ML093430216
| ML093430216 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/07/2009 |
| From: | NRC/RGN-II/DRS/OLB |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/09-302, 50-366/09-302 | |
| Download: ML093430216 (60) | |
Text
FACILITY NAME: _-=-H.;.;..A..;..;T:...;:C;;.;;.H~ _ _ _ _ _ _ _ _ ___
_....;..H..;.;.,A..;..;T...;:C;..:,.H.:......-_ Section 3 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT SRO WRITTEN EXAM CONTENTS:
oD Draft SRO Written Exam (25Q with ES-401-5 Information)
Location of Electronic Files:
O:\Hatch Examinations\lnitial Exam 2009-302 Submitted By: Bruno Caballero Verified BY:-I---lf---l---W!~-----f-""-"-:"-~~~-
HLT 5 NRC EXAM 2009-302
- 76. 211000G2.2.44 OO1l2/11SBLCINEWIHIGHERfHT2009-302/SRO/ARB/CME 001l2/l/SBLCINEWIHIGHERlHT2009-302/SRO/ARB/CME Unit 2 was operating at 100% power when a transient occurred causing the following conditions/indications:
o APRMs 0% power (100 control rods not full in) o Recirc pumps Both Tripped o RWL -60" to -90" controlled by RFPT 2B o Reactor pressure 843 psig controlled by ERC o SBLC 2A SBLC2A injecting with the following tank level TANK lEVEL 2C41-R601 2R25*S101 P
E R
C E
N T
(
Which ONE of the choices below completes the following statement?
IAW EOP flowcharts, the Shift Supervisor will direct R RWL WL to be _____ and for reactor pressure to be _ _ _ __
A. maintained in the present band; maintained at the present ERC setpoint B. maintained in the present band; lOO°FIhr cooldown rate lowered, but NOT to exceed a 100°Fihr C~ raised to between +3" to +50";
C:'
maintained at the present ERC setpoint D. raised to between +3" to +50";
lOO°F/hr cooldown rate lowered, but NOT to exceed a 100°Fihr
(
Tuesday, September 08, 2009 8:30:53 AM 145
HLT 5 NRC EXAM 2009-302
Description:
Based upon the conditions/indications an ATWS is in progress requiring SBLC injection.
IA W RCA & CP-3 flowcharts. SBLC tank level is indicating Reactor pressure and level are set lAW below 35% (Hot Shutdown Boron Weight - HSBW). With SBLC tank level <35%, CP-3 allows RWL to be raised to +3" to +50" while monitoring power. Reactor pressure will be maintained at its present EHC setpoint until either all rods are inserted or Cold Shutdown Boron Weight is injected.
Maintaining present R RWL WL band would be plausible if the candidate does not recognize the value or the required actions for HSBW, therefore maintains the present band.
Lowering reactor pressure is plausible because with both recirc pumps tripped (Non-ATWS), an aggressive cooldown will be started to minimize thermal stratification. Also if the candidate confuses the actions required when CSBW is injected, commencing a pressure reduction would be valid.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
(
D. Incorrect - See description above.
(
Tuesday, September 08, 2009 8:30:53 AM 146
HLT 5 NRC EXAM 2009-302
( Reference(s) provided to the student:
None KIA: 211000G2.2.44 SLC verify the status and operation of a system, 2.2.44 Ability to interpret control room indications to verifY and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5/43.5/45.12) IMPORTANCE RO 4.2 SRO 4.4 SRO only because of link to 10CFR55.43 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
EOP-CP3-LP-20327, "Level"Level/Power
/ Power Control (CP-3)", EO 201.092.A.02 & .09 Reference(~)
Reference(s) used to develop this question:
EOP-CP3-LP-20327, "Level/Power Control (CP-3)"
31EO-EOP-017-2, "CP-3 ATWS Level Control"
(
(
Tuesday, September 08, 2009 8:30:53 AM 147
HLT 5 NRC EXAM 2009-302
- 77. 21S003G2.1.27 215003G2.1.27 00 1I2/11IRMlNEW 11211 IIRMINEWIHIGHERlHT2009-302/SROIARB/CME Unit 1 is in Startup making preparations to transfer the mode switch to RUN.
All IRMs are reading between 25 on range 9 and 30 on range 10.
I&C reports that ALL IRMs are inoperable for their neutron flux - High trip (will not give trip).
All other requirements of 34GO-OPS-00I-I, "Plant Startup," are met for going to "Run" mode.
of34GO-OPS-001-1, Which ONE of the choices below completes the following statements?
IAW TS Bases 3.3.1.1, the purpose of the IRM Neutron Flux - High function is to monitor lAW neutron flux levels from the upper range of the Source Range Monitors to the lower range of the
_ _ _ _ Power Range Monitors.
IA W with Tech Spec 3.0.4, the Reactor Mode Switch _ _ _ _ be placed in the "RUN" mode.
lAW A. Oscillation; can B~ Average; can
( C. Average; canNOT D. Oscillation; canNOT
(
Tuesday, September 08, 2009 8:30:53 AM 148
HLT 5 NRC EXAM 2009-302 HLT
Description:
Unit 1 TS Bases B 3.3.1.1 "Applicable Safety Analysis LCO, and Applicablility 1a. la. IRM Neutron Flux-High states that IRMs monitor neutron flux levels from the upper range of the Source Range Monitors to the lower range of the Average Power Range Monitors.
OPRMS are plausible because 34GO-OPS-001-l 34GO-OPS-001-1 step 7.4.7 requires confirmation that 3 APRMs
& 3 OPRMs are operable prior to transferring the mode switch to "Run".
TS 3.0.4 states:
"When an LCO is not met, entry into a MODE or other specified Condition in the Applicability shall only be made:
- a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time,"
Since IRMs are not required to be operable in mode 1, the mode switch can be place in "Run".
Plausible if the candidate does not remember 3.0.4 requirements.
A. Incorrect - 1st part; see description above.
2nd part is correct
( B. Correct - see description above C. Incorrect - 1st part is correct 2nd part; see description above.
D. Incorrect - 1st part; see description above.
2nd part; see description above.
(
Tuesday, September 08, 2009 8:30:53 AM 149
HLT 5 NRC EXAM 2009-302
( Reference(s) provided to the student:
None KIA: 215003G2.1.27IRM 2.1.27 Knowledge of system purpose and/or function. (CFR: 41.7)
IMPORTANCE ................ RO 3.9 SRO 4.0 SRO only because of link to 10CFR55.43 (2): Facility operating limitations in the technical specifications and their bases.
LESSON PLAN/OBJECTIVE:
C51-IRM-LP-01202 C51-lRM-LP-01202 EO 012.003.C.02 Reference(s) used to develop this question:
Unit 1 TS 3.3.1.1 Reactor Protection System Instrumentation (page 3.3-1 thru 3.3-6)
Unit 1 Bases 3.3.1.1 (page B3.3-4)
C51-IRM-LP-01202 C51-lRM-LP-01202
(
Tuesday, September 08, 2009 8:30:54 AM 150
HL T 5 NRC EXAM 2009-302
- 78. 216000A2.l4 216000A2.14 001l2/2IRPV INSTRUMENTATIONINEWiHIGHERlHT2009-302/SRO/ARB/CME 00 112/2IRPV INSTRUMENTATIONINEWIHIGHERlHT2009-302/SRO/ARB/CME Unit 2 is operating at 100% reactor power when the "2A" Recirc pump trips.
Which ONE of the following completes both of these statements?
Indicated reactor water level on 2C32-R606A, Band C, "Narrow Range" instruments will initially _ __
IAW IAW with Tech Specs 3.4.1, "Recirculation Loops Operating", the MAXIMUM amount of time allowed to satisify the LCO for Recirc pump single loop operation is hours.
A. increase; Increase; 12 B:' increase; 24 C. decrease; 24 D. decrease; 12
(
Description:
When the Recirc pump trips, indicated reactor water level will increase due to formation of more voids in the core. This additional voided area will increase the backpressure in the downcomer region, causing annulus level to rise. Since RWL is measured in the annulus region, indicated RWL increases. Also the recirc pump, that trips, will stop entraining water from the downcomer region causing indicated RWL to increase.
IAW with Tech Specs 3.4.1, "Recirculation Loops Operating", Condition "A", (Required Action A.l) requires the LCO to be met in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. RWL decreasing is plausible because as voids increase in the core, water level in the core will actually decrease. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is plausible because this is the time requirement for exceeding Condition A.
A. Incorrect - See description above.
B. Correct - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
(
Tuesday, September 08,2009 08, 2009 8:30:54 AM 151
HLT 5 NRC EXAM 2009-302 HLT
( Reference(s) provided to the student:
None KIA: 216000A2.14 Nuclear Boiler Inst.
A2. Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 /45.6)
A2.l4 Recirculation flow: Design-Specific ............................ 2.9 2.92.9 2.9 SRO only because of link to 10CFR55.43 (2): Facility operating limitations in the technical specifications and their bases.
LESSON PLAN/OBJECTIVE:
Reference(s) used to develop this question:
( Tech Specs 3.4.1, "Recirculation Loops Operating", Condition "A", (Required Action A.l)
(
Tuesday, September 08, 2009 8:30:54 AM 152
HLT 5 NRC EXAM 2009-302
- 79. 234000G2.2.25 00 1/2/2IFUEL l/2/2/FUEL HANDLINGIBANKlHIGHERlHT2009-302/SROIARB/CME Fuel movement is in progress on Unit 2 along with control rod un-coupling.
lAW IA W 34GO-OPS-066-0, "Control Rod Withdrawal in Shutdown or Refeul," the Control Room Operator has just withdrawn a control rod to position 48, but the full-in reed switch has NOT been bypassed.
The Refueling Bridge is over the Fuel Pool and loaded with a fuel assembly.
When the Refueling Bridge Operator positions the Refueling Bridge over the proper core coordinates, the Reactor Operator in the Main Control Room informs the Refueling SRO that annunciator 603-238 "ROD OUT BLOCK" is now alarming.
Which ONE of the following describes the impact on the refueling operations and the required action lAW IA W Tech Spec 3.9 "Refueling Operations"?
A'!'
A'! The Refueling Platform should have automatically stopped prior to reaching the Reactor Cavity. Suspension of fuel movement is required after placing the fuel assembly in any available Spent Fuel Pool location.
B. The Refueling Platform should have automatically stopped prior to reaching the reactor cavity. Suspension of fuel movement is required after placing the fuel assembly in any available Core location.
(
C. The Refueling Grapple is prevented from lowering. Bypassing the full-in reed switch is required and then continued fuel movement is allowed.
D. The Refueling Grapple is prevented from lowering. Fully inserting the withdrawn control rod is required and then continued fuel movement is allowed.
Tuesday, September 08, 2009 8:30:54 AM 153
HLT 5 NRC EXAM 2009-302
Description:
TS Bases 3.9 "Refueling Operations" states a control rod not at its full-in position interrupts power to the refueling equipment and prevents operating the equipment over the reactor core when loaded with a fuel assembly. Conversely, the refueling equipment located over the core and loaded with fuel inserts a control rod withdrawal block in the Control Rod Drive System to prevent withdrawing a control rod.
TS Bases 3.9.1 Refueling mterlocks - Criticality and, therefore, subsequent prompt reactivity excursions are prevented during the insertion of fuel, provided all control rods are fully inserted during the fuel insertion. The refueling interlocks accomplish this by preventing loading of fuel into the core with any control rod withdrawn or by preventing withdrawal of a rod from the core during fuel loading.
SRO only because of knowledge ofTS Bases 3.9 which states: "Suspension of in-vessel fuel movement shall not preclude completion of movement of a component to a safe position." The safe position would be to place the fuel assembly back to any fuel pool location and not into any core location.
A. Correct - See description above B. Incorrect - 1st part is correct.
2nd part is incorrect due to description above. Plausible if the candidate believes that a fuel assembly can be placed into any core location. Actually a fuel bundle can be placed into any
( fuel pool location.
C. Incorrect - 1st 1st part is correct.
2nd part is incorrect due to description above. Plausible if the candidate believes that bypassing the full-in reed switch is the only refueling interlock problem and does not remember that bridge travel should have been stopped before reaching the core location.
D. Incorrect - 1st part is correct.
2nd part is incorrect due to description above. Plausible if the candidate believes that inserting the withdrawn control rod is the only refueling interlock problem and does not remember that bridge travel should have been stopped before reaching the core location.
(
Tuesday, September 08, 2009 8:30:55 AM 154
HLT 5 NRC EXAM 2009-302 Reference(s) provided to the student:
None KIA:
KJA: 234000G2.2.25 Fuel Handling Equipment 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations IMPORTANCE RO 3.2 SRO 4.2 and safety limits. (CFR: 41.5 /41.7/43.2) Th1PORTANCE SRO only because of oflink link to 10CFR55.43 (2): Facility operating limitations in the technical specifications and their bases.
LESSON PLAN/OBJECTIVE:
F15-RF-LP-04502 "Refueling" EO 045.018.a.01 & EO 3045.019.a.02 Reference(s) used to develop this question:
F15;;.RF-LP-04502 F15"-RF-LP-04502 "Refueling" TS Bases - 3.9.1 "Refueling Interlocks" TS Bases - 3.9.2 "Refuel Position One-Rod-Out Interlock" TS Bases - 3.9.3 "Control Rod Position"
{
\ Fermi 2009 NRC Exam SRO #18
(
Tuesday, September 08, 2009 8:30:55 AM 155
HLT 5 NRC EXAM 2009-302
- 80. 261000A2.12 001l2/l/SBGT 001/2/1/SBGT RADIMODIFIEDIHIGHERlHT2009-302/SRO/ARB/CME RADIMODIFIEDIHIGHERlHT2009-302/SROIARB/CME
(
Unit 2 is at 100% with fuel movement in progress during cask loading.
Minor damage to a fuel bundle results in the Refueling Floor Area radiation levels reaching 70 mrlhr:
mr/hr:
The "Refueling Floor Vent Exhaust" monitors are reading:
o 2Dll-K634A - 15 mRemlhr o 2Dll-K634B - 14 mRemlhr o 2DII-K634C 2D ll-K634C - 18 mRemlhr o 2Dll-K634D - 19 mRem/hr 2DII-K634D mRemlhr Which ONE of the following predicts BOTH the impact of these conditions on the Unit 1 and Unit 2 Standby Gas Treatment Systems (SBGT) and the procedural requirements?
The total number of SBGTs trains that will automatically start is _ _ __
The Shift Supervisor will direct the entry into _ __
A. two (ONLY);
34AB-DII-001-2, 34AB-Dll-001-2, "Radioactivity Release Control" and perform a Prompt Offsite Dose
( Assessment ONLY B. four; 34AB-DII-001-2, "Radioactivity Release Control" and perform a Prompt Offsite Dose 34AB-Dll-001-2, Assessment AND 34GO-OPS-013-2, "Normal Plant Shutdown" and perform a normal plant shutdown C. two (ONLY);
34AB-DII-001-2, "Radioactivity Release Control" and perform a Prompt Offsite Dose Assessment AND 34GO-OPS-013-2, "Normal Plant Shutdown" and perform a normal plant shutdown D~ four; D'!'"
34AB-DII-001-2, "Radioactivity Release Control" and perform a Prompt Offsite Dose Assessment ONLY
((
Tuesday, September 08, 2009 8:30:55 AM 156
HLT 5 NRC EXAM 2009-302
(
Description:
There are 12 Refuel Floor Process Radiation monitors.
Setpoints:
o 2DII-K634A-D rad monitors for V2 mRJhr U2 .... 5.7 mR/hr o 2DII-K635A-D rad for V2 .... 6.9 mR/hr monitors forU2 radmonitors mRJhr o 2DII-K611A-D rad monitors for V2 U2 .... 18 mR/hr mRJhr With all 4 of the 2DII-K634 rad monitors above the setpoint, alla1144 SBGT systems will auto start.
34AB-DII-001-2 34AB-T22-003-2 "Secondary Containment Control" directs the entry into 34AB-Dll-001-2 "Radioactivity Release Control" which dictates that a Prompt Offsite Dose Assessment must be performed 7373EP-EIP-018-0.
EP-EIP-O 18-0.
For plausibility, the following system operation was considered. Exceeding the setpoint on the "A" and "B" monitors auto start only SBGT "A." The system requires monitors "C" and "D" to reach their setpoints to auto start the "B" fan of SBGT. VI ofSBGT. Ul only has 4 process rad monitors for the Refuel Floor with a setpoint of 18 mRlhr.
mRJhr.
For plausibility, EOP SC flowchart does direct entry into 34GO-OPS-013-2, Normal "Normal Plant Shutdown" after Max Safe is reached in more than one area. The Refuel Floor rad levels are high enough to exceed Max Normal (50 mr/hr) mrlhr) but not high enough to exceed Max Safe (1000 mr/hr) mrlhr) which would require shutting down the plant.
( A. Incorrect - See description above.
B. Correct - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
(
Tuesday, September 08, 2009 8:30:55 AM 157
HLT 5 NRC EXAM 2009-302
( Reference(s) provided to the student:
None KIA: 261000A2.12 SGTS A2. Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /45.6)
A2.12 High fuel pool ventilation radiation: Plant-Specific ...................... 3.23.4 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
T46-SBGT-LP-03001, "Standby Gas Treatment System" 030.006.a.Ol Reference(s) used to develop this question:
(
34AB-T22-003-2, "Secondary Containment Control" 34AB-DI1-00l-2 34AB-DII-OOl-2 "Radioactivity Release Control" Tuesday, September 08, 2009 8:30:55 AM 158
HLT 5 NRC EXAM 2009-302
- 81. 264000A2.09 001l211IEDGINEWIHIGHERlHT2009-302/SROIARB/CME 00 1I2/1/EDGINEWIHIGHERlHT2009-302/SROIARB/CME Both Units are operating at 100% power with all systems normally aligned when a siesmic event switchyard and ALL offsite power is lost to BOTH units. A SO has been damages the switchyard dispatched to monitor EDG parameters.
Current time is 10:00 a.m.
o At 10:05 Unit 1 receives a LOCA signal 10:10 o At 10: 10 Unit 2 receives a LOCA signal Which ONE of the following predicts the impact of the LOSP on the 1B lB Emergency Diesel Generator (EDG) and the Shift Supervisors procedural direction for these conditions?
At 10:01 a.m. EDG lB IB is supplying _ _ _ _ Emergency Bus.
At 10:11 10: 11 a.m. the Shift Supervisor will direct an operator to enter _____
_ _ _ _ the lB IB EDG.
A'!
A"! IF; 34AB-R43-001-2 34AB-R43-00 1-2 "Diesel Generator Recovery" and trip B. 2F; 34S0-R43-001-2 "Diesel Generator Standby AC System" and continue monitoring 34S0-R43-00l-2
( C. 2F; 34AB-R43-001-2 "Diesel Generator Recovery" and trip 34AB-R43-00l-2 D. IF; 34S0-R43-00l-2 34S0-R43-001-2 "Diesel Generator Standby AC System" and continue monitoring Tuesday, September 08, 2009 8:30:56 AM 159
HL HLTT 5 NRC EXAM 2009-302
Description:
34AB-R43-001-2, 'Diesel Generator Recovery' Attachment 3 lists which unit will receive power from the 1BIB EDG. In this case, the 1B IB EDG will supply power to Unit 1 until the LOCA signal IB EDG will not be supplying power to either unit or is received on Unit 2, at which time the 1B will be automatically cycling between the units.
34AB-R22-002-2 "Loss Of 4160V Emergency Bus" Step 4.3.2 states IF SAT 2C AND 2D are NOT available, energize bus from associated Diesel Generator in accordance with 34AB-R43-001-2, Diesel Generator Recovery. 34AB-R43-001-2 states 4.2 LOCA and LOSP ACTIONS 4.2.1 IF concurrent LOCA AND LOSP signals are present on both units, THEN perform the following:
4.2.1.1 IB DIG room, At the 1B IB DIG by depressing the EMERGENCY STOP pushbutton.
TRIP the 1B therefore the IB EDG is tripped locally.
Plausible if the candidate does not remember the need to trip the 1B IB EDG, then continued monitoring of EDG parameters will be done.
(
A. Correct - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
Tuesday, September 08, 08,2009 2009 8:30:56 AM 160
HLT 5 NRC EXAM 2009-302
( Referencels) provided to the student:
Reference(s)
None KIA: 264000A2.09 EDGs A2. Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /45.6)
A2.09 Loss of A.C.
A.c. power ........................................ 3.74.1 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
R43-EDG-LP-02801 "Emergency Diesel Generators" EO 028.025.A.04 Referencels)
Reference(s) used to develop this question:
R43-EDG-LP-02801 "Emergency Diesel Generators"
( 34AB-R43-001-2 "Diesel Generator Recovery"
(
Tuesday, September 08, 2009 8:30:56 AM 161
HLT 5 NRC EXAM 2009-302
- 82. 272000A2.l1 272000A2.11 001l2121RAD 00 1/2/21RAD MONITORINGINEW MONITORINGINEW!FUND/HT2009-302/SRO/ARB/CME
/FUND/HT2009-302/SROI ARB/CME
(
Unit 1 is operating at 100% power when the "lA" RWCU pump develops a severe leak and cannot be isolated. Area temperatures on the 158' Reactor Building are as followed:
Ambient Temperatures:
Pt.2 Hx Room (lG31-N016B)
(lG31-NOI6B)
Pt.3 "A" Pump Room (North) (lG31-N016C)
(lG31-NOI6C)
Differential Temperatures:
Pt.1 Hx Room (lG31-N022AIN023A)
Pt.2 A Pump Room (lG31-N022BIN023B)
Which ONE of the following choices correctly predicts the impact on 1D11-K609A-D IDI1-K609A-D "RB Bldg. Contaminated Area Radiation" monitors AND the action to control these conditions?
When 1D11-K609A-D IDll-K609A-D monitors exceed - _____
- - - - , the Reactor Building HVAC system will isolate.
IAW EOP flowcharts, after the reactor has been shutdown, reactor pressure will be lowered using EOP flowchart _ __ ____ __
( REFERENCE PROVIDED A. 6.9 mr/hr; RC/P maintaining <100 oo P/hr cooldown B:o" 18 mr/hr; B'!
RC/P maintaining <100 oo P/hr cooldown C. 18 mr/hr; CP-l point G "Emergency Depress" CP-1 D. 6.9 mrlhr; CP-1 CP-l point G "Emergency Depress" Tuesday, September 08, 2009 8:30:56 AM 162
HLT 5 NRC EXAM 2009-302
(
Description:
lDll-K609A-D IDI1-K609A-D "Reactor Bldg. Exhaust Radiation" monitors will trip at a setpoint of 18 mrlhr.
Once tripped all supply/exhaust fans and all isolation valves, trip and isolate. After the reactor has been shutdown, reactor pressure will be controlled by RCIP, maintaining < 1Ooop
<100 Ihr o Plhr cooldown. lAW IAW SC/RR SCIRR flowchart, with a primary system discharging, an emergency depress will be required when a Max Safe is exceeded in more that one area. In this question, only one Max Safe temperature has been exceeded (differential temps), therefore, reactor pressure will be RC/P.
controlled by RCIP.
Plausible if candidate remembers the wrong monitor 2D ll-K634A-D "U2 Refuel Ploor Vent Exhaust" trip setpoint of 6.9 mr/hr.
Plausible for emergency depress if candidate does not remember that it takes two Max Safes exceeded in more that one area to emergency depress.
A. Incorrect - 1st part is the wrong exhaust rad monitor setpoint.
2nd part is correct.
B. Correct - See description above.
C. Incorrect - 1st part is correct.
2nd part is incorrect due to NOT having a Max Safe exceeded in more that one area.
( D. Incorrect - 1st part is the wrong exhaust rad monitor setpoint.
2nd part is incorrect due to NOT having a Max Safe exceeded in more that one area.
Tuesday, September 08, 2009 8:30:56 AM 163
HLT 5 NRC EXAM 2009-302
/
( Reference(s) provided to the student:
Table 4 of31EO-EOP-014-1, of 31EO-EOP-014-1, SC/RR Flowchart KIA: 272000A2.11 Radiation Monitoring A2. Ability to (a) predict the impacts of the following on the RADIATION RADlA TION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR:
(CPR: 41.5/45.6) 41.5 145.6)
A2.11 Leakage and/or breaks from contaminated systems to atmosphere or to other process systems .................................... 3.4 3.7 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
DII-PRM-LP-lO007 "Process Rad Monitor" EO 200.030.a.10 D11-PRM-LP-10007 EOP-SCRR-LP-20325 "Secondary Containment / Radioactivity Release Control" EO 201.077.A.02,201.079.A.05.
( Reference(s) used to develop this question:
DII-PRM-LP-lO007 Dll-PRM-LP-10007 "Process RadMonitor" Rad Monitor" EO 200.030.a.10 EOP-SCRR-LP-20325 "Secondary Containment / Radioactivity Release Control" EO 201.077.A.02,201.079.A.05.
31EO-EOP-014-1 SC/RR flowchart
(
Tuesday, September 08, 2009 8:30:56 AM 164
HLT 5 NRC EXAM 2009-302 HLT
- 83. 295001A2.04 00 1I111lRECIRCINEWIHIGHERlHT2009-302/SROIARB/CME OOlI1I1IRECIRCINEWIHIGHERJHT2009-302/SRO/ARB/CME
(
Unit 2 is at operating at 59% power with both Recirc Pumps operating at 48% speed when a transient occurs. Reactor power stabilizes at 57% power with the following Recirc indications:
o "A" and "B" Recirc Pump Speeds ................................... 48%
2B2l-R6llA "TOTAL A FLOW" .................................. 24 Mlbm/hr o 2B21-R611A 2B2l-R6llB "TOTAL B FLOW" .................................. 12 Mlbm/hr o 2B21-R611B The crew performs 34SV-SUV-023-2, "Jet Pump and Recirculation Flow Mismatch Operability" .
Jet Pumps 5 & 6 show a 50% difference from the current average jet pump differential pressures.
IAW IA W Tech Specs 3.4.1, "Recirculation Loops Operating" and 3.4.2, "Jet Pumps" which ONE of the following choices completes both of these statements concerning the operational status of the Recirc Pump loops, AND the MOST LIMITING required actions for the Recirc Loop and JET pump conditions?
The Reactor Recirculation system is considered to be operating in ____ Loop Operation.
The SRO will direct the operator to _ _ __
A. single;
( enter 34S0-B3l-00l-2, " Reactor Recirc System"and raise "B" loop flow within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
34S0-B31-001-2, "ReactorRecirc B~ single; B:t "Normal Plant Shutdown" and be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
enter 34GO-OPS-013-2 Normal C. Two; enter 34S0-B3l-00l-2, 34S0-B31-00 1-2, " Reactor Recirc System"and raise "B" loop flow within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Two; enter 34GO-OPS-013-2 "Normal Plant Shutdown" and be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(
Tuesday, September 08, 2009 8:30:57 AM 165
HLT HL T 5 NRC EXAM 2009-302
(
Description:
Tech Spec Bases is required for the operator to know single or two loop operation.
Tech Spec Surveillences is required for the operator to know that >20% mismatch makes a jet pump inoperable and requires a shutdown.
A. Incorrect - See description above.
B. Correct - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
Reference(s) provided to the student:
NONE KIA:
K/ A: 295001A2.04 Partial or Complete Loss of Forced Core Flow Circulation AA2. Ability to determine and/or interpret the following as they apply to PARTIAL OR
( COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
(CFR: 41.10 / 43.5/45.13) 41.10/43.5/45.13)
AA2.04 Individual jet pump flows: Not-BWR-1&2 ............... 3.0 3.1 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
B31-RRS-LP-00401 "Reactor Recirculation System" EO 200.084.A.01 Reference(s) used to develop this question:
B31-RRS-LP-00401 "Reactor Recirculation System" EO 200.084.A.01 34AB-B21-004-0, "Jet Pump Failure" 34AB-B31-001-2, 34AB-B31-00 1-2, "Reactor Recirculation Pump(S) Trip, Or Recirc Loops Flow Mismatch, Or ASD Power Cell Failure"
(
Tuesday, September 08, 2009 8:30:57 AM 166
HLT 5 NRC EXAM 2009-302 HLT
- 84. 295004G2.1.23 001/111/DC/NEW OOl/1/1/DCINEWIHIGHERlHT2009-302/SRO/ARB/CME IHIGHERlHT2009-302/SROIARB/CME
(
Unit 2 is at 80% power with a normal nonnal plant shutdown in progress due to a loss of 250V DC MCC-2B RX BLDG FEEDER, 2R24-S022.
A transient occurs causing the following conditions:
o APRMs ................................................................ 6%
o RWL ................................................................... -175 inches, going down 2"/min o DW pressure ....................................................... 3.5 psig o Reactor pressure .................................................. 880 psig controlled by LLS o MSNs ................................................................. closed Which ONE of the following completes both statements?
The ____ System can be used for R RWLWL control.
IAW EOP flowcharts, if the current RWL trend continues for the next 5 minutes, the SS will direct the operator to perform perfonn to control RWL.
A. HPCI; 31EO-EOP-114-2, "Preventing Injection Into The RPV From Core Spray And LPCI" B. RCIC;
( 31EO-EOP-114-2, "Preventing Injection Into The RPV From Core Spray And LPCI" C. HPCI; "Tenninating And Preventing Injection Into The RPV" 31EO-EOP-113-2, "Terminating D~
D:' RCIC; "Tenninating And Preventing Injection Into The RPV" 31EO-EOP-113-2, "Terminating
(
Tuesday, September 08, 2009 8:30:57 AM 167
HLT 5 NRC EXAM 2009-302
(
Description:
With 250V DC MCC-2B RX BLDG FEEDER, 2R24-S022 deenergized, the HPCI System will not be available for RWL control due to no power to operate MOVs. RCIC will be used to inject into the RPV but with Rx power above RCIC capability, RWL will continue to lower.
IAW EOP-CP-3, -155" is the lowest level at which injection must be re-established via Table 13 systems. The only high pressure systems available would be RCIC, CRD and SLC. These 3 can put out a combined flow of about 750 gpm (CRD - 300gpm, RCIC - 400gpm, SLC - 50gpm).
At 6% power flow needed would be about 1,500 gpm. So level can not be maintained greater than -185" and an Emerg. Depress. is required.
31EO-EOP-113 to be used prior to an emergency depress. 31EO-EOP-114 CP-3 calls for 31EO-EOP-I13 "Preventing Injection Into The RPV From Core Spray And LPCI" can be used when Drywell pressure is above 1.85 psig. However, it is not allowed when adequate core cooling is not assured. 31EO-EOP-114 is plausible but wrong.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
( D. Correct - See description above.
Reference(s) provided to the student:
None KIA: 295004G2.1.23 Partial or Total Loss of DC Pwr 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10/43.5/45.2 41.10 / 43.5/45.2/45.6)
/ 45.6) IMPORTANCE RO 4.3 SRO 4.4 SRO only because of link to 10CFR55.43 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
Reference(s) used to develop this question:
(
Tuesday, September 08, 2009 8:30:57 AM 168
HL HLTT 5 NRC EXAM 2009-302
- 85. 295005A2.02 OOII1I1/MAIN 00 11111 !MAIN TURBINEINEWIHIGHERJHT2009-302/SRO/ARB/CME TURBINEINEWIHIGHERlHT2009-302/SRO/ARB/CME Unit 2 is operating at 25% power when alarm 650-136 "Vibration Alarm" is received.
The Main Turbine is operating with the following vibration indications:
o Bearing ##lX1X - 11 mils o Bearing #2X - 14 mils o Bearing ##11Y - 10 mils o Bearing #2Y - 10 mils Which ONE of the following completes both statements concerning Main Turbine operation?
IAW with the "Vibration Alarm" ARP, the Unit 2 Main Turbine ___ exceeded the automatic trip setpoint for high vibration.
If continued turbine operation is desired, the LOWEST level of authority required to disable the high vibration trips is the _ __
A. has NOT; Shift Supervisor B. has; Operations Manager C~ has NOT;
( Operations Manager D. has; Shift Supervisor
Description:
34S0-N30-00 1-2 the High vibration trip is 12 mils on any bearing (2 of Per 34S0-N30-001-2 of22 probes for one or more bearings) Per 34AR-650-l36-2 34AR-650-136-2 the Main Turbine High Vibration Trips may be disabled with the OPS Manager and System Engineer approval.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
D. Incorrect - See description above.
(
Tuesday, September 08, 2009 8:30:57 AM 169
HLT HLT 5 NRC EXAM 2009-302
( Reference(s) provided to the student:
None KIA: 295005A2.02 Main Turbine Generator Trip AA2. Ability to detelTIline detennine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: (CFR: 41.10/43.5/45.13)
AA2.02 Turbine Vibration ............................. .2.4 / 2.7 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
N30-MTA-LP-01701 "Main Turbine" EO 017.004.A.02 Reference(s) used to develop this question:
N30-MTA-LP-01701 "Main Turbine"
(
(
Tuesday, September 08, 2009 8:30:57 AM 170
HLT 5 NRC EXAM 2009-302
- 86. 295007A2.01 OOlll12/RX OOll1l21RX PRESSINEWIHIGHERlHT2009-302/SROIARBICME PRESSINEWIHIGHERlHT2009-302/SRO/ARB/CME
(
Unit 2 is at 100% power when a transient occurs causing the following alarm to be received:
REACTOR VESSEL HIGH PRESSURE TRIP (603 -105)
Also as a result of the transient, Torus water level decreases to 88".
The operator controlling Rx pressure reports that ONLY 4 SRVs are operable.
Which ONE of the following identifies the alarm setpoint and the required procedure to control reactor pressure?
The alarm setpoint is psig.
pSlg.
EO-EOP-Ol15-2, "CP-l ", the SS will direct RPV pressure control using _ __
IAW 3 1EO-EOP-O lAW A. 1074; 31EO-EOP-107-2 "Alternate RPV Pressure Control" B. 1055; 31EO-EOP-107-2 "Alternate RPV Pressure Control" C:' 1074;
( 3 1EO-EOP-l 08-2 "Alternate RPV Depressurization" 31EO-EOP-108-2 D. 1055; 31EO-EOP-108-2 "Alternate RPV Depressurization"
(
Tuesday, September 08, 2009 8:30:58 AM 171
HL HLTT 5 NRC EXAM 2009-302
('
\
Description:
ARP 603-105 setpoint is 1074 psig. 1055 psig is plausible since this is the high reactor pressure setpoint per ARP 603-114.
A torus level that can not be maintained greater than 98" requires an Emergency Depress.
4 SRVs is below the limit for the number ofSRVs required for emergency depress (5 required).
Since the minimum is not met, CP-1CP-l requires the SS to direct the operator to use 31EO-EOP-I08-2 "Alternate RPV Depressurization" for reactor pressure control.
31EO-EOP-108-2 31EO-EOP-107-2 31EO-EOP-I07-2 "Alternate RPV Pressure Control" is plausible since this procedure is used for RPV pressure control, but not in this situation.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
D. Incorrect - See description above.
(
(,
Tuesday, September 08,20098:30:58 08, 2009 8:30:58 AM 172
HLT 5 NRC EXAM 2009-302 Reference(sl provided to the student:
Reference(s)
None K/ A:
KIA: 295007 A2.0l High Reactor Pressure 295007A2.01 determine and/or interpret the following as they apply to HIGH REACTOR AA2. Ability to detennine 41.10/43.5/45.13)
PRESSURE: (CFR: 41.10/43.5 / 45.13)
AA2.0 1 Reactor pressure ...................................... 4.1
- 4.1
- SRO only because of link to 10CFR55.43 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
C71-RPS-LP-OlOOl "Reactor Protection System" EO 300.008.a.02 C7l-RPS-LP-01001 Bll-RXINS-LP-04404 "Reactor Vessel Vessellnstrumentation" Instrumentation" EO 200.002.A.12 201.085.A.l5 EOP-CPl-LP-20309, "CP-l" EO 201.085.A.15 Reference(sl used to develop this question:
Reference(s)
( 3lEO-EOP-015-2, "CP-l" 33lEO-EOP-107-2, 1EO-EOP-l 07-2, "Alternate RPV Pressure Control" 3lEO-EOP-108-2, "Alternate RPV Depressurization" 31EO-EOP-I08-2, C7l-RPS-LP-OlOOl "Reactor Protection System" EO 300.008.a.02 C71-RPS-LP-OIOOl BIl-RXINS-LP-04404 "Reactor Vessel BII-RXINS-LP-04404 Vessellnstrumentation" Instrumentation" EO 200.002.A.12 EOP-CPI-LP-20309, "CP-l" EO 201.085.A.15 EOP-CPl-LP-20309,
(
Tuesday, September 08, 2009 8:30:58 AM 173
HLT 5 NRC EXAM 2009-302
- 87. 295012G2.4.11 00ll1l2IDW COOLINGINEWIHIGHERlHT2009-302/SRO/ARB/CME COOLINGINEWIHIGHERlHT2009-302/SRO/ARB/CME Unit 2 is operating at 100% RTP when an electrical problem causes a loss ofDW cooling.
The following conditions exist at 12:00:
UPPER MIDDLE LOWER 2T47-N002: ...... 302°F 2T47-N003: .... 235°F 2T47-N001L:
2T47-NOOIL: .... 195°F 2T47-N010:
2T47-NOlO: ...... 298°F 2T47-N009: .... 233°F 2T47-N004: ...... 193°F 2T47-N001A:
2T47-NOOIA: ... 296°F 2T47-N007: ...... 196°F 2T47-N001K:
2T47-NOOIK: ... 301°F 2T47-N008: ...... 194°F IAW 34AB-T47-001-2 "Complete Loss ofDW Cooling", which ONE of the following choices identifies the time limit allowed for temperature restoration and the required procedural direction if temperature cannot be restored?
If Drywell temperatures cannot be reduced by no later than enter _ __
REFERENCE PROVIDED A. 1230 34GO-OPS-0l3-2 "Normal Plant Shutdown".
( B. 1300 34GO-OPS-0l3-2 "Normal Plant Shutdown".
34GO-OPS-013-2 C~ 1230 C!"
34GO-OPS-014-2 "Fast Reactor Shutdown" D. 1300 l300 34GO-OPS-014-2 "Fast Reactor Shutdown" Tuesday, September 08, 2009 8:30:58 AM 174
HLT HLT 5 NRC EXAM 2009-302
Description:
34AB-T47-001-2 34AB-T4 7-001-2 "Complete Loss of ofDW DW Cooling" contains a subsequent action that if any of the temperatures are exceeded in Attachment 1, then a 30 minute clock starts for restoring temperatures. If this time limit is exceeded, then a fast reactor shutdown will be initiated per 34GO-OPS-014-2.
34GO-OPS-0 14-2.
34GO-OPS-013-2, "Normal Plant Shutdown" is plausible because this is the normal plant shutdown procedure.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time limit is plausible if the candidate thinks the high temperature affects Tech Spec 3.6.1.1, "Primary Containment Operability" (the actual design limit is 340 deg F). The LCO would require contaiment to be restored to operable status in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (a normal shutdown).
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
D. Incorrect - See description above.
( Reference(s) provided to the student:
34AB-T47-001-2 "Complete Loss ofDW Cooling" Attachment 1 without "Maximum 30 minute" column heading KIA: 295012G2.4.11 High Drywell DryweII Temperature 2.4.11 Knowledge of abnormal condition procedures. (CFR: 41.10/43.5/45.13)
IMPORTANCE RO 4.0 SRO 4.2 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
Reference(s) used to develop this question:
34AB-T47-001-2 "Complete Loss ofDW Cooling" Tuesday, September 08, 2009 8:30:58 AM 175
HLT HL T 5 NRC EXAM 2009-302
- 88. 295013A2.01 001l1l21RHR OOl/1/2/RHR TORUS COOLINGIMODIFIEDIFUNDIHT2009-302/SRO/FNF/CME Unit 2 is at 15% power following a refueling outage.
o HPCI is running for surveillence 34SV-E41-002-2, 34SV-E4l-002-2, "HPCI PUMP OPERABILITY".
o Annunciator "TORUS WATER TEMP HIGH" (654-020) alanns alarms o Bulk Suppression Pool temperature reaches 102°F and stab1izes stablizes Which ONE of the choices below completes the following statement?
lAW IAW Tech Specs 3.6.2.1, "Suppression Pool Average Temperature", the Shift Supervisor will direct that suppression pool temperature be monitored, as a MINIMUM, every minutes andlbut HPCI testing continue.
A. 30; can B. 30; canNOT C~ 5; C:-"
can D.5; D. 5*,
( canNOT
Description:
lAW IA W 34AB-T23-003-2 and Tech Spec SR 3.6.2.1.1:
Logging of suppression pool temperature every 5 minutes is required when adding heat to the Torus. 30 minute checking is required if temp is between11O-120 between 1 10-120 and mode switch is placed in shutdown.
Testing is required to be suspended at 105 deg F. The EOPs were entered at 100 deg F and allow for both loops of RHR to be placed in suppression pool cooling. With temperature stable at 102 deg F, testing can continue.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
D. Incorrect - See description above.
(
Tuesday, September 08, 2009 8:30:59 AM 176
HLT 5 NRC EXAM 2009-302 Reference(s) provided to the student:
None KIA: 295013A2.01 High Suppression Pool Temp.
andlor interpret the following as they apply to HIGH SUPPRESSION AA2. Ability to detennine and/or POOL TEMPERATURE: (CPR: 41.10 /43.5/ 45.l3)
/43.5 /45.13)
AA2.01 Suppression pool temperature .......................... 3.84.0 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
T23-PC-LP-0l30l, LT-48 T23-PC-LP-01301, Reference(s) used to develop this question:
Modified from Browns Perry 2008 SRO Exam, question 79 T23-PC-LP-0l301 T23-PC-LP-01301
( 34AB-T23-003-2 Tech Spec SR 3.6.2.1.1.
(
\
Tuesday, September 08, 2009 8:30:59 AM 177
HL T 5 NRC EXAM 2009-302 HLT
- 89. 295019A2.02S OOl/1/1/AIRlNEWIHIGHERJHT2009-302/SRO/ARB/CME OOlil/1/AIRlNEWIHIGHERlHT2009-302/SRO/ARB/CME Unit 2 is at 100% power with the following conditions:
o An un-isolable un-iso1ab1e air line break occurs just downstream of the SSAC air receivers which results in a Control Air header Pressure of 20 psig and going down.
Which ONE of the following completes both of these statements?
Without any operator actions, the 2P52-F565 "Rx Bldg Inst N2 To Non-Int Air El 185 Isol E1185 Iso1 Vlv" will open and _ _ _ _ ___
50AC-MNT-001-0, "Maintenance Program," section 8.1.7, "Emergency Maintenance", the IAW 50AC-MNT-00I-0, Shift Supervisor required to sign the Work Order PRIOR to repairs being performed on the leak.
A. remain remam open; IS B. cycle closed and open; is C. remam open; is NOT
(
D~ cycle closed and open; is NOT 08, 2009 8:30:59 AM Tuesday, September 08,20098:30:59 178
HLT 5 NRC EXAM 2009-302
Description:
IAW 34AB-P51-001-2, "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" a caution prior to step 4.14.6 states:
"Allowing 2P52-F565 to continuously cycle full open to full closed could cause excessive duty on the valve motor and may cause the eventual failure of the motor."
50AC-MNT-001-0, "Maintenance Program," section 8.1.7, "Emergency Maintenance" states that Emergency Maintenance may be performed without a Work Order (WO). In this case, the SS will not have the WO, therefore, the signature is not required. Emergency Maintenance will be documented/reviewed promptly after completion of the work. Section 8.5.9, "Work Authorization" states the applicable Unit SS will authorize plant maintenance.
Plausible because "Limitations" step 6.2.4 states "Approval in the Released for Work block of the Work Order is required for plant related work prior to physical work on plant equipment".
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
( D. Correct - See description above.
(
Tuesday, September 08, 2009 8:30:59 AM 179
HLT 5 NRC EXAM 2009-302 Reference(s) provided to the student:
None KIA: 295019A2.02 Partial or Total Loss of ofInst.
Inst. Air AA2. Ability to detennine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR: 41.10/43.5/45.13)
AA2.02 Status of safety-related instrument air system loads (see AK2.1 AK.2.1 - AK2.19 Below) .................................. 3.6 3.63.7 3.7 AK2.14 Plant air systems ..................................... 3.2 3.2 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
P51-P52-P70-Plant Air-LP-03501 'Plant Air Systems' EO 200.025.B.02 Reference(s) used to develop this question:
(
P51-P52-P70-Plant Air-LP-03501 'Plant Air Systems' 34AB-P51-001-2, "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System"
(
Tuesday, September 08, 08,20098:30:59 2009 8:30:59 AM 180
HLT 5 NRC EXAM 2009-302
- 90. 295030G2.I.20 OOl/III/TORUS LEVELINEWIHIGHERlHT2009-302/SRO/ARB/CME 295030G2.1.20 OOllllllTORUS LEVELINEWIHIGHER/HT2009-302/SRO/ARB/CME Unit 2 was operating at 100% power when a transient resulted in the following conditions:
o Reactor Power ...................... 2.5% (Highest power since scram was 9%)
o Reactor pressure ................... 960 psig maintained by LLS o Reactor water level .............. -85" maintained using RCIC IAW CP-3 flowchart o Torus level ........................... 97 inches and slowly lowering o HPCI ................................... Out of service Which ONE of the following completes both of these statements?
IAW 31EO-EOP-012-2, "PC Primary Containment Control" flow chart, continued operation of the RCIC system allowed.
The NEXT required EOP step the Shift Supervisor will direct the operator to perform is from EOP Flowchart - - - - -
A. IS; CP-I, OPEN 7 ADS valves CP-l, B. is NOT;
( CP-I, OPEN 7 ADS valves CP-l, C. is NOT; CP-3, Terminate & & Prevent ALL injection into the RPV D~ is; CP-3, Terminate & & Prevent ALL injection into the RPV Tuesday, September 08, 2009 8:30:59 AM 181
HLT HLT 5 NRC EXAM 2009-302
\.
Description:
The PC "Primary Containment Control" flowchart requires HPCI to be tripped irrespective of adequate core cooling when Torus level cannot be maintained above 110". RCIC exhaust flowrate is approximately equal to that of decay heat, and is thus consistent with the basis used for determining the Primary Containment Pressure Limit. Also elevated torus pressure will cause the RCIC turbine to trip much sooner than the HPCI turbine, therefore RCIC is allowed to continue to run.
Plausible if candidate remembers that either HPCI or RCIC is securred on Torus level low.
An emergency depressurization is required with Torus level less than 98".
3lEO-EOP-OlS-2, "Alternate Level Control, CP-l, point G for emergency depress, the SS Per 31EO-EOP-015-2, will wait until ALL injection into RPV has been terminiated before giving the order to open 7 EO-EOP-Ol17-2, " "CP-3 ATWS Level Control", when an emergency ADS valves. Per 3 1EO-EOP-O depress is required, CP-3 will direct the SS to order "Terminate & Prevent" before 7 ADS valves can be opened.
Plausible if candidate does not remember that a terminate and prevent in an ATWS must be completed prior to opening 7 ADS valves.
A. Incorrect - See description above.
( B. Incorrect - See description above.
C. Incorrect - See description above.
D. Correct - See description above.
(
08, 2009 8:31 :00 AM Tuesday, September 08,20098:31 182
HLT 5 NRC EXAM 2009-302
( Reference(sl Reference(s) provided to the student:
None KIA: 295030G2.1.20 Low Suppression Pool Wtr Lvi LvI 2.1.20 Ability to interpret and execute procedure steps. (CFR: 41.10 41.10/43.5/45.12)
/43.5/45.12)
IMPORTANCE RO 4.6 SRO 4.6 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
EOP-PC-LP-2031O "Primary Containment Control (PC)" EO 201.075.A.ll & A.l3 EOP-PC-LP-20310 A.13 Reference(sl Reference(s) used to develop this question:
EOP-PC-LP-20310 "Primary Containment Control (PC)"
31EO-EOP-012-2, "PC Primary Containment Control" flow chart Tuesday, September 08,20098:31 08, 2009 8:31 :00 AM 183
HL HLTT 5 NRC EXAM 2009-302
- 91. 295031 295031G2.2.44 00 l/1/1/LOW RWLINEWIHIGHERJHT2009-302/SRO/ARB/CME G2.2.44 OOll1l1/LOW RWLINEWIHIGHERJHT2009-302/SRO/ARB/CME
(
Unit 2 was operating at 100% power when a transient occured causing the following indications:
o 2B21-R623A "Fuel Zone" ........................ -160 inches, decreasing 2"lminute 2"/minute o 2B21-R623B "Fuel Zone" ........................ -163 inches, decreasing 2"lminute 2"/minute o RHR Pump "2D" ................................. Green and White lights are illuminated, Red light extinquished Which ONE of the following completes both of these statements?
RHR pump "2D" has _ __
Reactor water level control will be directed from _ __
A. been manually secured; 31EO-EOP-010-2, "RC" (Non-ATWS) flow chart, RC/L path 31EO-EOP-01O-2, B~ been manually secured; 31EO-EOP-015-2, "CP-1""CP-l" flow chart, Alternate Level Control path C. automatically tripped; 31EO-EOP-01O-2, "RC" (Non-ATWS) flow chart, RC/Lpath 31EO-EOP-OI0-2, RC/L path
(
D. automatically tripped; 31EO-EOP-015-2, "CP-l""CP-1" flow chart, Alternate Level Control path
Description:
EII-RHR-LP-00701 E11-RHR-LP-00701 "Residual Heat Removal System" states when an RHR pump has auto started and then the pump is securred, that the white Override light above the pump switch will be illuminated.
EOP-RC-LP-20308 "RPV Control (Non-ATWS)" states if previously operating systems fail to maintain RWL above top of active fuel, then transitioning to CP-l CP-1 provides instructions to submerge the core. Also the CP-lCP-1 flowchart A. Incorrect - See description above.
B. Ccorrect - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
Tuesday, September 08, 08,20098:31 2009 8:31 :00 AM 184
HLT 5 NRC EXAM 2009-302 Reference(s) provided to the student:
None KIA: 295031G2.2.44 Reactor Low Water Level 2.2.44 Ability to interpret control room indications to verify verifY the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5/43.5 (CPR: 41.5 /43.5/45.12)
/45.12) IMPORTANCE RO 4.2 SRO 4.4 SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
E11-RHR-LP-00701 "Residual Heat Removal System" EO 006.007.a.05 EOP-RC-LP-20308 "RPV Control (Non-ATWS)" EO 201.083.A.02 Reference(s) used to develop this question:
E11-RHR-LP-00701 "Residual Heat Removal System" EOP-RC-LP-20308 "RPV Control (Non-ATWS)"
( 31EO-EOP-OlO-2, "RC" (Non-ATWS) flow chart 31EO-EOP-010-2, 31EO-EOP-015-2, "CP-1" flow chart
(
Tuesday, September 08,2009 08,20098:31:00 8:31 :00 AM 185
HLT 5 NRC EXAM 2009-302
- 92. 400000A2.02 00 1I211IRBCCW 11211 IRBCCW/NEWIHIGHERlHT2009-302/SROIARB/CME
(
\
Unit 2 is operating at 100% power, when an event caused the following annunciators/conditions to exist:
o RBCCW SURGE TK LEVEL LOW OR EXCESS LEAKAGE, (650-248) o RBCCW HX OUTLET TEMP HIGH, (650-249) o RBCCW PUMPS DISCH PRESS LOW, (650-239) o 2P42-R601, RBCCW Pump Disch Press Indicator - 85 psig A Systems Operator reports that the RBCCW surge tank sightglass is empty and the make-up valve is full open.
Which ONE of the following predicts the impact on the RBCCW system standby pump and the required procedure actions?
IAW 34AB-P42-001-2, "Loss Of Reactor Building Closed Cooling Water" _ _ RBCCW pumps are expected to be running at this time.
If IfRBCCW RBCCW suction temperature reaches 105°F, the Shift Supervisor will direct the operator to enter A. two (2);
( 34AB-C71-001-2, "Scram Procedure", and scram the Reactor AND 34S0-B31-00 1-2, "Reactor Recirculation System and trip the Recirc Pumps B. two (2);
34AB-C71-001-2, "Scram Procedure", (ONLY) and scram the Reactor C~ three (3);
34AB-C71-001-2, "Scram Procedure", and scram the Reactor AND 34S0-B31-00 1-2, "Reactor Recirculation System", and trip the Recirc Pumps D. three (3);
34AB-C71-001-2, "Scram Procedure", (ONLY) and scram the Reactor
(
Tuesday, September 08,20098:31 :00 AM 186
HLT 5 NRC EXAM 2009-302
Description:
34AB-P42-00l-2, "Loss Of Reactor Building Closed Cooling Water" states that the standby 34AB-P42-001-2, RBCCW pump will automatically start at 90 psig, which is the setpoint for alarm (650-239).
Two pumps are normally running.
Step 4.8 requires, at 105 deg F, the SS will direct a reactor scram and then trip both reactor recirc pumps.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
D. Correct - See description above.
Reference(s) provided to the student:
None
(
K/
KIA:A: 400000A2.02 Component Cooling Water A2. Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 41.5/45.6) operation: (CFR: 41.5 /45.6)
A2.02 High/low surge tank:tank level ...................................... 2.83.0 SRO only because of oflink link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
P42-RBCCW-LP-0090l, "Reactor Building Closed Cooling Water", EO 200.0l4.A.04 P42-RBCCW-LP-00901, 200.014.A.04 Reference(s) used to develop this question:
P42-RBCCW-LP-0090 1, "Reactor Building Closed Cooling Water" P42-RBCCW-LP-00901, 34AB-P42-00l-2, "Loss Of Reactor Building Closed Cooling Water" 34AB-P42-001-2, 34AR-650-239-2 "RBCCW PUMPS DISCH PRESS LOW" Tuesday, September 08,20098:31 08, 2009 8:31 :00 AM 187
HLT 5 NRC EXAM 2009-302
- 93. 700000A2.03 OOllllllDEGRADED OOlilil/DEGRADED GRIDINEWIHIGHERJHT2009-302/SRO/ARB/CME At 1200 the Northern Control Center (NCC) notified the Control Room Operator that the 230KV Bus voltage cannot be maintained above the normal minimum voltage.
The following parameters currently exist on Unit 2:
o Main Generator H2 pressure ....... 43 psig o Main Generator Megawatt ...... 860 MWe o Main Generator Megavar ..... +280 MVar o "2E" 4160 V Emergency Bus volts ......... 3820 volts o "2F" 4160 V Emergency Bus volts ......... 3820 volts o "2G" 4160 V Emergency Bus volts ........ 3815 volts Which ONE of the following completes BOTH of these statements?
The Unit 2 Main Generator is operating ___ the acceptable limits of the generator capability curve.
If 4160 V Emergency Bus voltages remain at their present values, lAW 34AB-S 11-00 1-0, 11-001-0, Operation With Degraded System Voltage", a MINIMUM of 2 4160 V Emergency Unit 24160 Bus(es) is (are) required to be supplied from an Emergency Power source.
(
RERFERNCE PROVIDED A. within; one B. within; two C~ outside; C:o' one D. outside; two
(
Tuesday, September 08, 08,20098:31 2009 8:31 :01 AM 188
HLT HLT 5 NRC EXAM 2009-302
Description:
Plotting 43 psig & 860 MWe on Attachtment 1I "Generator Capability Curve' of 34S0-N40-001-2, "Main Generator Operation" results in operation outside the acceptable limits.
lAW 34AB-SII-00I-0, "Operation With Degraded System Voltage" step 4.3.3 places only the IAW 34AB-Sll-001-0, "2E" 4160 V Emergency Bus on its emergency power source. This procedure will align one emergency bus to its emergency power source for both units, therefore having two as a distractor is plausible.
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
D. Incorrect - See description above.
Reference(s) provided to the student:
34S0-N40-001-2 Attachtment Artachtment 1 "Generator Capability Curve' K/A: 700000A2.03 Generator Voltage and Electric Grid Disturbances
(
GENERATOR AA2. Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:
(CFR: 41.5 and 43.5/45.5,45.7, and 45.8)
AA2.03 Generator current outside the capability curve ..................... 3.5 3.6 SRO only because of link to 10CFR55.43 (5): Assessment offaciIity of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
Sll-LP-02706, "Basic Grid Concepts", EO 200.016.A.04 Reference(s) used to develop this question:
34S0-N40-001-2, "Main Generator Operation" S ll-LP-02706, "Basic Grid Concepts" 34AB-SII-00I-0, "Operation With Degraded System Voltage" 08,20098:31 Tuesday, September 08,2009 8:31 :01 AM 189
HLT 5 NRC EXAM 2009-302
- 94. G2.1.28 001l31IEALIMODIFIED/HIGHERlHT2009-302/SROI 001/31IEALIMODIFIED/HIGHERlHT2009-302/SROIARB/CME i
\
Unit 2 was operating at 100% reactor power with 2EII-FOI7A, 2EII-F017A, "RHR Outbd Injection Valve" tagged in "Close" for repair. The following occurs:
o "2C" Main Steam Line breaks in the Steam Chase o 2B21-F022C and 2B21-F028C, "Inboard & & Outoboard Isolation Valves" are stuck "OPEN" o A partial loss of High pressure feedwater. Only RCIC is available for injection.
Currently:
o Compensated RWL R WL is -160" and is stable o Un-compensated RWL is -170" o 2EII-S17A, "Containment Spray Vlv", switch position is "RESET" 2EII-SI7 o 2Ell-SI8A, 2EII-S18A, Cnmt Spray Vlv Cnt12/3 Core Ht Permissive", switch position is "OFF" Which ONE of the following completes both of these statements?
34S0-Ell-01O-2, "RHR SYSTEM," in order to place the "A" Loop ofRHR in Torus IAW 34S0-E11-010-2, Cooling, the interlock override switch(es) that MUST be manipulated is (are) _ __
IAW 73EP-EIP-00I-0, 73EP-EIP-001-0, "Emergency Classifications and Initial Actions," the MOST SEVERE Emergency that the Shift Manager is required to declare is a Emergency.
( REFERENCE PROVIDED A'! 2Ell-S17A 2ElI-SI7A ONLY General B. 2EII-S17AONLY 2EII-SI7A ONLY Site Area 2EII-SI7Aand2EII-SI8A C. 2Ell-S17Aand2Ell-S18A General D. 2Ell-S17Aand2Ell-S18A 2E II-S 17A and 2E II-S 18A Site Area Tuesday, September 08,2009 8:31 :01 AM 08,20098:31 190
HL HLTT 5 NRC EXAM 2009-302
Description:
34S0-E11-01O-2, 34S0-EII-0I0-2, "RHR SYSTEM", section 7.2.5 "Suppression Pool Cooling Mode" states if a LOCA signal is present, then place 2E II-S 17A in the "MAN" position. 2E II-S 18A will only be manipulated ifRWL is below -193" (uncompensated). Plausible for both switches if the candidate thinks since RWL is below TAF that both switches must be manipulated.
73EP-EIP-OOI-0, "Emergency Classifications and Initial Actions," Attachment 1 - Fission" 73EP-EIP-00I-0, Product Barrier Evaluation Chart - Modes 1-2-3" indicates with RWL less than -155" along with failure of both valves in anyone line to close and downstream breach outside Primary Containment that a "General" emergency exists. Plausible for Site Area emergency if candidate does not consider both key parameters (R(RWL WL & unisolable break).
A. Correct - See description above.
B. Incorrect: - See description above.
C. Incorrect - See description above.
D. Incorrect: - See description above.
Reference(s) provided to the student:
73EP-EIP-00I-0, "Emergency Classifications and Initial Actions," Attachment 1 - Fission"
( 73EP-EIP-OOI-0, Product Barrier Evaluation Chart - Modes 1-2-3" KIA: 2.1.28 2.1. 28 Knowledge of the purpose and function of major system components and controls.
LESSON PLAN/OBJECTIVE:
EII-RHR-LP-00701, "RHR System" EO 007.003.A.03 EP-LP-20101, "Initial/Terminating Activities", TO 001.017.A OOl.OI7.A Reference(s) used to develop this question:
73EP-EIP-00I-0, 73EP-EIP-OOI-0, "Emergency Classifications and Initial Actions," Attachment 1 - Fission" Product Barrier Evaluation Chart - Modes 1-2-3" 34S0-EII-01O-2, "RHR SYSTEM" 34S0-EII-0l0-2, EII-RHR-LP-00701, "RHR System" EP-LP-20101, "Initial/Terminating Activities" Tuesday, September 08,20098:31 :01 AM 08,20098:31:01 191
HLT 5 NRC EXAM 2009-302
- 95. G2.1.37 OOl/31lREACTIVITY 001/31/REACTIVITY MANAGEMENINEWIFUND/HT2009-302/SRO/ARB/CME MANAGEMENINEWIFUND/HT2009-302!SRO! ARB/CME Unit 1 is starting up from a scheduled Refueling outage. Control rod movement is in progress to raise reactor power to 5% power. The Shift Manager and the Shift Technical Advisor, along with the following, are in the main control room:
Unit 1 Unit 2 o Shift Supervisor Shift Supervisor o Reactivity Management SRO o 3 NPOs INPO Which ONE of the following completes both of these statements?
IA W with 30AC-OPS-003-0, "Plant Operations" and NMP-OS-OO 1, I, "Reactivity Management Program" the number ofNPOs on Unit 1 meet the minimum required.
Any changes to the Unit 1 reactivity plan must be approved by the _ _ ___
A. does; Reactivity Management SRO B:' does; B:t Shift Supervisor C. does NOT; Reactivity Management SRO D. does NOT; Shift Supervisor Tuesday, September 08,20098:31 :01 AM 192
HLT 5 NRC EXAM 2009-302 HLT
Description:
30AC-OPS-003-0, "Plant Operations"section 8.3, requires at least two licensed NPOs in the MCR for each reactor in the process of startup, scheduled reactor shutdown, rapid power reduction, and during recovery from reactor trips caused by transients or emergencies. In this question, Unit 1 is moving control rods to increase reactor power, therefore the 3 NPOs meet this requirement.
NMP-OS-OOI, NMP-OS-OOl, "Reactivity Management Program" section 6.4 states "While the reactivity management SRO provides direct oversight of the planned reactivity additions, the SS must approve the reactivity plan as well as any changes to the plan."
A. Incorrect - See description above.
B. Correct - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
Reference(s) provided to the student:
None KIA: 2.1.37 2.1. 37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
SRO only because of link to 10CFR55.43 10CFR55.43 (6): Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming, and determination of various internal and external effects on core reactivity.
LESSON PLAN/OBJECTIVE:
Reference(s) used to develop this question:
30AC-OPS-003-0, "Plant Operations"section 8.3 NMP-OS-OOI, "Reactivity Management Program" section 6.4 NMP-OS-OOl,
(
Tuesday, September 08,2009 08, 2009 8:31:01 8:31 :01 AM 193
HL HLTT 5 NRC EXAM 2009-302
- 96. G2.2.01S 001l311STARTUP 001l31/STARTUP PREPSINEWIHIGHERlHT2009-302/SRO/ARB/CME Unit 2 is in Mode 3 making preparations to commence control rod withdrawal. The Reactor Mode switch has just been placed in the "Startup" position.
o All control rods are fully inserted.
o The "A" SRM is inoplbypassed inop/bypassed for module drawer replacement.
o An operator informs you that the "B" SRM is indicating 0 cps (downscale).
I&C reports it will be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to repair either "A" or "B" SRM.
Which ONE of the following completes both of these statements?
IAW with 34GO-OPS-OOI-2, "Plant Startup" and Tech Specs, all operable SRM channels must lAW be indicating a MINIMUM of cps.
When I&C completes the repairsrypairs on either the "A" or "B" SRM, the reactor mode switch will be in the position.
REFERENCE PROVIDED A. 3;3*,
Startup
( B. 5;5*,
Startup C:-' 3; C:'
Shutdown D. 5; Shutdown Tuesday, September 08, 2009 8:31 :02 AM 194
HLT 5 NRC EXAM 2009-302
Description:
TS SR 3.3.1.2.4. requires ::::3 cps.
With two SRMs inop, Condition A is entered with a Required Action to restore one of the SRMs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Condition C is entered to be in mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
This is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> total and the SRMs will not be fixed for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5 cps might be selected because it is the SRM downscale setpoint.
Startup would be selected if the candidate thought: IRMs are on Range 2 (0 SRMS required), or if confused with the requirements of Modes 3,43, 4 or 5 (2 SRMs required).
A. Incorrect - See description above.
B. Incorrect - See description above.
C. Correct - See description above.
D. Incorrect - See description above.
( Reference(s) provided to the student TS 3.3.1.2, "SRM Instrumentation" WITHOUT Surveillance Requirements & Table KIA: 2.2.01 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
C51-SRM-LP-01201, "Source Range Monitor" EO 300.010.A.34 Reference(s) used to develop this question:
34GO-OPS-001-2, "Plant Startup" section 7.1 "Preparations" TS 3.3.1.2, "SRM Instrumentation" TS SR 3.3.1.2.4
( C51-SRM-LP-01201, "Source Range Monitor" Tuesday, September 08,20098:31 08, 2009 8:31 :02 AM 195
HLT 5 NRC EXAM 2009-302
- 97. G2.2.23 001l311TECH SPEC TRACKINO/MODIFIEDIFUND/HT2009-302/SRO/ARB/CME 97.02.2.23 TRACKING/MODIFIEDIFUND/HT2009-302/SRO/ARB/CME IAW with 31 GO-OPS-006-0, "Conditions, Required Actions and Completion Times", which lAW ONE of the following completes following statement.
If plant equipment becomes inoperable when the equipment is not presently required to be operable then a(an) Required Action Sheet will be written and the Shift Supervisor and Shift Manager will the appropriate TSA ACTWE box below.
I SS SIGN / TSA ACTNE ACTIVE SOS SIGN I A'! Tracking; initial B. Active; sign SIgn C. Active; initial D. Tracking; SIgn
(
Description:
31 GO-OPS-006-0, "Conditions, Required Actions and Completion Times" Section 7.1, "Initiation Of A Required Action Sheet" step 77.1.1.5
.1.1.5 directs you to Section 7.3 for initiating a Required Action Sheet when a SSC is inoperable in a condition when it is not required to be operable. SS & SM signatures makes a RAS active.
Section 7.3 (Tracking RAS) directs the SS & SM to initial the appropriate boxes of the form OPS-1349. This will make the RAS a Tracking RAS.
A. Correct - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
Tuesday, September 08, 08,20098:31 2009 8:31 :02 AM 196
HLT 5 NRC EXAM 2009-302 Reference(s) provided to the student:
None KIA: 2.2.23 Ability to track Technical Specification limiting conditions for operations.
SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
LT-LP-30006, "LCOIRAS "LCO/RAS TRACKING" EO 300.027.A.03 Reference(s) used to develop this question:
31GO-OPS-006-0, 31 GO-OPS-006-0, "Conditions, Required Actions and Completion Times" LT-LP-30006, "LCO/RAS "LCOIRAS TRACKING" OPS-1349, "REQUIRED "REQUlRED ACTION SHEET"
(
(
Tuesday, September 08,20098:31 08, 2009 8:31 :02 AM 197
HLT 5 NRC EXAM 2009-302
- 98. 02.3.138 G2.3.13S OOl/3//RAD ADMININRC 2009IFUNDIHT2009-302/8RO/
20091FUNDIHT2009-302/SRO/ARB/CME ARB/CME Which ONE of the following choices answers both of these statements IAW with the requirements of 73EP-RAD-OO 73EP-RAD-00 1-0, "Radiological Event"?
When an Area Radiation Monitor (ARM) UNEXPECTEDLY alarms and radiation levels in the vicinity of the monitor have risen to AT LEAST greater than times normal, then a Plant Page Announcement is required.
The is the MINIMUM level of qualification necessary to declare a Radiological Event AND will make immediate decisions concerning Emergency Call List notifications.
A. 10 Shift Manager B:'
B:" 10 Control Room Shift Supervisor C. 2 Shift Manager D.2 Control Room Shift Supervisor
(
73EP-RAD-00I-0, Section 6.0, states:
73EP-RAD-OOI-0, The Control Room Shift Supervisor, normally in consultation with HP Supervision, must have determined it to be prudent to alert plant personnel to an unusual radiological condition.
Such conditions include, but are not limited to the following:
An Area Radiation Monitor (ARM) UNEXPECTEDLY alarms indicating radiation levels in the vicinity of the monitor of greater than 10 times normal but NOT sufficiently high to require an emergency declaration of an ALERT or higher (refer to 73EP-EIP-00I-0, sections 2.0 and 19.0).
(
Tuesday, September 08, 2009 8:31 :03 AM 198
HLT 5 NRC EXAM 2009-302
( Reference(s) provided to the student:
None KIA: 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
SRO only because of link to 10CFR55.43 10CFR55.43 (4): Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.
LESSON PLAN/OBJECTIVE:
LT-LP-30001, "Offsite Dose Calculation Manual" TO 200.051.A LT-LP-3000l, Reference(s) used to develop this question:
73EP-RAD-00I-0, "Radiological Event" LT-LP-30001, "Offsite Dose Calculation Manual"
( 2009 NRC EXAM Q#98
(
Tuesday, September 08,20098:31 08, 2009 8:31 :03 AM 199
HLT 5 NRC EXAM 2009-302
- 99. G2.4.37 OOl/31IEMERG DIR DUTIESINEWIFUNDIHT2009-302/SROIARBICME DUTIESINEWIFUNDIHT2009-302/SRO/ARB/CME lAW IAW 73EP-EIP-004-0, "Duties Of Emergency Director", which ONE of the following completes both of these statements?
"Initially, the Emergency Director position is filled by the Shift Manager (SM). If the SM is unavailable, then the _ _ unit's Shift Supervisor (SS) will become the Emergency Director.
If the SM is unavailable and the event involves BOTH units, the _ _ Shift Supervisor (SS) will become the Emergency Director."
A'! affected; Unit 1I B. affected; Unit 2 c.
C. Non-affected; Unit 1 D. Non-affected; Unit 2
(
Description:
73EP-EIP-004-0, "Duties Of Emergency Director", states at step 7.1 "Initially, the Emergency Director position is filled by the Shift Manager (SM). If the SM is unavailable, then the affected unit's Shift Supervisor (SS) will become the Emergency Director. IF the SM is unavailable and the event involves both units, the Unit 1 Shift Supervisor (SS) will become the Emergency Director."
A. Correct - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
Tuesday, September 08, 2009 8:31 :03 AM 200
HLT 5 NRC EXAM 2009-302
( Reference(s) provided to the student:
None KIA: 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.
SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
EP-LP-201001, "Initial/Terminating Activities" EP-LP-20l00l, Reference(s) used to develop this question:
73 EP -EIP -004-0, "Duties Of Emergency Director" 73EP-EIP-004-0, EP-LP-20l00l, "Initial/Terminating Activities" EP-LP-201001,
(
(
Tuesday, September 08, 2009 8:31 :03 AM 201
HL T 5 NRC EXAM 2009-302 100. G2.4.41 001/31IEALIMODIFIEDIHIGHERlHT2009-302/SROIFNFICME 001/3/IEALIMODIFIEDIHIGHERlHT2009-302/SROIFNF/eME Unit 1 is at 100% power when the following sequence of events occurs:
o 1100 1B EDG tagged for repairs o 1130 Offsite power is lost to Unit 1 ONLY o 1130 All operable EDGs start and tie to their associated Emergency Busses.
o 1135 SO reports lA EDG Jacket Water Temp of 200°F, rising 0.5°F Imin o 1145 1C EDG trips on Differential Lockout o 1205 Current Time Which ONE of the choices below completes the following statement?
The HIGHEST emergency classification reached during the event is a(n) and once formal declaration of the event is made the maximum amount of time allowed to make initial notification to State and local governments is _ __
REFERENCE PROVIDED A'! Alert; 15 minutes B. Alert; 30 minutes
( C. Site Area Emergency; 15 minutes D. Site Area Emergency; 30 minutes
(
Tuesday, September 08, 2009 8:31 :03 AM 202
HLT HLT 5 NRC EXAM 2009-302
Description:
Correct Answer: A Unit 1 has lost off-site power. The lA EDG would trip on high jacket water temp (205 (20S OF) ifit were in test but the trip is not active now. At 11 :45
- 4S the plant only has the lA EDG running, 15IS minutes later, the plant will already be in an Alert (SA5).
(SAS).
After declaration of event 15 IS minutes is the requirement to notify State and local government:
(30 minutes == 15 IS minutes to classify and 15IS minutes to notify).
The operator would select SAE if the thought the 1lA A EDG tripped.
The operator would select 30 minutes if he added the times to classify and notify.
ifhe A. Correct - See description above.
B. Incorrect - See description above.
C. Incorrect - See description above.
D. Incorrect - See description above.
( Reference(s) provided to the student:
73EP-EIP-OOI-0, 73EP-EIP-OOI-O, "Emergency Classification & Initial Actions", Attachment 2 "Hot" Initiating Condition Matrix Evaluation Chart, AC Power Section ONLY.
KIA: 2.4.41 Knowledge of the emergency action level thresholds and classifications.
SRO only because of link to 10CFR55.43 (5): Assessment of facility conditions and selection of appropriate procedure, recalling the action in the body of procedure and when to take the action.
LESSON PLAN/OBJECTIVE:
EP-LP-20101-04,001.017.A EP-LP-20101-04,00l.017.A Reference(s) used to develop this question:
Modified from Brunswick 2008 SRO Exam 73EP-EIP-00I-0, "Emergency Classification & Initial Actions", Attachment 2
(
You have completed the test!
Tuesday, September 08,20098:31 :03 AM 203