ML101520086
| ML101520086 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/28/2010 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| ES-301, Rev 9 | |
| Download: ML101520086 (130) | |
Text
ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Vogtle Date of Examination:
July I August 2007 Examination Level: SRO Operating Test Number: 2007-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Title:
Perform QPTR Calculation
==
Description:==
Perform Quadrant Power Tilt Ration (QPTR) Calculation.
Conduct of Operations M
SRO will also determine the appropriate Tech Spec Actions to be taken.
K/A: G2.1.7(3.714.0)
Title:
Perform Loss of Safety Function Determination Conduct of Operations D
==
Description:==
A Train A Safety Related component will be tagged out when a 12OVAC 1E Vital Bus is required to be put on the regulated transformer (alternate source). The candidate will have to perform a LOSE Evaluation and determine that a loss of safety functions exists.
K/A: G2.1.33 (3.4/ 4.0)
Title:
Perform Emergency Boration Flow Path Verification
==
Description:==
The plant will be in Mode 4 with CVCS components tagged Equipment Control N
out. Failure of another component will require performance of a boric acid flow path verification. This verification will be UNSATISFACTORY and require notification of the Unit SS. K/A: G2.2.12 (3.0/ 3.4)
Title:
Perform Stay Time Calculation to Limit Dose to the Public During a Declared Emergency Radiation Control N
==
Description:==
The SRO will have to calculate the stay time to prevent exceeding Emergency Exposure Limits to limit dose to the public during isolation of a LOCA Outside Containment and venting of an RHR pump.
Candidate will have to fill out 91301-C Authorization form.
K/A: 2.3.1 (2.6/ 3.0)
Title:
Make Emergency Classification, PAR Recommendations, Fill Out ENN form.
==
Description:==
K/A: The candidate will be given conditions requiring classification of a General Emergency (or upgrade Site to a General).
A General Emergency declaration requires that a PAR recommendation be made. G2.4.38 (2.2 / 4.0),
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank (1)
(P)revious 2 exams (/11; randomly selected)
(S)imulator
Facility: Vogtle Date of Examination:
July I August 2007 Examination Level: RO Operating Test Number: 2007-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Title:
Perform QPTR Calculation
==
Description:==
Perform Quadrant Power Tilt Ration (QPTR) Calculation Conduct of Operations M
(this could be done in dass setting or simulator, if in simulator could be set up where Human Performance Factors come into play.
K/A: G2.1.7 (3.7 / 4.0)
Conduct of Operations N/A Not applicable for this examination.
Title:
Perform Emergency Boration Flow Path Verification
==
Description:==
The plant will be in Mode 4 with CVCS components tagged Equipment Control N
out. Failure of another component will require performance of a boric acid flow path verification. This verification will be Unsatisfactory and require notification of the Unit SS. K/A: G2.2.12 (3.0 / 3.4)
Title:
Perform Stay Time Calculation to Protect Valuable Equipment During a Declared Emergency Radiation Control M
==
Description:==
An RHR pump will require local manual operations to vent the pump during an emergency. Candidate will be given transit dose rates to and from area along with dose rates in pump room. Candidate will calculate stay time without exceeding IOR dose limits.
K/A: 2.3.1 (2.6 / 3.0)
Title:
Make Emergency Notifications with Total Failure of the ENN.
==
Description:==
An ENN Notification is required and the candidate will Emergency Plan M
experience the inability to reach multiple agencies requiring notification.
This will require the candidate to use the backup conference bridge since two or more agencies cannot be reached with the ENN.
K/A: G2.4.43 (2.8 / 3.5)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank 1)
(P)revious 2 exams ( 1; randomly selected)
(S)imulator ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1
ES-301, Rev. 9E Control Room/In-Plant Systems Outline Form ES-301-2 Draft I..
Facility: Vogtle Date of Examination: July I August 2007 Exam Level (circle one): RO / SRO-l I SRO-U (see each JPM)
Operating Test No.: 2007-301 Control Room Systenls@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function
- a. Perform Control Rcd Operability Test. Two Rods will drop during N, A, S I
exercise requi ring a reactor trip from QMCB. (RO / SRO-I) iii K/A: 001A2.11 (4.4/4.1)
- b. Transfer ECCS Pumps to Hot Leg Recirculation. Multiple Train A D, A, E, L, S 2
Components Fail tQAlign (RO / SRO-I / SRO-U) fl Jwp;el K/A: 006A4.05 (3.9 I 3.S)
N A E L S 3
Two valves wont have power and will require vent of accumulator.
(RO/SRO-I/SRO-U)
K/A: 062A4.07 (3. 1 / 3.1)
supply will not shutrequiring RNO actions. (RO I SRO-i)
I
- v KJA: 035A4.06 (45 I 4.
- e. Swap AFW Pump &ctions to the Alternate Source. CST level will N E L 4S require suction ancirnini flow swap to the alternate CST source.
(RO/SRO-I)
K/A: 061A1.04(3. 9/ 3.9) f.
Post LOCA Cntairrnent Hydrogen Purge Operation. High CNMT M E L S 5
Hydrogen Concentration will require Purge operations.
/
fr 1
(RO/SRO-I/SRO-U)
K/A: 028A2.03 (3.4 / 4.C)
- g. Synchronize Main Generator to the Grid. Field amps not indicated D, A, S 6
on one phase requirs Main Turbine trip. (RO)
K/A: 062A4.07 (3.1 / 3.1)
- h. Respond to Hig h Coitainment Radiation. (RO/SRO-I)
D, E, L, S 7
iA K/A: 072A3.O1 (2.9/3.1) 9)
n
& /
PD S)\\
J
.1 2
J 3
7
S.
(j; ES-301, Rev. 9E Control Room/In-Plant Systems Outline Form ES-301-2 Draft In-Plant Systems (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)
- i. Locally Manually Trip Reactor during ATWT. The trip breakers wont M A E open requiring opening of the MG Set Output Breakers.
(R0/SRO-l/SRO-U)
K/A: 029EA1.12 (4.1 /4.0)
- j. Minimize Environmental and Secondary System Contamination D, E, L 4S (Cb Following a SGTR. (RO / SRO-l)
[,
K/A: 062A4.07 (3.1 /3.1)
N R E L
6 This JPM will also require candidate to open the battery breaker due to < 105 V DC on I E bus.
(RO / SRO-l / SRO-U)
K/A: 062A2.08 (2.7 / 3.0)
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrom bank
- 9/#81#4 (E)mergency or abnormal in-plant 3 1 / 3 1 / 3 1 (L)ow-Power/Shutclown 31/31/31 (N)ew or (M)odified from bank including 1(A) 3 2 /3 2 / 3 1 (P)revious 2 exams
- 3 / # 3 / # 2 (randomly selected)
(R)CA 31f31/31 (S)imulator
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ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2 Draft Facility: Vogtle Date of Examination: July! August 2007 Exam Level (circle one):
RO / SRO-l ! SRO-U (see each JPM)
Operating Test No.: 2007-301 Control Room Systems© (8 for RO; 7 for SRO-; 2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function
- a. Perform Control Rod Operability Test. Two Rods will drop during N, A, S 1
exercise requiring a reactor trip from QMCB. (RD / SRD-I)
K/A: 001A2.11 (4.4/4.7)
- b. Transfer ECCS Pumps to Hot Leg Recirculation. Multiple Train A D, A, F, L, 5 2
Components Fail to Align (RD / SRO-I / SRO-u)
K/A: 006A4.05 (3.9 / 3.8)
- c. Isolate SI Accumulators during Post LOCA Cool down, Depress.
N A E L S 3
Two valves wont have power and will require vent of accumulator.
(RD I SRD-I / SRO-U)
K/A: 062A4.07 (3.1 / 3.1)
- d. Identify and Isolate SG during SGTR. MSIV and TDAFW steam D, A, E, L, S 4P supply will not shut requiring RNO actions. (RD / SRO-I)
K/A: 035A4.06 (4.5 / 4.6)
E L
4S require suction and mini flow swap to the alternate CST source.
(RD / SRD-I)
K/A: 061A1.04 (3.9/ 3.9) f.
Post LOCA Containment Hydrogen Purge Operation. High CNMT M E L S 5
Hydrogen Concentration will require Purge operations.
(RO/SRD-I/SRD-U)
K/A: 028A2.03 (3.4 / 4.0)
- g. Synchronize Main Generator to the Grid. Field amps not indicated D, A, S 6
on one phase requires Main Turbine trip. (RD / SR0-I)
K/A: 062A4.07 (3.1 / 3.1)
- h. Respond to High Containment Radiation. (RD I SRO-)
D, E, L, S 7
K/A: 072A3.01 (2.9/3.1)
ES-301, Rev. 9E Control Room/In-Plant Systems Outline Form ES-301-2 Draft In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)
- i. Locally Manually Trip Reactor during ATWT. The trip breakers wont M A E open requiring opening of the MG Set Output Breakers.
(RO / SRO-I / SRO-U)
K/A: 029EA1.12 (4.1 /4.0)
- j. Minimize Environmental and Secondary System Contamination D, E, L 4S Following a SGTR. (RO / SRO-I)
K/A: 062A4.07 (3.1 / 3.1)
N R E L
6 This JPM will also require candidate to open the battery breaker
dueto< 1O5VDCon lEbus.
(RO / SRO-I / SRO-U)
K/A: 062A2.08 (2.7 / 3.0)
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO / SRO-I I SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irect from bank 9 /
8 /
4 (E)mergency or abnormal in-plant 1 /
1 I 1
(L)ow-Power / Shutdown 1 /
1 I 1
(N)ew or (M)odified from bank including 1(A) 2 /
2/
1 (P)revious 2 exams 3 /
3 /
2 (randomly selected)
(R)CA (S)imulator
SOUTHERNA COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 3130-003 PERFORM PosT-LOCA CONTAINMENT HYDROGEN PURGE THIS ISA MODIFIED JPM FOR THE HL-14 NRC EXAM Revision 0 June 12, 2007 Written By:
Thad N. Thompson Date:
6/12/2007 Approved By:
R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
A LOCA has occurred on Unit 1. Containment Hydrogen concentration cannot be reduced below 4% by any other method.
Assigned Task:
The USS has directed you to perform Post-LOCA Containment Hydrogen Purge Operations to reduce Containmnet Hydrogen concentration per SOP-i 3130-1, Post Accident Hydrogen Control section 4.4.3 for Post LOCA Containment Hydrogen Purge System Operation.
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RQ-JP-1 3130-003 START TIME:
JPM STEPS STEP 1 SAT UNSAT D Appropriate procedure selected D
- 13130, Section 4.4.3 selected (#)
CUE:
(#) Steps 4.4.3.1 through 4.4.3.7 have already been performed.
STEP2 CRITICAL(.)
SAT Dc UNSAT D
2 L
Aligns local valves and Containment IRC valves for Post-LOCA purge release.
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- Verifies 1-HV-2624A and 1-HV-2624B are closed until personnel have compk LJ
- Verifies ZLB for 1-1508-U4-012 red light illuminated.
D
- Verifies conditions of Gaseous Waste Permit are met (# 2) fl
D
(# 1) The SS has dispatched someone to locally open 1-1 508-U4-01 2.
(# 2) The SS has verified the Gaseous Waste Permit conditions are met.
NOTE: The CVI reset handswitches on the QMCB A panel will NOT reset CVI from rad to allow opening 1 -HV-2624A or 1 -HV-2624B.
STEP 3 CRITICAL (,)
SAT Dc UNSAT D Initiates Post-LOCA Containment Hydrogen Purge fl
LJ
- Verifies Post-LOCA Purge flow rises to between 450 and 500 scfm using 1-Ul-2693B.
D
- Monitors 1-Ul-2693B, plant vent flow in compliance with Gaseous Release Permit. (#)
CUE:
(#)
The SS will have an operator monitor plant vent stack flow.
5
RQ-JP-1 3130-003 JPM STEPS STEP4 CRITICAL (,)
SAT Dc UNSAT D.c Resets CIA and aligns I establishes Service Air to Containment.
U
- Resets CIA
. Opens SERVICE AIR CNMT HDR ISOL 1-HV-9385 by performing the following sequence.
- Place HS-9385A on the QPCP to the OPEN position.
i1
- HOLDS 1-HS-9385B on the QPCP until 1-HV-9385 is fully open. (NOTE below)
Monitors Air Header pressures on the QMCB using 1 -P1-9377 and 1 -P1-9361. (#)
NOTE: If the correct sequence is not performed, 1-HV-9385 will NOT open.
CUE:
(#) The SS will have another operator monitor air pressure and complete the prodedure.
STEP 5 SAT D UNSAT LJs Report to USS D
- Post-LOCA Containment Hydrogen Purge is in Service.
STOP TIME:
Field Notes 6
SOUTHERNA COMPANY Energy to Serve Your Wor1d PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-13610-OO1 TRANsFER AFW PUMP SUCTION To CONDENSATE STORAGE TANK 2 THIS ISA NEW JPM WRITTEN FOR HL-14 NRC ExAM Revision 0 June 12, 2007 Written By
- Thad N. Thompson Date:
6/12/2007 Approved By
- R. Lee Mansfied Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
A reactor trip has occurred due to a feed water transient. CST # 1 has developed a leak and level is currently < 15% requiring AFW pump suction swap per the EOP Fold Out Page to prevent a Loss of Secondary Heat Sink.
Assigned Task:
The SS has directed you to Perform SOP-i 3610-1 Auxiliary Feedwater System and Transfer AFW pump suction to CST # 2.
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RQ-JP-1 3610-001 START TIME:
JPM STEPS STEP I CRITICAL (+)
SAT D.
UNSAT Di Selects section for swapping CST suction and performs transfer of MDAFW A suctions.
- Selects section 4.4.1, Transferring AFW pump Suction To And From Condensate Storage Tank 2.
s.D
- Opens 1-HV-5119, CST-2 SUPPLY TO MDAFW PMP-A using 1-HS-5119A.
- Requests IV for opening of 1-HV-51 19. (# 1)
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- Requests IV for closure of 1 -HV-5095. (# I)
D
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- Requests IV for opening of 1-1 302-U4-1 85. (# 1)
E
- Requests IV for opening of 1-1 302-U4-1 80. (# 1)
NOTE: Operation of 1 -HV-5095, 1-1 302-U4-1 85, 1-1 302-U4-1 80 are all LOCAL actions at the CST.
CUES:
(# 1)..
The SS will have an operator IV the step.
(# 2)..
The SS will have an operator locally operate the valve.
STEP 2 CRITICAL (.)
SAT D.c UNSAT Dc Performs transfer of MDAFW B suctions.
- Opens 1-HV-5118, CST-2 SUPPLY TO MDAFW PMP-B using 1-HS-5118A.
D
- Requests IV for opening of 1-HV-51 18. (# 1)
L1 Requests closure of MDAFW 2 SUCT FROM CST 1, 1-HV-5094. (#2)
LJ
- Requests IV for closure of 1-HV-5094. (# I)
- Requests IV for opening of 1-1 302-U4-1 84. (# 1)
- Requests IV for opening of 1-1302-U4-181. (#1)
NOTE: Operation of 1 -HV-5094, 1-1 302-U4-1 84, 1-1 302-U4-1 81 are all LOCAL actions at the CST.
CUES:
(# 1)..
The SS will have an operator IV the step.
(# 2)..
The SS will have an operator locally operate the valve.
5
RQ-JP-1 3610-001 JPM STEPS STEP 3 CRITICAL (*)
SAT Eis UNSAT Dc Performs transfer of TDAFW pump suctions.
Opens 1-HV-5113, CST-2 SUPPLY TO TDAFW using 1-HS-5113A.
E
- Requests IV for opening of I -HV-51 13. (# 1)
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- Requests IV for closure of I -HV-5093. (# 1)
E
- Requests IV for opening of 1-1 302-U4-1 83. (# 1)
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- Requests IV for opening of 1-1 302-U4-1 82. (# 1)
NOTE: Operation of 1-HV-5093, 1-1302-U4-183, 1-1302-U4-182 are all LOCAL actions at the CST.
CUES:
(# 1)..
The SS will have an operator IV the step.
(# 2)..
The SS will have an operator locally operate the valve.
STEP 4 Non-CRITICAL (.)
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STOP TIME:
Field Notes 6
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This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
A plant startup is in progress. The unit has been stabilized at approximately 25% power. The System Operator has given approval to synchronize to the grid. Main Generator field excitation has already been established by the previous shift.
Assigned Task:
The USS has directed you to Synchronize the Main Generator to the power grid, and assume 60 to 80 MWe using 13830 section 4.1.3.
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JPM STEPS RQ-JP-1 3830-002 START TIME:
STEP I CRITICAL ()
SAT D,c UNSAT D.ec Synchronize the Main Generator to the Grid per section 4.1.3
- Selects a PCB for synchronizing. (1), (2)
EJ
- Place synch switch SS-BUSI in position R D
- Place synch scope switch SS-U1 in position I
JJ
- Verify rotation of Synch scope ISI-40125 D
- Place Volt/Freq switch VS-US1 in BUSI D
- 230 KV system voltage observed on El-40124 D
- Place Volt/Freq switch VS-US1 in UNIT I U
- Generator voltage observed on El-40124 iZJ
- AC Raise/Lower switch adjusted to establish Unit voltage 0
- 1 KV> 230 KV system voltage CUE:
(1)
SS reports The Generator Field Ground Detector Relay testing has been completed.
(2)
If asked, Close PCB 161710.
STEP 2 CRITICAL (+)
SAT Dc UNSAT D Adjust generator voltage
- Note, When simulated, the cue given will require the operator to raise turbine speed to achieve the desired rotation.
- 230 KV system frequency observed on Sl-40125 D
- Turbine control Increase Load / Decrease Load pushbuttons adjusted to attain slow clockwise rotation on Sl-40125 CUE:
© SI-401 25 is rotating slowly counter clock wise.
5
RQ-JP-1 3830-002 JPM STEPS STEP 3 CRITICAL ()
SAT Ei UNSAT D Synchronize main generator to the grid D
- Place Synch selector TS-US1 in 161710 (161810)
(1) iJ
- Verify Synch scope rotating slowly clockwise (10 sec rotation)
D
- Verify Red Auto Synch light lit at 12 oclock D
- Auto synch pushbutton PB-161710 (PB-161810) depressed D
- Verify current indicated on each phase (111-40127, 40128, & 40129)
CUE:
(1)
USS states Use automatic Synchronization.
STEP 4 CRITICAL (+)
SAT Dis UNSAT D Verifies PCB not properly closed and Trips the Main Turbine.
zsD
- Observes Phase B (1 11-4028) not reading amps on meter or IPC Point (J2833)
U
- Depresses the TRIP pushbutton on the Main Turbine Control Panel STEP 4 SAT D UNSAT Li Report to USS D
- Main Turbine tripped due to improper PCB closure. Initiate 1801 1-C, Turbine Trip Below P-9.
STOP TIME:
Field Notes 6
SOUTHERN COMPANY Energy to Serve Your Wor1d PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 4410-001 PERFORM CONTROL ROD OPERABILITY TEST (FAULTED PATH)
THIS IS A NEW JPM WRITTEN FOR HL-14 NRC ExAM Revision 0 June 12, 2007 Written By
- Thad N. Thompson Date:
6/12/2007 Approved By
- R. Lee Mansfied Date:
June 15, 2007
(
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
The Unit is at 100% power. Dsp-i 4410-1, Control Rod Operability Test is to be performed. An SO is stationed at the P to A Converter to obtain Control Bank position readings. All prerequisites and intial conditions have been verified.
Assigned Task:
The SS has directed you to Perform OSP-i 441 0-1 Control Rod Operability Test starting with CBA.
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RQ-JP-1 4410-001 START TIME:
JPM STEPS STEP I CRITICAL (,)
SAT D.c UNSAT D.
Records CBA Initial Group Counter, Individual rod positions, and the PIA Converter.
U
- Records the INITIAL CBA Group Step Counter and individual DRPI readings on Data Sheet 1.
Records the INITIAL CBA P I A Converter reading. (#)
D
- Places ROD BANK SELECTOR SW 1-HS-40041 to CBA.
CUES:
(#)..
The SO at the P/A Converter reports CBA is at 228 steps.
STEP 2 CRITICAL (.)
SAT D.ec UNSAT Dec Inserts CBA at least 10 steps and verifies rod motion on DRPI, records data.
- Using ROD MOTION SWITCH 1-HS-40040 inserts CBA at least 10 steps.
Checks RODS IN light is lit and a change in position for CBA occurs on DRPI.
D
- Records the TEST Group Step Counter and DRPI reading for CBA on Data Sheet 1. (#)
CUES:
(#)..
The SO at the P/A Converter reports CBA is at 218 steps. Unless inserted to another position.
STEP 3 CRITICAL (.)
SAT D.
UNSAT D Initiates CBA withdrawal to original position.
Using ROD MOTION SWITCH 1-HS-40040 initiates withdrawal of CBA.
.U
- Checks RODS OUT light is lit and a change in position for CBA occurs on DRPI.
5
RQ-JP-1 4410-001 JPM STEPS STEP 4 CRITICAL (*)
SAT D.c UNSAT Eis Initiates manual reactor trip when 2 CBA rods drop.
- Observes 2 CBA rods drop.
- Attempts MANUAL reactor trip using C panel Reactor Trip handswitch.
.D
- MANUALLY trips the reactor using A panel Reactor Trip handswitch.
NOTE: The candidate may open AOP-1 8003 and initiate steps of section A for Dropped Control Rods in Mode 1 prior to initiating the reactor trip. This would be satisfactory performance. IF, the candidate continues past step A2 of this procedure without performing a reactor trip, performance would be UNSAT.
STEP 5 Non-CRITICAL (.)
- Informs SS of manual reactor trip due to 2 dropped rods in CBA.
STOP TIME:
Field Notes 6
SOUTHERNA COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 9012-001 ISOLATE SI AccuMuLAToRs DURING POST LOCA COOLDOwN (FAULTED PATH)
THIS ISA NEW JPM WRITTEN FOR HL-14 NRC Ex.4M Revision 0 June 12, 2007 Written By
- Thad N. Thompson Date:
6/1 2/2007 Approved By
- R. Lee Mansfied Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
Unit 1 was at 100% power when a LOCA occurred. After transition to 19012-C, Post LOCA Cooldown and Depressurization, a IE Emergency bus was de-energized. The crew is performing the steps to isolate SI Accumulators per 19012-C. An SO has closed the ACCUM ISO VALVE MOV breakers.
Assigned Task:
The SS has directed you to Perform step #38 of 19012-C, and Isolate the SI Accumulators.
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RQ-JP-1 9012-001 START TIME:
JPM STEPS STEP I CRITICAL (,)
SAT Dc UNSAT D.
Resets SI and closes Accumulator Isolation valves that have power.
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- Place HV-8808A in CLOSED position D
- Place HV-8808C in CLOSED position CUES:
©..
After HS placed in Close position, The green light is lit and the red light is not lit.
STEP 2 SAT Dc UNSAT Vents any non-isolable accumulators.
.E
- Verifies N2 supply valve HV-8880 is closed. (I)
D
- Places either HV-8875B or HV-8875F in the OPEN position (2)
D
- Places either HV-8875D or HV-8875H in the OPEN position (2)
- Places either HV-0943A or HV-0943B the in OPEN position (3)
CUES:
(1)
The green light is lit and the red light is not lit after each valve is identified.
(2)
The red lights is lit and the green light is not lit after each valve is identified.
(3)
The red UP arrow is lit, the green down arrow is extinguished after the valve is identified.
STEP 3 Non-CRITICAL (.)
SAT D.es UNSAT D.&
Isolate Aux Building Ventilation System at QHVC D
CUES:
©...
The SS will dispatch an SO to open the Accumulator Isolation valve breakers.
5
RQ-JP-19012-OO1 JPM STEPS STEP 4 SAT D UNSAT Report to SS
- 19012-C, step # 38 for Isolation of SI Accumulators has been completed.
STOP TIME:
Field Notes 6
SOUTHERNA COMPANY Energy to Serve Your Wor1d PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-19014-003 TRANSFER ECCS PUMPS TO HOT LEG REcIRcuLATI0N WITH FAILURE OF TRAIN A RHR & SI ALIGNMENTS (FAULTED JPM)
Revision 1 June 12, 2007 Written By: Thad N. Thompson Date:
6/12/07 Approved By: R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
A large break LOCA occurred 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago. The crew is in 19010-C.
Assigned Task:
The SS has directed you to Transfer the ECCS pumps to hot leg recirculation using 19014.
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RQ-JP-19014-003 START TIME:
JPM STEPS STEP I CRITICAL (,)
SAT Dtc UNSAT D.e Align RHR for hot leg recirculation Note:
The operators would have positioned all lockout switches to ON by reaching step 19 of 19010.
. Cold leg injections HV-8809A and HV-8809B CLOSED
- RHR Train B to Hotleg Crossover Isolation, HV-8716B OPEN
- Identify RHR Train A to Hotleg Crossover Isolation, HV-8716A will NOT OPEN O
- Re-open HV-8809A per RNO 1 B direction EJ
- Hot leg injection HV-8840 OPEN STEP 2 CRITICAL (,)
- SIP A Stopped STEP 3 CRITICAL (,)
SAT Eic UNSAT Dc Align Train A SI for hot leg recirculation fl
- Crossconnect HV-8821A CLOSED JJ
- Identify that Hot leg injection HV-8802A will NOT OPEN
.fl
- Ensure Cold Leg Injection HV-8835 OPEN U
- Crossconnect HV-8821A OPEN STEP 4 CRITICAL (,)
SAT D.es UNSAT Dc Start SIP A fl
- SIP A Running D
- Train A SI flow verified> 100 gpm CUES:
© Indicate Train A SI flow 400 gpm.
5
RQ-JP-1 9014-003 JPM STEPS STEP 5 CRITICAL (,)
- SIP B Stopped STEP 6 CRITICAL (,)
SAT D UNSAT D Align Train B SI for hot leg recirculation D
- Crossconnect HV-8821 B CLOSED i:i
- Hot Leg Injection HV-8802B OPEN STEP 7 CRITICAL (*)
SAT Dis UNSAT Ei!
Start SIP B
?E1
- SIP B Running D
- Train B SI flow verified> 100 gpm O
- Determines that both SI trains not aligned to HL Recirc and leaves HV-8835 OPEN CUES:
© Indicate Train B SI flow 400 gpm.
STEP 8 SAT Dc UNSAT LJc Report to SS iZI
- Train B ECCS aligned for Hot Leg Recirc D
- Train A SIS must remain aligned for Cold Leg Recirc STOP TIME:
Field Notes:
6
SOUTHERN COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 9030-005 ISOLATE A RUPTURED STEAM GENERAr0R WITH FAILURE OF TDAFW STEAM AND MSIVs TO CLOSE (FAULTED JPM)
Revision 1 June 12, 2007 Written By
- Thad N. Thompson Date:
6/12/07 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
THIS IS A TIME CRITICAL JPM Initial Conditions:
A turbine trip/reactor trip occurred from 100% power. While the crew was attempting to stabilize the plant, a low PRZR pressure SI occurred. The crew was transitioned from 19000, E-0 to 19030.
Assigned Task:
The SS has directed you to Isolate the ruptured SG using 19030.
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RQ-JP-1 9030-005 JPM STEPS L
- Verify at least one CCP/SIP running
- RCS pressure verified> 1375 psig L
Performance of this step is optional based on the Initial Conditions given to the operator.
.D
- SC # 2 identified as ruptured based on uncontrolled level rise CUES:
© Provide indication SG # 2 NR level is ¶ rapidly.
STEP 2 CRITICAL (,)
SAT D.e UNSAT Dc Identify ruptured steam generator START TIME:
TIME CRITICAL
STEP 3 CRITICAL (,)
SAT D UNSAT D.c Adjust ARV setpoint Note:
The ARV should be allowed to control pressure automatically. Placing the controller in Manual and closing the ARV is considered UNSA T.
L
- ARV controller PIC-3010 in AUTO (see note above)
.D
- Adjust PIC-301 0 potentiometer at 7.73 ( 1 160 psig)
.D
- Check ARV PV-3010 closed fl
.D
- TDAFW steam supply HV-3019A identified will NOT close fl
- Places T & T valve HS-1 5111 to the CLOSE position.
STEP 4 CRITICAL (,)
SAT D.e UNSAT D Attempt to Shut TDAFW steam supply, Shut T & T valve per RNO 5
RQ-JP-1 9030-005 JPM STEPS STEP 5 SAT UNSAT Dc Isolate SG blowdown Note:
Positioning the handswitch to CLOSE should be performed for satisfactory completion.
O
- Place SGBD isolations HV-7603A, B, C, D in close position STEP 6 CRITICAL (,
SAT D UNSAT D Attempt to shut MSL isolation and bypass valves
- MSIVs HV-3016A and HV-3016B identified will NOT shut.
. MSBVs HV-1 3007A and HV-1 3007B closed STEP 6 CRITICAL (,)
SAT D UNSAT Dc Performs Step 3 RNO when MSIV for SG # 2 does not shut D
- Shuts all remaining MSIVs (HV-3006A & B, 3026A & B, 3036A & B)
D
- Shuts all remaining MSBVs (HV-13005A & B, 13006A & B, 13008A & B)
- Verifies shut all steam dump valves on ZLB-2 and closes dumps if not shut. (1) fl
- Verifies HV-6194A Aux and Main Steam Sparger valve LJ
- Shuts SJAE valves by selecting HS-4084A (HV-4084B closed by ZLB) to OFF (2) fl
- Verifies shut MSR A & C Reheat Steam Source Stop Valves (FIS-6030 verified in CLOSE)
D
- Verifies shut MSR B & D Reheat Steam Source Stop Valves (HS-6015 verified in CLOSE) fl
- Use intact ARV for steam dump (control of Tave) lJ
(1)
If Steams Dumps are open (expected), the operator can close by either:
- Selecting OFF I RESET on handswitch, or
- Selecting Steam Pressue Mode and using the I PIC-507 controller.
(2)
Taking the SJAE HS-4084A (HV-4084B) to close will satisfy this step. The valves for this are long winded and the candidate does not have to wait for these to close to proceed as he has no further control over the valves from the QMCB.
CUES:
(#)
If necessary, state Another operator will verify the SJAE valves go fully shut.
6
RQ-JP-1 9030-005 JPM STEPS STEP 8 CRITICAL (,)
SAT D.
UNSAT D.
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- Check ruptured SG #2 NR level> 10%
D
- MDAFW throttle valve HV-5132 closed (1)
D
- TDAFW throttle valve HV-5125 closed L1
- AFW flow to ruptured SG at 0 gpm NOTE: (1) This is the stop time for time critical as there are no further valves required for isolation unless the student has missed performing a step or incorrectly performed a step.
STOP TIME:
STEP 9 SAT UNSAT Iic Checks ruptured SG(s) isolated from intact SG(s).
D
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CLOSED.
STEP 10 SAT D.-
UNSAT D Report to SS
>l
- Ruptured SG isolated Field Notes 7
SOUTHERNA COMPANY Energy to Serve Your Worlif PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 9253-001 RESPOND TO CoNTAINMENT HIGH RADIATION Revision 7 June 12, 2007 Written By
- Thad N. Thompson Date:
6/12/2007 Approved By
- R. Lee Mansfied Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
Unit 1 was at 100% power when a LOCA occurred. After transition to 19010-C, Containment Area Rad Monitors RE-002 and RE-003 indicated radiation levels in Containment had reached 750 mR/hr.
Assigned Task:
The SS has directed you to Perform 19253-C, Response to High Containment Radiation Level.
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RQ-JP-1 9253-001 START TIME:
JPM STEPS STEP I CRITICAL (,)
SAT Dc UNSAT D Isolate Containment Air Radiation monitor at QPCP l
- Place HV-1 2975 in CLOSED position fl
- Place HV-1 2976 in CLOSED position D
- Place HV-1 2977 in CLOSED position fl
- Place HV-1 2978 in CLOSED position CUES:
©..
After HS placed in Close position, The green light is lit and the red light is not lit.
STEP 2 SAT fl.c UNSAT U Verify Containment Purge isolated at QHVC l
- Verify HV-2626A and B are CLOSED D
- Verify HV-2627A and B are CLOSED iZJ
- Verify HV-2628A and B are CLOSED D
- Verify HV-2629A and B are CLOSED D
- Verify HV-2624A and B are CLOSED CUES:
©..
The green light is lit and the red light is not lit after each damper is identified.
STEP 3 CRITICAL (,)
SAT Eic UNSAT D.
Isolate Aux Building Ventilation System at QHVC l
- Place HV-1 2604 in CLOSED position D
- Place HV-1 2605 in CLOSED position D
- Place HV-1 2606 in CLOSED position D
- Place HV-1 2607 in CLOSED position CUES:
©...
After HS placed in the closed position, The green light is lit and the red light is not lit.
5
RQ-JP-1 9253-001 JPM STEPS STEP 4 CRITICAL (,)
SAT D.c UNSAT Eies Isolate Recycle Holdup Tank Ventilation at QHVC D
- Place HV-1 2596 in CLOSED position
- i
- Place HV-1 2597 in CLOSED position CUES:
©...
After HS placed in the closed position, The green light is lit and the red light is not lit.
STEP 5 SAT D.
UNSAT ELc Checks Piping Penetration Filtration and Exhaust Units Both running fl
. Checks Piping Penetration Unit Train A running fl Checks Piping Penetration Unit Train B running CUES:
©...
After HS placed in the START position, The green light is not lit and the red light is lit.
STEP 6 Non-critical (.)
SAT ELe UNSAT E:Lec Containment Preaccess Filter Units placed in service Note:
19253 directs operator to start filter units per sop 13125. If requested inform the operator to start all available Preaccess Filter Units.
fl
- Place HS-2620 in start position (1)
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- Place HS-2621 in start position D
CUES:
(1)
SS reports Per chemistry request, place both Preaccess Filters Units in service.
©..
After each HS placed in start, The red light is lit and the green light is not lit.
STEP 7 SAT UNSAT D.
Report to SS Note:
The step prior to completion is to notify the TSC of the radiation level in Containment. Inform the operator that The USS has notified the TSC of Containment radiation levels.
l
- 19253-C, Response to Containment High Radiation Level has been completed.
STOP TIME:
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ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Vogtle Date of Examination:
July I August 2007 Examination Level: SRO Operating Test Number: 2007-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Title:
Perform QPTR Calculation
==
Description:==
Perform Quadrant Power Tilt Ration (QPTR) Calculation.
Conduct of Operations M
SRO will also determine the appropriate Tech Spec Actions to be taken.
K/A: G2.1.7(3.7 / 4.0)
Title:
Perform Loss of Safety Function Determination Conduct of Operations D
==
Description:==
A Train A Safety Related component will be tagged out when a 120V AC 1E Vital Bus is required to be put on the regulated transformer (alternate source). The candidate will have to perform a LOSF Evaluation and determine that a loss of safety functions exists.
K/A: G2.1.33 (3.4/ 4.0)
Title:
Perform Emergency Boration Flow Path Verification
==
Description:==
The plant will be in Mode 4 with CVCS components tagged Equipment Control N
out. Failure of another component will require performance of a boric acid flow path verification. This verification will be UNSATISFACTORY and require notification of the Unit SS. K/A: G2.2.12 (3.0 / 3.4)
Title:
Perform Stay Time Calculation to Limit Dose to the Public During a Declared Emergency Radiation Control N
==
Description:==
The SRO will have to calculate the stay time to prevent exceeding Emergency Exposure Limits to limit dose to the public during isolation of a LOCA Outside Containment and venting of an RHR pump.
Candidate will have to fill out 91301-C Authorization form.
K/A: 2.3.1 (2.6 / 3.0)
Title:
Make Emergency Classification, PAR Recommendations, Fill Out ENN form.
==
Description:==
K/A: The candidate will be given conditions requiring classification of a General Emergency (or upgrade Site to a General).
A General Emergency declaration requires that a PAR recommendation be made. G2.4.38 (2.2 / 4.0),
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(S)im u lator
ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Vogtle Date of Examination:
July! August 2007 Examination Level: RO Operating Test Number: 2007-301 Administrative Topic (see f Type Describe activity to be performed Note) j Code
Title:
Perform QPTR Calculation
==
Description:==
Perform Quadrant Power Tilt Ration (QPTR) Calculation Conduct of Operations N
(this could be done in class setting or simulator, if in simulator could be set up where Human Performance Factors come into play.
K/A: G2.1.7(3.7 / 4.0)
Conduct of Operations N/A Not applicable for this examination.
Title:
Perform Emergency Boration Flow Path Verification
==
Description:==
The plant will be in Mode 4 with CVCS components tagged Equipment Control N
out. Failure of another component will require performance of a boric acid flow path verification. This verification will be unsatisfactory and require notification of the unit SS. K/A: G2.2.12 (3.0/ 3.4)
Title:
Perform Stay Time Calculation to Protect Valuable Equipment During a Declared Emergency Radiation Control M
==
Description:==
An RHR pump will require local manual operations to vent the pump during an emergency. Candidate will be given transit dose rates to and from area along with dose rates in pump room. Candidate will calculate stay time without exceeding 1OR dose limits.
K/A: 2.3.1 (2.6 / 3.0)
Title:
Make Emergency Notifications with Total Failure of the ENN.
==
Description:==
An ENN Notification is required and the candidate will Emergency Plan M
experience the inability to reach multiple agencies requiring notification.
This will require the candidate to use the backup conference bridge since two or more agencies cannot be reached with the ENN.
K/A: G2.4.43 (2.8 / 3.5)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(S)imulator
p SOUTHERNA COMPANY Energy to Serve Your Worki PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE n,
7/i 1
qt 1
RQ-JP-14405-002 BORIC INJECTION FLOW PATH VERIFICATION THIS Is A MODIFIED JPM FOR THE HL-14 NRC ExAM (RO VERSION)
Revision 0 June 13, 2007 Written By
- Thad N. Thompson Date: June 13, 2007 Approved By
- R. Lee Mansfied Date: June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
The plant is at 100% power. During an inspection of HV-8801A MCC breaker, a dropped tool resulted in a short in the breaker bucket. The SS has declared HV-8801A to be INOPERABLE and entered LCO 3.5.2 for ECCS.- Operating.
Also, the crew has just entered AOP-1 8007-C section A for Total Loss of Charging Flow due to an apparent failure of FV-0121 to the closed position. Maintenance investigation estimates 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for repair.
Assigned Task:
Perform 14405-1, Boron Injection Flow Path Verification and determine if the Acceptance Criteria are met.
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RQ-J P-I 4405-002 START TIME:
JPM STEPS STEP I CRITICAL (*)
SAT D.c UNSAT D Perform Boron Injection Flow Path Verification per 14405-I.
- Obtains SS Approval and fills in Date, Time and Mode.
Verifies steps 5.1.a 14225-1 Operations Surveillance Logs is active. (# I)
.fl Verifies steps 5.1.b 14705-1 Boron Injection Flow Rate Verification is active. (# 1)
.fl Verifies steps 5.1.c 14811-1 BA Transfer Pump & Discharge Check Valves Inservice active. (# I)
Verifies steps 5.1.d 14808-1 CCP & Check Valves 1ST & Response Test is active. (# I)
Verifies steps 5.1.e 14000-1 Operations Shift & Daily Surveillance Logs is active. (# 1)
.U Identifies 2 acceptable Boron Injection Flow Paths per Figure 1 are NOT available. (NOTE: 2)
Determines Acceptance Criteria NOT met.
Notifies SS that BA Flow Path Verification Acceptance Criteria are NOT met.
CUES:
(1)
The surveillance is active.
NOTES (2)
Two paths must NOT share any active components on figure 1. All the flow paths would go through HV-8801B (an active component). Therefore, there are NOT two Boric Acid Flow Paths Available.
STOP TIME:
Field Notes
SOUTHERNA COMPANY Energy to Serve Your Wor1d PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-91 002-003 MAKE EMERGENCY NOTIFICATIONS WITH COMPLETE FAILURE OF THE ENN (Faulted JPM)
Revision 1 June 13, 2007 Written By
- Thad N. Thompson Date:
4/11/2005 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
THIS IS A TIME CRITICAL JPM G Initial Conditions:
An emergency has been declared and the Shift Manager has assumed the duties of the Emergency Director.
Assigned Task:
The Emergency Director has directed you to Perform the duties of the ENN Communicator and perform a recall for an Alert Emergency and a roll call in accordance with Checklist 2 and standby to transmit a message.
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RQ-JP-91 002-003 JPM STEPS START TIME FOR TIME CRITICAL:
TIME CRITICAL 0 STEP I CRITICAL (.)
SAT Dc UNSAT D.tc Locate PRIMARY Recall System Remote Activation Instructions Note:
The Emergency Preparedness Primary Recall System Remote Activation Instructions should be located in the middle drawer(Labeled ENN Communicator) of the file drawer on the Shift Supervisor Area Of The Simulator.
- Envelope Located STEP 2 CRITICAL (.)
SAT D.c UNSAT Dc Call Emergency Recall System Note:
The requirement for using 9 prior to dialing the number will depend on which phone the Examinee uses.
If the Plant Vogtle PBX System Phones are used a 9 will be required.
If a Bell South Outside Line is used, dialing 9 prior to the to the number is NOT required.
- Dial 554-4316 STEP 4 CRITICAL (,)
SAT D.
UNSAT D.c Scenario ID
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- Enter {91 7 566 662} followed by the(pound sign) # sign STEP 3 CRITICAL (.)
SAT D
UNSAT D
- Enter {934 987 509} followed by the # sign Scenario Activation Password 5
RQ-JP-91 002-003 JPM STEPS STEP 5 CRITICAL (.)
SAT D.c UNSAT Dec Start Scenario Note:
The (pound sign) # should only be pressed AFTER the completion of the message the scenario is building D
- Press {3}
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- Press (pound sign) # and hang up STEP 6 CRITICAL (*)
SAT EL UNSAT Dc Verify Recall System Working Properly D
- Extension 3652 called by the recall system STEP 7 NON-CRITICAL (.)
SAT Dc UNSAT D.c Initiate roll call Note:
The Emergency Response Telephone Directory, or the dial code card, should be consulted as needed for required ENN dial codes.
The dial code,
, should be used initially to ring ALL required agencies.
D
- Burke County notified (# 1)
O
- GEMA notified (# 1)
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- Aiken County notified (# 1)
D
- SRS notifed # 1)
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- Allendale County notified (# 1)
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- State of South Carolina notified (# 1)
D
- Barnwell County # 1)
CUES:
(# 1)
DO NOT respond when ENN communicator performs a roll call. If requested, provide cue that NONE of the emergency centers hailed has responded.
6
RQ-JP-91 002-003 JPM STEPS STEP 8 CRITICAL (,)
SAT D.c UNSAT Eic Establish Back-Up ENN Conference Bridge.
- Identity to use # 4369 dialed if using plant extension or (1-706-826-4369) if using an outside line.
D
- Identify to use # 4369 entered when asked for a CONFERENCE CODE (1) (2)
CUES:
(1)
When the candidate dials 4369, the booth instructor can answer and talk with the candidate in the instructor booth. (Exam security NOT to use the real bridges)
(2)
When proper number identified, provide the cue that there are Beeping Tones on the phone at this time if there is no one to answer in the Sim booth.
STEP 9 CRITICAL (.)
SAT L7,s UNSAT 12r Initiate roll call s.D
- Burke County notified
(# 1)
D
- GEMA notified (# 1)
- Aiken County notified (# 1)
D
- SRSnotifed(#1)
- Allendale County notified (# 1)
D
- State of South Carolina notified (# 1)
- Barnwell County (# 1)
CUES:
(# 1)
When requested, provide cue that each Emergency center hailed has responded.
STEP 10 SAT UNSAT L1 Transmit fascimile Note:
On the Fax machine in the Simulator, the pushbutton labelled NOTIFY(Training) should be identified as the button to simulate NOTlFY A cue to the examinee should be provided NOT to depress any pushbuttons for Exam Security.
D
- Place message face down in transmit tray
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- NOTIFY(Training) pushbutton SIMULATED depressed (# 1)
CUES:
(# 1)
When proper button is identified, provide the cue that Notification via the Fax has been performed (DO NOT let Examinee depress any of the buttons).
7
RQ-JP-91 002-003 JPM STEPS STEP 11 CRITICAL (,)
SAT Eic UNSAT D Communicate notification via ENN Note:
Examiner should arbitrarily pick a number between I and 100 and verify that the authentication codeword is correctly identified by examinee.
D
- Lines 1 & 2 transmitted
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- Line 2, Notification time & date completed (1)
.D
- Site data and Control Room confirmation phone number transmitted CUES:
(# 1)
After completion of Emergency Notification form line 2, provide the following cue, The State of South Carolina request that you authenticate number 27 (Mustang).
STOP TIME FOR TIME CRITICAL:
STEP 12 CRITICAL (,)
SAT D.
UNSAT D Message authentication Note:
The authentication codes are located in the Emergency Response Telephone Directory.
The codeword provided should match the number given in the cue of JPM Step 3.
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- Authentication codeword correctly provided.
STEP 13 CRITICAL (,)
SAT Dc UNSAT Dc Transmit classification data
.D
. Emergency Classification D
- Emergency description
- Protective Action Recommendations U
- Emergency Release Data Not occurring 8
RQ-JP-91 002-003 JPM STEPS STEP 14 CRITICAL (,)
SAT D UNSAT Dc Transmit current plant radiological I plant conditions El
- Release significance
- Event prognosis D
- Current meteorological data I
- Declaration Time and Date
- Affected Unit(s)
- Unit Status
- Remarks
- Approved by Date and Time
- Notified by Date and Time STEP 15 SAT D.
UNSAT Dc Notify ED
- Initial Emergency Notification completed Field Notes:
9
SOUTHERNA COMPANY
?rgy to Serve Your World
,PQ 1
PLANT VOGTLE tj.t7° 1
K.!
A 5f I -
)L ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-91 301-001 STAY TIME CALCULATION FOR EMERGENCY EXPOSURE To PROTECT VALUABLE PLANT EQUIPMENT Revision 1 June 13, 2007 Written By
- Thad N. Thompson Date: June 13, 2007 Approved By
- R. Lee Mansfield Date: June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
During a Loss of Emergency Coolant Recirculation event, it has been discovered that cooling water was valved out to RHR pump A during emergency maintenance. The pump has been restarted and motor winding temperatures are slowing rising. Cold Leg Recirculation has been established with RHR pump A.
An Alert Emergency has been declared for this event.
You have been authorized by the Emergency Director to receive an Emergency Exposure to protect RHR pump A motor from damage by opening 1-1202-U4-096 and 1-1202-U4-097 NSCW cooling water inlets/outlets.
You are to be briefed by Health Physics on the anticipated dose for the areas to traverse to RHR pump room A and inside the pump room.
Your current TEDE dose for this quarter is 500 m/r.
Assigned Task:
Calculate your maximum stay time so as not to exceed your Emergency Exposure Limit.
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RQ-JP-91 301-001 JPM STEPS START TIME:
STEP I CRITICAL (*)
SAT D UNSAT Dc Determine Maximum Stay Time to open NSCW cooling water valves to RHR pump A motor.
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- Maximum stay time in RHR pump room A determined to be 3.8 minutes (3 minutes 48 seconds)
(Acceptance critera + or 5%).
NOTE: (1) (2) (3) (4)
NOTE:
(I)
Transit time from stairwell to and from pump room = 1 minute @ 3ORIHr = 0.5 R transit dose.
(2)
Dose in pump room = 150 RIHr or 2.5 Rlminute.
(3)
IOR Exposure Limit 0.5 R transit = 9.5 R in pump room. 9.5 R/ 2.5 R minute = 3.8 minutes.
(4)
Students are provided with Level D aux. building map and survey map of RHR A pump room with dose projections on each and estimated transit time.
STOP TIME:
Field Notes
SOUTHERN COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE LO-JP-1 4915-002 CALCULATE QUADRANT POWER TILT RATIO THIS ISA MODIFIED JPM FOR THE HL-14 NRC Ex.4M (RO VERSION)
Revision 3 June 13, 2007 Written By
- Thad N. Thompson Date:
06/13/2007 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
The unit is at 100% power.
Assigned Task:
The USS has directed you to Perform a QPTR Calculation using 14915, Special Conditions Surveillance Logs.
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LO-JP-1 491 5-002 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 14915-1
. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a ©... are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to examinee during performance of this JPM. This JPM provides data for two different conclusions (QPTR> or< 1.02).
REQUIRED ITEMS:
1.
14915, Special Conditions Surveillance Logs 2.
Unit 1 Plant Technical Data Book (Tab 5.0)
SIMuLATOR SETuP:
1.
Not applicable Setup time: Not applicable This JPM is based on the Current Unit I Cycle. The Unit I PTDB Normalization Factors should be used to calculate the QPTR.
DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.
INITIAL CONDITIONS:
The unit is at 100% power.
ASSIGNED TASK:
The USS has directed you to Perform a QPTR Calculation using 14915, Special Conditions Surveillance Logs.
4
LO-J P-I 491 5-002 START TIME:
JPM STEPS STEP I CRITICAL (,)
SAT Dec UNSAT Qis Record provided detector data on DSP-I 4915-1.
D
- Upper detector currents recorded on DSP-i 491 5-1.
D
- Lower detector currents recorded on DSP-I 4915-1.
STEP 2 CRITICAL (,)
SAT Dc UNSAT Dc Determine QPTR Note:
If this JPM is being PERFORMED, ensure the Unit I PTDB Normalization Factors are used. The attachment should be provided to the examinee for performance of this step.
.D
- Upper detector currents normalized (see note above)
D
- Average upper detector current calculated D
- Lower detector currents normalized (see note above)
.D
- Average lower detector current calculated E1
. QPTR determined to be> 1.02 (1.03 Upper and 1.04 Lower)
STEP 3 SAT LJ UNSAT c Report to USS D
- Upper and lower QPTR is> 1.02 STOP TIME:
Field Notes 5
PROVIDE DATA ON THIS PAGE TO STUDENTS FOR CALCULATION NI Channel Detector Current N41 A
424 mA N42 A
380 mA N43 A
450 mA N44 A
415 mA N41 B
450 mA N42 B
395 mA N43 B
460 mA N44 B
425 mA NORMALIZATION FACTORS FROM UNIT I PTDB N4IA (Top) 1.130 N42A (Top) 1.152 N43A (Top) 1.048 N44A (Top) 1.145 NORMALIZATION FACTORS FROM UNIT I PTDB N4IB (Bottom) 1.052 N42B (Bottom) 1.087 N43B (Bottom) 1.000 N44B (Bottom) 1.072 6
Calculation of QPTR (do not provide to students)
NORMALIZATION FACTORS FROM UNIT I PTDB N4IA (Top) 1.130 X 424 = 479.12 N42A (Top) 1.152 X 380 = 437.76 N43A (Top) 1.048 X 450 = 471.6 N44A (Top) 1.145 X 415 = 475.175 Average = 465.914 QPTR = 479.121465.914 = 1.03 NORMALIZATION FACTORS FROM UNIT I PTDB N41 B (Bottom) 1.052 X 450 = 473.4 N42B (Bottom) 1.087 X 395 = 429.365 N43B (Bottom) 1.000 X 460 = 460 N44B (Bottom) 1.072 X 425 = 455.6 Average = 454.591 QPTR = 473.4 I 454.591 = 1.04 7
SOUTHERN COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 4405-002 BORIC INJECTION FLOW PATH VERIFICATION THIS Is A MODIFIED JPM FOR THE HL-14 NRC ExAM (SRO VERSION)
Revision 0 June 13, 2007 Written By
- Thad N. Thompson Date: June 13, 2007 Approved By
- R. Lee Mansfied Date: June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
The plant is at 100% power. During an inspection of HV-8801A MCC breaker, a dropped tool resulted in a short in the breaker bucket. The SS has declared HV-8801A to be INOPERABLE and entered LCO 3.5.2 for ECCS.- Operating.
Also, the crew has just entered AOP-1 8007-C section A for Total Loss of Charging Flow due to an apparent failure of FV-0121 to the closed position. Maintenance investigation estimates 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for repair.
The SS has directed for you to perform the following and advise him of any additional applicable Tech Spec or TRM LCOs (if any) and Conditions that would apply.
Assigned Task:
Perform 14405-1, Boron Injection Flow Path Verification
RQ-J P-I 4405-002 Evaluation Method
[ ] Performed
[ ] Simulated Evaluation Location
[ ] Simulator
[ ] Control Room
[ ] Unit 1
[ ] Unit 2 Performance Time:
OVERALL JPM EVALUATION
[] SATISFACTORY
[ ] UNSATISFACTORY Examiner Comments:
JPM INFORMATION OPERATORS NAME:
EVALUATION DATE:
/
I JPM TITLE:
REVISION:
COMPLETION TIME:
Boron Injection Flow Path Verification 0
June 13, 2007 Application:
K/A Number:
10 minutes ROISRO G2.2.1 2 RO 3.0 SRO 3.4 Examiners Signature:
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RQ-JP-1 4405-002 JPM STEPS START TIME:
STEP I CRITICAL (*)
SAT Eis UNSAT D Perform Boron Injection Flow Path Verification per 14405-1.
- Obtains SS Approval and fills in Date, Time and Mode.
Verifies steps 5.1.a 14225-1 Operations Surveillance Logs is active. (# 1)
Verifies steps 5.1.b 14705-1 Boron Injection Flow Rate Verification is active. (# 1)
Verifies steps 5.1.c 14811-1 BA Transfer Pump & Discharge Check Valves Inservice active. (# 1)
Verifies steps 5.1.d 14808-1 CCP & Check Valves 1ST & Response Test is active. (# 1)
Verifies steps 5.1.e 14000-1 Operations Shift & Daily Surveillance Logs is active. (# 1)
Identifies 2 acceptable Boron Injection Flow Paths per Figure 1 are NOT available. (NOTE: 2)
D
- Determines Acceptance Criteria NOT met and refers to TR 13.1.3 for Boration Flow Paths Operating D
, Determines Condition A requires shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if flow paths not returned to OPERABLE.
CUES:
(1)
The surveillance is active.
NOTES (2)
Two paths must NOT share any active components on figure 1. All the flow paths would go through HV-8801 B (an active component). Therefore, there are NOT two Boric Acid Flow Paths Available. The TRM 13.1.3 is NOT met and Condition A should be entered.
STOP TIME:
Field Notes
SOUTHERN COMPANY Energy to Serve Your Worlit PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-91 001-015 CLASSIFY AN EMERGENcY EVENT, FILL OUT NOTIFICATION FORMS AND MAKE PAR REc0MMMENDATI0Ns THIS Is A NEW JPM FOR HL-14 NRC ExAM Revision 0 June 13, 2007 Written By
- Thad N. Thompson Date:
6/13/07 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information descrThes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
Unit 1 DBA SGTR in progress on SG # 4.
A Main Steam Safety is lifting for SG # 4 and will not reseat. Visual indication confirms steam blowing out of the safety valve. High radiation in the area wifl prevent maintenance gagging the valve within the next hour.
Chemistry reports RCS coolant activity is 411 micro Curies per gram Equivalent 1-131.
PAGs dose at the site boundary is expected to be> 1.0 Rem TEDE.
Wind direction is from 94.26 degrees, there is no precipitation, wind speed is 4.0 mph with a stability class of D Neutral.
Assigned Task:
You have been directed to Determine the HIGHEST emergency classification level based on events which are in progress and PARS if applicable, considering past events, and their impact on the current plant conditions and take appropriate actions for notification of state and local authorities.
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RQ-JP-91 001-015 JPM STEPS START TIME:
STEP I CRITICAL (,)
SAT D
UNSAT Ds Classify the event EJ
- Plant conditions evaluated EJ
- Emergency event classified as a General Emergency (Loss of 3 barriers) within 15 minutes.
5
RQ-JP-91 001-015 JPM STEPS STEP 2 CRITICAL (.)
SAT Dc UNSAT D Fill out notification form. (NOTE 1)
- Line 1 block A for this is a drill checked, Message # left blank for ENN Communicator
- Line 2 block A for INITIAL checked, Notification: Time and Date and Authentication left blank.
- Line 3 Vogtle 1 filled in, Confirmation Phone # left blank.
- Line 4 block D for GENERAL EMERGENCY checked and event description filled in.
- Line 5 block B checked to EVACUATE 05 mile radius and downwind to 10 miles.
ZONES affected should be listed as A, B5, C5, D5, E5, F5, 15, J5, K5, ClO, D10, ElO (These are thePAR 3 recommendations)
- Line 5 block D checked to Advise Remainder of EPZ to monitor Local Radio I TV Stations / TARS for additional information and consider the use of KI ) potassium iodide) in accordance with State plans and policy.
.D
- Line 6 block B checked for EMERGENCY RELEASE is occurring.
- Line 7 block C checked for RELEASE SIGNIFICANCE above normal operating limits.
- Line 8 for EVENT PROGNOSIS, candidate checks the block he feels is appropriate.
U
- Line 9 METEOROLOGICAL DATA filled in according to turnover.
D
- Line 10 block A checked for DECLARATION with proper time and date filled in.
- Line 11 block 1 checked for AFFECTED UNIT(S)
- Line 12 block 1 check and appropriate power and shutdown time, etc. filled in.
- Line 13 REMARKS filled in.
- Line 14 through Line 16 NOT REQUIRED ON AN INITIAL NOTIFICATION.
O
- Line 17 Approved by HL-14 candidate signature and time/date filled in within 15 minutes. (2)
- Line 17 Notified by left blank for the ENN Communicator.
NOTE:
(1)
Evaluator will have markups of expectations for notification form attached with JPM with proper dates, etc. filled in at time of exam.
(2)
When candidate bring forward notification form, this will stop his 15 minute notification clock.
STOP TIME:
Field Notes 6
SOUTHERNA COMPANY Energy to Serve Your Worlif PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-91 301-002 STAY TIME CALCULATION FOR EMERGENCY EXPOSURE To LIMIT DOSE FOR PROTECTION OF LARGE POPULATION (SRO VERSION)
Revision 0 June 13, 2007 Written By
- Thad N. Thompson Date: June 13, 2007 Approved By
- R. Lee Mansfield Date: June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
During a LOCA Outside Containment event, it has been discovered that a release flow path from Train A RHR to the RWST exists. Power has been lost to the RHR Train A isolation valves.
A General Emergency has been declared for this event and wind direction is currently blowing toward heavily populated areas.
You are the Emergency Director and need to authorize an Emergency Radiation Exposure to perform actions to isolate the LOCA.
Two System Operators (SOs) have been selected (not volunteers) by the OSC to perform manual valve manipulations required to isolate the LOCA. The following is the yearly exposure for the SOs to be dispatched to perform the local isolations in the RHR pump rooms.
J. Smith John Doe 300 mrem 400 mrem SSN: 123-45-6789 SSN: 987-65-4321 TLD #12345 TLD #54321 No previous emergency No previous emergency exposure history.
exposure history.
HP has determined the dose rates to be received by the SOs in the RHR pump room to be 35 rem/hr.
Assigned Task:
Calculate the maximum stay times for the SOs to remain on station and not exceed the emergency radiation exposure limits and complete Date Sheet 1 of 91301-C, Permit for Emergency Radiation Exposure. Round the calculation for minutes to 1 decimal place.
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RQ-JP-91 301-002 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91301-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a © are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the exam inee during the performance of this JPM.
REQuIRED ITEMS:
1.
Procedure 91301-C, Emergency Exposure Guidelines.
2.
Calculator SIMULATOR SETuP:
Simulator not required for JPM performance DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.
INITIAL CONDITIONS:
During a LOCA Outside Containment event, it has been discovered that a release flow path from Train A RHR to the RWST exists. Power has been lost to the RHR Train A isolation valves.
A General Emergency has been declared for this event and wind direction is currently blowing toward heavily populated areas.
You are the Emergency Director and need to authorize an Emergency Radiation Exposure to perform actions to isolate the LOCA.
Two System Operators (SOs) have been selected (not volunteers) by the OSC to perform manual valve manipulations required to isolate the LOCA. The following is the yearly exposure for the SOs to be dispatched to perform the local isolations in the RHR pump rooms.
J. Smith John Doe 300 mrem 400 mrem SSN: 123-45-6789 SSN: 987-65-4321 TLD # 12345 TLD #54321 No previous emergencyexposure history No previous emergency exposure history.
HP has determined the dose rates to be received by the SOs in the RHR pump room to be 35 rem/hr.
Assigned Task:
Calculate the maximum stay times for the SOs to remain on station and not exceed the emergency radiation exposure limits and complete Data sheet 1 of 91 301-C, Permit for Emergency Radiation Exposure. Round the calculation for minutes to 1 decimal place.
RQ-JP-91 301-002 START TIME:
JPM STEPS STEP I CRITICAL (,)
SAT D
UNSAT Dc Determine Maximum Stay Time to isolate RHR LOCA Outside Containment to protect large public population area.
D
. Maximum stay time in RHR pump room A determined to be 42.9 minutes (42 minutes 54 seconds) for both operators. Previous exposure does not apply toward the Emergency Exposure Limit. (NOTE 1)
NOTE:
(1) Dose projection = 25 Rem / 35 Rem / Hr dose rate = 42.9 minutes (.9 X 60 54 seconds)
Acceptance Criteria is + or 5%.
STEP 2 CRITICAL (.)
SAT Ei UNSAT Dc 91301-C date sheet I properly completed for I System Operator.
D
- Exposure # 1 entered.
- Prepared by date / time I blocks completed.
D
- Protection of large population circled.
- Task description filled in.
D
- Dose limit 25 Rem D
- Projected dose from step 1 of JPM (N/A)
D
- Health Physics Supervisor signature.
D
- ED approval or signature or initials of person receiving verbal authorization to exceed 1 OCFR2O exposure limits.
NOTE:
(1) Dose projection = 25 Rem / 35 Rem / Hr dose rate = 42.9 minutes (.9 X 60 = 54 seconds)
STOP TIME:
Field Notes
SOUTHERN COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE V-LO-J P-I 0008-001 LOSF EvALuATIoN THIS ISA BANK JPM FOR THE HL-14 NRC EXAM Revision 0 June 13, 2007 Written By:
Thad N. Thompson Date:
6/13/2007 Approved By: R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
With DC lA out of service for corrective maintenance, a loss of I BY2B occurs due to a fault on inverter 1 BD1 112.
1 BY2B is subsequently reenergized via the regulated transformer power source.
Assigned Task:
The SS has directed you to use 10008-C and determine what LCO conditions are required to be entered and if a LOSF exists. Using a highlighter, also trace the flowpath utilized on the 10008-C Figure 5 LOSF Evaluation Flowchart. Identify any LCO conditions and determine whether an LOSE exists.
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START TIME:
STEPI CRITICAL (,)
SAT D.s UNSAT Dc LCO Conditions Identified Note:
The previously in effect LCO Conditions may be identified but are not required for satisfactory performance.
D
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.D
- TS LCO 3.8.9 Condition B (may be identified as temporarily being entered prior to bus reenegization)
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SAT UNSAT D.ec LOSF Evaluation Note:
LOSF exists via inoperability of both DGs (DG A initially OOS and declaration of DB ¶B via IBDIII2 support inoperability to the ¶8 sequencer).
C
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J
- Performs LOSF Evaluation (Step 3.5.6) of 10008-C
.D
- Determines YES to LOSE present STEP 3 CRITICAL (,)
SAT Dc E1 LJ STOP TIME:
UNSAT D LCO Conditions Identified
- TS LCO 3.8.1 Condition F identified to be entered due to the LOSE exists determination
- TS LCO 3.8.1 Condition G and B (specifically note the offsite source verification) identified to be entered STEP 4 SAT D.
UNSAT Lic Report to USS
.LJ
- LCO conditions identified and LOSE exists determination made Field Notes
SOUTHERNA COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE LO-JP-1 4915-002 CALcuLATE QuADRANT POWER TILT RATIO THIS IS A MoDIFIED JPM FOR THE HL-14 NRC EXAM (SRO VERSION)
Revision 3 June 13, 2007 Written By
- Thad N. Thompson Date:
06/13/2007 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
Initial Conditions:
The unit is at 100% power.
Assigned Task:
The USS has directed you to Perform a QPTR Calculation using 14915, Special Conditions Surveillance Logs. Determine appropriate LCO Entry, Conditions, and Required Actions (if any) 2
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LO-JP-1 4915-002 JPM STEPS START TIME:
STEP I CRITICAL (,)
SAT Dc UNSAT Eic Record provided detector data on OSP-1 4915-1.
fl
- Upper detector currents recorded on OSP-1 491 5-1.
D
- Lower detector currents recorded on OSP-i 491 5-1.
STEP 2 CRITICAL (+)
SAT Ds UNSAT D.c Determine QPTR Note:
If this JPM is being PERFORMED, ensure the Unit I PTDB Normalization Factors are used.
The attachment should be provided to the examinee for performance of this step.
l
- Upper detector currents normalized (see note above)
.U
- Average upper detector current calculated LJ
- Lower detector currents normalized (see note above)
D
- Average lower detector current calculated D
- QPTR determined to be> 1.02 (1.03 Upper and 1.04 Lower)
STEP 3 CRITICAL (.)
SAT D UNSAT D
Determine LCO entry and Conditions and Required Actions
.D
- LCO 3.2.4 for Quadrant Power Tilt Ratio must be entered Condition A
- Reduce THERMAL POWER to < 88% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Al) AND D
- Perform a QPTR calculation (SR3.2.4.1)(A2.1) every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND D
- Limit THERMAL POWER to < 88% (A.2.2) AND
.D
- Perform SR 3.2.1.1 and SR 3.2.2.1 (A.3) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of stabilizing power < 88% and once per 7 days after.
U Perform a Safety Analysis (A.4) AND Calibrate Excore Detectors (A.5) to show QPtR < 1.00 prior to increasing THERMAL POWER to > 88%.
D
- Perform SR 3.2.1.1 and SR 3.2.2.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reaching RTP (A.6) OR 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of increasing THERMAL POWER> 88% (A.6) 5
LO-JP-14915-002 JPM STEPS STEP 3 SAT I UNSAT Report to SS
- Upper and lower QPTR is> 1.02 STOP TIME:
Field Notes 6
PROVIDE DATA ON THIS PAGE TO STUDENTS FOR CALCULATION NI Channel Detector Current N41 A
424 mA N42 A
380 mA N43 A
450 mA N44 A
415 mA N41 B
450 mA N42 B
395 mA N43 B
460 mA N44 B
425 mA NORMALIZATION FACTORS FROM UNIT I PTDB N4IA (Top) 1.130 N42A (Top) 1.152 N43A (Top) 1.048 N44A (Top) 1.145 NORMALIZATION FACTORS FROM UNIT I PTDB N4IB (Bottom) 1.052 N42B (Bottom) 1.087 N43B (Bottom) 1.000 N44B (Bottom) 1.072 7
SOUTHERNA COMPANY Energy to Serve Your Worid PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 3431-001 SHUTDOWN I 20V AC I E VITAL INVERTER DuRING Loss OF ALL AC THIS Is A NEW JPM FOR THE HL-14 NRC ExAM (THIS JPM REQUIRES AN RCA ENTRY)
Revision 0 June 12, 2007 Written By
- Thad N. Thompson Date:
6/12/2007 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
REMEMBER: All steps required for this task are to be simulated.
Plant equipment is not to be operated.
Initial Conditions:
Unit____ control room has experienced a prolonged Loss of All AC Power.
1 25V 1 E DC Bus voltage has lowered to less than 105V DC.
Assigned Task:
You have been directed by the SS to shutdown 1 20V AC 1 E Vital Inverter per SOP-I 3431, 12OVAC 1E Vital Instrument Distribution System 4.3.2 for 1BDI 112 Inverter Shutdown. Once the inverter is shutdown, open the associated battery breaker for
____BD1.
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RQ-JP-1 3431-001 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 13432-1/2. Verify this JPM is in accord with the latest procedural revision prior to use. Cues designated by (#) are to be provided to the exam inee during the performance of this JPM.
REQuIRED ITEMS:
1.
13431-1/2, 12OVAC 1E Vital Instrument Distribution System 2.
EDRD Dosimetry COMPONENT LOCATION:
Unit 1/2 Train B: Level B Control Building (Battery Breaker & Switchgear)
Unit 1/2 Train B: Level I Auxiliary Building (Inverter)
RWP required.
DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.
REMEMBER: All steps required for this task are to be simulated.
Plant equipment is not to be operated.
INITIAL CONDITIONS:
Unit control room has experienced a prolonged Loss of All AC Power. 1 25V DC 1 E Bus BDI voltage has lowered to less than 105V DC.
ASSIGNED TASK:
You have been directed by the SS to shutdown 120V AC 1 E Vital Inverter per SOP-i 3431, 120V AC 1E Vital Instrument Distribution System section 4.3.2 for 1BD1I12 Inverter Shutdown. Once the inverter is shutdown, open the associated battery breaker for 4
RQ-JP-1 3431-001 JPM STEPS START TIME:
STEP I SAT fl UNSAT Uc This is located in Control Builing Level B.
Procedure 13431, section 4.3.2 selected.
U
- Verifies closed the applicable Battery Breaker BD1-O1. (#)
CUE:
(#) The breaker red light is illuminated OR the breaker position indicator flag is red and reads CLOSED.
STEP 2 CRITICAL (*)
SAT D.e UNSAT D NOTE: This is located in the Auxiliary Building Level I and will require an RWP for entry.
Opens the INVERTER OUTPUT Breaker EJ
- lnverter BD1 112 Output Breaker OPEN. (#)
CUE:
(#) Give indication the toggle switch is showing open.
.D
(#) Give indication the toggle switch is showing open.
- Inverter BD1 112 DC INPUT Breaker OPEN. (#)
STEP 4 SAT EL UNSAT LJ Verifies Inverter completely shutdown.
t1
- Observes zero volts showing on the Inverter AC OUTPUT Voltmeter. (#)
CUES:
(#) Indicate the AC output voltmeter is ZERO V DC.
CUE:
STEP 3 CRITICAL (.)
SAT D.c UNSAT ELs Opens the Inverter DC INPUT Breaker 5
RQ-JP-1 3431-001 JPM STEPS STEP 5 CRITICAL SAT D.ec UNSAT Ei NOTE: This is located in Control Building Level B.
Opens Inverter DC Supply Breaker at 125V DC Switchgear BDI.
sU
- Inverter DC Supply Breaker BD1-04 handswitch taken to Open or Trip push button depressed.
CUES:
(#) Indicate the DC supply breaker BD1-04 open by hand switch green light lit, red extinguished OR by breaker flag showing green and reading OPEN.
STEP 6 CRITICAL (,)
SAT Dc UNSAT D
Opens BDI Battery Breaker E1
- Panel BD1 Battery Breaker BD1-O1 hand switch taken to Open or Trip push button depressed.
CUES:
(#) Indicate the DC supply breaker BD1-04 open by hand switch green light lit, red extinguished OR by breaker flag showing green and reading OPEN.
STEP 7 SAT UNSAT Ds Report to USS D
- Inverter BD1 112 has been shutdown and BD1 Battery Breaker has been opened.
STOP TIME:
Field Notes 6
SOUTHERNA COMPANY Energy to Serve Your WorliT PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 9030-005 MINIMIZE ENVIRONMENTAL AND SECONDARY SYSTEM CONTAMINATION FOLLOWING SGTR Revision 14 June 12, 2007 Written By
- Thad N. Thompson Date:
6/12/2007 Approved By
- R. Lee Mansfield Date:
June 15, 2007
This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you
- S_
understand the task before beginning. You will be allowed access to any item normally used to perform this task.
REMEMBER: All steps required for this task are to be simulated.
Plant equipment is not to be operated.
Initial Conditions:
A steam generator tube rupture occurred on Unit.
Assigned Task:
The USS has directed you to:
Align the Unit SJAE and SPE exhaust to HEPA filters by initiating 13310-_; and Manually close the condensate dump valves(LV-441 5A) manual isolation valve
-1 305-U4-042 (TB-A-TH
); and Align the turbine building sump effluent to the Turbine Building Drain Tanks by placing _-HS-0877 in the RECIRC position.
RQ-JP-1 9030-005 JPM INFORMATION OPERATORS NAME:
EVALUATION DATE:
I
/
JPM TITLE:
Minimize Environmental and Secondary System Contamination Following SGTR REVISION:
14 June 12, 2007 COMPLETION TIME:
10 minutes Application:
ROISRO K/A Number:
055A3.03 RO:
2.5 SRO:
2.7 Evaluation Method
[ ] Performed
[ I Simulated Evaluation Location
[ ] Simulator
[ ] Control Room
[ ] Unit 1
[ I Unit 2 Performance Time:
OVERALL JPM EVALUATION
[ I SATISFACTORY
[] UNSATISFACTORY Examiner Comments:
Examiners Signature:
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RQ-JP-1 9030-005 JPM STEPS START TIME:
Note: Cues should be provided as to damper indications when referenced. Red light illuminated when full open.
Green light illuminated when full closed. Dual indication when intermediate position.
STEP I CRITICAL (*)
SAT D.
UNSAT D.
Transfer Steam Jet Air Ejector discharge to HEPA filter Note:
Damper positions can be verified locally at the dampers or remotely at the HVAC panel.
s.E:J
- Selects section 4.4.4 of SOP-i 3310-1/2 for SJAE Filter Mode Control.
I
- Place SJAE Filter Unit HS-2875 in FILTER.
.D
- Install Caution Tag per 10000-C. (#)
s.D
.LJ
- Verify Bypass Damper HV-2875A CLOSED.
CUE:
(#) The SS will have another operator install a Caution Tag.
STEP 2 CRITICAL (,)
SAT D.
UNSAT D Transfer Steam Packing Exhauster discharge to HEPA filter Note:
Damper positions can be verified locally at the dampers or remotely at the HVAC panel.
.D
- Selects section 4.4.3 of SOP-i 3310-1/2 Steam Packing Exhauster Filter Mode Control EJ
- Place SPE Filter Unit HS-2876 in FILTER.
.U
- Install Caution Tag per 10000-C (#)
D
- Verify SPE Fan starts (Red light above HS-2876)
.D
- Verify Bypass Damper HV-2876A CLOSED.
CUE:
(#) The SS will have another operator install a Caution Tag.
STEP 3 CRITICAL (,)
SAT Dec UNSAT Dc Close condensate dump valve manual isolation valve.
.EI
- Condensate dump isolation 1305-U4-042 located.
.D
- 1305-U4-042 CLOSED.
5
RQ-JP-1 9030-005 JPM STEPS STEP 4 CRITICAL (,
SAT D UNSAT D
Place Turbine Building Sumps on Recriculation.
- Place HS-0877 in the RECIRC position.
. Verify proper valve lineup for Turbine Building Sump Effluent STEP 5 SAT C]
UNSAT Report to USS D
- Condensate Dump Valve 1305-U4-042 isolated.
D
- Turbine Building Sumps in Recirculation Mode.
STOP TIME:
Field Notes EJ 6
SOUTHERNA COMPANY Energy to Serve Your Wor1d PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-1 921 1-007 LOCALLY TRIP THE REACTOR (FAULTED PATH)
THIS IS A MODIFIED JPM FOR THE HL-14 NRC ExAM Revision 0 June 12, 2007 Written By
- Thad N. Thompson Date:
06/12/2007 Approved By
- R. Lee Mansfield Date:
June 15, 2007
RQ-JP-1 9211-007 JPM INFORMATION This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.
THIS IS A TIME CRITICAL JPM G REMEMBER: All steps required for this task are to be simulated.
Plant equipment is not to be operated.
Initial Conditions:
An ATWT is in progress on Unit_____
Assigned Task:
The USS has directed you to Locally open the Unit_____ reactor trip breakers, RTA and RTB. If the trip breakers will NOT open, then trip the Control Rod Drive MG Set output breakers at the Reactor Trip Switchgear.
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RQ-JP-1 9211-007 JPM STEPS START TIME:
TIME CRITICAL STEP I CRITICAL (,)
SAT Oi UNSAT O
(#1) ( WARNING: DO NOT OPEN THE DOORS OR TOUCH ANY EQUIPMENT!)
Locally trip reactor trip breakers Note:
The silver trip pushbuttons on the switchgears exterior are for the bypass breakers. In addition, RTB operation should be simulated using attached photographs.
D
- RTA and RTB located.
D
- Trip pushbutton for each breaker depressed. (#)
WARNING: DO NOT TOUCH ANY EQUIPMENT OR OPEN THE DOORS!
CUE:
(#) The trip breaker does NOT open.
STEP 2 CRITICAL (.)
SAT Eis UNSAT D.
Locally trips the Control Rod Drive MG Set output breakers.
Note:
The candidate coud trip the output breakers by either depressing the TRIP button on the actual breakers (located under the MG Set Hand Switch Panel. However, these doors should NOT be opened. A description of the candidates actions would be sufficient for credit.
The other method (Prefered) to open the MG Set output breakers would be to use the local handswitches and turn to the TRIP position.
s.D
- Control Rod Drive MG Set output breakers OR hand switches located.
.D
- MG Set Output Breaker Handswitch taken to TRIP for both breakers. (# 1)
&D
- Trip pushbutton for both breakers depressed. (# 2) ( WARNING: DO NOT OPEN THE DOORS!)
CUE:
(# 1) The breakers have opened. There is a page announcement of a Unit Reactor Trip.
(# 2) The breakers have opened. There is a page announcement of a Unit Reactor Trip.
RQ-JP-1 9211-007 JPM STEPS STEP 3 SAT l UNSAT U Report to USS fl
- The Control Rod Drive MG Set output breakers have been opened.
. The Reactor Trip Breakers would NOT open.
STOP TIME:
Field Notes