ML17276B835
| ML17276B835 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/03/2017 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-424/17-301, 50-425/17-301 50-424/OL-17, 50-425/OL-17 | |
| Download: ML17276B835 (32) | |
See also: IR 05000424/2017301
Text
ILT21 SRO NRC Makeup Examination KEY
Answers
- ID 0
1 004G2.4.41 1 A
2 008AG2.4.47 1 C
3 011G2.1.20 1 C
4 012A2.06 1 C
5 013A2.05 1 D
6 015G2.1.25 1 B
7 054AG2.2.04 1 B
8 055EA2.05 1 A
9 058AG2.1.23 1 A
10 059A2.07 1 D
11 061G2.2.22 1 C
12 077AA2.08 1 C
13 086A2.03 1 D
14 G2.1.34 1 A
15 G2.1.45 1 C
16 G2.2.15 1 D
17 G2.2.44 1 D
18 G2.3.06 1 D
19 G2.4.32 1 A
20 G2.4.38 1 A
21 WE02EA2.01 1 A
22 WE05EA2.01 1 D
23 WE08EG2.4.34 1 B
24 WE13EA2.02 1 A
25 WE16EG2.4.04 1 C
SECTION 1 ( 25 items) 25.00
Page 1 of 1
Name: ________________________
ILT21 SRO NRC
Makeup
Student Test
Start Time: _______
Stop Time: _______
ILT21 SRO NRC Makeup
1.
Initial conditions:
- Unit 1 is at 100% reactor power.
- ALB07-C05 LP LTDN RELIEF HI TEMP is received.
- PRT pressure, level, and temperature are slowly rising.
- VCT auto makeup is in progress.
Current conditions:
- OATC placed charging in manual and stabilized pressurizer level.
- 1FI-121, Charging Flow, indicates 161 gpm.
- 1FI-132, Letdown Flow, indicates 120 gpm.
- RCP seal injection flow is 8 gpm to each RCP.
- RCP seal leak-off is 2.5 gpm from each RCP.
Which one of the following completes the following statement?
Per Tech Spec LCO 3.4.13, "RCS Operational Leakage," the current RCS leakage is
classified as __(1)__,
and
per NMP-EP-110, "Emergency Classification Determination and Initial Action," an
emergency classification threshold value __(2)__ been exceeded.
__(1)__ __(2)__
A. identified has
B. identified has NOT
C. unidentified has
D. unidentified has NOT
Page 1 of 25
ILT21 SRO NRC Makeup
2.
Procedure titles as follows:
- 18000-C, "Pressurizer Spray, Safety, or Relief Valve Malfunction"
- 18001-C, "Systems Instrumentation Malfunction"
Initial conditions:
- Unit 1 is at 100% reactor power.
- ALB12-F04 PV-456A OPEN SIGNAL is received.
- 1PV-456, Pressurizer PORV, indicates open on the QMCB.
- 1PI-455, Pressurizer Pressure, is 2200 psig and lowering.
- 1PI-456, Pressurizer Pressure, is 2550 psig and stable.
- 1PI-457, Pressurizer Pressure, is 2210 psig and lowering.
- 1PI-458, Pressurizer Pressure, is 2195 psig and lowering.
Current conditions:
- OATC places 1HS-456, Pressurizer PORV, in the CLOSE position.
- PRT pressure, temperature, and level stabilize.
Which one of the following completes the following statement?
Based on the given conditions, the Shift Supervisor is required to enter __(1)__,
and
per the Bases of Tech Spec LCO 3.4.11, "Pressurizer PORVs," 1PV-456, Pressurizer
__(1)__ __(2)__
A. 18000-C is
B. 18000-C is NOT
C. 18001-C is
D. 18001-C is NOT
Page 2 of 25
ILT21 SRO NRC Makeup
3.
Initial condition:
- Unit 2 is at 90% reactor power.
Current condition:
- 2LT-459, Pressurizer Level, fails high.
Which one of the following completes the following statement?
Tech Spec LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation," Function 9,
Pressurizer Water Level - High, __(1)__ met,
and
per the Bases of Tech Spec LCO 3.3.1, the Pressurizer Water Level - High reactor trip
provides __(2)__.
A. (1) is
(2) a backup to the Pressurizer High Pressure reactor trip
B. (1) is
(2) the primary protection for a Loss of Turbine Load event
C. (1) is NOT
(2) a backup to the Pressurizer High Pressure reactor trip
D. (1) is NOT
(2) the primary protection for a Loss of Turbine Load event
Page 3 of 25
ILT21 SRO NRC Makeup
4.
Initial conditions:
- Unit 1 is at 100% reactor power.
- ALB09-C01 STM GEN LOOP 3 LO-LO LEVEL REACTOR TRIP is received.
- Reactor will NOT trip using either Reactor Trip handswitch in the Control Room.
- 19211-1, "Response to Nuclear Power Generation / ATWT," is in progress.
Current conditions:
- Crew is at Step 8 to "Check the following trips have occurred - reactor trip."
- System Operator reports that the RTBs will NOT open locally.
Which one of the following completes the following statement?
Based on the current conditions and per 19211-1, the next required action is to
__(1)__,
and
per NMP-EP-110, "Emergency Classification Determination and Initial Action," an
emergency classification threshold value __(2)__ been exceeded.
A. (1) initiate emergency boration
(2) has
B. (1) initiate emergency boration
(2) has NOT
C. (1) open the Control Rod Drive MG Set output breakers
(2) has
D. (1) open the Control Rod Drive MG Set output breakers
(2) has NOT
Page 4 of 25
ILT21 SRO NRC Makeup
5.
Given the following:
- Unit 2 is at 100% reactor power.
- 2CD1M de-energizes due to a fault.
Which one of the following completes the following statements?
Based on the given conditions and per Tech Spec LCO 3.7.5, "Auxiliary Feedwater
(AFW) System," the required action completion time is __(1)__.
Based on the given conditions, if an AFW actuation signal were to occur, the TDAFW
pump __(2)__ automatically start and provide flow.
REFERENCES PROVIDED
__(1)__ __(2)__
A. 7 days would
B. 7 days would NOT
C. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> would
D. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> would NOT
Page 5 of 25
ILT21 SRO NRC Makeup
6.
Given the following:
- Unit 1 is at 97% reactor power.
- All plant parameters are stable.
- OATC checks AFD on the IPC.
Which one of the following completes the following statement?
Based on the IPC data provided, Tech Spec LCO 3.2.3, "Axial Flux Difference (AFD)
(Relaxed Axial Offset Control (RAOC) Methodology)," __(1)__ met,
and
based on the given conditions and per the Bases of Tech Spec LCO 3.3.1, "Reactor
Trip System (RTS) Instrumentation," the OT delta T reactor trip function __(2)__
REFERENCES PROVIDED
__(1)__ __(2)__
A. is is
B. is is NOT
C. is NOT is
D. is NOT is NOT
Page 6 of 25
ILT21 SRO NRC Makeup
7.
Initial conditions:
- Unit 2 is at 100% reactor power.
- A total loss of feedwater occurs.
Current conditions:
- An automatic reactor trip occurs.
- RTB 'A' is open.
- RTB 'B' is NOT open.
Which one of the following completes the following statement?
With no operator action, the Main Feed Isolation Valves (MFIVs) __(1)__ closed,
and
per the Bases of Tech Spec LCO 2.1.2, "Reactor Coolant System (RCS) Pressure SL,"
the RCS pressure transient safety analysis takes credit for the SG __(2)__.
__(1)__ __(2)__
A. are ARVs
B. are Safety Valves
C. are NOT ARVs
D. are NOT Safety Valves
Page 7 of 25
ILT21 SRO NRC Makeup
8.
Initial conditions:
- Unit 2 is at 100% reactor power.
- DG2A is tagged out.
- A loss of all off-site power occurs.
- DG2B starts and then trips on overspeed.
Current conditions:
- 19100-2, "Loss of All AC Power," is in progress.
- Crew is at the step to "Perform DC Load Shed."
Which one of the following completes the following statements?
Based on the initial conditions and per the Bases of Tech Spec LCO 3.8.4, "DC
Sources - Operating," 1E batteries are sized to have sufficient capacity to supply the
required loads for a minimum of __(1)__ hours.
Per 19100-2, the Shift Supervisor __(2)__ required to direct the performance of the DC
load shed using an Attachment in 19100-2.
__(1)__ __(2)__
A. 4 is
B. 4 is NOT
C. 2.75 is
D. 2.75 is NOT
Page 8 of 25
ILT21 SRO NRC Makeup
9.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- All Train 'A' MSIV red and green handswitch lights extinguish.
- RTB 'A' red and green lights extinguish.
- RCP #1, 1E breaker red and green handswitch lights extinguish.
- Channel I TSLB bistable lights are lit.
Which one of the following completes the following statement?
The Shift Supervisor __(1)__ required to enter 18034-1, "Loss of Class 1E 125 VDC
Power,"
and
the Shift Supervisor __(2)__ required to enter 19000-1, "Reactor Trip or Safety
Injection."
__(1)__ __(2)__
A. is is
B. is is NOT
C. is NOT is
D. is NOT is NOT
Page 9 of 25
ILT21 SRO NRC Makeup
10.
Initial conditions:
- Unit 1 is at 60% reactor power and stable.
- MFP 'B' startup is in progress and has been idling at 1200 rpm for 15 minutes.
Current conditions:
- ALB15-D03 MFPT A TRIPPED is received.
- Feed flow indications indicate 0 MPPH on all SGs.
- MFP 'B' continues to idle in manual.
- All SG NR levels are 60% and lowering.
Which one of the following completes the following statements?
Based on the initial conditions, Tech Spec LCO 3.3.2, "ESFAS Instrumentation,"
Fu 6.d "Auxiliary Feedwater - Trip of all Main Feedwater Pumps," __(1)__ met.
Based on the given conditions and per 18016-C, "Condensate and Feedwater
Malfunction," the first action the crew is required to perform is to __(2)__.
__(1)__ __(2)__
A. was raise MFP 'B' speed
B. was check reactor power 70%
C. was NOT raise MFP 'B' speed
D. was NOT check reactor power 70%
Page 10 of 25
ILT21 SRO NRC Makeup
11.
Given the following:
- Unit 2 is at 100% reactor power.
- CST #1 is at 64% level (320,000 gallons).
- CST #2 is at 12% level (60,000 gallons).
- All AFW pump suctions are aligned to CST #1.
Which one of the following completes the following statement?
Based on the given conditions, Tech Spec LCO 3.7.6, "Condensate Storage Tank
(CST)," __(1)__ met,
and
per the Bases of Tech Spec LCO 3.7.6, the Unit 2 CST minimum required volume
__(2)__ maintained to supply AFW for an RCS cooldown of up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to
putting RHR in service.
__(1)__ __(2)__
A. is is
B. is is NOT
C. is NOT is
D. is NOT is NOT
Page 11 of 25
ILT21 SRO NRC Makeup
12.
Initial conditions:
- Unit 1 is at 100% reactor power.
- Power Control Center reports it is one contingency away from being unable to
maintain stable grid voltage.
- 18017-C, "Abnormal Grid Disturbance / Loss of Grid," Section A, "Degraded Grid
Conditions," is in progress.
Current conditions:
- 1AA02 and 1BA03 Normal Incoming Breakers trip open.
- DG1A and DG1B start and re-energize their associated buses.
Which one of the following completes the following statements?
If bus voltages were steady at 3595 VAC, the Normal Incoming Breakers tripped open
after a minimum of __(1)__ seconds.
Based on the given conditions and per 18017-C, the crew __(2)__ required to trip the
reactor.
__(1)__ __(2)__
A. 0.8 is
B. 0.8 is NOT
C. 20 is
D. 20 is NOT
Page 12 of 25
ILT21 SRO NRC Makeup
13.
Initial conditions:
- Both units are at 100% reactor power.
- Motor-Driven Fire Pump is tagged out.
- One Fire Water Jockey Pump is in service.
- Sprinklers actuate in the Turbine Building due to welding.
Current conditions:
- FAILURE TO START is received on the Diesel-Driven Fire Pump #1 local control
panel.
- Fire water header pressure is 92 psig and slowly lowering.
Which one of the following completes the following statements?
Consider each statement separately.
Based on the given conditions, Fire Protection LCO 4.3, "Suppression System
Operability," __(1)__ met.
If required by Fire Protection LCO 4.3, a credited backup fire suppression system is
__(2)__.
__(1)__ __(2)__
A. is the portable B.5.b pump
B. is a Burke County EMA pumper truck
C. is NOT the portable B.5.b pump
D. is NOT a Burke County EMA pumper truck
Page 13 of 25
ILT21 SRO NRC Makeup
14.
Given the following:
- Unit 2 is stable at 65% reactor power.
- Chemistry reports that RCS Dose Equivalent I-131 is 98 µCi/gram.
Which one of the following completes the following statements?
Per Tech Spec LCO 3.4.16, "RCS Specific Activity," the current Dose Equivalent I-131
activity falls in the __(1)__ operating region.
Per the Bases of Tech Spec LCO 3.4.16, the RCS activity limit ensures that the off-site
dose will be limited to within a small fraction of the dose guideline values in the event of
a __(2)__.
REFERENCES PROVIDED
__(1)__ __(2)__
A. acceptable SGTR
B. acceptable large break LOCA
C. unacceptable SGTR
D. unacceptable large break LOCA
Page 14 of 25
ILT21 SRO NRC Makeup
15.
Initial conditions:
- Unit 1 reactor trip and SI occur due to a LOCA.
- 19012-1, "Post-LOCA Cooldown and Depressurization," is in progress.
- Both Trains of COPS are armed.
Current conditions:
- ALB12-C05 B COLD OP LOW AUCT RCS TEMP is received.
- ALB12-F04 PV-456A OPEN SIGNAL is received.
Which one of the following completes the following statement?
Based on the given conditions, an RCS WR __(1)__ leg temperature instrument has
failed,
and
per the Bases of Tech Spec LCO 3.3.3, "Post Accident Monitoring (PAM)
Instrumentation," for diverse indication of the failed RCS WR temperature, the operator
__(2)__ directed to use the associated loop's SG pressure.
__(1)__ __(2)__
A. hot is
B. hot is NOT
C. cold is
D. cold is NOT
Page 15 of 25
ILT21 SRO NRC Makeup
16.
Initial conditions:
- Unit 2 is at 100% reactor power.
- 2-1204-U6-100, SI Pump 'A' Discharge Isolation, is found unlocked.
- Shift Supervisor determines that 2-1204-U6-100 is on 11867-2, "Safety Related
Locked Valve Verification Checklist."
Current condition:
- System Operator is dispatched to verify the position and re-lock the valve.
Which one of the following completes the following statement?
Per 10019-C, "Control of Safety Related Locked Valves," the Shift Manager __(1)__
required to authorize the sign out of the safety related locked valve key,
and
per 10019-C, when the key is issued for 2-1204-U6-100, a(n) __(2)__ verification of the
valve position is required to be performed.
__(1)__ __(2)__
A. is concurrent
B. is independent
C. is NOT concurrent
D. is NOT independent
Page 16 of 25
ILT21 SRO NRC Makeup
17.
Initial conditions:
- Unit 1 is at 100% reactor power.
- SI Pump 'B' is tagged out.
Current conditions:
- NSCW Train B supply header pressure is 75 psig and lowering.
- NSCW Train B supply header flow is 25,000 gpm.
- NSCW Train B return header flow is 10,000 gpm.
- 18021-C, "Loss of Nuclear Service Cooling Water System," is entered.
Which one of the following completes the following statement?
Based on the given conditions and per 18021-C, the crew is required to __(1)__ the
standby Train B NSCW pump,
and
after completing the actions of 18021-C, the Shift Supervisor will determine per
10008-C, "Recording Limiting Conditions for Operation," that a LOSF __(2)__ exist.
__(1)__ __(2)__
A. start does
B. start does NOT
C. place in PTL does
D. place in PTL does NOT
Page 17 of 25
ILT21 SRO NRC Makeup
18.
Initial conditions:
- Both units are at 100% reactor power.
- Shutdown Gas Decay Tank (SDT) #10 release is in progress.
Current conditions:
- ARE-0014, Waste Gas Effluent, fails downscale low.
- The release has been stopped.
Which one of the following completes the following statement?
Per the ODCM, to permit any additional SDT releases, ARE-0014 __(1)__ required to
be returned to service,
and
per the ODCM Bases for gaseous effluent releases, the allowed quantity of gaseous
effluent released __(2)__ based on Control Room habitability limitations.
__(1)__ __(2)__
A. is is
B. is is NOT
C. is NOT is
D. is NOT is NOT
Page 18 of 25
ILT21 SRO NRC Makeup
19.
At time 0800:
- Unit 1 is at 100% reactor power.
- 1PV-3000, SG#1 ARV, fails open.
- 18008-C, "Secondary Coolant Leakage," is in progress.
At time 0805:
- Power is lost to all annunciators in the Main Control Room.
- IPC and PSMS are available.
At time 0817:
- Shift Manager makes an emergency declaration.
Which one of the following completes the following statement?
Indication of ARV tailpipe temperature __(1)__ available on the QPCP,
and
per NMP-EP-110, "Emergency Classification Determination and Initial Action," the Shift
Manager is required to declare an Emergency based on __(2)__.
REFERENCES PROVIDED
__(1)__ __(2)__
A. is SU3
B. is SA4
C. is NOT SU3
D. is NOT SA4
Page 19 of 25
ILT21 SRO NRC Makeup
20.
Given the following:
- Unit 1 reactor is tripped.
- An Alert Emergency is declared.
- Shift Manager is incapacitated due to a medical condition.
Which one of the following completes the following statements?
Per 91101-C, "Emergency Response Organization," filling the role of the alternate for
the Emergency Director will initially be the __(1)__.
Based on the given conditions and per 91401-C, "Assembly and Accountability,"
ordering an assembly and accountability __(2)__ required.
__(1)__ __(2)__
A. Shift Supervisor is
B. Shift Supervisor is NOT
C. Shift Technical Advisor is
D. Shift Technical Advisor is NOT
Page 20 of 25
ILT21 SRO NRC Makeup
21.
Initial conditions:
- Unit 2 reactor trip and SI occur.
- CCP 'A' is tagged out.
- 19000-2, "Reactor Trip or Safety Injection," is in progress.
- OATC and UO Initial Actions pages are complete.
Current conditions:
- RCS pressure is 2150 psig and slowly rising.
- CETCs are 559 °F and slowly lowering.
- Pressurizer level is 26% and slowly rising.
- Containment pressure is 0.3 psig and stable.
- SG #1 and #4 NR levels are 35% and slowly rising.
- SG #2 and #3 NR levels are 32% and stable.
- SG #1 and #4 pressures are 1040 psig and slowly lowering.
- SG #2 and #3 pressures are 1050 psig and stable.
Which one of the following completes the following statement?
Based on the current conditions, the Shift Supervisor will first transition from 19000-2
to ____________.
A. 19011-2, "SI Termination"
B. 19020-2, "Faulted Steam Generator Isolation"
C. 19010-2, "Loss of Reactor or Secondary Coolant"
D. 19012-2, "Post-LOCA Cooldown and Depressurization"
Page 21 of 25
ILT21 SRO NRC Makeup
22.
Procedure titles as follows:
- 19010-1, "Loss of Reactor or Secondary Coolant"
- 19011-1, "SI Termination"
Initial conditions:
- Unit 1 reactor trips due to a loss of all feedwater.
- 19231-1, "Response to Loss of Secondary Heat Sink," is in progress.
- RCS bleed and feed has been established.
Current conditions:
- TDAFW pump has been returned to service.
- RCS bleed and feed has been secured.
- RCS hot leg temperatures are slowly lowering.
- RCS pressure is 1575 psig and slowly rising.
- Pressurizer level is 36% and stable.
- Containment pressure is 4.2 psig and stable.
Which one of the following completes the following statement?
Based on the current conditions and per 19231-1, the minimum SG level that was
required to secure RCS bleed and feed was at least one SG NR level greater than
__(1)__%,
and
the Shift Supervisor is required to transition to __(2)__.
__(1)__ __(2)__
A. 9 19010-1
B. 9 19011-1
C. 30 19010-1
D. 30 19011-1
Page 22 of 25
ILT21 SRO NRC Makeup
23.
Procedure titles as follows:
- 13503B-2, "Train 'B' Reactor Control Solid-State Protection System"
- 19241-2, "Response to Imminent Pressurized Thermal Shock Condition"
Initial conditions:
- Unit 2 reactor trip and SI occur.
- 19241-2 is in progress.
Current conditions:
- Crew is at the step to "Reset SI."
- Shift Supervisor determines an RCS soak will be required.
Which one of the following completes the following statements?
The RCS soak minimizes thermal gradients, which reduces corresponding __(1)__
stresses on the reactor vessel inner wall.
If SI Train 'B' will NOT reset, the Shift Supervisor will dispatch an operator to
de-energize both SSPS 48 VDC power supplies and unlatch the slave relays using
guidance in __(2)__.
__(1)__ __(2)__
A. tensile 13503B-2
B. tensile 19241-2
C. compressive 13503B-2
D. compressive 19241-2
Page 23 of 25
ILT21 SRO NRC Makeup
24.
Initial conditions:
- Unit 1 is at 100% reactor power.
- RAT '1A' and RAT '1B' de-energize due to a switchyard fire.
Current conditions:
- Unit 1 reactor is tripped.
- 19232-1, "Response to Steam Generator Overpressure," is in progress.
- SG #2 pressure is 1250 psig.
- SG #2 NR level is 85%.
- 1PV-3010, SG #2 ARV, will NOT open.
Which one of the following completes the following statements?
Consider each statement separately.
Per 19232-1, one of the allowed methods to lower SG #2 pressure is to dump steam
__(1)__.
When SG NR level is greater than 93%, steam flow is NOT initiated because of the
risk of __(2)__.
A. (1) to the TDAFW pump
(2) water hammer
B. (1) to the TDAFW pump
(2) rapid SG pressure drop
C. (1) through the MSIVs to the steam dumps
(2) water hammer
D. (1) through the MSIVs to the steam dumps
(2) rapid SG pressure drop
Page 24 of 25
ILT21 SRO NRC Makeup
25.
At time 1400:
- Unit 2 reactor trip and SI occurs due to a small break LOCA.
- 19010-2, "Loss of Reactor or Secondary Coolant," is in progress.
At time 1430:
- All RCPs are stopped.
- Containment pressure is 8 psig.
- Containment emergency sump level is 17 inches.
- RCS pressure is 1395 psig.
- CETCs are 559 °F.
- The lowest RCS WR Tcold temperature is 440 °F.
- RVLIS Full Range level is 43%.
- 2RE-002 and 2RE-003, Containment Area Radiation, indicate 780 mr/hour.
- All SG NR levels are approximately 32%.
- The highest SG pressure is 1170 psig.
- The STA reports that entry criteria are met for a CSFST YELLOW path.
At time 1430, YELLOW path entry criteria are met for entry into ___________.
A. 19223-2, "Response to Saturated Core Cooling"
B. 19235-2, "Response to Steam Generator Low Level"
C. 19253-2, "Response to High Containment Radiation Level"
D. 19242-2, "Response to Anticipated Pressurized Thermal Shock Condition"
Page 25 of 25
ILT-21 Makeup SRO Exam Provided References Index
1. NMP-EP-110-GL03, VEGP EALs - ICs, Threshold Values, and Basis, Page 126
(Figure 2 - edited) (rev. 9.0)
2. Tech Spec LCO 3.7.5, Auxiliary Feedwater (AFW) System, Page 3.7.5-1 (rev.
161)
3. Unit 1 Integrated Plant Computer Screenshot, Delta Flux Parameters
4. Tech Spec LCO 3.4.16, "RCS Specific Activity," Figure 3.4.16-1, "RCS Dose
Equivalent I-131 Versus Percent of Rated Thermal Power" (Amendment 96)
AFW System
3.7.5
3.7 PLANT SYSTEMS
3.7.5 Auxiliary Feedwater (AFW) System
LCO 3.7.5 Three AFW trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS
NOTE--------------------------------------------------------
LCO 3.0.4b is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME
A. One steam supply to A.1 Restore affected 7 days
turbine driven AFW equipment to OPERABLE
pump inoperable. status.
NOTE------------
Only applicable if
MODE 2 has not been
entered following
refueling.
One turbine driven AFW
pump inoperable in
MODE 3 following
refueling.
B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
inoperable for reasons OPERABLE status.
other than Condition A.
(continued)
Vogtle Units 1 and 2 3.7.5-1 Amendment No. 180 (Unit 1)
Amendment No. 161 (Unit 2)
RCS Specific Activity
3.4.16
FIGURE 3.4.16-1
REACTOR COOLANT DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY
LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT
SPECIFIC ACITVITY >1 µCi/gram DOSE EQUIVALENT I-131
Vogtle Units 1 and 2 3.4.16-4 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)