESW Loop "8" supply to EDG cross-tie isolation valve EVALUATOR CUE: When turned CW, the handwheels do not turn.

B. Reviews "NOTE" pertaining to Reviews "NOTE" on directions to remove caps. SAT/UNSAT locking devices. -5 of 8

S/RO/NPO 20042468 TASK TITLE: Supplying Cooling Water to EOG's 8 and 0 from Fire Protection STEP

9. I Cross-tie ESW and Fire Protection STANDARD Line-up the cross-tie between Fire Protection and ESW as follows:

a. Remove caps, by pushing the red detents, from the following:

46ESW-2000 76FPS-2000 EVALUATOR CUE: Red detent pushed, caps rotated CCW

b. Connect short length of hose between the following valves: (hose located in cabinet 76CAB-1 on west wall of north emergency service water room) 46 ESW-2000 76FPS-2000 EVALUATOR CUE: Hose connected

c. Unlock and Open 76FPS-2000.

EVALUATOR CUE: Using P2 Key, valve unlocked and turned CCW to hard stop

d. Unlock and Open 46ESW-2000.

EVALUATOR CUE: Using P5 Key, valve unlocked and turned CCW to hard stop EVALUATION I COMMENT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT/UNSAT -6 of 8

I S/RO/NPO 20042468 TASK TITLE: Supplying Cooling Water to EDG's 8 and D from Fire Protection STEP

10. Reviews "NOTE" pertaining to the ESW lockout matrix.

11. Opens circuit breaker 71 MCC-262-0D1 and declutches 46MOV-1018 and manually shuts 46MOV-1018

12. Ensure shut the following:

46MOV-1018
46MOV-1028 STANDARD Reviews "NOTE" pertaining to lockout matrix.

EVALUATOR CUE: When asked, inform the candidate that the lockout matrix is activated.

Opens circuit breaker 71 MCC-262-0D1 EVALUATOR CUE: Inform candidate that the breaker for 46MOV-1018 has been opened by another operator.
Declutches 46MOV-1018
Manually shuts 46MOV-1018 by tuming the handwheel CWo EVALUTOR CUE: When declutch mechanism pulled downward and handwheel turned CW, the handwheel turns several rotations, then hits a hard stop.

Ensure shut the following valves:

46MOV-1018, ESW System "8" Injection Valve 46MOV-1028, ESW System "8" Test Valve EVALUATOR CUE: 46MOV-1028 is closed EVALUATOR: Terminate the task at this point.

-7 of 8 EVALUATION I COMMENT. SAT I UNSAT CRITICAL STEP SAT I UNSAT CRITICAL STEP SAT I UNSAT SAT I UNSAT

HANDOUT

The plant has sustained a loss of off-site power.
The A and C EDG's have failed to start.
Upon initiation of the 8 and D EDG's, the "8" ESW System failed due to a fault in the supply breaker to the "8" ESW purrlp.

The Shift Manager has directed you to supply cooling water to EDG's 8 and D from the Fire Protection System per OP-22, Section G.25" -8 of 8

JAMES A.FITZPATRleK NUCLEAFfpOWER PLA.N'f lOI-12;01NRC EXAMINATION SCENARIO 2 TITLE: LOI-12-01 NRC EXAMINATION SCENARIO 2 SCENARIO NUMBER: SCENARIO #2 PATH: STAND ALONE CANDIDATES CRS ATC BOP LOI 12-01 NRC Examination Scenario 2 Page 1 of 25

I RECORD OF CHANGES SOURCE OF BRIE.F DESCRIPTION OF . >: t*. DATE HANGE CHANGE INITIATOR REVIEWED 10/2011 New New Scenario D. Kelly LOI 12-01 NRC Examination Scenario 2 Page 2 of 25

A. TITLE: LOI-12-01 NRC EXAMINATION SCENARIO 2 B. SCENARIO SETUP:

1. Initial Protected IC 45

2. Special Instructions:

a. Plant at 75 % CTP

b. Control Rod Sequence Exchange.

c. Three Rods to be moved to 48

d. Marked up copy of OP-65, Power Reduction Section G.4 complete up to and including G.4.6, then go to Section G.5, Power Ascension G.5.1 thru G.5.15 "circled" open.

e. Rx Engineering Pull Sheet with Start and Final positions using Continuous Withdrawal.

3. Preset Conditions:

a. Preset, RD13 for 30-15, 30-23, 22-23, 26-27, 34-19, 38-35, 42-15, 46-11

b. Preset, DG01:C EDG C fails to start

c. Preset, DG06: A EDG A slow start

d. Preset{ SLO1A&B SLC pumps trip

e. Preset{ RP01 A, B, RPS Auto and Manual Failure

f. Preset, RP09 ARI fails

g. TRIGGER 1{ M:RD07: 42-19 Rod Drift In

h. TRIGGER 2, M:RM01 :29 17RIS-452A fails downscale

i. TRIGGER 3, OS ED ZDI11 HONC05 10300-10500 Brkr Trip J. TRIGGER 4, M:MS02:A Steam leak in Containment

k. TRIGGER 20, R:RP09 RPS A Alt EPA Brkr reset

4. Consumable Forms and Procedures:

ST-23B
Reactivity Maneuvering sheets LOI 12-01 NRC Examination Scenario 2 Page 3 of 25

C. SCENARIO

SUMMARY

The scenario will begin with the plant operating at 75% Power. A Control Rod Sequence Exchange is in progress. The Crew will begin restoring Control Rods to position 48 and perform Rod Coupling checks lAW ST-23B. When the third Control Rod is withdrawn to 48, it will unexpectedly drift in. AOP-27 (Control Rod Drift) will be entered, Rx power will be lowered and Tech Spec 3.1.3 will be addressed. Once the Rod Drift issue is complete, one Reactor Building Exhaust Ventilation Radiation Monitor 'A' fails downscale. The SRO will consult ODCM 3.1 (Gaseous Effluent Monitors) and TS 3.3.6.2 (Secondary Containment Isolation Instrumentation). When actions for the failed RB Exhaust Rad Monitor failure have been addressed, the10500 Bus de energizes. AOP-18 (Loss of 10500 Bus) will be entered. The Crew will recognize that EDG lA' has started "slow" and EDG 'C' failed to automatically start. Additionally, AOP-59 will be entered due to loss of RPS IA'. The Crew will restore RPS lA' from its Alternate Power Supply. Following the 10500 Bus transient, a small leak occurs in the Drywell. AOP-39 (Loss of Coolant) will be entered. A vent on the Torus may be attempted to mitigate the Torus pressure rise. However, oryweII pressure will slowly approach the Benchmark scram value set by the SRO and a manual scram will be inserted. The leak will result in Torus Spray to be ordered. The Scram is unsuccessful at inserting Control Rods (High Power ATWS). EOP-2, EOP-3 and EOP-4 will be entered. The ATWS is complicated in the fact that Standby Liquid Control (SLC) will not remain running and injecting. RPV level will be intentionally lowered by Terminating and Preventing injection except for SLC, RCIC and CRD. When the order to pull RPS fuses has been given, most Control Rods will insert. This will result in Rx Power being less than 2.5% however; the Crew will remain in EOP-3 and continue to manually insert Control Rods via CRD and\\or manual scrams. Rx power is less than 2.5%, RPV level is in assigned band and Control Rod insertion is in progress or completed. LOI 12-01 NRC Examination Scenario 2 Page 4 of 25

Shift Turnover The Plant is operating at 75% due to a Control Rod Sequence Exchange. Shift activities are to continue restoring Control Rods to the new Rod Pattern, then return the Plant to Full Power iaw RAP*7.3.16. The next Control Rod to be withdrawn is 42-35. Withdrawal Control Rods and perform Rod Coupling checks lAW OP-26 \\ ST*23B. LOI 12*01 NRC Examination Scenario 2 Page 5 of 25

Critical Tasks/Standards Critical Task #1: Given the Plant in a failure to Scram condition, inhibit the Automatic Depressurization System (ADS) iaw EOP-3. Critical Task #2: Given the Plant in a failure to Scram condition, terminate and prevent all injection into the RPV with the exception of SLC, RCIC and CRD iaw EOP-3. LOI 12-01 NRC Examination Scenario 2 Page 6 of 25

EVENT NO.

1.

Rod Sequence Exchange. (Rod Coupling Check).

2.

Rod Drift In.

3.

RB Exh Vent Rad Monitor failure

4.

Loss 10500 Bus.

5.

Small leak in Drywell.

6.

Hi PwrATWS.

7.

SLC failure.

8.

RPS fuses \\ RM CS. D. TERMINATION CUES: EVENT SEQUENCE (Normal: ATC \\ SRO) (Component: ATC \\ SRO) (Reactivity: BOP, SRO) (TS: SRO) (ODCM: SRO) (Component: All) (TS: SRO) (Component: BOP \\ SRO) (Major: All) (Component: ATC \\ SRO) (Component: ATC \\ SRO) Rx power is less than 2.5%, RPV level is in assigned band and Control Rod insertion is in progress. LOI 12-01 NRC Examination Scenario 2 Page 7 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/ST ANDARD COMMENTS/EVAlUA TION

Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All SAT / UNSAT I NA allow no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch SRO SAT I UNSAT I NA
Perform Crew Brief
Direct ATC to perform control rod pattern adjustment.
Provides Reactivity monitoring oversight ATC SAT I UNSAT I NA
Obtain OP-26 ST -23B Section 8.4
Ensure ROD SEL PWR switch is in ON Ensure control rod to be moved is selected by depressing rod select pushbutton on ROD SEL matrix Rod 42-35
Verify the following:
Select pushbutton is brightly backlit
Control rod indicating light is on (light with coordinates on FULL CORE DISPLAY)

LOI 12-01 NRC Examination Scenario 2 -8 I

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONSIST ANDARD COMMENTS/EVALUA TION SAT / UNSAT / NA ATC

ROD OUT PERM light is on (continued)
Perform the following:
Continuous withdrawal as follows:
Place and hold ROD EMERG IN NOTCH OVERRIDE control switch in OVERRIDE
Place and hold ROD MOVEMENT CNTRL switch to OUT NOTCH.
Verify Four Rod display indicator displays outward rod motion.
Verify Four Rod display indicator displays 48
Verify red FULL OUT light is on at FULL CORE DISPLAY
Verify ROD SETTLE light is off.
IF control rod is withdrawn to position 48, THEN ensure control rod coupling integrity test is completed per ST-23B.

ATC SAT / UNSAT / NA (coupling check)

Ensure Control Rod is withdrawn to position 48 and performs coupling integrity tested as follows:
Place and hold ROD EMERG IN NOTCH OVERRIDE control switch in OVERRIDE.
Place and hold the ROD MOVEMENT CNTRL control switch in OUT NOTCH.

LOI 12-01 NRC Examination Scenario 2 -9

-~~~-~ -~~ INSTRUCTOR ACTIVITY Po ;ITION. Al C (CI uJling check) Icc n :inued) ACTIVATE TRIGGER 1 Al C Rod 42-19 Drift In Note: The Malf is to be activated after 00 and before 48. SR o LOI 12-01 NRC Examination Scenario 2 OPERATOR ACTIONS/ST ANDARD

Verify the following for the selected control rod:
Four rod display indicates 48.
Red FULL OUT light is on at FULL CORE DISPLAY.
Verify annunciator 09-5-2-4 ROD OVERTRAVEL is clear.
Release the following control switches:
ROD MOVEMENT CNTRL
ROD EMERG IN NOTCH OVERRIDE
Document results of coupling integrity test on.
Performs this activity for Rod: 10-19
When Rod 42-19 is at 48
Recognize \\ report Rod Drift Alarm (09-5-2-03)
Identify 42-19 drifting in
Report Annunciator 09-5-1-60 (CRD Temp Hi Alarm)
Acknowledge report
Enter AOP-27 (Control Rod Drift)
Direct A TC and BOP to perform AOP-27 actions COMMENTS/EVALUATION SAT I UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA

-10

INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT / UNSAT / NA

Monitor for THI
Dispatch NPO to investigate HCU 42-19 SRO Assigns benchmark scram to A TC if more than 1 rod drifts BOP SAT / UNSAT I NA
Rapidly lower reactor power until either:
Rx power at least 25 % below pre-transient value
Core Flow is approx 55% (42.4 Mlbs\\hr)
Rotates RWR M\\A station small knobs simultaneously ATC SAT I UNSAT INA
Fully insert control rod using Rod Emergency In Notch Override
Note: may have drifted to 00 by itself depending on timing of Crew actions Booth Operator:

BOP SAT I UNSAT / NA when directed to disarm

Demand official 3D Monicore case HCU, delete Drift Malf report HCU is disarmed
Direct NPO to electrically and hydraulically disarm HCU 42-19 when SRO directs it.

LOI 12-01 NRC Examination Scenario 2 -11

INSTRUCTOR ACTIVITY POSITION SRO ACTIVATE TRIGGER 2 RB Exh Vent Rad Monitor 'A' fails downscale BOP SRO LOI 12-01 NRC Examination Scenario 2 OPERA TOR ACTIONS/ST ANDARD

Declare Rod 42-19 inoperable
Tech Spec 3.1.3.C
Direct HCU 42-19 disarmed
Exit AOP-27
Inform Station Management
Report Annunciator 09-3-2-19, refers to ARP
Report RB Exh Vent Rad Mon 'A' 17RM-452A downscale
Confirms downscale on Panel 09-12
Declare RB Exh Vent Rad Monitor (17RM-452A) inoperable
Refer to ODCM 3.1 Gaseous Effluent Monitors (verify 'B' operable)
Refer to TS 3.3.6.2 Secondary Containment Isolation Instrumentation (isolate RB Vent and place SBGT in service w\\in 24 hrs.
Inform Station Management

-12 COMMENTS/EVALUA TION SAT I UNSAT INA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT INA

INSTRUCTOR ACTIVITY ACTIVATE TRIGGER 3 Loss 105:)0 Bus Booth Op Irator if dispatc led to investigate Breaker t p, report Protective Relay fault \\ trip on Breake r 10514 Booth Op erator: Restore R BC temp when directed Booth Op Irator: if dispatc led to investigate status of ={PS MG set, report physical d amage to MG set. MG set c Innot be restarted POSITION All SRO BOP ATC OPERA TOR ACTtONS/ST ANDARD

Recognize \\ report loss of 10500 bus
09-8-2-8 Bus 10300-10500 Tie Bkr 10514 Trip
Enter AOP-18 (Loss of 10500 Bus)
Enter AOP-69 (Loss of CRD)
Report EOG 'A' "slow" start
Report EDG 'C' did not start
Secure OW Fans that auto started (68FN-2D and 4A)
Dispatch NPO to restore RBC temp to normal
Report % Scram RPS I A'
09-5-1-3 RPS A Auto Scram
Report Y2 PCIS Group 1 isolation
09-5-1-55 (PCIS Sys A Group 1 Isoll COMMENTS/EVALUA TION SAT I UNSAT INA SAT I UNSAT I NA I

SAT I UNSAT I NA I SAT I UNSAT INA LOI 12-01 NRC Examination Scenario 2 -13 I

INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD SRO

Enter AOP-59 (Loss of RPS 'A')

,-----~~~ BOP

Verifies SBGT train'A' running
Verifies RB Ventilation train' A' isolation
Isolates 'B' train by depressing Isol. pushbutton
Verifies RWCU isolation {OP-28 Section G.2, closes 12MOV-18 and 69.

-~~~~-~~ ~-~ ~-~ Role Play: BOP As NPO when dispatched to

Re-energize RPS 'A' iaw AOP-59 as follows:

reset EPAs, wait 5 minutes then Insert Remote

Obtain OP-18 Section D Trigger 20 (RP09) close Ensure Alternate Power Source is available (EPA's need to be reset first)
Place the RPS A PWR SOURCE SEL switch to TRANS at Panel 09-16

-~ ~~~-~~ ATC

Reset half-scram as follows:
Place Rx Scram Reset switch to Group 2 & 3, then to Group 1 & 4, spring return to Norm
Verify RPS 'A' Scram Groups 1,2,3,4 lights are on

~~-~~ ~~~- ~-~~ LOI 12-01 NRC Examination Scenario 2 14 COMMENTS/EVALUATION SAT / UNSAT I NA SAT I UNSAT I NA I SAT I UNSAT INA I SAT I UNSAT I NA

INSTRUCTOR ACTIVHY POSITION BOP SRO ACTIVATE TRIGGER 4 Loss of Coolant in Drywell Ali LOI 12-01 NRC Examination Scenario 2 OPERA TOR ACTJONS/ST ANDARD

Ensure closed valves listed on Attachment 1
Reset containment isolation logic as follows:
Ensure control switch for each of the following valves is in Close:
02-2AOV-39 and 40
Place 20AOV-83 control switch in Close
Place 20AOV-95 control switch in Close
Rotate both PCIS Valve Reset switches to Reset, spring return to Norm
16A-S32 and 1 6A-S33
Restore RB Ventilation
Refer to Tech Spec 3.8.1 Condition D.
ST-9R performed within 1 hour
Inform Station Management
Recognize \\ report DW pressure rise
Recognize rise in DW Floor Drain rate

-15 COMMENTS/EVALUATJON SAT / UNSAT / NA SAT I UNSAT I NA SAT I UNSAT / NA I

INSTRUCTOR ACTIVITY POSITION SRO ATC ,~~~~~~ LOI 12-01 NRC Examination Scenario 2 OPERA TOR ACTIONS/STANDARD

Enter AOP-39 (Loss of Coolant)
Ensure Control Room and Reiay Room Ventilation are isolated per Section G of OP-55B within 30 minutes.
Ensure TSC filtered ventilation is operating per Section 0 of OP-59B within 60 minutes.
Set benchmark value (2.3 psig) for Manual Scram
May direct CRAM rods inserted (RWR flow was lowered earlier)
Insert CRAM rods if directed Report OW pressure at Benchmark value (09-5-1-34 OW Press Alarm Hi)
Insert Manual Scram
Report Manual Scram pushbuttons failed
Place Mode Switch to Shutdown
Report Mode Switch fails to scram the Rx
Initiate ARI
Enter AOP-1
Report all Control Rods failed to insert

-16 COMMENTS/EVALUA TION SAT I UNSAT I NA SAT I UNSAT I NA

INSTRUCTOR ACTIVITY POSITION SRO Critical Task #1 Critical Task #1 Standard: LOI 12-01 NRC Examination Scenario 2 OPERATOR ACTIONSIST ANDARD

Acknowledge Scram failure and Control Rods fail to insert
Enter EOP-2, exit EOP-2, Enter EOP-3
Direct A TC to perform Power Leg of EOP-3
Direct lowering RPV water level below 110 inches by terminating and preventing all injection except SLC, RCIC and CRD. Level band: 80-100 inches (EP-5)
Authorizes SLC injection and EP-3 execution
Direct injection from Core Spray and RHR prevented (EP-5)
Direct RPV pressure stabilized below 1080 psig with SRVs
Direct ADS Overridden
Direct MSIV low level isolation bypassed {EP-21
Direct Initiations \\ Isolations verified Given the Plant in a failure to Scram condition, inhibit the Automatic Depressurization System (ADS) iaw EOP-3.

Both ADS Override switches placed in Override 17 COMMENTS/EVALUATION SAT / UNSAT / NA Pass / Fail

INSTRUCTOR ACTIVITY POSITION ATC Booth Operator: BOP When directed to install MSIV low water level jumpers, run MSIVLEVELcae ~~~~ ~~------~ LOI 12-01 NRC Examination Scenario 2 ORIlZRATOR ACTIONS/STANDARD

Executes Power Leg of EOP-3 as follows:
Reduces RWR flow to minimum
Trips both RWR pumps
Overrides ADS (both switches to Override)
Attempts SLC injection, reports both trains failed to inject
Executes EP-3 (Backup Control Rod Insertion)
RPV pressure stabilization < 1080 psig with SRVs
Override of MSIV low level isolation per EP-2 to NPO
Termination I prevention RHR / Core Spray injection per EP-5 as follows:

RHR:

Place 1 OMOV-27 A (B) Auto Bypass switch 10A-S23A in Bypass
Verify white light is on
Ensure closed 1 OMOV-27 A (B)
Stop RHR Pumps A,B,C,D at SRO discretion (may leave running)

-18 COMMENTS/EVALUATION SAT / UNSAT / NA SAT I UNSAT / NA SAT! UNSAT / NA

INSTRUCTOR ACTIVITY POSITION BOP (continued) ,~~~ ~ ~ ~ ~~~-~~~~ LOI 12-01 NRC Examination Scenario 2 OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION Core Spray: Place 14MOV-11 A (B) Auto Bypass switch 14A-S16A in Bypass

Verify white light is on
Ensure close 14MOV-11 A (B)
Ensure CS Pumps A, B stopped
Monitors Torus water temperature for approach to BIIT and HCTL Control of RPV water level: Initially lowers RPV level to

< 110", Controls level band between 80 to 100", Injects thru 34FCV-137, may augment with 34MOV-100A\\B

Terminates and prevents injection as follows:

FW:

Ensure Flow Control 06-84A (B) in manual
Lower Flow Control 06-84A (B) to minimum Ensure open Min Flow Valve 34FCV-135A (B)
Ensure closed Discharge Valve 34MOV-100A (B)
Ensure Startup Valve 34FCV-137 in manual
Ensure closed Startup Valve 34FCV-137 HPCI:
Depress Turb Trip 23A-S19

-19

INSTRUCTOR ACTIVITY POSITION Booth Operator All modify coolant leak severity to 10% when Terminate and Prevent actions are complete SRO SRO OPERA TOR ACTIONS/ST ANDARD Recognizes/reports EOP-4 entry conditions: Drywell pressure

Recognizes and enters EOP-4 and carries out actions in parallel paths as plant priorities and personnel availability permit
Monitors APRM power, the BIIT curve and if required, determines level must be lowered for power control if necessary, directs second termination and prevention of all injection except CRD, RCIC and SLC per EP-5
Directs shift personnel to monitor for ANY of the following:
APRM downscales
RPV level at 0"
SRVs remain closed and pressure not rising
Monitors margin to HCTL
Uses EOP-3 override to direct reduction of RPV pressure to maintain margin to HCTL.

COMMENTS/EVALUATION SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT I NA LOI 12-01 NRC Examination Scenario 2 -20

INSTRUCTOR ACTIVITY POSITION BOP Booth Operator: when RPV level is 80-100 inches and controlled \\ stable, if directed, pull RPS fuses by running SCRAM FUSEOUT.cae ATC ATC OPERA TOR ACTIONS/STANDARD

Reduces RPV pressure with SRV operation as directed to maintain margin to HCTL
Note: if RPV level is controlled and MSIV jumpers are installed this will not be applicable
Report majority of Control Rods inserted (5 Rods still out)
Rx power < 2.5%
Continue Rod insertion with RMCS and\\or manual scrams
EP-3 Section 5.7
RWM bypassed
Closes 03CRD-56
CRD controller to Manual
Rod Movement switch to IN
Report Turbine trip
Report all Control Rods full in caMMENTS/EVALUAnON SAT / UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA LOI 12-01 NRC Examination Scenario 2

-21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUA TION SRO

Directs SLC to be secured
Exit EOP-3
Enter EOP-2
Direct RPV level band 177-222.5 inches with Condensate
Direct Torus Spray BOP
Secures SLC by placing switch to center position
Establish RPV level of 177-222.5 inches with Condensate SRO
Address Primary Containment Control (EOP-4)
Direct Torus Spray SAT I UNSAT I NA SAT I UNSAT I NA LOt 12-01 NRC Examination Scenario 2

-22

INSTRUCTOR ACTIVITY POSITION. ATC EAL OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION SAT I UNSAT I NA

Spray the Torus as following:
Verify torus pressure is GREATER THAN 2.7 psig.
Place SPRAY CNTRL 1 OA-S 17B switch to MANUAL, spring return to normal.
Verify white SPRAY PERM 10A-DS-67B light is on.
Ensure available RHR pumps in RHR loop B are running:
RHR PMP 10P-3B
RHR PMP 10P-3D
NOTE: 10MOV-3B may be throttled when 10MOV-39B has dual position indication.
Open RHR TEST TORUS ClG & SPRAY 10MOV-39B
Throttle TORUS SPRAY INBD VlV 10MOV-38B to establish desired torus spray flow rate.
WHEN RHR Loop B flow is GREATER THAN 1500 gpm, ensure closed MIN FLOW VLV IOMOV-16B.
Throttle RHR TEST & TORUS CLG 1 OMOV-34B to divert excess flow to the torus to maintain> 6,500 gpm RHR loop B flow with one RHR pump operating or > 13,000 gpm RHR loop B flow with two RHR pumps operating.
Establish RHRSW flow and temperature control.

SS2.1 SAT I UNSAT I NA Termination Criteria: Rx power is less than 2.5%, RPV level is in assigned band and Control Rod insertion is in progress or completed. LOI 12-01 NRC Examination Scenario 2 -23

ATTACHMENT 1 Shift Turnover The Plant is operating at 75% due to a Control Rod Sequence Exchange. Shift activities are to continue restoring Control Rods to the new Rod Pattern, then return the Plant to Full Power iaw RAP-7.3.16. The next Control Rod to be withdrawn is 42-35. Withdrawal Control Rods and perform Rod Coupling checks lAW OP-26 \\ ST-23B. LOI 12-01 NRC Examination Scenario 2 -24

Initial Step Action Rod From Notch To Notch Method Notes SM Approval 1 Raise Power by rod withdrawal 42 - 35 00 48 Continuous 2 Complete Coupling Check ST-23B 3 Raise Power by rod withdrawal 10 - 19 00 48 Continuous 4 Complete Coupling Check ST-23B 5 Raise Power by rod withdrawal 42 - 19 00 48 Continuous 6 Complete Coupling Check ST-23B LOI 12-01 NRC Examination Scenario 2 -25

Re:tl.-tie.d A'5.:5c.,uuLv-c.,o

2- 'h P'\\*')o....L E)(~

,JAMt;S A. FITZPATRICK NUCLEAR POWER PLANT LOI-12-01 NRC EXAMINATION SCENARIO 3 TITLE: LOI-12-01 NRC EXAMINATION SCENARIO 3 SCENARIO NUMBER: SCENARIO #3 PATH: STAND ALONE CANDIDATES CRS ATC BOP LOI 12-01 NRC Examination Scenario 3 Page 1 of 24

RECORD OF CHANGES SOURCE OF BRIEF DESCR.IPTIONOF I DATe CHANGE CHANGE INITIATOR REVIEWED 12/2011 New New Scenario D. Kelly LOI 12-01 NRC Examination Scenario 3 Page 2 of 24

A. TITLE: LOI-12-01 NRC EXAMINATION SCENARIO 3 B. SCENARIO SETUP:

1. Initial Protected IC 46

2. Special Instructions:

a. Plant at 68% CTP

b. CRD pump 'B' out of service with Red tag hanging

c. RHR Loop' A' out of service with Red tags hanging

d. ADS Valve 'D' inoperable with Red tag hanging

3. Preset Conditions: need to "setup" Event Trigger to dmf RH04A:B

a. TRIGGER 3, ED43:A, LHH Line 3 Fault-TRUE

b. Preset l RP01 :A, RPS Auto scram failure-TRUE

c. TRIGGER 5, ED44, Loss 115KV Sys-TRUE

d. Preset l HP01 1 HPCI Fail to Auto Start-TRUE

e. TRIGGER 6, HP02, HPCI Turbine Trip-TRUE

f. TRIGGER 71 RR15:A, Coolant Leak Inside Containment-5%

g.. Preset, RP09, ARI Fails to Actuate-TRUE

h. Preset, RP12:A\\B & RP13, PCIS GP1 Inboard\\Outboard & Isolation Failure-TRUE

i.

TRIGGER 2, AD06:H, Rx Press Relief Valve H Inadvertent Opens

j.

Preset l RH 14, LPCI fails to auto initiate

k. Preset, SW04:A\\C, RHRSW pumps A & B trip I.

TRIGGER 4, FW19:B\\C 1 Condensate Pump Band C trip

m. Preset, AD03 & 4 &7:D, SRV D inop

n. Preset, TC11, Main Turbine fails to auto trip 0.. Preset, RD06:B, CRD Pump B trip p.. TRIGGER 8, ED18A, 10500 fault

q. Preset, CS02B, Core Spray valve 1 2B fails to auto open

r.

Preset, RH04A:A, LPCI valve 25A fails closed

s. TRIGGER 20, AD02H, SRV H Fuse Pull-OUT

t. TRIGGER 1, AN932:01 Core Spray Header B Pipe Break Detector-ON

u. Preset, OL RD ZL03BS3B(1), CRD Feedpump-Green Light-OFF

v. Preset, OS RP ZDI5AS3A\\B, Reactor Scram A\\B Pushbuttons -NORMAL

w. Preset, OL SW ZL01 OAS20A(C)(1} RHRSW Pump A(C) Green Light-OFF

x. Preset, OL AD ZL0271 D(1) 'D'SRV Green Light-OFF

y. Preset, OL RH ZL01 OP2A(1) RHR Keepfull pump Green Light-OFF

z. Preset, OS RH ZDI1 OAS4A(C) Torus Suction Valve-CLOSED aa. Preset, RHZL01 OAS3A(1), C(1}' RHR Pump A and C Green light OFF bb.Preset, SWZL01 OAS49, 50A, SW Cross-tie Green OFF cc. Preset, RHZDI1 OAS16A lVIin Flow CLOSED dd.Preset, S16A Min Flow Byp OFF ee. Preset, S8A(1) LPCI Inbd Valve OFF

4. Consumable Forms and Procedures:

Reactor Engineer Instructions OP-65 open and circle \\ slashed up to and including Step F.2.5. OP-65 open and circle open Step F.2.6. LOI 12-01 NRC Examination Scenario 3 Page 3 of 24

C. SCENARIO

SUMMARY

The scenario will begin with the Plant shutting down from 68% CRD Pump 'B' out of service and ADS valve '0' inoperable. Also, RHR Loop 'A' is out of service due to an issue with the suction strainer identified by System Engineer (Day 7 of a 7 day LCO). Shift activity is to lower power lAW OP-65 to less than 65% with Control Rods, remove a Condensate (Condensate Booster) Pump and Circulating Water Pump from service. Once the Circulating Water Pump is secured, the Core Spray Leak Detection alarm is received. The SRO will consult Tech Specs and declare Core Spray Loop 'B' inoperable After the Core Spray Tech Spec LCO is addressed, a Safety Relief Valve (SRV) inadvertently opens. The Crew will enter AOP-36. Torus Cooling placed in service. EOP-4 may be entered on Torus Water Temperature depending on execution timeliness of Crew actions. When the fuses for the open SRV are pulled, the SRV will close. Tech Specs will be consulted and Station Management informed of the transient. Once the Plant is stable, the 115KV Line 3 will de-energize. AOP-72 (115KV Grid Loss, Instability or Degradation) will be entered. Communication with Power Control reveals that the "Low Voltage Post Contingency Alarm" voltage is < 112KV. This requires the SRO to declare both 115KV lines inoperable and enter TS 3.8.1 (AC Sources-Operating). Additionally, TS 3.5.1 (ECCS Operating) will have to be entered due to Core Spray Loop 'B' being inoperable. After the SRO has addressed the 115KV issue, Condensate Pump B trips. This will cause RPV level to lower and iaw AOP-41 a manual scram should be inserted. When the ATC depresses the Manual Scram pushbuttons, RPS fails to operate. All Rods will insert if \\ when the ATC rotates the Mode Switch to Shutdown. The Main Turbine fails to automatically trip following the scram and a manual Turbine Trip should be inserted. When RPV level restoration begins, Line 4 de-energizes resulting in a loss 01all offsite power. The loss of Line 4 along with the previous loss of Line 3 results In a complete loss of non vital AC power. With no Circulating Water Pumps running, the Crew is required to manually close the MSIVs. The Emergency Diesel Generators will start and power the "vital" busses. RPV Level control will be complicated by HPCI failing to auto start (manual start is successful however, once started, HPCI will trip). A coolant leak in Containment will occur due to the scram transient. With limited high pressure injection, RPV level will lower. The Crew will ultimately transition to the Alternate RPV Level Control leg of EOP-2. The Crew will make the determination that RPV level cannot be maintained greater that "Top of Active Fuel" (TAF) and prior to (-) 19 inches the Crew will Emergency Depressurize the RPV. When the ED is directed, only 5 ADS SRVs can be opened due to the previous issue with SRV '0' and 'H'. The Crew will open additional SRVs to complete the ED. RPV pressure will eventually lower enough to allow low pressure ECCS pumps (LPCI \\ CS) to inject and raise RPV level to a band of 177-222.5 inches however, ECCS operation is challenged. A loss of the 10500 bus occurs. This renders one RHR pump and one Core Spray pump unavailable. Additionally, the LPCI Mode of RHR fails to automatically initiate (manual operation is successful) and the remaining Core Spray Loop's injection valve fails to automatically open (manual opening is successful). The Scenario will be terminated when the Reactor is depressurized and RPV level is above 0" and rising. LOI 12-01 NRC Examination Scenario 3 Page 4 of 24

Shift Turnover The Plant is shutting down from 68%. CRD Pump 'B' is danger tagged out of service. ADS Valve '0' is inoperable due to incorrect parts installed during last RFO. The valve will not open electrically and is danger tagged shut. RHR Loop 'A' is danger tagged out of service (Day 7 of a 7 day LCO). After assuming Shift, continue lowering Rx power to < 65% with Control Rods using Reactor Engineering maneuvering sheets. Secure one Condensate and Condensate Booster Pump and one Circulating Water Pump. Wait for further Rx Engineering instructions. LOI 12-01 NRC Examination Scenario 3 Page 5 of 24

Critical Tasks/Standards Critical Task #1: Given the Plant in a failure of RPS to automatically shutdown the Rx, the Crew will take actions to manually scram the Rx. Critical Task #2: Given the Plant in a condition with the Rx shutdown, Rx pressure greater than the shutoff head of low pressure systems and at least one injection source available, the Crew will initiate an Emergency Depressurization prior to RPV level reaching (-) 19 inches.

Critical Task #3 Given the Plant in a condition with the Rx shutdown, reactor pressure less than the shutoff head of low pressure systems and at least one injection source available, the Crew will inject into the RPV until level is greater than 0 inches (TAF).

LOI 12-01 I\\IRC Examination Scenario 3 Page 6 of 24

EVENT NO. EVENT SEQUENCE

1.

Lower Rx power with Control Rods.

2.

Remove Condensate \\ Circ Water pumps.

3.

Core Spray Leak Detection break.

4.

SBV opens then closes.

5.

Loss Line 3.

6.

Condensate Pump B trip.

7.

RPS failure. Mode Switch ok.

8.

Failure of Main Turbine auto trip.

9.

Loss Line 4 (LOOP).

10.

Loss of Coolant.

11.

HPCI fail to auto start. Trips after manual start.

12.

Limited injection sources. Emergency Depressurization.

13.

Loss 10500 Bus.

14.

LPCI B fails to auto initiate.

15.

Core Spray inj vlv fails to auto open. D. TERMINATION CUES: (Reactivity: ATC \\ SRO) (Normal: BOP \\ SRO) (TS: SRO) (Component: BOP \\ SRO) (TS: SRO) (TS: SRO) (Major: All) (Component: ATC \\ SRO) (Component: ATC) (Major: All) (Major: All) (Component: BOP \\ SRO) (Major: All) (Component: BOP \\ SRO) (Component: BOP \\ SRO) (Component: BOP \\ SRO)

1. Reactor is depressurized and RPV level is above 0 inches and rising.

LOI 12-01 NRC Examination Scenario 3 Page 7 of 24

INSTRUCTOR ACTIVITY POSITION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1) After the shift turnover, allow no more than five minutes for panel walkdown All SRO ATC LOI 12-01 NRC Examination Scenario 3 OPERATOR ACTIONS/STANDARD

Walkdown the control panels and assume the watch
Direct Rx power lowered < 65% using Control Rods.
Using Rx Eng instructions, selects the following Control Rods and fully insert them using ROD MOVEMENT CNTRL "Rod In" position
Monitors Nuclear Instrumentation and 4 Rod Display
26-27 (4S-00)
1S-35 (OS-OO) 34-35 (OS-OO) 34-19 (OS-OO)
1S-19 (OS-OO)
10-27 (OS-OO)
26-43 (OS-OO)
42-27 (OS-OO)
26-11 (OS-OO)

-S COMMENTS/EVALUATION SAT I UNSAT / NA SAT I UNSAT / NA SAT I UNSAT I NA

INSTRUCTOR ACTIVITY POSITION All SRO Role Play: BOP When directed to reduce Chlorine Injection pump stroke, report action performed. (no action by Booth Operator necessary) Hydrogen injection is being adjusted as necessary. LOI 12-01 NRC Examination Scenario 3 OPERATOR ACTIONS/STANDARD Report Rx power < 65% (approximately 61.5%) Direct Condensate Booster \\ Condensate Pump 'C' removed from service lAW OP-3 Section F.1 Then directs Circulating Water Pump 'C' removed from service lAW OP-4 Section F.7 Condensate Booster \\ Condensate Pum~ Obtain OP-3 Section F.1 Notify Radwaste of Condensate lineup change Check Cond Demin dP and flow Places and holds Condensate Booster Pump IC' control switch in STOP, wait for system stabilization, return switch to Normal

Verifies Green light on, Red light off Places and holds Condensate Pump 'CI control switch in STOP, wait for system stabilization, return switch to Normal Verifies Green light on, Red light off Circulating Water Pump
Obtain OP-4 Section F.7 Place Circ Water Pump 36P-1 C to Stop
Verify closed Circ Water Pump Discharge Valve 36MOV 100C (Green on, Red off)

-9 COMMENTS/EVALUA TION SAT! UNSAT I NA SAT I UNSAT I NA SAT I UNSAT ! NA

INSTRUCTOR ACTIVITY POSITION ACTIVATE TRIGGER 1 Core Spray Header '8' Pipe 8reak Role Play: All when contacted as I&C \\ NPO, wait 5 minutes and report Core Spray '8' Leak detector dP pegged high (positive) and alarm is valid. 14DPIS-438 SRO ACTIVATE TRIGGER 2 SRV 'H' inadvertently opens 80P ATC LOI 12-01 NRC Examination Scenario 3 OPERA TOR ACTIONS/STANDARD

Recognize \\ report Annunciator 09-3-2-1 Core Spray Header '8' Pipe 8reak Detector alarm
Refer to ARP, dispatch I&C \\ NPO
Run 3D case
Consult TRM 3.3.H (monitor once every 12 hrs)
Declare Core Spray Loop '8' inoperable (TS 3.5.1.A, 7 day LCO) and with RHR A inoperable (TS 3.5.1.H - enter LCO 3.0.3 immediately)
Inform Station Management
Report Annunciator 09-4-1-16 SRV LEAKING
Report Annunciator 09-4-2-6 SRV SONIC MON ALARM
Using Acoustic Monitor determine SRV 'H' open
Confirms SRV is open by panel 09-5 indications

-10 COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA I I SAT / UNSAT / NA

INSTRUCTOR ACTIVITY POSITION SRO -~~~~~ Role Play: BOP When Candidate contacts NPO, coordinate with Candidate and insert TRIGGER 20, Remote AD02H (OUT). ATC ~----- LOI 12-01 NRC Examination Scenario 3 OPERA TOR ACTIONS/STANDARD Acknowledge report

Enter AOP-36 Review TS 3.5.1.E (ECCS Operating)
3.6.2.4.A
May place vent on Torus depending on timeliness of actions.

Executes AOP-36 as follows: Cycles control switch for SRV 'H' open and close Reports SRV still open Contact NPO and coordinate pulling fuses. The following fuses will be pulled: F41 (F12H) F30 (F11 H) F19 (F4H)

F9 (F3H)

Reports SRV 'H' closes Monitor \\ report Power, Pressure, Level parameters Confirms SRV is shut per panel 09-5 indications -11 COMMENTS/EVALUA TION SAT I UNSAT / NA SAT / UNSAT / NA SAT I UNSAT I NA

ACTIVITY POSITION BOP OPERATOR ACTIONSlSTANDARD COMMENTS/EVALUATION I SAT I UNSAT I NA Places RHR in Torus Cooling as follows: Ensure at least one of the following RHR pumps is running: 10P-3B, D Open RHR Test Torus Clg & Spray 10MOV-39B Throttle RHR Test & Clg 10MOV-34B to establish desired flow When RHR Loop B is greater than 1500 gpm, ensure closed Min Flow Valve 10MOV-16B. Establish RHRSW flow and temp control as follows: Verify one of the following alarms is clear: 09-4-3-4 (RHRSW A or B Discharge Line Not Full) or EPIC-D-135 (10LS-l05B) Start the following RHRSW pump(s): 1 OP-l B, D Throttle RHRSW Disch Valve From HXB 1 OMOV-89B to establish 2500 to 4000 gpm Start second RHRSW pump if desired Throttle RHRSW Disch Valve From HXB 1 OMOV-89B to establish 2500 to 4000 gpm per RHRSW pump Close HXB Bypass Valve 10MOV-66B Control containment heat removal rate by using one or more of the following methods: Throttle valves Start or stop pumps Shutdown loop LOI 12-01 NRC Examination Scenario 3 -12

INSTRUCTOR ACTIVITY POSITION ACTIVATE TRIGGER 3 loss line 3 (115KV) All SRO Role Play: BOP When Power Control contacted, report restoration of line 3 is unknown. The Low Voltage Post Contingency Alarm voltage is 110.5KV SRO OPERA TOR ACTIONS/ST ANDARD

Recognize \\ report loss line 3
Annunciator 09-8-6-10 lHH-FITZ 115KV LINE 3 BKR 10022 TRIP
Enter AOP-72
Monitor Electric Plant parameters \\ lineup
Report reclosure scheme status
Call National Grid (Power Contro\\) and Nine Mile Point
Relay info concerning low Voltage Post Contingency Alarm voltage is 11 0.5KV to SRO Acknowledge low Volt Post Contingency value of 110.5KV Declare both l15KV lines inoperable Enter TS 3.8.l.A and C (AC Sources Operating)

Recognize ST-9R is required to be performed within 1 hr. COMMENTS/EVAlUATION SAT I UNSAT I NA SAT I UNSAT / NA SAT I UNSAT / NA SAT / UNSAT I NA lOI 12-01 NRC Examination Scenario 3

INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/ST ANDARD COMMENTS/EVALUA TION Critical Task #1 Given the Plant with a failure of the manual scram Pass \\ Fail pushbuttons to shutdown the Rx, the Crew will use alternate methods to scram the Rx. ~ Critical Task #1 standard Rx Mode Switch rotated to Shutdown position prior to the loss of adequate core cooling. ACTIVATE TRIGGER 4 Condensate Pump B trip and Condensate C pump will trip if started All SAT / UNSAT I NA

Recognize \\ report trip of Condensate Pump B
Recognize \\ report trip of Condensate Pump C when started.

ATC SAT / UNSAT / NA

Report RPV level lowering SRO SAT / UNSAT / NA
Enter AOP-41, Feedwater Malfunction
Recognize Condensate parameters not with capacity of required Feedwater
Direct Manual Scram LOI 12-01 NRC Examination Scenario 3

-14

c----

INSTRUCTOR. ACTIVITY POSITION ATC SRO OPERA TOR ACTIONS/STANDARD COMMENTSfEVAlUATION SAT I UNSAT I NA

Depress Manual Scram Pushbuttons, report failure to scram
Rotate Mode Switch to Shutdown
Report all Control Rods full in
Carryout AOP-1 actions:
Fully Insert all SRM's and IRM's
Verify reactor power is rapidly lowering
APRM downscales
Inserted IRMs and SRMs trending down
Verify all rods in
Ensure SDIV Vent and Drain valves closed
When APRM's downscale:
Ensure Main Turbine tripped, recognize still connected to Grid, manually trips Main Turbine
Verify 4KV loads transfer to reserve power SAT I UNSAT f NA
Enter EOP-2
Confirm all Control Rods in
Direct RPV water level band 177-222.5 inches LOI 12-01 NRC Examination Scenario 3

-15

I INSTRUCTOR ACTIVITY POSITION BOP Activate Trigger 5 Loss of Offsite Power (when RPV level is 140 inch and rising) All ATC BOP OPERATOR ACTIONS/STANDARD

Monitor RPV water level response
Prepare for manual Feedwater control by observing Narrow Range level meter response
Place both Feedwater MA stations in manual and lower RFP speed when RPV water level "bottoms out"
Rotates MA station control knob clockwise and begin raising RPV water level to 177-222.5 inches
Recognize \\ report loss of all 115KV offsite power
Recognize \\ report loss of all non-vital AC power
Recognize \\ report loss of all Circulating Water
Manually close MSIVs
Recognize \\ report loss of RBC, TBS, Service Water and Instrument Air
Recognize \\ report complete loss of Condensate and Feedwater.

COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA LOI 12-01 NRC Examination Scenario 3 -16

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUA TION SRO SAT I UNSAT INA Direct RPV level control with HPCI and RCIC. Direct RPV pressure control 800-1000 psig with SRVs. Activate Trigger 6 BOP SAT I UNSAT INA HPCI trip Monitor RCIC start \\ status (after manually started) Recognize \\ report HPCI failed to auto start Manually start HPCI Report HPCI running Report HPCI tripped Controls RPV pressure in the assigned band. Activate Trigger 7 Coolant leak in Drywell (when RPV level at 160 inch) All SAT I UNSAT INA Recognize rising drywell pressure SRO SAT I UNSAT INA

Directs AOP-39 actions LOI 12-01 NRC Examination Scenario 3

-17

INSTRUCTOR ACTIVITY POSITION BOP Modify RR 15 to 10% when ALL DW pressure is 2.7#. SRO BOP OPERATOR ACTIONS/ST ANDARD

Direct Relay Room, Control Room and TSC Ventilation aligned per AOP-39.
Direct H202 monitors restored
Recognize/report drywell pressure > 2.7psig
Enters EOP-4 and renters EOP-2
Directs Torus Spray initiated before 15 psig
Monitors for 1 5 psig in Torus
Direct drywell Spray
Spray the Torus as following:
Verify torus pressure is GREATER THAN 2.7 psig.
Place SPRAY CNTRL 1 OA-S 17B switch to MANUAL.
Verify white SPRAY PERM 10A-DS-67B light is on.
Ensure available RHR pumps in RHR loop B are running:
RHR PMP 10P-3B \\ RHR PMP 10P-3D
NOTE: 10MOV-3B may be throttled when 10MOV-39B has dual position indication.
Open RHR TEST TORUS CLG & SPRAY 10MOV-39B
Throttle TORUS SPRAY INBD VLV 10MOV-38B to establish desired torus spray flow rate.

COMMENTSfEVALUA TlON SAT I UNSAT I NA SAT I UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA LOI 12-01 NRC Examination Scenario 3 -18

INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION.

WHEN RHR Loop B flow is GREATER THAN 1500 gpm, ensure closed MIN FLOW VLV IOMOV-16B.

BOP continued

Throttle RHR TEST & TORUS CLG 1 OMOV-34B to divert excess flow to the torus to maintain > 6,500 gpm RHR Loop B flow with one RHR pump operating or > 13,000 gpm RHR Loop B flow with two RHR pumps operating.
Establish RHRSW flow and temperature control.

when Drywell Spray BOP SAT / UNSAT / NA initiated, Modify RR1 5 to Spray the Drywell 30% Ramp 5 min.

Ensure the following components are tripped:
02-2P-1A,B
68FN-2 & 4 A,B,C,D Verify parameters are within DWSIL
Place Spray Control switch 1 OA-S 17A \\B to Manual, spring return to Normal
Verify white Spray Permissive 1 OA-DS67 A \\B light on
Ensure available RHR pumps are running
Open DW Spray Outboard Valve 10MOV-26A\\B
Throttle DW Spray Inboard Valve 1 OMOV -31 A \\B to establish desired drywell spray flow rate
When RHR loop flow is > 1500 gpm, ensure closed Min Flow Valve 10MOV-16A\\B

--~ LOI 12-01 NRC Examination Scenario 3 -19

~~~~ INSTRUCTOR* ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUA TION SRO SAT / UNSAT I NA

Evaluate high pressure injection resources Determine that only high pressure Group 1 injection sources are CRD and RCIC
Exercise IF \\ THEN override in EOP-2 Level Leg
Direct SLC to be injected

~-~ BOP SAT / UNSAT / NA

Injects SLC as directed SRO SAT / UNSAT / NA
Maintains awareness of RPV water level trend
Recognizes RPV level cannot be restored and maintained

> T AF (0 inches)

Transitions to Alternate Level leg of EOP-2
Directs ADS to be overridden
Monitors for RPV level of 0 inches

-~ -~ ATC \\ BOP SAT / UNSAT / NA Overrides ADS by placing both switches to Override Report \\ trend RPV water level ~- -~ ~- LOI 12-01 NRC Examination Scenario 3 -20

INSTRUCTOR ACTIVITY POSITION Critical Task #2 Critical Task #2 standard SRO r--~~~~ Activate TRIGGER 8 ATC when 7 SRVs are opened Loss of 10500 Bus SRO LOI 12-01 NRC Examination Scenario 3 OPERATOR ACTIONS/STANDARD Given the Plant in a condition with the Rx shutdown, Rx pressure greater than the shutoff head of low pressure systems and at least one injection source available, the Crew will initiate an Emergency Depressurization prior to RPV level reaching H 19 inches. All operable ADS SRVs (5) open and two additional non-ADS SRVopen

Determines RPV level is less than 0 inches.
Directs Emergency Depressurization prior to RPV level reaching (-) 19 inches

-~~~~~~

Attempts to open 7 ADS SRVs
Inform SRO that only 5 ADS SRVs can be opened due to SRV '0' and 'H' being inoperable
Open additional SRVs to obtain 7 SRVs open
Reports loss of 10500 Bus
Acknowledge loss of 10500 Bus
Assess low pressure ECCS sources
Prepares Crew for RPV injection once RPV pressure is less than shutoff head of Low Pressure ECCS systems
Discusses strategy for RPV level control

-21 COMMENTS/EVALUA TION Pass \\ Fail SAT I UNSAT ! NA SAT! UNSAT I NA SAT I UNSAT / NA

INSTRUCTOR ACTIVITY POSITION Critical Task #3 Critical Task #3 standard NOTE: Either RHR Loop B or Core Spray Loop B have to be used to satisfy CT #3 BOP BOP I OPERA TOR ACTIONS/ST ANDARD COMMENTS/EVALUA TION Given the Plant in a condition with the Rx shutdown, reactor Pass \\ Fail pressure less than the shutoff head of low pressure systems and at least one injection source available, the Crew will inject into the RPV until level is greater than 0 inches (T AF). RPV injection commenced once RPV pressure is less than the shutoff head of LPCI and \\ or Core Spray and RPV level raised above 0 inches (TAF) SAT I UNSAT / NA

Recognize \\ report Core Spray injection valve fails to open
Manual open Core Spray injection valve 14MOV-12B SAT I UNSAT I NA
Recognize \\ report LPCI B failed to auto initiate (2.7# or 59.5 inch)
Start LPCI pump B
Monitor injection valve 258 for auto open when RPV pressure less than open setpoint
Recognize 25B failed to auto open
Manually open 25B valve LOI 12-01 NRC Examination Scenario 3

-22

I INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD* COMMENTS/EVALUATION BOP SAT / UNSAT / NA

. When HPVpressure is less than the shutoff head of LPCI \\

Core Spray, RPV level restoration is as follows:

Throttles Core Spray injection valve
Secures RHR pump
Report RPV level in band SRO SAT / UNSAT INA
Once RPV level is rising, direct re-establishing Torus and Drywell sprays SAT / UNSAT I NA EALs FA 1.1 or SA2.1 meets the Alert Classification TERMINATE THE SCENARIO The Scenario be terminated when the Reactor is depressurized and RPV level is 0 inches and rising.

LOI 12-01 NRC Examination Scenario 3 -23

ATTACHMENT 1 Shift Turnover The Plant is shutting down from 68%. CRO Pump 'B' is danger tagged out of service. ADS Valve '0' is inoperable due to incorrect parts installed during last RFO. The valve will not open electrically and is danger tagged shut. RHR Loop 'A' is danger tagged out of service (Day 7 of a 7 day LCO). After assuming Shift, continue lowering Rx power to < 65% with Control Rods using Reactor Engineering maneuvering sheets. Secure one Condensate and Condensate Booster Pump and one Circulating Water Pump. Wait for further Rx Engineering instructions. LOI 12-01 NRC Examination Scenario 3 -24}}

v t e Letter Sequence Draft Other
TAC:U01843, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML12116A225, ML12116A242, ML12116A252, ML12116A259, ML12116A275, ML12116A290, ML122710023, ML122710026, ML122750357, ML122750389, ML12356A250
MONTHYEAR2012-04-03 [Table View]

ML12072A353

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Title:

3.9 REFERENCES

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3.9 REFERENCES

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4.1 REFERENCES

Title:

3.7 REFERENCES

Title:

Description:

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REFERENCES:

SUMMARY

SUMMARY

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