ML12072A353
| 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: |
| References | |
| TAC U01843 | |
| Download: ML12072A353 (186) | |
Text
{{#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):
I JPM RESULTS*: 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 L-=:J Simulate r------i f---------j Simulator 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
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
PERFORMANCE: 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. START TIME:
- 1. Procedure Step: Verify correct loading of Control Cell 38-35.
Standard Operator determines that the following bundles are in the correct location and orientation:
- JLV675
- JLV682
- JLK804
- JLK817 Cue Notes Results I SAT D UNSAT D
- 2. Procedure Step: Determine the INCORRECT loading of Control Cell 14-35.
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.
I~ i Results SAT Critical Step UNSATCI 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: Verify the correct loading of Control Cell 14-35.
I Standard Operator determines two Control Cell 14-35 bundles are the correct bundles
. and in the correct orientation:
- JLK805
- JLK812 Cue i
Notes i
- SAT i I I I I I I I I
*4. Procedure Step: Determine the INCORRECT loading of Control Cell 38-15.
Standard Operator determines one Control Cell 38-15 bundle is in the correct orientation but is the INCORRECT bundle
- JLV668 i Cue i Notes The correct bundle should be JLV698.
I Results SAT D Critical Step UNSATI I I
- 5. Procedure Step: Verify the correct loading of Control Cell 38-15.
Standard Operator determines three Control Cell 38-15 bundles are the correct
. bundles and in the correct orientation:
- JLV674
- JLK807
- JLK820 I
Cue I Notes I I Results SAT D UNSAT 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. Procedure Step: Determine the INCORRECT loading of Control Cell 14-15.
Standard Operator determines that the two single blade guides are in the wrong I orientation. 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 Results I SAT D Critical Step UNSATC i
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. NRC 2012 REVISION NO. 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
- 2 FUEL BUNDLE JLV682 SFP 26-CC-2 CORE 37-36 a!ll TOI02112 031() eo 3 DOUBLE BLADE GUIDE N/A CORE 39-36 37- SFP 26-EE-2 a!ll 10/02/12 0320 eo 34 26-DD-l
<1 FUEL BlJNDLE JLK804 SFP 26-DD-2 CORE 37-34 a!ll 10102112 0330 eo 5 FUEL BUNDLE JLKS!7 SFP 26-EE-2 CORE 39-36 a!ll 10102/12 0340 (>.:V 6 FUEL BUNDLE JLV678 SFP 26-FF-2 CORE 15-34 a!ll 1()102112 0350 eo 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-\ 9 FUEL BUNDLE JLK805 SFP 26-X-3 CORE 13-34 a!ll 10/02/12 0420 C:v l(l FUEL BUNDLE JLK812 SFP 26-Y-3 CORE \5-36 a!ll W102/12 043lJ C:v II FUEL BUNDLE JLV698 SFP 26-Z-3 CORE 39-14 a!ll W/lJ2112 0440 e:v 12 FUEL BUNDLE JLV674 srp 26-AA-3 CORE 37-16 a!ll 10102/12 0450 C:v 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 Description Seri~1 No. I From To Performed Daterrime Y<:rified No. of Malt:rial Equipment ID ICA Coord, ICA Coord, by Executed by (5) (5) (6) (7) (8) (9) (11) (12) (13) 13 DOUBLE BLADE GUIDE N/A CORE 39-11 37 I SFP 26-CC-2 a9J 1O/()2/12 ()S()() e!lJ 14 26-8B-I 14 FUEL BUNDLE JLK807 SFP 26-88-1 CORE 37-14 a9J 1()/()2/12 ()SI() e!lJ 15 FUEL BUNDLE JLK820 SFP 26-CC-I CORE 39-16 a9J to/021t2 0520 e:o 16 SINGLE BLADE GUIDE N/A SFP 25-FF-II CORE 13-16 a9J 10102/12 ()53() e:o 17 SINGLE BLADE GUIDE N/A SFP 25-FF-I CORE 15-14 a9J 10102/12 ()S4() e!lJ 18 I FUEL BUNDLE JLynO CORE 13-14 SFP 35-N-7 a9J 10/02/12 0550 e:t> 19 FUEL BUNDLE JLyn5 CORE 15-16 SFP 35-N-6 a9J 10102/12 0600 e!lJ 20 N/A 21 N/A 22 N/A ~ N/A N/A NOTES/COMMENTS Line #: Line #: Line#: ____ (14) SNM Records Updated by: _ _ _ _ _ _ _ _ _ __ Lines Thru Date (15) Verified by: _ _ _ _ _ _ _ _ _ _ _ _ Lines Thru Date ENTERGY NUCLEAR Page90fl3 E-DOC TITLE: E-DOC NO. REVISION NO. I NRC 2012 Admin-l 0 I
HANDOUT S N 0 0
..... U T
H H
\VEST CONTROL CELL 38-35 I ENTERGY NUCLEAR Page 10 of 13 I E-DOC TITLE: E-DOCNO. REVISION NO.
NRC 2012 Admin-l I 0
HANDOUT EAST N S 0 0 R U I rI-H H
'"VEST CONTROL CELL 14-35 ENTERGY NUCLEAR Pa~e II of 13 I E-DOC TITLE: E-DOCNO. REVISION NO.
NRC 2012 Admin-l I o
HANDOUT E,.L\ST N S o 0
'Ii. 1J l T II H 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
HANDOUT EAST N s o o f H U T H
\VEST CONTROL CELL 14-15 IE-DOC TITLE:
ENTERGY NUCLEAR Page 13 of 13 E-DOC NO. REVISION NO. NRC 2012 Admin-1 I 0
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 RESULTS*: 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 ENTERGY NUCLEAR Page 1 of7 I 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
~E-DOC TITLE: ENTERGY NUCLEAR Page 3 of7 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: i *1. Procedure Step: Determine required staffing and required action/time limit. 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. Procedure Step: Determine required staffing and required action/time limit.
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. Procedure Step: Determine required staffing and required action/time limit.
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. Procedure Step: Determine that other positions meet staffing requirements. i Standard After reviewing Tech Specs and Operations Procedure, candidate does NOT identify other positions as being understaffed.
Cue i Notes Results SAT D UNSAT 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 I I E-DOC TITLE: E-DOC NO. REVISION NO. . 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 RESULTS*: 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 l _ _ _- - - - ' Classroom (Admin) Prepared: Date: Reviewed: Date: Approved: Date: ENTERGY Nl;CLEAR Pa~e 1 of8 I I E-DOC TITLE: ST-26K Recirc Loop Startup Differential E-DOCNO. REVISION NO. [ Temperature SRO Review 2012 NRC Admin 3 o
REVISION LOG Revision Number: 0 I Date Originated: J Pages Affected:
Description:
I 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 0 i
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". I 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 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 I Notes 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 I D
- 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 LE__ 5 Notes Re_s_ul_ts--,I_S_A_T_ _ Procedure Step: i 1 __ I _ _ _c_r_'t,_ca_I_S_te_p_ _ _U_N_SA_T_I_ _ _ Documents in the remarks section problems found 1 _ _ _- - ' Standard i Indicates in remarks section:
- 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 I Notes I Results SAT D Critical Step UNSAT\ J
*7 !
Procedure Step: 11.2.5 IF Level 1 acceptance criteria is not satisfied, THEN I immediately notify Operations Manager or alternate. Record name of person notified. I I i I Standard Notifies Operations Manger or alternate. Cue When candidate indicates a call to the Operations Manager, tell the I candidate Chris Adner has been notified. , Notes i I I Results SAT D Critical Step UNSATD 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 i Step 11.1.3 requires a CR if level 1 acceptance criteria was not met. Results SAT D UNSAT D 9 Procedure Step: . 11.2.7 Sign and record date and time. Management SRO Date/Time Standard Candidate will sign, date and time the surveillance test i
~
I Cue ~ R_es_ul_ts~I_SA_T ~ Notes ___ _ _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 1 No (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
REVISION LOG Revision Number: 0
- Date Originated: I 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. Procedure Step: Ensure reactor power level is not raised during drywell entries. i i
Standard Determines that withdrawing control rods for the rod shuffle is not permitted I 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. Procedure Step: The following are required for drywell entries while primary containment is in effect: Specific RWP per AP-07.01.
Standard Determines that a specific RWP is required. Cue Notes AP-12.02,7.8 Results i SAT Critical Step UNSATD I I I D
*3. Procedure Step: . The following are required for drywell entries while primary containment is in effect: ALARA Review per RP-ALARA-01.01. i Standard I 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: The drywell atmosphere is between 19.5 and 23,5% oxygen following an initial entry and verification Standard Determines oxygen concentration is to low for entry OR that a confined space entry permit is required.
Cue Notes AP-12.02,8.2.1.8 Results SAT Critical Step UNSATD I D
*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 Critical Step UNSATD I I
*6. I Procedure Step: 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. Standard 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. i Notes Tech Specs 3.6.1.2.8 Results SAT Critical Step UNSATD D 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:
OPERA TlONS 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 JQb Suuervisor: J Ih': h.Il!lli't"d j)U'l"r I r'!i.It;II!:d I~~~~~ Ac!ual Dose: Actual Huurs: 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::: .,.,: ."
l'u,k.,':': :, .:: : '." .... I::: :.,:.
~
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
,,' "., .': ....: .........:, i i * : .. ,' ,:,: Rl!quirlilllt!'nlii .' .... , .", .' '., ."": '.,:' I::' , .', ,.,.
Requirement Croups I Requirement Descriptiolls NiA I Page 1 of 2
HANDOUT c,f~:l,ii~ ENTERGY NUCLEAR OPERATIONS. INC. .~~Entergy. JAMES A. FITZPATRICK NUCLEAR POWER PLANT
,~
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 RESULTS*: 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
REVISION LOG Revision Number: 0 Date Originated: Pages Affected:
Description:
i i ENTERGY NUCLEAR Page 2 of 12 E-DOC TITLE: Determine Protective Action E-DOC NO. REVISION NO .
- Recommendations and Complete Event Notification 2012 NRC
, Form I Admin 5 0 I
TASK
Title:
Task Number K&ASYSTEM: K&ARATING: Detennine Protective Action 4.4 2.4.38 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 I ENTERGY NUCLEAR Pa2C 3 of12 I I E-DOC TITLE: Determine Protective Action E-DOC NO. REVISION NO. I
- Recommendations and Complete Event Notification 2012 NRC Form Admin 5 o
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 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.
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. Procedure Step: Applicants review the handout sheet and ask any questions regarding the initial conditions or initiatin cues.
Standard A Iicants review initial conditions and initiatin cues. Cue Notes Results SAT D UNSAT 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. Procedure Step: Obtains Notification Form (Attachment 1 ofEAP-l.1, Offsite Notifications)
Standard Applicant completes Notification Form Item #2, circling "A, Actual Emergencv". Cue Notes Results SAT UNSAT D D
*4. Procedure Step: Record the correct event classification.
i Standard i Applicant completes Notification Form Item #3, circling liD. General Emergency". I I Cue i Notes I i Results SAT Critical Step UNSATD I 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. Procedure Step: Determine release rate using EAP-4 and EAP-4.1 (Step 4.1.2 or Attachment 2 from mr/hr
- 2.54 factor) I Standard Applicant determines release rate is 29,718 Ci/sec.
Cue Notes Critical Step UNSATO I , I 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: ! Determine and record the protective active recommendations using EAP-4 !
Attachment 1, Tables 4.1.1 and 4.1.2. Standard Applicant completes Notification Form Item #6, circling "B. EVACUATE and IMPLEMENT the KI PLAN fqr the following ERPAs and All remaining ERPAs MONITOR the EMERGENCY ALERT SYSTEM" and by circling ERPAs # 1,2,3,4,7,9,26,27. Cue Notes Examiner Note: These are 2 mile radius and 5 mile downwind ERPAs. Results SAT Critical Step UNSATO I I ENTERGY NCCLEAR Pae:e 7 of 12 E-DOC TITLE: Determine Protective Action E-DOCNO. REVISION NO. I Recommendations and Complete Event Notification 2012 NRC Form Admin 5 0
*9. appropriate EAL number and brief description.
Critical Step UNSAT
*10 Proc;dure Step: I Record reactor status. . " _ _ _ _-<
Standard
- Applicant completes Notification Form Item #8, circling "B. Shutdown" and date time of 02/28111 at 0342.
-----------~I------*
i L- Cue* l----N-o-=-te=s'----t-I--**~~=-**_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-_-:_-_-_-_-~~~~~~~~~~~~~: Results i SAT D Critical Step UNSAT D ~ ___L-____________ _________________________________ ~
*11 Procedure Step: Record appropriate wind speed I
Standard Records wind speed by filling in Notification Form Item #9 as "A. hl Miles/Hour at elevation £Q.Q Feet (Elevated), . I Cue i Notes Results SAT D Critical Step 12 1 Procedure Step: . Record meteorological stability class as determined using provided data per EAP-42. 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 Critical Step UNSATD D Terminating Cue: This completes this JPM. ENTERGY NUCLEAR Page 9 of 12 E-DOC TITLE: Determine Protective Action E-DOCNO. REVISION NO. Recommendations and Complete Event Notification 2012 NRC Form 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 IRecommendations and Complete Event Notification Form 2012 NRC Admin 5 o
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 I E-DOC NO. 2012 NRC Admin 5
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 STANDARD EVALUATION I COMMENT
- 9. Verify the following system Observes and verifies component operation during the SAT I UNSAT response: shutdown of 'B' SBGT.
Component Status White light AIR HTR 01-125E-5B is on. 01-125E-5B White light on Red light for AIR HTR 01-125E-5B is off 01-125E-5B Red light off Train B CLG VLV 01-125MOV-100B is open 01-125MOV-100B Red light on, green light off FN DISCH 01-125MOV-15B is ----- closed 01-125MOV-15B Green light on, red light off TRAIN B FN 01-125FN-1B is stopped. 01-125FN-1 B Green light on, red light off
- 10. IF SGT Train 'A' is in service EVALUATOR: Candidate verifies that SGT lA' is in service SAT I UNSAT THEN verify flow rate on SGT and f10wrate on 01-125FI-1 06A is FLOW 01-125FI-106A.
- RB isolated: approximately 5600-5800 scfm.
- RB un-isolated approx .
6000 scfm.
- RB isolated approx .
5600-5800 scfm.
- 11. Reports to the CRS that SGT Reports to the CRS that SGT 'B' is shutdown and the task is SAT I UNSAT
'B' is shutdown complete.
EVALUATOR: Terminate the task at this point.
-6 of 7
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
~2~1=20~1~0~10~0~9________ JAF QUAL STANDARD NUMBER:
JAFTASKNUMBER:
-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 2012 NRC S-2 TASK TITLE: (F) Reset an RPS Scram with Scram Valve Failure to Close APPL. TO JPM NUMBER Current Update: By: Date Int Outstanding Items o Technical Review o Additional Information Questions and Answers Validation Procedural Change Required [SJ None Comments: Current Update: By: Date Int. Previous Revision Date:
-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 EVALUATION I COMMENT
- 1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SAT/UNSAT 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. SAT IUNSAT perform the task. EVALUATOR; Provide candidate a copy of section F.1
- 3. IF ARI actuated, THEN reset The candidate observes that ARI is reset. SAT I UNSAT ARI.
- 4. Verify annunciator 09-5-1-33 The candidate observes that the annunciator window for SAT/UNSAT 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 CRITICAL STEP keylock switch in BYPASS. BYPASS. (09-5-1-11 Alarm) 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 2012 NRC S-3 TASK TITLE: HPCI Manual Startup for RPV Pressure Control & Manual Trip Required (Alternate Path). APPL. TO ..IPM NUMBER Current Update: By: Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments: Current Update: By: Date 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 Attachment 7
- 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 STANDARD EVALUATION I COMMENT
- 5. IF amber RX HI LVL SIGNAL The candidate reviews step and recognizes that it is NA. SAT IUNSAT 23A-DS65 light is on at panel 09 3, THEN reset high water level trip as follows:
- 6. Verify open CST SUCT VL V The candidate verifies 23MOV-17 is open at 09-3 panel SAT I UNSAT 23MOV-17. with red light on, green light off.
- 7. Verify closed the following valves: The candidate verifies the Torus Suction Valves closed at SAT I UNSAT panel 09-3 with red light off, green light on.
- OUTBD TORUS SUCT VLV 23MOV-57
- INBD TORUS SUCT VLV 23MOV-58
*8. Ensure open OUTBD STM SUPP The candidate opens 23MOV-16, at panel 09-3. CRITICAL STEP VLV 23MOV-16. SAT I UNSAT
- 9. Verify open OUTBD STM SUPP The candidate verifies 23MOV-16 is open at 09-3 panel VLV 23MOV-16 with red light on, green light off
*10. Throttle open TEST VLV TO CST The candidate throttles open 23MOV-21 approximately 10 CRITICAL STEP 23MOV-21 approximately 10 secs, at panel 09-3. SAT I UNSAT secs.
-5 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
- 11. Verify throttled open TEST VLV The candidate verifies 23MOV-21 is throttled at 09-3 panel SAT I UNSAT TO CST 23MOV-21. with red light on, green light on.
*12. Open HPCI & RCIC TEST VLV The candidate opens 23MOV-24, at panel 09-3. CRITICAL STEP TO CST 23MOV-24. SAT I UNSAT
- 13. Verify open HPCI & RCIC TEST The candidate verifies 23MOV-24 is open at 09-3 panel SAT I UNSAT VL V TO CST 23MOV-24. with red light on, green light off.
- 14. Ensure GLAND SEAL CNDSR The candidate starts 23P-140, at panel 09-3, with red light SAT I UNSAT BLOWER 23P-140 is running. on, green light off.
*15. Ensure open TURB STM SUPP The candidate opens 23MOV-14, at panel 09-3. CRITICAL STEP VLV 23MOV-14. SAT IUNSAT
- 16. Verify open TURB STM SUPP The candidate verifies 23MOV-14 is open at 09-3 panel SAT / UNSAT VLV 23MOV-14. with red light on, green light off.
- 17. IF annunciator 09-3-3-28 HPCI The candidate will verify 09-3-3-28 HPCI TURBINE TRIP SAT / UNSAT TURBINE TRIP SOLENOID SOLENOID ENERGIZED is not in alarm ENERGIZED is in alarm, THEN depress INITIATION SIG/MAN TURBINE TRIP RESET 23A-S17 pushbutton.
-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
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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 Operating HPCI at less than 2100 speed on 23SPI-161.
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 Failure to closely monitor HPCI discharge pressure on 23PI-109.
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. VLV 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: fh ~ OPERATIONS REVIE ~~~~~~-----~------------------------------- CANDIDATE NAME: JPM Completion D Simulated ~ Performed Location: D Plant ~ 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 STANDARD EVALUATION I COMMENT
- 3. Ensure closed the following valves: Candidate closes and/or observes green closed light SAT I UNSAT on and red open light off at the following locations:
./ MSIV 29AOV-80A-D
./ MSIV 29AOV-80A-D at 09-3 and 09-4
./ MSIV 29AOV-86A-D
./ MSIV 29AOV-86A-D at 09-3 and 09-4
./ MAIN STM DRN 29MOV-74, 77, 78
./ MAIN STM DRN 29MOV-74, 77, 78 and 79 at 09-3 and 79 and 09-4
./ MAIN STM DRN VLV 29MOV
./ MAIN STM DRN VLV 29MOV-101A-D at 09-7 101A-D
./ RFPT A and B HP STOP VLV HP SVA-1 at 09-6
./ RFPT A and B HP STOP VLV HP SVA-1 and SVB-1
./ TSV-1-4 at 09-5
./ TSV-1-4
./ TO PCV 96MOV-S1 at 09-7: depresses Close PB
./ TO PCV 96MOV-S1
./ PCV BYP 96MOV-S2 at 09-7: may depress Close
./ PCV BYP 96MOV-S2
./ ***29MST-105 (SJAE MST supply 29PCV-1 07 outlet isol valve) (remote operated from East Electric Bay)
./ 29MST-105 (SJAE MST supply by tel con to NPO***
29PCV-107 outlet isol valve) (remote operated from East Electric
./ ***29MST-107 (SJAE MST supply 29PCV-107 Bay) bypass strainer outlet isol valve) (remote operated from East Electric Bay) by telcon to NPO.***
./ 29MST-107 (SJAE MST supply 29PCV-107 bypass strainer outlet
***INSTRUCTOR NOTE***
isol valve) (remote operated from Remote: MC31 TO 0 (to close 29MST-105/107) East Electric Bay) Page 5 of 9
S/RO 2012 NRC S-4 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED STEP STAi'1lDARD EVALUATION I COMMENT
*4. Open the following valves: SAT I UNSAT At panel 09-3 and 4 candidate opens 29 MOV-74 and 77.
MAIN STM DRN 29MOV-74 *CRITICAL STEP* MAIN STM DRN 29MOV-77
- 5. Verifies open the following valves: At panel 09-3 and 4 candidate verifies open 29 MOV-74 SAT I UNSAT and 77, red lights on, green lights off.
MAIN STM DRN 29MOV-74 MAIN STM DRN 29MOV-77
- 6. Jog open MAIN STM DRN 29MOV-79 At panel 09-4 candidate jogs opens 29 MOV-79 until full SAT I UNSAT until full open. open and observes red light on, green light off
*7. Open the following valves: At panel 09-3 candidate opens 29AOV-86 A-D. SAT I UNSAT MSIV 29AOV-86A *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
- 8. Verifies open the following valves: 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
*9. Open MAIN STM DRN 29MOV-78. At panel 09-4 candidate opens 29 MOV-78. SAT I UNSAT Simulator O~erator: Insert Trigger 2. *CRITICAL STEP*
- 10. Verifies open MAIN STM DRN 29MOV At panel 09-4 candidate verifies open 29 MOV-78 and SAT I UNSAT
- 78. observes red light on, green light off.
- 11. Close MAIN STM DRN 29MOV-79. EVALUATOR 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
*12. WHEN differential pressure across the 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
- 13. Verfies open the following valves: 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 T4 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: (h ~ OPERATIONS REVIE : 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 STANDARD EVALUATION I COMMENT
- 5. Ensure Clark Energy Control The candidate notifies ECC of impending transfer of bus SAT / UNSAT Center notified that 10300 Bus 10300 to Transformer T3.
will be transferred from normal EVALUATOR: If candidate inquires, inform candidate to to reserve service. call the simulator booth operator for all ECC actions. Simulator Operator: Act as ECC Dispatcher/Niagara Mohawk as necessary to simulate communications.
- 6. Station operators as follows: The candidate ensures that operators are stationed at the SAT I UNSAT LTC Controls and to operate breaker control switches.
- One to adjust Bus voltage at LTC Control
- One to operate breaker EVALUATOR: If candidate inquires, inform the candidate control switches that an operator is standing by to adjust the LTC Control as directed by the candidate.
*7. Place Bus 10300 FOR Places the Bus 10300 FOR Synch Switch in RES. CRITICAL STEP SYNCH switch in RES. SAT / UNSAT
- 8. Match voltages on Non- Observes that incoming and running voltages are matched SAT / UNSAT EMERG BKRS INCOMING on Non-Emerg Bkr 4KV Panel.
and RUNNING volt meters using LTC CONTROL switch.
-5 of 10
S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 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 without unnecessary delay, to switch to CLOSE.
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 I
-6 of 10
S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP STANDARD EVALUATION I COMMENT
- 11. I Place Bus 10300 FOR Restore 10300 Bus Controls and Indications to normal SAT/UNSAT SYNCH SW switch in OFF lineup.
and remove handle. Remove operating handle and return handle to its normal storage location. Simulator Operator: Activate Trigger 1 at this point
- 12. I Recognize Loss of Bus 10300 I Operator recognizes the loss of the 10300 bus and informs SAT/UNSAT 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.
- 13. I Performs AOP-16 immediate I Refers to Attachment 2 of AOP-16. SAT I UNSAT 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).
-7 of 10
S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP STANDARD EVALUATION I COMMENT
- 14. Verify closed L 14 L24 L34 L44 Observes red light on, green light off for breakers: SAT I UNSAT 4KV FOR BKR 10440.
- L14 600V FOR Bkr 11402
- L24 600V FOR Bkr 12402
- L34 600V FOR Bkr 13402
- L44 600V FOR Bkr 14402
*15. Cross-tie L43 with L44 as Operator performs the following: CRITICAL STEP follows: SAT I UNSAT
- Places control switch for L43 600V FOR BKR 14302
- a. Open L43 600V FOR BKR to the PULL TO LOCK position 14302 and place its control switch in PULL TO LOCK.
- Places the L43-L44 Tie Synch SW to the ON position.
- b. Close L43-L44 TIE BKR 14304.
- Places the L43-L44 TIE BKR 14304 to the CLOSE position.
*16. Cross-tie L33 with L34 as Operator performs the following: CRITICAL STEP follows: SAT I UNSAT
- Places control switch for L43 600V FOR BKR 14302
- a. Open L33 600V FOR BKR to the PULL TO LOCK position 13302 and place its control switch in PULL TO LOCK.
- Places the L33-L34 Tie Synch SW to the ON position.
- Places the L33-L34 TIE BKR 14304 to the CLOSE
- b. Close L33-L34 TIE BKR position.
13404.
-8 of 10
S/RO 2012 NRC S-5 TASK TITLE: Shift Aux Buses from T4 to Reserve Station Service STEP STANDARD EVALUATION I COMMENT
*17. Cross-tie L23 with L24 as Operator performs the following: CRITICAL STEP follows: SAT I UNSAT
- Places control switch for L43 600V FOR BKR 14302
- a. Open L23 600V FOR BKR to the PULL TO LOCK position 12302 and place its control
- Places the L23-L24 Tie Synch SW to the ON switch in PULL TO LOCK. position.
- b. Close L23-L24 TIE BKR 12404.
- Places the L23-L34 TIE BKR 14304 to the CLOSE position.
*18. Cross-tie L 13 with L 14 as Operator performs the following: CRITICAL STEP follows: SAT I UNSAT
- At panel 9-6 places RBC PMP A 15P-2A control
- a. Place RBC PMP A 15P-2A switch in PULL TO LOCK.
control switch in PULL TO LOCK.
- At panel 9-6 places RBC PMP C 15P-2C control switch in PULL TO LOCK.
- b. Place RBC PMP C 15P-2C control switch in PULL TO
- Places control switch for L43 600V FOR BKR 14302 to the PULL TO LOCK position LOCK.
- c. Open L 13 600V FOR BKR
- Places the L23-L24 Tie Synch SW to the ON 11302 and place its control position.
switch in PULL TO LOCK.
- Places the L23-L34 TIE BKR 14304 to the CLOSE position.
- d. Close L 13-U4 TIE BKR 11304.
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 EA 1.08 3.8/3.9 JAF TASK NUMBER: 2050104048 5010.501 ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: 6b~ APPROVED: ~~~~~-=~~________________
~---------------------------------
CANDIDATE NAME: JPM Completion o Simulated ~ Performed Location: o Plant ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: o Satisfactory 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 Obt am 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 . pumps are running, red light on, green light off: I ,
'II
- COND XFER PUMP A 33P-13A 'Ii I Ensure condensate transfer pumps are , CRITICAL STEP ,
- 3. running
- COND XFER PUMP B 33P-13B (starts) i' I SAT I UNSAT I I I I '
._l 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 inner isol valve) SAT I UNSAT
- 4.
- 1ORHR-257 A (RHR Loop A LPCI cond xfer NOTE: Only Step A OR step B outer isol valve) needs to be directed.
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 At panel 09-6, verifies condensate transfer pressure I i I II' Verify condensate transfer pressure II! I 5 I is GREATER THAN RPV pressure SAT I UNSAT I
' I 1
1- - I I I Ensures closed at least one of the following by taking I 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 1OMOV-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 V I closed Torus Spray Inboard 38A b Y ta k'109 the controiSWltc
' h to t h e CLOSE 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 1 OMOV-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 1 UMUV-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 STANDARD EVALUATION I COMMENT
- 1. Obtain a controlled copy of OP Obtains a controlled copy of OP-51 A. SAT I UNSAT 51A, Reactor Building Ventilation and Cooling System.
Evaluator: Provide working copy.
- 2. Reviews the correct section of the Reviews Special Procedures Section of OP-51A and selects SAT / UNSAT procedure. Section G.3, Restoration from isolation.
- 3. IF Reactor Building Ventilation Candidate remembers from initial conditions that the SAT I UNSAT isolated due to low RPV water isolations are reset OR contacts CRS/SM.
level (177 inches) or high drywell pressure (2.7 psig) THEN either reset isolation per AOP-15 OR EVALUATOR: If asked in isolations are reset, inform the ensure isolation is overridden per candidate they are. EOPs.
-4 of 9
S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP STANDARD EVALUATION I COMMENT
- 4. Ensures one below refuel floor Ensures one below refuel floor exhaust fan is running with SAT/UNSAT exhaust fan is running and red its control switch red flagged.
flagged:
- Below EI. 369" EXH FAN 66FN-12A
- Below EI. 369' EXH FAN
- Below EI. 369' EXH FAN 66FN-12B 66FN-12A Observes red light on, green light off for the running fan.
- Below EI. 369' EXH FAN 66FN-12B
- 5. Ensures the control switch for the Ensures the control switch for the shutdown below refuel SAT I UNSAT shutdown below refuel floor floor exhaust fan fan {Below EI. 369' EXH FAN 66FN-12A or exhaust fan (Below EI. 369' EXH B) is green flagged.
FAN 66FN-12A or B) is green Observes red light off, green light on. flagged.
- 6. Ensure two of the supply fans are Ensures two of the supply fans are running with their SAT I UNSAT running with switch red flagged. associated control switches are red flagged.
- Supp FN A 66FN-5A
- Supp FN A 66FN-5A
- Supp FN B 66FN-5B
- Supp FN B 66FN-5B
- Supp FN C 66FN-5C
- Supp FN C 66FN-5C Observes red lights on, green lights off for the running fans.
- 7. Ensure control switch for the Ensures shutdown supply fan (SUPP FN 66FN-5A, B, or C) SAT I UNSAT shutdown supply fan (SUPP FN switch is green flagged.
66FN-5A, B, or C) is green Observes red light off, green light on. flagged.
-5 of 9
S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP STANDARD EVALUATION I COMMENT
*8. Ensure control switches for above Ensures the control switch for one of the below fans is in CRITICAL STEP refuel floor exhaust fans (EL 369' PULL TO LOCK and the other is RED FLAGGED.
EXH FN 66FN-13A and 8) are as SAT I UNSAT follows:
- 66FN-13A RED FLAGGED
- One Fan Control Switch RED
- 66FN-13B PULL TO LOCK Flagged.
- One Fan Control Switch in PULL TO LOCK.
- 9. Verifies that one fan is running For the running fan observes red light on, green light off and SAT I UNSAT and one fan is not. for the fan in PULL TO LOCK observes red light off, green light on.
- 10. Ensure control switch for tank Ensures the control switch for the tank exhaust fan 66FN-35 SAT I UNSAT exhaust fan is red flagged. is red flagged.
- 11. Ensure one crescent supply fan is Ensure the control switch for one of the crescent supply SAT I UNSAT running with control switch red fans is red flagged and the fan is running.
flagged.
- CRESC SUPP FN 66FN-26A
- Ensures the control switch for the crescent supply fan
- CRESC SUPP FN 66FN-26B 66FN-26A is red flagged.
Observes red light on, green light off.
- 12. Ensure control switch for the Ensures the control switch for the shutdown crescent area SAT I UNSAT shutdown crescent supply fan is supply fan 66FN-26B is green flagged.
green flagged.
-6 of 9
S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP STANDARD EVALUATION I COMMENT
- 13. Verify the shutdown crescent Verifies the shutdown crescent area supply fan 66FN-26B is SAT/UNSAT supply fan is not running not running, red light off, green light on.
*14. Reset Reactor Building Ventilation Depress and Hold "Reset" push buttons concurrently or CRITICAL STEP Isolation. Depress and Hold individually until the following valves indicate open; then SAT I UNSAT "RESET' AlB pushbuttons to release the push buttons:
open: "A" Reactor Building Ventilation:
- 66AOV-100A INBD SUPP
- 66AOV-100A OPEN ISOL
- 66AOV-101A OPEN
- 66AOV-101A OUTB SUPP ISOL "B" Reactor Building Ventilation:
- 66AOV-100B INBD SUPP ISOL
- 66AOV-100B OPEN
- 66AOV-101B OUTB EXH
- 66AOV-101B OPEN ISOL
- 15. Verifies the Reactor Building Verifies 66AOV-100AlB and 66AOV-101A1B are open, SAT / UNSAT Ventilation Isolation is reset. observing red light on, green lights off.
- 16. Verify one of the following above Verifies that the above refuel floor exhaust fan 66FN-13A is SAT I UNSAT refuel floor fans is running: running, red light on, green light off.
- EL 369' EXH FAN 66FN-13A
- EL 369' EXH FAN 66FN-13B
-7 of 9
S/RO/NPO 2012 NRC S-7 TASK TITLE: Restore Reactor Building Ventilation following an Isolation STEP STANDARD EVALUATION / COMMENT
- 17. Place the control switch for the Release PULL TO LOCK and "Green" flag the switch and CRITICAL STEP shutdown above refuel floor verify red light off, green light on. SAT / UNSAT exhaust fan in "NORMAL AFTER OFF" (Green Flagged).
EVALUATOR: Previous step (#8) had the control switch in PULL TO LOCK.
- 18. Verify tank exhaust fan is running. Verifies tank exhaust fan 66FN-35 started and is running. SAT I UNSAT
- 66FN-35 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 [gJ Simulated D Performed Location: [gJ Plant D 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 Questions and Answers D Validation D Procedural Change Required cg) 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 I. SAFETY CONSIDERATIONS 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
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 27 A 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 STANDARD EVALUATION I COMMENT
- 5. Shuts the following valves: Shuts the following valves: SAT I UNSAT
'03CRD-2030 (Filter 27A Inlet Isolation)
'03CRD-2030
'03CRD-2031 (Filter 278 Inlet Isolation)
'03CRD-2031 EVALUTOR CUE: When turned CW, the handwheel turns several rotations, then hits a hard stop.
- 6. Opens drain valve on air filters. Locates the drain valve on the bottom of each filter CRITICAL STEP and OPENS both filter drain valves.
03F-27A (is a 8all Valve) SAT I UNSAT EVALUTOR CUE: When turned CCW, the petcock \ 03F-278 (is a Petcock Valve) paddle turns then hits a hard stop.
- 7. Verifies scram air header pressure Locates pressure indication 03PI-229 and verifies that SAT I UNSAT lowers. 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". 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 27 A 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.
EVALUATOR: Terminate the task at this point. 7
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: (h~ OPERATIONS REVIE APPROVED: CANDIDATE NAME: JPM Completion rg] Simulated D Performed Location: rg] Plant D 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 STANDARD EVALUATION I COMMENT
- 1. Obtain a controlled copy of Obtains a controlled copy of procedure and proceeds SAT / UNSAT procedure, EP-6. 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
- 2. Reviews prerequisites, precautions Reviews applicable portions. SAT / UNSAT and special instructions associated with the procedure.
- 3. Selects section 5.7, Venting Selects the correct section of the procedure to be SAT / UNSAT Containment. performed.
- 4. CAUTION: Reviews Caution and Attachment 1, and determines SAT / UNSAT PCPl is based upon the maximum whether containment conditions will allow venting.
pressure that primary containment vent and purge Isolation valves (AOVs EVALUATOR CUE: When candidate locates and MOVs) can be operated. PCPl indication of pressure and level, inform the candidate curve is shown on Attachment 1. that Torus Pressure is 50 psig and Torus level is 29.0 ft.
WARNINGS: Reviews Warnings: 5. While venting the primary
- Ensures Radiation Protection has been informed
----,--- SAT I UNSAT containment, radiation dose rates will regarding the potential change in radiation levels rise in the following areas: in these areas.
- Along Primary Containment vent
- Ensures any operators in the vicinity of SGT are piping in the Reactor Building. warned of the potential for rupture.
- Above underground vent piping between the Reactor Building and Stack.
- In the vicinity of the Stack.
- In the Standby Gas Treatment System room. EVALUATOR CUE: Acknowledge the Radiation While venting the Primary Protection and operator warning from the candidate.
Containment, the in-service SGT could rupture and cause a ground level release.
- 6. Ensure only one SGT is in service per Candidate either goes to, or contacts the control SAT I UNSAT OP-20. room to ensure the SGT is in service.
EVALUATOR CUE: When candidate requests feedback, acknowledge that only one SGT is in service.
- 7. CAUTION: Reviews Caution. SAT I UNSAT Failure to close 01-125MOV-11 and 01-125MOV-12 could release primary containment atmosphere to the reactor building.
- 8. Ensure each of the following valves is Contacts the control room to ensure the valves are SAT I UNSAT closed with its control switch in closed.
to-lock:
- ABOVE EL. 369' SUCT 01 EVALUATOR CUE: When candidate requests 125MOV-11 feedback regarding valves from the control room,
- BELOW EL. 369' SUCT 01 acknowledge the valves are closed and in PTL.
125MOV-12
- 9. Ensure closed the following valves: 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.
- 10. Ensure the following switches are in Contacts the control room to ensure switches are in SAT / UNSAT RESET: RESET.
- 27 SYS DIV II ISOL VLVS at panel 09-3 EVALUATOR CUE: When candidate requests
- 27 SYS DIV I ISOL VLVS at panel feedback regarding switches from the control room, 09-4 acknowledge the switches are in RESET.
11 . Ensure open the following valves: For each valve, candidate locates its red/green SAT / UNSAT
- DW/TORUS EXH TO SGT ISOL position lights and indicates it should be open.
VLV 2MOV-120 EVALUATOR CUE: When candidate inquires about
- DWITORUS EXH TO SGT ISOL light status, inform the candidate the green light is VLV 27MOV-121 off, red light is on.
- 12. NOTE: Reviews Note and selects step 5.7.6 to perform as SAT / UNSAT Steps 5.7.6 and 5.7.7 may be directed.
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 Verifies pressure is less than PCPL and level is less SAT I UNSAT the following: than 29.5 ft.
- Verify torus pressure is LESS THAN PCPL
- Verify primary containment water level is LESS THAN 29.5 feet.
EVALUATOR CUE: When candidate locates
- While venting torus, frequently indication of pressure and level, inform the candidate monitor torus pressure and that Torus Pressure is 50 psig and Torus Level is primary containment water level.
29.0 ft.
- IF primary containment water level reaches 29.5 feet while venting the torus, THEN vent drywell per Step 5.7.7.
13 cont
- Open TORUS EXH INNER BYP Candidate places TORUS EXH INNER BYP VLV SAT / UNSAT VLV 27MOV-117. 27MOV-117 control switch to the OPEN position
- EVALUATOR CUE: When candidate indicates placing CRITICAL TASK the control switch to open, inform the candidate that the green light is off, red light is on.
- Open TORUS EXH OUTER BYP Candidate places TORUS EXH OUTER BYP VLV SAT / UNSAT VLV 27MOV-1 27MOV-123 control switch to the OPEN position.
CRITICAL TASK EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.
- Ensure closed the following For each valve, candidate locates its red/green SAT / UNSAT valves: position lights and indicates it should be closed.
0 OW EXH OUTER BYP VLV 27MOV-113. 0 OW EXH INNER BYPASS VLV 27MOV-122. EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is 0 OW EXH INNER ISOL VLV on, red light is off. 27AOV-113. 0 OW EXH OUTER ISOL VLV EVALUATOR CUE: After 27MOV-117 & 123 are 27AOV-114. open, inform the candidate that the control room has called to inform the candidate that Torus Water level is 30 ft.
- 14. IF primary containment water level Candidate refers to section 5.7.7 SAT I UNSAT reaches 29.5 feet while venting the torus, THEN vent drywell per Step 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.
- 15. IF drywell will be vented, THEN Verifies pressure is less than PCPL. SAT / UNSAT perform the following:
- Verify torus pressure is BELOW 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
*
- Open OW EXH OUTER BYP VLV Candidate places OW EXH OUTER BYP VLV 27MOV SAT / UNSAT 27MOV-113 113 control switch to the OPEN position CRITICAL TASK EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.
- Open OW EXH INNER BYPASS Candidate places OW EXH INNER BYPASS VLV SAT / UNSAT
- VLV 27MOV-122. 27MOV-122 control switch to the OPEN position CRITICAL TASK EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.
- Ensure closed the following valves:
- 0 TORUS EXH INNER BYP Candidate places TORUS EXH INNER BYP VLV SAT / UNSAT VLV 27MOV-117 27MOV-117 control switch to the CLOSE position.
CRITICAL TASK EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off.
0 TORUS EXH OUTER Candidate places TORUS EXH OUTER BYP VLV SAT / UNSAT BYP VLV 27MOV-123 27MOV-123 control switch to the CLOSE position. CRITICAL TASK EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off. 0 TORUS EXH INNER For each valve, candidate locates its red/green SAT / UNSAT ISOL VlV 27AOV-117 position lights and indicates it should be closed. 0 TORUS EXH OUTER ISOL VLV 27AOV-118 EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is on, red light is off.
- 16.
- IF it becomes necessary to raise Contacts control room and requests direction on vent SAT / UNSAT vent rate, AND torus pressure is rate.
LESS THAN PCPl, THEN attempt to open the following valves: 0 OW EXH INNER ISOl VlV 27AOV-113 EVALUATOR CUE: When candidate requests 0 OW EXH OUTER ISOL VlV direction for vent rate, respond that current rate of 27AOV-114 pressure reduction is acceptable.
- 17.
- IF containment purge is not in Contacts the control room on the status of SAT I UNSAT 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.
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 2012 NRC P-3 TASK TITLE: Supplying Cooling Water to EDG's Band D from Fire Protection APPL. TO ..IPM NUMBER Current Update: By: Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments: Current Update By: Date Int Previous Revision Date:
-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 STANDARD EVALUATION I COMMENT
- 1. Obtain a controlled copy of the The candidate determines where to obtain a controlled copy SAT I UNSAT procedure OP-22. of OP-22. (Control Room, Merlin, EDG room)
EVALUATOR: Provide trainee a current copy of OP-22 G.25.
- 2. Reviews the precautions of the Reviews the precautions associated with OP-22 and notes SAT I UNSAT procedure. applicable sections.
- 3. BEFORE cross connecting safety EVALUATOR CUE: If asked, inform the candidate that SAT I UNSAT systems, review system status to the review is complete and a single failure of one system ensure failure of one system will will NOT result in common-cause failure.
not result in common-cause failure.
- 4. Verify ESW pumps not available From initial conditions, verifies that ESW pumps 46P-2A SAT I UNSAT
- 46P-2A and 46P-2B ARE NOT available.
- 46P-2B
- 5. Reviews "CAUTION" pertaining to Reviews "CAUTION" and notes reference to screenwell SAT I UNSAT fire protection pumps and forebay level.
reference to screenwell forebay level. EVALUATOR CUE: If asked for forebay level state that forebay level is normal.
-4 of 8
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 STANDARD EVALUATION I COMMENT
*9. I Cross-tie ESW and Fire Line-up the cross-tie between Fire Protection and ESW as Protection follows:
- a. Remove caps, by pushing the red detents, from the CRITICAL STEP following:
- 46ESW-2000 SAT I UNSAT
- 76FPS-2000 EVALUATOR CUE: Red detent pushed, caps rotated CCW
- b. Connect short length of hose between the following CRITICAL STEP valves: (hose located in cabinet 76CAB-1 on west wall of north emergency service water room) SAT I UNSAT
- 46 ESW-2000
- 76FPS-2000 EVALUATOR CUE: Hose connected
- c. Unlock and Open 76FPS-2000. CRITICAL STEP SAT I UNSAT EVALUATOR CUE: Using P2 Key, valve unlocked and turned CCW to hard stop
- d. Unlock and Open 46ESW-2000. CRITICAL STEP EVALUATOR CUE: Using P5 Key, valve unlocked and SAT/UNSAT turned CCW to hard stop
-6 of 8
S/RO/NPO 20042468 TASK TITLE: Supplying Cooling Water to EDG's 8 and D from Fire Protection STEP STANDARD EVALUATION I COMMENT. I
- 10. Reviews "NOTE" pertaining to the Reviews "NOTE" pertaining to lockout matrix. SAT I UNSAT ESW lockout matrix. EVALUATOR CUE: When asked, inform the candidate that the lockout matrix is activated.
*11. Opens circuit breaker
- Opens circuit breaker 71 MCC-262-0D1 CRITICAL STEP 71 MCC-262-0D1 and SAT I UNSAT declutches 46MOV-1018 and manually shuts 46MOV-1018 EVALUATOR CUE: Inform candidate that the breaker for 46MOV-1018 has been opened by another operator.
- Declutches 46MOV-1018 CRITICAL STEP
- Manually shuts 46MOV-1018 by tuming the handwheel SAT I UNSAT CWo EVALUTOR CUE: When declutch mechanism pulled downward and handwheel turned CW, the handwheel turns several rotations, then hits a hard stop.
- 12. Ensure shut the following: Ensure shut the following valves: SAT I UNSAT
- 46MOV-1018
- 46MOV-1018, ESW System "8" Injection Valve
- 46MOV-1028
- 46MOV-1028, ESW System "8" Test Valve EVALUATOR CUE: 46MOV-1028 is closed EVALUATOR: Terminate the task at this point.
-7 of 8
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
RECORD OF CHANGES
.. SOURCE OF BRIE.F DESCRIPTION OF . >: t *.
DATE HANGE CHANGE INITIATOR REVIEWED 10/2011 New New Scenario D. Kelly I 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{ SLO 1A&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. EVENT SEQUENCE
- 1. Rod Sequence Exchange. (Normal: ATC \ SRO)
(Rod Coupling Check).
- 2. Rod Drift In. (Component: ATC \ SRO)
(Reactivity: BOP, SRO) (TS: SRO)
- 3. RB Exh Vent Rad Monitor failure (ODCM: SRO)
- 4. Loss 10500 Bus. (Component: All)
(TS: SRO)
- 5. Small leak in Drywell. (Component: BOP \ SRO)
- 6. Hi PwrATWS. (Major: All)
- 7. SLC failure. (Component: ATC \ SRO)
- 8. RPS fuses \ RM CS. (Component: ATC \ SRO)
D. TERMINATION CUES: 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 I
- 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
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONSISTANDARD COMMENTS/EVALUATION 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. OPERATOR ACTIONS/ST ANDARD COMMENTS/EVALUATION Al C (CI u Jling ch eck)
- Verify the following for the selected control rod:
Icc n :inued)
- Four rod display indicates 48.
- Red FULL OUT light is on at FULL CORE DISPLAY.
SAT I UNSAT / NA
- Verify annunciator 09-5-2-4 ROD OVERTRAVEL is clear.
- Release the following control switches:
- ROD MOVEMENT CNTRL
- ROD EM ERG IN NOTCH OVERRIDE
- Document results of coupling integrity test on Attachment 2.
- Performs this activity for Rod: 10-19 ACTIVATE TRIGGER 1 Al C SAT / UNSAT / NA Rod 42-19 Drift In
- When Rod 42-19 is at 48 Note:
- Recognize \ report Rod Drift Alarm (09-5-2-03)
The Malf is to be activated after 00 and before 48.
- Identify 42-19 drifting in
- Report Annunciator 09-5-1-60 (CRD Temp Hi Alarm)
SR o SAT / UNSAT I NA
- Acknowledge report
- Enter AOP-27 (Control Rod Drift)
- Direct A TC and BOP to perform AOP-27 actions LOI 12-01 NRC Examination Scenario 2
-10
INSTRUCTOR ACTIVITY POSITION OPERATOR 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 HCU, delete Drift Malf report
- Demand official 3D Monicore case 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 OPERATOR ACTIONS/ST ANDARD COMMENTS/EVALUA TION SRO SAT I UNSAT INA
- Declare Rod 42-19 inoperable
- Tech Spec 3.1.3.C
- Direct HCU 42-19 disarmed
- Exit AOP-27
- Inform Station Management ACTIVATE TRIGGER 2 RB Exh Vent Rad Monitor
'A' fails downscale BOP SAT I UNSAT I NA
- 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 SRO SAT I UNSAT I NA
- 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.
SAT I UNSAT INA
- Inform Station Management LOI 12-01 NRC Examination Scenario 2
-12
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTtONS/ST ANDARD COMMENTS/EVALUA TION ACTIVATE TRIGGER 3 Loss 105 :)0 Bus Booth Op Irator All SAT I UNSAT INA if dispatc led to investigate
- Recognize \ report loss of 10500 bus Breaker t p, report Protective Relay fault \ trip
- 09-8-2-8 Bus 10300-10500 Tie Bkr 10514 Trip on Breake r 10514 SRO SAT I UNSAT I NA I
- Enter AOP-18 (Loss of 10500 Bus)
- Enter AOP-69 (Loss of CRD)
BOP SAT I UNSAT I NA
- Report EOG 'A' "slow" start
- Report EDG 'C' did not start Booth Op erator:
- Secure OW Fans that auto started (68FN-2D and 4A)
Restore RBC temp when
- Dispatch NPO to restore RBC temp to normal directed . I Booth Op Irator: ATC SAT I UNSAT INA if dispatc led to investigate
- Report % Scram RPS A' I status of ={PS MG set, report physical d amage to MG set.
- 09-5-1-3 RPS A Auto Scram MG set c Innot be restarted
- Report Y2 PCIS Group 1 isolation
- 09-5-1-55 (PCIS Sys A Group 1 Isoll
--_.- ---- I LOI 12-01 NRC Examination Scenario 2
-13
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO SAT / UNSAT I NA
- Enter AOP-59 (Loss of RPS 'A')
,-----~~~ BOP SAT I UNSAT I NA
- 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.
-~~~~-~~ ~-~ ~-~ I Role Play: BOP SAT I UNSAT INA 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
-~ ~~~-~~
I ATC SAT I UNSAT I NA
- 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
INSTRUCTOR ACTIVHY POSITION OPERA TOR ACTJONS/ST ANDARD COMMENTS/EVALUATJON BOP SAT / UNSAT / NA
- 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
---------------- I SRO SAT I UNSAT I NA
- Refer to Tech Spec 3.8.1 Condition D.
- ST-9R performed within 1 hour
- Inform Station Management ACTIVATE TRIGGER 4 Loss of Coolant in Drywell Ali SAT I UNSAT / NA
- Recognize \ report DW pressure rise
- Recognize rise in DW Floor Drain rate LOI 12-01 NRC Examination Scenario 2
-15
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUA TION SRO SAT I UNSAT I NA
- 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)
ATC SAT I UNSAT I NA
- 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
,~~~~~~ ---------- LOI 12-01 NRC Examination Scenario 2
-16
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONSIST ANDARD COMMENTS/EVALUATION SRO SAT / UNSAT / NA
- 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 Pass / Fail Critical Task #1 Given the Plant in a failure to Scram condition, inhibit the Automatic Depressurization System (ADS) iaw EOP-3.
Critical Task #1 Standard: Both ADS Override switches placed in Override LOI 12-01 NRC Examination Scenario 2 17
INSTRUCTOR ACTIVITY POSITION ORIlZRATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT / UNSAT / NA
- 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)
Booth Operator: BOP SAT I UNSAT / NA When directed to install MSIV low water level
- RPV pressure stabilization < 1080 psig with SRVs jumpers, run MSIVLEVELcae
- 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 1OMOV-27 A (B) Auto Bypass switch 10A-S23A in Bypass
- Verify white light is on
- Ensure closed 1OMOV-27 A (B)
SAT! UNSAT / NA
- Stop RHR Pumps A,B,C,D at SRO discretion (may leave running)
~~~~ ~~------~ LOI 12-01 NRC Examination Scenario 2
-18
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP (continued) Core Spray:
- Place 14MOV-11 A (B) Auto Bypass switch 14A-S 16A 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
,~~~ ~ ~ ~ ~~~-~~~~ LOI 12-01 NRC Examination Scenario 2
-19
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/ST ANDARD COMMENTS/EVALUATION Booth Operator All SAT / UNSAT I NA modify coolant leak severity to 10% when Terminate and
- Recognizes/reports EOP-4 entry conditions: Drywell pressure Prevent actions are complete SRO SAT / UNSAT / NA
- Recognizes and enters EOP-4 and carries out actions in parallel paths as plant priorities and personnel availability permit SRO SAT / UNSAT I NA
- 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.
LOI 12-01 NRC Examination Scenario 2
-20
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD caMMENTS/EVALUAnON BOP SAT / UNSAT I NA
- 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 Booth Operator: ATC SAT I UNSAT I NA when RPV level is 80-100 inches and controlled \
- Report majority of Control Rods inserted (5 Rods still out) stable, if directed, pull RPS fuses by running Rx power < 2.5%
SCRAM FUSEOUT .cae
- 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 ATC SAT I UNSAT I NA
- Report all Control Rods full in LOI 12-01 NRC Examination Scenario 2
-21
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUA TION SRO SAT I UNSAT I NA
- 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 SAT I UNSAT I NA
- 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 LOt 12-01 NRC Examination Scenario 2
-22
INSTRUCTOR ACTIVITY POSITION. OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT I UNSAT I NA
- Spray the Torus as following:
- Verify torus pressure is GREATER THAN 2.7 psig.
- Place SPRAY CNTRL 1OA-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 1OMOV-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.
EAL 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 Raise Power by rod 1 42 - 35 00 48 Continuous withdrawal Complete Coupling 2 ST-23B Check Raise Power by rod 3 10 - 19 00 48 Continuous withdrawal Complete Coupling 4 ST-23B Check Raise Power by rod 5 42 - 19 00 48 Continuous withdrawal Complete Coupling 6 ST-23B Check LOI 12-01 NRC Examination Scenario 2
-25
Re:tl.-ti e.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 RP01 :A, RPS Auto scram failure-TRUE l
- c. TRIGGER 5, ED44, Loss 115KV Sys-TRUE
- d. Preset HP01 HPCI Fail to Auto Start-TRUE l 1
- 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 RH 14, LPCI fails to auto initiate l
- k. Preset, SW04:A\C, RHRSW pumps A & B trip I. TRIGGER 4, FW19:B\C Condensate Pump Band C trip 1
- 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. (Reactivity: ATC \ SRO)
- 2. Remove Condensate \ Circ Water pumps. (Normal: BOP \ SRO) 3.
Core Spray Leak Detection break. (TS: SRO) 4. SBV opens then closes. (Component: BOP \ SRO) (TS: SRO) 5. Loss Line 3. (TS: SRO) 6. Condensate Pump B trip. (Major: All) 7. RPS failure. Mode Switch ok. (Component: ATC \ SRO) 8. Failure of Main Turbine auto trip. (Component: ATC) 9. Loss Line 4 (LOOP). (Major: All)
- 10. Loss of Coolant. (Major: All)
- 11. HPCI fail to auto start. (Component: BOP \ SRO)
Trips after manual start.
- 12. Limited injection sources. (Major: All)
Emergency Depressurization.
- 13. Loss 10500 Bus. (Component: BOP \ SRO)
- 14. LPCI B fails to auto initiate. (Component: BOP \ SRO)
- 15. Core Spray inj vlv fails to auto open. (Component: BOP \ SRO)
D. TERMINATION CUES:
- 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 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1) After the shift turnover, All SAT I UNSAT / NA allow no more than five minutes for panel walkdown
- Walkdown the control panels and assume the watch SRO SAT I UNSAT / NA
- Direct Rx power lowered < 65 % using Control Rods.
ATC SAT I UNSAT I NA
- 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)
LOI 12-01 NRC Examination Scenario 3
-S
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION All SAT! UNSAT I NA
- Report Rx power < 65% (approximately 61.5%)
SRO SAT I UNSAT I NA
- 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 Role Play: BOP SAT I UNSAT ! NA When directed to reduce
- Condensate Booster \ Condensate Pum~
Chlorine Injection pump stroke, report action
- Obtain OP-3 Section F.1 performed. (no action by
- Notify Radwaste of Condensate lineup change Booth Operator necessary)
- Check Cond Demin dP and flow
- Places and holds Condensate Booster Pump IC' control Hydrogen injection is being switch in STOP, wait for system stabilization, return adjusted as necessary. switch to Normal
- Verifies Green light on, Red light off
- Places and holds Condensate Pump 'C I 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)
LOI 12-01 NRC Examination Scenario 3
-9
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVATE TRIGGER 1 Core Spray Header '8' Pipe 8reak Role Play: All SAT / UNSAT / NA when contacted as I&C \
- Recognize \ report Annunciator 09-3-2-1 Core Spray NPO, wait 5 minutes and Header '8' Pipe 8reak Detector alarm report Core Spray '8' Leak detector dP pegged high
- Refer to ARP, dispatch I&C \ NPO (positive) and alarm is valid.
- Run 3D case 14DPIS-438 SRO SAT / UNSAT / NA
- 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 ACTIVATE TRIGGER 2 SRV 'H' inadvertently opens 80P SAT / UNSAT / NA
- 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 I
I ATC SAT / UNSAT / NA
- Confirms SRV is open by panel 09-5 indications LOI 12-01 NRC Examination Scenario 3
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INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/STANDARD COMMENTS/EVALUA TION SRO SAT I UNSAT / NA
- 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.
-~~~~~ Role Play: BOP SAT / UNSAT / NA
- Executes AOP-36 as follows:
When Candidate contacts
- Cycles control switch for SRV 'H' open and close NPO, coordinate with Candidate and insert
- Reports SRV still open TRIGGER 20, Remote
- Contact NPO and coordinate pulling fuses.
AD02H (OUT).
- The following fuses will be pulled:
- F41 (F12H)
- F30 (F11 H)
- F19 (F4H)
- F9 (F3H)
- Reports SRV 'H' closes ATC SAT I UNSAT I NA
- Monitor \ report Power, Pressure, Level parameters
- Confirms SRV is shut per panel 09-5 indications
~-----
LOI 12-01 NRC Examination Scenario 3
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ACTIVITY POSITION OPERATOR ACTIONSlSTANDARD COMMENTS/EVALUATION BOP 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): 1OP-l B, D
- Throttle RHRSW Disch Valve From HXB 1OMOV-89B to establish 2500 to 4000 gpm
- Start second RHRSW pump if desired
- Throttle RHRSW Disch Valve From HXB 1OMOV-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 OPERA TOR ACTIONS/ST ANDARD COMMENTS/EVAlUATION ACTIVATE TRIGGER 3 loss line 3 (115KV) All SAT I UNSAT I NA
- Recognize \ report loss line 3
- Annunciator 09-8-6-10 lHH-FITZ 115KV LINE 3 BKR 10022 TRIP SRO SAT I UNSAT / NA
- Enter AOP-72 Role Play: BOP SAT I UNSAT / NA When Power Control
- Monitor Electric Plant parameters \ lineup contacted, report restoration of line 3 is unknown. The
- Report reclosure scheme status Low Voltage Post
- Call National Grid (Power Contro\) and Nine Mile Point Contingency Alarm voltage is 110.5KV
- Relay info concerning low Voltage Post Contingency Alarm voltage is 11 0.5KV to SRO SRO SAT / UNSAT I NA
- 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.
lOI 12-01 NRC Examination Scenario 3 INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/ST ANDARD COMMENTS/EVALUATION 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
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--------c----
INSTRUCTOR. ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTSfEVAlUATION ATC 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 SRO 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
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INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I BOP SAT / UNSAT / NA
- 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 Activate Trigger 5 Loss of Offsite Power (when RPV level is 140 inch and rising)
All SAT / UNSAT / NA
- Recognize \ report loss of all 115KV offsite power
- Recognize \ report loss of all non-vital AC power ATC SAT / UNSAT / NA
- Recognize \ report loss of all Circulating Water
- Manually close MSIVs
- Recognize \ report loss of RBC, TBS, Service Water and Instrument Air BOP SAT / UNSAT / NA
- Recognize \ report complete loss of Condensate and Feedwater.
LOI 12-01 NRC Examination Scenario 3
-16
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION 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
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INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/ST ANDARD COMMENTSfEVALUA TlON BOP SAT I UNSAT I NA
- Direct Relay Room, Control Room and TSC Ventilation aligned per AOP-39.
- Direct H202 monitors restored Modify RR 15 to 10% when ALL SAT I UNSAT / NA DW pressure is 2.7 #.
- Recognize/report drywell pressure > 2.7psig SRO SAT I UNSAT / NA
- Enters EOP-4 and renters EOP-2
- Directs Torus Spray initiated before 15 psig
- Monitors for 1 5 psig in Torus
- Direct drywell Spray BOP
- Spray the Torus as following: SAT / UNSAT / NA
- Verify torus pressure is GREATER THAN 2.7 psig.
- Place SPRAY CNTRL 1OA-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.
LOI 12-01 NRC Examination Scenario 3
-18
INSTRUCTOR ACTIVITY POSITION OPERATOR 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 1OMOV-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 RR 1 5 to 30% Ramp 5 min.
- Spray the Drywell
- 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 1OA-S 17A \B to Manual, spring return to Normal
- Verify white Spray Permissive 1OA-DS67 A \B light on
- Ensure available RHR pumps are running
- Open DW Spray Outboard Valve 10MOV-26A\B
- Throttle DW Spray Inboard Valve 1OMOV -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 OPERATOR 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 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUA TION Critical Task #2 Given the Plant in a condition with the Rx shutdown, Rx Pass \ Fail 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. Critical Task #2 standard All operable ADS SRVs (5) open and two additional non-ADS SRVopen SRO
- Determines RPV level is less than 0 inches. SAT I UNSAT ! NA
- Directs Emergency Depressurization prior to RPV level reaching (-) 19 inches r--~~~~ ---------- -~~~~~~ ----------
Activate TRIGGER 8 ATC SAT! UNSAT I NA when 7 SRVs are opened
- Attempts to open 7 ADS SRVs Loss of 10500 Bus
- 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 SRO SAT I UNSAT / NA
- 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 LOI 12-01 NRC Examination Scenario 3
-21
INSTRUCTOR ACTIVITY POSITION OPERA TOR ACTIONS/ST ANDARD COMMENTS/EVALUA TION Critical Task #3 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). Critical Task #3 standard 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) NOTE: Either RHR Loop B or BOP SAT I UNSAT / NA Core Spray Loop B have to be used to satisfy CT #3
- Recognize \ report Core Spray injection valve fails to open
- Manual open Core Spray injection valve 14MOV-12B BOP SAT I UNSAT I NA
- Recognize \ report LPCI B failed to auto initiate (2.7# or I 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
INSTRUCTOR ACTIVITY POSITION OPERATOR 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: I
- 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
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