ML080460189
| ML080460189 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/14/2008 |
| From: | Michael B Division of Reactor Safety II |
| To: | |
| References | |
| 50-321/07-301, 50-366/07-301 | |
| Download: ML080460189 (50) | |
See also: IR 05000321/2007301
Text
Draft submittal (Pink Paper)Senior Reactor Operator Written Exam HATCH DECEMBER 2007 EXAM 05000321/2007301
AND 05000366/2007301
DECEMBER3-6, 2007, AND DECEMBER 10, 2007, (WRITTEN)
QUESTIONS REPORT for SRO 76.201003A2.05
OOl/2/2/CRDMINEW/FUND/HT2007-301/SRO/BLC/RFA
Unit 2 is performing
a shutdown in accordance
with 34GO-OPS-013-2, Normal Plant Shutdown.All control rods have b.een fully inserted per the selected rod sequence when the operator reaches this step in the procedure:
WHEN all control rods are fully inserted, PLACE the Reactor Mode Switch in SHUTDOWN AND record the'time REACTOR placed in Condition 3 in the Operators Log AND below: Time in Condition 3----------
Which ONE of the following predicts how the CRD Mechanisms
will be affected and identifies
the preferred procedure used to bypass the discharge volume high level trip and reset the scram after the mode switch is placed in the SHUTDOWN position?Reactor pressure WILL cause the CRDM internal ball valve to shift after the accumulator
depressurizes.
34GO-OPS-013-2, Normal Plant Shutdown B.Reactor pressure WILL cause the CRDM internal ball valve to shift after the accumul'ator
depressurizes.
34AB-C71-001-2, Scram Procedure C.All full-in (green)lights on the full core display will EXTINGUISH
until the scram is reset.34GO-OPS-013-2, Normal Plant Shutdown D.All full-in (green)lights on the full core display will EXTINGUISH
until the scram is reset.34AB-C71-001-2, Scram Procedure A.Correct.B.Incorrect because the 34GO-OPS-013-2
procedure includes steps to reset the scram.Plausible if applicant does not know that the shutdown procedure contains the steps to bypass the high SDV level trip and reset the scram.C.Incorrect because the S51 (overtravel
in)and S52 (normal full-in)reedswitches
ensure the green full-in light remains illuminated.
Plausiblesincethe applicant may know that the CROM will be in the overtravel
position until the scram is reset.D.Incorrect because the S51 (overtravel
in)and S52 (normal full-in)reedswitches
ensure the green full-in light remains illuminated.
Also incorrectbecausethe
procedure includes steps to reset the scram.Plausible'since the applicant may know that the CRDM will be in the overtravel
position until the scram is reset.Also plausible if applicant does not know that the shutdown procedure contains the steps to bypass the high SDV level tripandreset the scram.Friday, September 28, 2007 9:24:38 AM 1
QUESTIONS REPORT for SRO A2.Ability to (a)predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM;
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)
A2.05ReactorScram
4.1*/4.1 SRO-only (tie to 10CFR55.43(5):
Assessment
of facility conditions
and selection of appropriatae
procedures
during norrmal, abnormal, and emergency situations.
References
34GO-OPS-013-2, Normal Plant Shutdown 34 AB-C71-00 1-2, Scram Procedure C11-CRDM-LP-00102, Control Rod Drive Mechanism lesson plan Tier: 2 Group: Keyword: CRDM Source: Cog Level: FUND Exam: Test: SRO Author/Reviewer:
Friday, September 28, 2007 9:24:39 AM 2 NEW HT2007-301
BLC/RFA 2
QUESTIONS REPORT for SRO 77.204000G2.1.2
00 1/2/2/RWCU/BANK-MOD/HIGHER/HT2007
-30 l/SRO/BLC/RF
A A leak has developed on the RWCU system.The following conditions
currently exist: RWCU HX room ambient temperature (N016C)195°F RWCU HX room ambient temperature (N016D)195°FRWCUHX room differential
temperature (N022C/N023C)
1 05°FT RWCU HX room differential
temperature (N022D/NO*23D)
1 05°FT 158'elevation south east area (2D21-K601
B)1100mR/Hr Based on these current plant conditions, which ONE of the following choices describes the required operator actions in accordance
with the Secondary Containment
Control?[Reference
provided]A.A reactor shutdown per 34GO-OPS-013
or 34GO-OPS-014
is required.An immediate reactor scram is currently notAn immediate reactor scram is required.Emergency depressurization
is not required.C.An immediate reactor scram is required.Emergency depressurization
is required.D.A reactor shutdown is currently not required.Operate the HVAC per 34S0-T41-005
and attempt to isolate the RWCU leak.A.Incorrect because a primary system is discharging
and the differential
temperature
and area radiation level is greater than max safe.These conditions
require an immediate reactor scram.Plausible if the applicant knows that a reactor shutdown is required when an area is above max safe and the leak is NOT a primary system.B.Correct.C.Incorrect because an emergency depressurization
is not required.Plausible since the applicant may not know that the two area temps (or two ambient temps)are in the same area (and therefore do not meet the intent of two areas above max safe.)D.Incorrect because ventilation
systems should NOT be operated when a secondary containment
radiation condition exists.Also incorrect because a reactor scram is required based on a primary system discharging
with one area differential
temperature
above max safe.Plausible if applicant interprets
the differential
temperature
as an ambient temperature.
Friday, September 28,20079:24:39
AM 3
QUESTIONS REPORT for SRO This question is SRO only because it is tied to 10CFR55.43(5).
Do NOT provide the flowchart to the applicant as a reference.
Provide ONLY Table 4 and Table 6 as a reference to the applicant.
SYSTEM: 204000 Reactor Water Cleanup System 2.1.2 Knowledge of operator responsibilities
during all modes of plant operation.(CFR: 41.10/45.13)
IMPORTANCE
3.0/4.0 References
31EO-EOP-014-2, Secondary Containment
Control Flowchart Tier: 2 Group: 2 Keyword: RWCU Source: BANK-MOD Cog Level: HIGHER Exam: HT2007-301
Test: SRO Author/Reviewer:
BLC/RFA Friday, September 28, 2007 9:24:39 AM 4
QUESTIONS REPORT for SRO 78.211 000G2.1.14
002/2/1/E-
PLANINEW/HIGHER/HT2007
-30 I/SRO/BLC/RF
A A transient has occurred involving a failure to scram (ATWS)that requires Standby Liquid Control (SLC)intiation per the emergency operating procedure guidance.Based on this status, which ONE of the following identifies
the required personnel notifications
in accordance
with 73EP-EIP-004-0, Duties of Emergency Director?At:'Dismissal of non-essential
personnel from the plant site is mandatory.
Notification
of protective
action recommendations (PARS)to state and local authorities
is NOT mandatory for these conditions.
B.Dismissal of non-essential
personnel from the plant site is mandatory.
Notification
of protective
action recommendations (PARS)to state and local authorities
IS mandatory for these conditions.
C.Dismissal of non-essential
personnel from the plant site is NOT mandatory.
Staff augmentation
MUST be performed if the emergency event is occurring outside of normal working hours, on the weekend, or on a holiday by activating
the HNP Autodialer
System in the control room.D.Dismissal of non-essential
personnel from the plant site is NOT mandatory.
The emergency response facilities (ERFs)MUST be activated.
A.Correct.B.Incorrect because these conditions
represent a site area classification, (new E-Plan classification
is SS2)which does not necessarily
require a mandatory PAR.Plausible if applicant thinks that this is a general emergency classification.
C.Incorrect because a site*evacuation
is required (73EP-EIP-004-0, Step 7.4.11).Plausible if applicant thinks that this is an Alert classification.
D.Incorrect because asiteevacuation
is required (73EP-EIP-004-0, Step 7.4.11).Plausible if the applicant thinks that this is an Alert classification.
SRO only based on 10CFR55.43
(5): assessment
of facility conditions
and selection of procedures
Do NOT provide any references
for this question.SYSTEM: 211000 Standby Liquid Control System 2.1.14 Knowledge of system status criteria which require the notification
of plant personnel.(CFR: 43.5/45.12)IMPORTANCE
2.5/3.3 References
DRAFT 73EP-EIP-OOI-0, Emergency Classification
and Initial Actions 73EP-EIP-004-0, Duties of Emergency Director Friday, September 28, 2007 9:24:39 AM 5
Tier: Keyword: Cog Level: Test: 2 E-PLAN HIGHER SRO QUESTIONS REPORT for SRO Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:39 AM 6
QUESTIONS REPORT for SRO 79.212000A2.20
00 1/2/1/RPS/NEW
/HIGHERJHT2007
-30 l/SRO/BLC/RF
A During an outage, maintenance
is in progress on seven hydraulic control units'(HCUs)
to replace the scram valve diaphrams.
The following conditions
currently exist: Mode switch: REFUEL position, all rods inserted Discharge volume isolation test switch: ISOLATE position, under clearance Scram discharge volume high level bypass switch: NORMAL position Due to a clearance error, one of the HCUs begins to slowly fill the discharge volume as the mechanics begin working and the following alarm is received: SCRAM DISCH VOL NOT DRAINED (603-119)With these current conditions, which ONE of the following describes the operation of the RPS logic and the technical specification
allowan'ces
associated
with the high level bypass switch?At:I A reactor scram has NOT occurred.Placing the high level bypass switch in the bypass position will PREVENT a scram.Bypassing this trip does NOT require entering ,.an RPS Instrumentation
LCO action.B.A reactor scram has NOT o*ccurred.
Placing the high level bypass switch in the bypass position will PREVENT a scram.Bypassing this trip does requires entering an RPS Instrumentation
LCO action.C.A reactor scram has occurred.If the high level switch had been in the bypass position, the scram would have still occurred.Bypassing this trip does NOT require entering an RPS Instrumentation
LCO action.D.A high level scram has occurred.If the high level switch had been in the bypass position, the scram would have been PREVENTED.
Bypassing this trip requires entering an RPS Instrumentation
LCO action.Friday, September 28, 2007 9:24:39 AM 7
Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF AQUESTIONSREPORT
for SRO A.Correct.B.Incorrect becausethebypass switch will work when the mode switch is in Refuel (or shutdown).
Also incorrect because the high level trip is only required in Mode 5 IF a rod is withdrawn.
Plausible if applicant doesn't know that the bypass switch also works when the mode swtich is in the refuel position (versus only the shutdown position).
C.Incorrect because the not drained alarm comes in at 3 gallons;whereas the high level trip occurs at 63 gallons, i.e., a scram has not occurred yet.Also incorrect because the bypass switch will prevent the high level trip when the mode switch is in Refuel (or shutdown).
Plausible if applicant doesn't know alarm setpoint and thinks that the bypass switch only works when the mode switch is in the shutdown position.D.Incorrect because the not drained alarm comes in at 3 gallons;whereas the high level trip occurs at 63 gallons, i.e., a scram has not occurred yet.Also incorrect because the high level trip is only required in Mode 5 IF a rod is withdrawn.
Plausible if applicant doesn't know alarm setpoint and thinks that this trip feature is required during mode 5 with all rods inserted.SRO only because of A2 K&A and 10CFR55.43
(2): Facility operating limitations
in the technical specfications
and their bases.A2.Ability to (a)predict the impacts of the following on the REACTOR PROTECTION
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)A2.20 Full system activation (full-SCRAM)
..4.1*/4.2*References
34AR-603-119-1, Scram Disch Vol Not Drained annunciator
procedure 34AR-603-101-1, Scram Disch Vol High Level Trip alarm procedure 34AR-603-110-1, Scram Disch Vol High Level Trip Bypass alarm procedure Tech Spec 3.3.1.1, RPS Instrumentation
Tier: 2 Keyword: RPS Cog Level: HIGHER Test: SRO Friday, September 28, 2007 9:24:39 AM 8
QUESTIONS REPORT for SRO 80.215004A2.02
002/2/1/REFUEL/NEW/HIGHERlHT2007-301/SRO/BLC/RFA
A complete core offload was performed at the begining of a refueling outage.Four bundles have just been reloaded around SRM"0" and the prescribed
fuel reload sequence continues by spiralling
outward from SRM"D." The operability
status of the remaining SRMs are: SRM"A" is inoperable;
post maintenance
testing is in progress All other SRMs are operable During the testing on SRM"A", the operator inadvertently
withdraws the SRM"c" detector a small amount and the following alarms are received: SRM DETECTOR RETRACTED WHEN NOT*PERMITTED
(603-222)ROD OUT BLOCK (603-238)Which ONE of the following identifies
the impact on refueling operations?
must now be suspended.Core alterations
may continue in the northwest quadrant.C.Core alterations
may continue only in the northeast quadrant.D.Core alterations
may continue anywhere in the core except in the quadrant where SRM"A" is located.A.Incorrect because core alterations
are allowed in a quadrant without an a9jacent operable SRM provided that the bundles being spiral reloaded are in a single fueled region containing
an operable SRM.Plausible if applicant does not know that tech specs allows refueling with only one operable detector.B.Correct.C.Incorrect
the partially withdrawn SRM is inoperable.
Plausible if applicant knows that the single fueled region tech spec LCO provision was exercised to begin the reload.D.Incorrect because SRM C is inoperable
due to being partially withdrawn.
Also incorrect because core alterations
may not be performed in the southwest quadrant where SRM"c" is located.Friday, September 28, 2007 9:24:39 AM 9
Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO SRO only because this is linked to 10CFR55.43(6):
Procedures
and limitations
involved in intial core loading, alterations
in core configuration, control rod programming, and determination
of various internal and external effects on core reactivity.
Also linked to Techspecs3.3.1.2
A2.Ability to (a)predict the impacts of the following on the SOURCE RANGE MONITOR (SRM)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)A2.02 SRM inop condition.
...3.4/3.7 References:
C51-SRM-LP-01201, SRM lesson plan TS 3.3.1.2, SRM Instrumentation
34AR-603-222, SRM Detector Retracted When Not Permitted annunciator
procedure 34AR-603-238, Rod Out Block annunciator
procedure F15-RF-LP-04502, Refueling Tier: 2 Keyword: REFUEL Cog Level: HIGHER Test: SRO Friday, September 28, 2007 9:24:39 AM 10
QUESTIONS REPORT for SRO 81.245000A2.07
00 1/2/2/EHC/NEW
/HIGHER/HT2007
-30 l/SRO/BLC/RF
A Due to a slowly degrading condenser vacuum leak on Unit 1, the control room crew has reduced reactor power from rated power over the last several hours.Current plant conditions
are: 285 MW(e)Condenser vacuum at 25.0"Hg and steady The SRO is evaluating
whether the current power configuration
will facilitate
a manual turbine trip while maintaining
the reactor critical.Which ONE of the following predicts the plant response if the turbine is manually tripped at this power, including the required procedure to be implemented
after the turbine is manually tripped?A.Steam flow will be within the capacity of the bypass valves.Enter 34GO-OPS-005-1, Power Changes, to adjust reactor power if necessary after the turbine is manually tripped.B.Steam flow will be within the capacity of the bypass valves.Enter 34GO-OPS-013-1, Normal Plant ShutdownSteam flow will NOT be within the capacity of the bypass valves.Enter 34AB-C71-001-1, Scram Procedure D.Steam flow will NOT be within the capacity of the bypass valves.Enter 34GO-OPS-005-1, Power Changes, after the turbine is tripped to lower reactor power.A.Incorrect because 285 MW(e)is more than 25%rated steam flow (bypass capacity).
285 MW(e)is also above the first stage turbine pressure bypass point (27.60/0 power=260 MW(e).Also incorrect because 34GO-OPS-005-1
is only used when reactor power level is greater than 350/0.Plausible if applicant doesn't know rated electrical
on Unit 1 (-91 5 MW(e)B.Incorrect because 285 MW(e)is more than 250/0 rated steam flow (bypass capacity).
285 MW(e)is also above the first stage turbine pressure bypass point (27.60/0 power=260 MW(e).Plausible if applicant doesn't know rated electrical
on Unit 1 (-915 MW(e)C.Correct.D.Incorrect because 34GO-OPS-005-1
is only used when reactor power level is greater than 35%.Plausible if the applicant thinks that the RPS turbine trip will be bypassed but forgets that the Reactor High Pressure scram will cause a scram.Plausible if applicant reasons that this procedure was previously
being used during the preceding power reduction(s).
Friday, September 28, 2007 9:24:39 AM 11
QUESTIONS REPORT for SRO SRO-only due to link to lOCFR55.43
(5): Assessment
of plant conditions
and selection of appropriate
procedures.
A2.Ability to (a)predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS;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)A2.07 Loss of reactor/turbine
pressure control system: Plant-Specific
3.8/3.9 References
34 AB-N 61-002-1, Main Condenser Vacuum Low 34AR-650-148-1, Turbine Vacuum Low-Low annunciator
procedure 34GO-OPS-005-1, Power Changes 34GO-OPS-013-1, Nonnal Plant Shutdown B21-SLLS-LP-01401, Main Steam&LowLow Set lesson plan Tier: 2 Group: Keyword: EHC Source: Cog Level: HIGHER Exam: Test: SRO Author/Reviewer:
Friday, September 28,2007 9:24:39 AM 2 NEW HT2007-301
BLC/RFA 12
QUESTIONS REPORT for SRO 82.262001A2.08
003/2/1/4160V
ACINEW/FUND/HT2007
-30 l/SRO/BLC/RF
A While performing
an electrical
tagout, a system operator inadvertently
opened breaker#1 in 125VDC Cabinet1D (1 R25-S004)which proviqes control power to a 4160VAC emergency bus.Subsequent
attempts to re-close the breaker are unsuccessful, i.e., the breaker keeps tripping open.Assuming that the 1A RHR SW Pump was initially.running
for a surveillance
test, which ONE of the following states how this pump's 4160 VAC breaker will be affected by the loss of control power, including the correct procedure needed to operate the breaker?A.The pump breaker will automatically
open.The control power undervoltage
trip must be disabled in accordance
with 34AB-R22-001-1, Lpss of DC Busses, in order to close ANY of the breakers on this emergency bus.B.The pump breaker will automatically
open.The control power undervoltage
trip must be disabled in accordance
with 34AB-R22-001-1, Loss of DC Busses, in order to re-close ONLY this breaker on this emergency bus.The pump will continue to run.The ONLY way to stop the pump is to depress the button marked"push-to-trip" (inside the breaker cubicle)in accordance
with 34S0-R22-001-1, 4160VAC System.D.The*pump will continue to run.The ONLY way to stop the pump is to depress the button marked"push-to-trip" (inside the breaker cubicle)in accordance
with 34AB-R22-001-1, Loss of DC Busses./Friday, September 28, 2007 9:24:39 AM 13
QUESTIONS REPORT for SRO A.Incorrect because only a few breakers have this auto-open feature and they are only located on 4160VAC emergency bus 1F.(This pump is powered from 1E.)Also incorrect because this AOP does not provide guidance for overriding
this trip feature.Plausible because this trip-open feature does exist on the1C RHR SW pump.B.Incorrect because only a few breakers have this auto-open feature and they are only located on 4160VAC emergency bus 1 F.Also incorrect because this AOP does not provide guidance for overriding
this trip feature.Plausible if the applicant knows that this AOP provides guidance for restoring control power.C.Correct.D.Incorrect because the loss of control power renderstheswitch on the outside of the cubicle door inoperable.
Also incorrect becausetheswitch on the outside of the door only works when the breaker is racked in the TEST position.Also incorrect because the guidance to locally open the breaker is not found in the AOP.Plausible if the applicant remembers that the charging spring will still be charged.SRO only because linked to lOCFR55.43(5):
Assessment
of facility conditions
and selection of appropriate
procedures
during normal, abnormal, and emergency situations.
A2.Ability to (a)predict the impacts of the following on the A.C.ELECTRICAL
DISTRIBUTION;
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)A2.08 Opening a disconnect
under load.....3.3/3.6 References
34S0-R22-001-1, 4160VAC System R22-4160VAC-LP-02702, 4160 VAC lesson plan 34AB-R22-001-1, Loss of DC Buses AOP Tier: 2 Keyword: 4160VAC Cog Level: FUND SRO Friday, September 28, 2007 9:24:39 AM Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A 14
QUESTIONS REPORT for SRO 83.295003AA2.04
00 l/l/l/TRANSFORMERINEW
/HIGHERlHT2007
-30 l/SRO/BLC/RF
A Unit 1 and 2 are operating at 100%power with all4KV busses normally aligned.A transformer
fire and fault occurs on Startup transformer
2C and all automatic actions associated
with the transformer
fault occur as expected.Which ONE of the following identifies
how the unavailability
of the transformer
affects the AC system lineup and describes the performance
of the 34SV-SUV-013-0, Weekly Breaker Alignment surveillance?
At:'BOTH units are in an active LCO for 3.8.1, AC Sources-Operating The surveillance
is required to be performed WITHIN 1 HOUR even though its acceptance
criteria will NOT be met.B.BOTH units are in an active LCO for 3.8.1, AC Sources-Operating'The surveillance
is required to be performed IMMEDIATELY
even though its acceptance
criteria will NOT be met.C.ONLY Unit 2 is in an active LCO for 3.8.1, AC Sources-Operating The surveillance
is required to be performed IMMEDIATELY
and its acceptance
criteria WILL be met.D.ONLY Unit 2 is in an active LCO for 3.8.1, AC Sources-Operating The surveillance
is required to be performed WITHIN 1 HOUR and its acceptance
criteria WILL be met.Friday, September 28, 2007 9:24:39 AM 15
Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO Note: Both SATs1C and 2C are fed from the same point on the 230 kV grid.A SAT 2C fault results in PCB s 179470,179480
tripping open, which affects SAT 1C availability.
A.Correct B.Incorrect because TS 3.8.1.A.1 requires surveillance
within one hour.Plausible because action statement is similar time frame.C.Incorrect because both units will be in an active LCD.Also incorrect becau.se TS 3.8.1.A.1 requires surveillance
within one hour.Plausible because transformer
is on Unit 2.D.Incorrect because both units will be in an active LCD.Also incorrect because the acceptance
criteria will not be met.Plausible because transformer
is on Unit 2.SRO only because of tie to lOCFR55.43(2):
Tech specs AA2.Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.POWER: (CFR: 41.10/43.5/45.13)
AA2.04 System lineups 3.5/3.7 References
34SV-SUV-013-0, Weekly Breaker Alignment Checks S22-ELECT-LP-0270 1, Electrical
Distribution
System lesson plan Tech Spec 3.8.1, AC Sources-Operating Tier: 1 Keyword: TRANSFORMER
Cog Level: HIGHER Test: SRO Friday,'September
28,2007 9:24:39 AM'16
QUESTIONS REPORT for SRO 84.295004AA2.02
OOI/I/I/DC
POWERINEW/FUND/HT2007-30I/SRO/BLC/RFA
Unit 2 was operating at 500/0 power when the 125VDG Distribution'Gabinet
20, 2R25-S129 was lost and the following annunciator
was received: ECCS/RPS DIVISION 1 TROUBLE (602-110)The SRO is in the process of identifying
which analog transmitter
trip system (ATTS)units were affected and is performing
a loss of safety function determination
in accordance
with the Technical Requirements
Manual (TRM).Which ONE of the following identifies
the affected analog transmitter
trip units and describes the TRM Loss of Function Diagrams (LFD)?A.Two RPS ATTS cabinets will be de-energized.
The loss of function statement found at the bottom of the LFD identifies
the channel combinations
which are no longer available for the safety function.B.Two RPS ATTS cabinets will be de-energized.
The loss of function statement found at the bottom of the LFD identifies
the channel combinations
req.uired to be operable in order to maintain the safety function.Two EGGS ATTS cabinets will be de-energized.
The loss of function statement found at the bottom of the LFD identifies
the channel combinations
required to be operable in order to maintain the safety function.D.Two EGCS ATTS cabinets will be
The loss of function statement found at the bottom of the LFD identifies
the channel combinations
which are no longer available for the safety function.Friday, September 28, 2007 9:24:39 AM 17
QUESTIONS REPORT for SRO Each ATTS panel has two internal power supplies.Only one power supply needs to be available to supply the entire ATTS panel.The ECCS division consists of panels H 11-P925, P926, P927 and P928.'125VDC Dist Cab 2D Breakers 1&2 power up both of the power supplies for panel 2H11-P925.
Breakers 5&7 power up both'of the power supplies for paneI2H11-P927.
The loss of function statement typically found at the bottom of the LFD identifies
the channel combinations
required to be operable in order for instrument
function capability
as defined in the instrumentation
specification
to be maintained.
A.Incorrect because the DC cabinet which was lost does not provide power to the RPS ATTS cabinets.Also'incorrect
because the LFD identifies
the channels required for the safety function.Plausible since RPS ATTS cabinets are similar to the ECCS cabinets.B.Incorrect because the DC cabinet which was lost does not provide power to the RPS A TTS cabinets.C.Correct.D.Incorrect because the LFD identifies
the channels required for the safety function.Plausible if applicant does not understand
the content provided in LFDs.SRO only because linked to lOCFR55.43
(2): Tech specs AA2.Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C.POWER: (CFR: 41.10/43.5
/45.13)AA2.02 Extent of partial or complete loss of D.C.power....3.5/3.9 References
TRM Section 11.0, Loss of Function Diagrams 34AB-R22-001-2, Loss of DC Buses AOP 34AR-602-110-2, ECCS/RPS Division 1 Trouble annunciator
procedure Tier: 1 Group: Keyword: DC POWER Source: Cog Level: FUND Exam: Test: SRO Author/Reviewer:
Fripay, September 28, 2007 9:24:39 AM 1 NEW HT2007-301
BLC/RFA 18
QUESTIONS REPORT for SRO 85.295014G2.4.31
00 1/1/2/RODS/NEW
/HI GHER/HT 2 007-30 l/SRO/BLC/RF
A Unit 2 is starting up and reactor power is 140/0 power.The operator is pulling rods to achieve 2 bypass valves to roll the turbine.Due to a previous rod being difficult to move, the CRD drive water pressure had been temporarily
raised to 300 psid and not re-adjusted
back down to a normal pressure.When the operator placed the rod movementcontrolswitch
to the single notch out position for the next control rod, the rod quickly moved from position 16 to 22.(intended position was 18)Which ONE of the following identifies
an expe,cted annunciator
that will be received and the evaluation
of this event?A.ROD OUT BLOCK (603-238)This is a mispositioned
control rod.Tech Spec 3.1.6.Rod Pattern Control has a required action statement.
B.ROD DRIFT (603-247)This is NOT a mispositioned
control rod.Tech Spec 3.1.3 Control Rod Operability
has a required action statement.RMCS/RWM ROD BLOCK OR SYSTEM TROUBLE (603-239)This is a mispositioned
rod.There are no required actions for tech specs for this condition.
D.ROD OVERTRAVEL
(603-248-1)
This is NOT a mispositioned
rod.There are no required actions for tech specs in this condition.
Friday, September 28, 2007 9:24:39 AM 19
Group: 2 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO Note: This condition will cause both annunciators
603-238&603-239 to alarm.A.Incorrect because BPWS Tech Spec is only applicable
in Modes 1&2 when thermal power is<100/0.Plausible because this alarm will be received and the rod is considered
mispositioned
lAW 34GO-OPS-065-0, Section 7.5.1 B.Incorrect because the rod is considered
mispositioned
lAW 34GO-OPS-065-0, Section 7.5.1.(Alarm may not be received.)
Plausible if applicant thinks that the rod is inoperable.
C.Correct.D.Incorrect because this alarm is only applicable
for full-out position 48.Also incorrect since rod is considered
mispositioned
lAW 34GO-OPS-065-0, Section 7.5.1.Plausible if applicant knows that tech specs do not apply and does not understand
the alarm input.SRO only because this question is tied to tech spec 10CFR55.43
(2)APE: 295014 Inadvertent
Reactivity
Addition.2.4.31 Knowledge of annunciators
alarms and indications
/and use of the response instructions.(CFR: 41.10/45.3)
IMPORTANCE
3.3/3.4 References
34GO-OPS-065-0, Control Rod Movement 34AR-603-248-1, Rod Overtravel
procedure 34AR-603-247-1, Rod Drift annunciator
procedure 34AR-603-238-1, Rod Out Block annunciator
procedure 34AR-603-239-1, RMCS/RWM Rod Block or System Trouble annunciator
procedure 34AB-C11-004-1, Mispositioned
Control Rods Tech Spec 3.1.6, Rod Pattern Control Tech Spec 3.1.3, Control Rod Operability
Tier: 1 Keyword: RODS Cog Level: HIGHER Test: SRO Friday, September 28, 2007 9:24:39 AM 20
QUESTIONS REPORT for SRO 86.295020AA2.04
00 1/1/2/HPCI/RCIC/NEW
/HI GHER/HT 2 007-3 0 l/SRO/A heatup and pressurization
on Unit 2 was in progress with the following plant conditions:
Reactor pressure: 130 psig HPCI/RCIC:
Operable in standby lineup MSIVs: Closed The heatup and pressurization
was temporarily
stopped to accomodate
opening the MSIVs in accordance
with 34GO-OPS-001-2, Attachment
2, (Opening the MSIVs with Reactor Pressure>0 psig.)While pressure was being equalized across the MSIVs, reactor pressure gradually lowered to 125 psig.Once the MSIVs were open, the crew re-commenced
the heatup and pressurization
by withdrawing
control rods and reactor pressure is now at 160 psig.(no other actions have been taken)Which ONE of the following describes the impact on the startup and the actions which are allowed by tech specs given the current status of HPCI and RCIC?A.The heatup and pressurization
can continue.The mode switch may be taken from startup to run.Restore HPCI to operable within 14 days.The heatup and pressurization
can continue.The mode switch may NOT be taken to run.Restore HPCI to operable within 14 days.C.The heatup and pressurization
can NOT continue.The mode switch may NOT be taken to run.Reduce steam pressure to=150 psig within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.D.The heatup and pressurization
can NOT continue.Place the mode switch to the shutdown position in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Reduce steam pressure to=150 psig within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.Friday, September 28, 2007 9:24:39 AM 21
QUESTIONS REPORT for SRO HPCI isolated at 128 psig.The crew should recognize that reactor pressure (125 psig)lowered below the HPCI isolation setpoint while they were equalizing
across the MSIVs.Thus;an inadvertent
containment
isolation (Group 3)has occurred.A.Incorrect because LCO 3.0.4 condition a or c cannot be met.Plausible if applicant thinks that LCO 3.0.4 condition b applies.B.Correct.C.Incorrect because the heatup and pressurization
in Mode 2 can continue.Plausible if applicant thinks that the LCO can be exited by simply lowering pressure.D.Incorrect because the heatup and pressurization
in Mode 2 can continue with RCIC operable.Plausi.ble
if the applicant thinks that both HPCI and RCIC have isolated and that Condition E is applicable.
SRO only because this question is tied to lOCFR55.43(2):
Facility operating limitations
in the technical specifications
and their bases.AA2.Ability to determine and/or interpret the following as they apply to INADVERTENT
CONTAINMENT
ISOLATION: (CFR: 41.10/43.5/45.13)
AA2.04 Reactor pressure 3.9/3.9 References
.34GO-OPS-001-2, Plant Startup procedure.Tech Spec 3.5.1, ECCS-Operating
34S0-E41-001-2, HPCI procedure E51-RCIC-LP-03901, RCIC lesson plan Tier: 1 Keyword: HPCI/RCIC Cog Level: HIGHER.Test: SRO Friday, September 28, 2007 9:24:.39 AM Group: Source: Exam: Author/Reviewer:
2 NEW HT2007-301
22
QUESTIONS REPORT for SRO 87.295025EA2.06
OOI/l/l/STEAM
COOLING/MODIFIED
BANK/HIGHER/HT2007-301/SRO/BLC/RFA
A loss of§!!high and low pressure injection has occurred on Unit 2 with the following conditions:
All rods inserted Reactor Water Level.-190 inches and decreasing
2"/min Reactor Pressure 858 psig being controlled
by LLS logic Steam Cooling is in progress Because of successful
maintenance
efforts, HPCI has become available and the crew has just started injecting to the vessel.The current reactor water level is-189 inches and rising.Given these conditions, which ONE of the following procedures
is required to be implemented?
.A.CP-2, RPV Flooding B.CP-1, Steam Cooling C.CP-1, Emergency DepressurizationRC RPV Control (Non-ATWS)
EOPs require remaining pressurized
following a loss of all high and low pressure injection systems and beginning steam cooling (@-185")UNTIL an injection system is regained;then ED.In this case ED'g will eliminate the injection system (HPCI);and EOPs specifically
exempt ED in this situation.
The question satisfiesKA
because requires interpretation
of RPV water level as it pertains to high reactor pressure, i.e.being in steam cooling.A.Incorrect because level instrumentation
is available.
Plausible because this is,an override step in the steam cooling procedure.
B.Incorrect because an override step in the steam cooling procedure states that if reactor water level is increasing, then perform RC/P (non atws).Plausible if the applicant realizes that level is still less than-185" (entry condition for steam cooling).C.Incorrect because an override step in the steam cooling procedure states that if any system is regained then emergency depressurization
is required IF level cannot be restored.Since level is being restored, then emergency depress is not required.Plausible if the
fails to assess that level is being raised and strictly adheres to the override step.D.Correct.Friday, September 28, 2007 9:24:39 AM 23
QUESTIONS REPORT for SRO SRO only because of link to lOCFR55.43
(5): Assessment
of facility conditions
and selection of appropriate
procedure.
EA2.Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: (CFR: 41.10/43.5/45.13)EA2.06 Reactor water leve1.3.7/3.8[N 0 reference provided to applicant]
References
Licensee's
LOR Exam Bank (modified)
Media Number: LR-LP-20309
Objective Number: 201.083.A.04
LR-LP-201083
SRO NRC CAT-B, RO NRC CAt-B, Active--1, References
-31EO-EOP-015-2S, rls, KeyWords-PUBLISH, PROCEDURE,BIENNIAL(B)
EOP-CP1-LP-20309, Contingency
Procedures (CP-1)lesson plan Tier: Keyword: Cog Level: Test: 1 STEAM COOLING HIGHER SRO Group: 1 Source: MODIFIED BANK Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:39 AM 24
QUESTIONS.REPORT for SRO 88.295026G2.1.28
001/1/1/TORUS
TEMP/NEW/FUND/HT2007-301/SRO/BLC/RFA
Which ONE of the following describes the suppression
pool water temperature
instrumentation
and tech spec 3.3.3.1, Post Accident Monitoring (PAM)instrumentation
channel requirements?
[Reference
provided]A.The T48-R647 recorder receives input from only the upper temperature
elements.The 2 torus temperature
channels required by TS 3.3.3.1 can ONLY be comprised of two lower elements, i.e., N009A-D.B.The T48-R647 recorder receives input from both upper and lower temperature
The 2 torus temperature
channels required by TS 3.3.3.1 can ONLY be comprised of two lower elements, i.e., N009A-DThe T 48-R64 7 recorder receives input from only the upper temperature
elements.The 2 torus temperature
channels required by TS 3.3.3.1 can ONLY be comprised of one lower element (N009A-D)AND one upper element.(N301-N311)
D..The T48-R647 recorder receives input from both upper and lower temperature
elements..The 2 torus temperature
channels required by TS 3.3.3.1 can ONLY be comprised of one lower element (N009A-D)AND one upper element.(N301-N311)
A.Incorrect because TRM Table 10.3-1 requires one N009 and one N300 temperature
element.Plausible since the TS function is for pool water temperature.
B.Incorrect because T48-R647 only receives input from the N300 elements.Also incorrect because TRM Table 10.3-1 requires one N009 and one N300 temperature
element.Plausible since the TS function is for pool watetr temperature.
C.Correct D.Incorrect because recorder T48-R647 only receives input from N300 elements.Plausible since this recorder is for torus temperature
indication.
SRO only because of tie to 10CFR55.43
(2): Tech specs Provide applicant only the Tech Spec 3.3.3.1.(Don't provide TRM)295026 Suppression
Pool High Water Temperature
2.1.28 Knowledge of the purpose and function of major system components
and controls.(CFR: 41.7)IMPORTANCE
3.2/3.3 34SV-SUV-019-1/2, Attachment
2, Torus Temperature
Monitoring
TS 3.3.3.1, PAM Instrumentation
TRM Table T10.3-1, Sheet 5 of7, Qualified Post Accident Monitoring
Instrumentation
34 AR-657-072-1, Multipoint
Rcdr1T 47-R611 Temp High annunciator
procedure 34 AR-6 54-009-1, Multipoint
Rcdr1T 47-R612 Temp High annunciator
procedure Friday, September 28, 2007 9:24:39 AM 25.
Tier: Keyword: Cog Level: Test: 1 TORUS TEMP FUND SRO QUESTIONS REPORT for SRO Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:39 AM 26
QUESTIONS REPORT for SRO 89.295028EA2.06
OOI/l/l/DW
TEMP/NEW/FUND/HT2007-301/SRO/BLC/RFA
A loss of drywell cooling has occurred.The SRO reaches the following ste.p in the primary containment
control flowchart drywell temperature
leg: P:ERF:O:RM
- C:O:N:C:URRENTLY
RC:[Ajpoiint
A Which ONE of the following describes the meaning of the word"Bulk" and the tech spec bases for the drywell temperature
limiting condition of operation?
A."Bulk" means a weighted average of the containment
atmosphere, i.e., drywell AND the torus air spaces.In the event of a DBA, with the intial drywell average air temperature
=340 of, the resultant peak accident temperature
is maintained
below the drywell design temperature.
B."Bulk" means a weighted average of the containment
atmosphere, i.e., drywell AND the torus air spaces.During a DBA, with the intial drywell average air temperature
=150 of, the resultant peak accident temperature
is maintained
below the drywell design temperature.
c."Bulk" means a weighted average of ONLY the drywell air space temperature.
During a DBA, with the intial drywell average air temperature
=340 of, the resultant peak accident temperature
is maintained
below the drywell design temperature."Bulk" means a weighted average of ONLY the drywell air space temperature.
During a DBA, with the intia!drywell average air temperature
=150 of, the resultant peak accident temperature
is maintained
below the drywell design temperature.
,.Friday, September 28,20079:24:39
AM 27
Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO A.Incorrect because bulk implies average.Also incorrect because analyses require a drywell starting temperature
of=150 to preclude reaching the 340 OF design temperature
of containment.
Plausible if applicant does not know the definition
of bulk or does not know the LCO bases.B.Incorrect because bulk implies average.Plausible if applicant thinks that the drywell also includes the torus airspace.C.Incorrect because analyses require a drywell starting temperature
of=150 to preclude reaching the 340 OF design temperature
of containment.
Plausible if applicant does not know the LCO bases.D.Correct.SRO only because of link to 10CFR55.43
(5): Tech Spec 3.6.1.5 bases for 150 deg LCO limit.Per discussion
w/RFA on 9/25/07: Ability to differentiate
between torus air space and drywell air space is implied.EA2.Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE: (CFR: 41.10/43.5/45.13)EA2.06 Torus/suppression
chamber air space temperature:
Plant-Specific
3.4/3.7 References
'EOP-TERMS-LP-20304, EOP Terminology
&Definitions
TS 3.6.1.5, Drywell Air Temperature (including
bases)TRM Table TI0.3-1, Qualified Post Accident Monitoring
Instrumentation
34SV-SUV-019-1, Surveillance
Checks Tier: 1 Keyword: DW TEMP Cog Level: FUND Test: SRO Friday, September 28, 2007 9:24:39 AM 28
QUESTIONS REPORT for SRO 90.295033G2.4.50
00 1/1/2/REFUEL/NEW
/HIGHER/HT2007
-30 l/SRO/BLC/RF
A A refueling accident occurred in the Unit 1 fuel pool and the following alarms were received in the Unit 1 control room: REFUELING FLOOR VENT EXHAUST RADIATION HIGH REFUELING FLOOR AREA RADIATION HIGH The operator has determined
that the 1 D11-K611 A-D are causing the valid EXHAUST rad alarm and the refueling floor 1 D21-K601 0 is causing the valid AREA rad alarm.Which ONE of the following describes the significance
of these secondary containment
alarm setpoints?
[Reference
provided]A.The annunciator
setpoint for the EXHAUST rad monitor satisfies the entry condition value listed in the secondary containment
control table 6.The threshold for an alert classification, due to fuel damage by fuel handling accident, is NOT met.B.The annunciator
setpoint for the AREA rad monitor satisfies the entry condition value listed in the secondary containment
control table 6.The threshold for an alert classification, due to fuel damage by fuel handling accident, IS met.c.The ,annunciator
setpoint for the AREA rad monitor satisfies*
the entry condition value listed in the secondary containment
control table 6.The threshold for an alert classification, due to fuel damage by fuel handling accident, IS met.The annunciator
setpoint for the EXHAUST rad monitor DOES NOT meet the entry condition value listed in the secondary containment
control table 6.The threshold for an alert classification, due to fuel damage by fuel handling accident, is NOT met.Friday, September 28, 2007 9:24:39 AM 29
QUESTIONS REPORT for SRO REFUELING FLOOR VENT EXHAUST RADIATION HIGH (601-409)REFUELING FLOOR AREA RADIATION HIGH (601-110)A.Incorrect because the exhaust alarm is only HIGH (versus HIGH HIGH).Plausible if applicant does not know there is a HIGH HIGH alarm available.
B.Incorrect because the ARM setpoint is 15 mr/hr, i.e., the operator must used 1 D21-P600 recorder to determine reading.Also incorrect because alert classification
occurs above the alarm setpoint value, which cannot be determined
from the information
provided.Plausible if applicant does not know the alarm setpoint is below the 50 mr/hr threshold value.C.Incorrect because the ARM alarm setpoint is 15 mr/hr.The alert classification
is not reached or cannot be determined
from the information
provided.Plausible if applicant does not know the difference
between the HIGH HIGH alarm and the HIGH alarm D.Correct.Provide Reference:
Page 33 of 46 in 73EP-EIP-001-0, Section 18.0 Fuel Damage By Fuel Handling Accident Provide Reference:
Table 4 and Table 6 of Secondary Containment
Control (not flowchart)
SRO-only because linked to 10CFR55.43
(5): Assessment
of facility conditions
and selection of appropriaate
procedures
during normal, abnormal, and emergency situations.
Also linkedto10CFR55.43
(7): Fuel handling facilities
and procedures.
EPE: 295033 High Secondary Containment
Area Radiation Levels 2.4.50 Ability to verify system alann setpoints and operate controls identified
in the alann response manual.(CFR: 45.3)IMPORTANCE
3.3/3.3.References
31EO-EOP-O 14-1, Unit 1 Secondary Containment
Control flowchart 73EP-EIP-00I-0, Section 18, Fuel Damage By Fuel Handling Accident 34 AR-601-409-1, Refueling Floor Vent Exhaust Radiation High annunciator
procedure 34 AR-601-110-1, Refueling Floor Area Radiation High annunciator
procedure Tier: 1 Group: 2 Keyword: REFUEL Source: NEW Cog Level: HIGHER Exam: HT2007-301 Test: SRO Author/Reviewer:
BLC/RFA Friday, September 28, 2007 9:24:39 AM 30
QUESTIONS REPORT for SRO 91.295038G2.2.22
00l/1/1/RELEASE/NEW/FUND/HT2007-301/SRO/BLC/RFA
While operating at 1000/0 power, the following alarm is received: OIG AVG ANNUAL REL LIMIT WILL BE EXCEEDED (601-406-2)
Which ONE of the following radiation monitors triggered this alarm and which limiting condition of operation (LCO)includes the required actions if the radiation monitor is declared inoperable?
A.Offgas pretreatment
rad monitors (D11-K601 and K602)Main Condenser Offgas LCO 3.7.6 B!I Offgas pretreatment
rad monitors (D11-K601 and K602).Offsite Dose Calculation
Manual (ODCM)Gaseous Effluent Monitoring
Instrumentation
LCO 3.1.1 C.Stack offgas rad monitor (Normal range D11-K600A and B)Main Condenser Offgas LCO 3.7.6 D.Stack offgas rad monitor (Normal range D11-K600A and B)Offsite Dose Calculation
Manual (ODCM)Gaseous Effluent Monitoring
Instrumentation
LCO 3.1.1 A.Incorrect because LCO 3.7.6 does not include action statements
when this rad monitor becomes inoperable.
Plausible because the rad monitor alarm setpoint is based on the 240 micoCurie limiting condition of op*eration
in LCO 3.7.6.B.Correct.C.Incorrect because the alarm is not triggered by the stack rad monitor.Also incorrect because LCO 3.7.6 does not include action statements
when this rad monitor becomes inoperable.
Plausible because the rad monitor alarm setpoint is based on the 240 micoCurie limiting condition of operation in LCO 3.7.6.Also plausible if applicant does not know what causes alarm and simply relies on annunciator
wording.D.Incorrect because the alarm is not triggered by the stack rad monitor.Plausible if applicant simply relies on the annunciator
label or does not know the basis for gaseous instrumentation
setpoints in ODCM.SRO only because tied to 10CFR55.43
(2): Licensing basis ODCM EPE: 295038 High Off-Site Release Rate 2.2.22 Knowledge of limiting conditions
for operations
and safety limits.(CFR: 43.2 I 45.2)IMPORTANCE
3.4 14.1 References
LCO 3.7.6, Main Condenser Offgas HNP ODCM, Chapter 3, Gaseous Effluents 34AR-601-406-2, O/G Avg Annual ReI Limit Will Be Exceeded annunciator
procedure Friday, SeptE?mber
28, 2007 9:24:39 AM 31.
Tier: Keyword: Cog Level: Test: 1 RELEASE FUND SRO QUESTIONS REPORT for SRO Group: 1 Source:, NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:39 AM 32
QUESTIONS REPORT for SRO 92.400000A2.03
OOl/2/1/CCW/NEW/HIGHER/HT2007-301/SRO/BLC/RFA
Unit 2 is at.300/0 power during a startup after an extended outage when the following alarm is received: RBCCW HX OUTLET TEMP HIGH (650-249)The control room operator observes the RBCCW pump suction temperature
is 101°F and dispatches
the system operator to increase service water flow through the heat exchanger.
As the operator is locally throttling
open the service water valve, service water system pressure lowers below the RBCCW system pressure and the following alarm is received: HX PSW/RBCCW DIFF PRESS LOW (650-238)Which ONE of the following identiffes
a service water valve listed in the high temperature
procedure that should have been opened to correct the high temperature
condition and also identifies
the minimum required tech spec actions for the low pressure condition?
A.2P41-F440A, RBCCW Hx service water discharge valve.Service water grab samples are required to be taken once per shift even if the service water system effluent rad monitor is operable.B!'2P41-F440A, RBCCW Hx service water discharge valve.The service water system effluent rad monitor isrequiredto
be operable.Grab samples are not required to be taken.C.2P41-F491, RBCCW Hx-PSW discharge valve.The service water system effluent rad monitor isrequiredto
be operable.Grab samples are not required to be taken.D.2P41-F491, RBCCW Hx-PSW discharge valve.Service water grab samples are required to be taken once per shift even if the service water system effluent rad monitor is operable.Friday, September 28, 2007 9:24:39 AM 33
Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO The P41-F440A(B)
valves are the heat exchanger outlet valves whereas the P41-F491 valve is a common discharge valve for both heat exchangers.
The F491 valve will affect the pressure.A.Incorrect because the service water grab samples are ONLY required if the rad monitor is inoperable.
Plausible because this is one of the required actions listed in this ODCM LCO.B.Correct.C.Incorrect because this is not the valve listed in the high temperature
alarm procedure.
Plausible if the applicant knows that this valve is named in the dP alarm procedure to adjust the PSW IRBCCW differential
pressure.D.Incorrect because this is not the valve listed in the high temperature
alarm procedure.
Incorrect because the service water grab samples are ONLY required if the rad monitor is inoperable.
Plausible because this is one of the required actions listed in this ODCM LCO.Plausible if the applicant knows that this valve is named in the dP alarm procedure to adjust the PSW IRBCCW differential
pressure.Also plausible if applicant knows that dP alarm procedure states that if the dP instruments
are inoperable, then confirm the rad monitor is operable.SRO only because this question is tied to lOCFR55.43
(2): Facility operating limitations
in the technical specifications
and their bases.Also tied to lOCFR55.43
(5): Assessment
of facility conditions
and selection of appropriate
procedures
during normal, abnormal, and emergency situations.
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 operation: (CFR: 41.5/45.6)
A2.03 High/low CCW temperature
..2.9/3.0 References
34AR-650-238-2, Hx PSW/RBCCW DiffPress Low annunciator
procedure 34AR-650-249-2, RBCCW Hx Outlet Temp High annunicator
procedure 34S0-P42-001-1, Section 7.3.8, Adjusting RBCCW/PSW Differential
pressure HNP ODCM, Section 2.1.1, Liquid Effluent Monitoring
Instrumentation
Control P42-RBCCW-LP-00901, RBCCW lesson plan.2 Keyword: CCW Cog Level: HIGHER Test: SRO Friday, September 28, 2007 9:24:3.9 AM 34
QUESTIONS REPORT for SRO 93.600000G2.4.29
00 l/l/l/E-PLAN/MODIFIED
BANK/HIGHERlHT2007-30
l/SRO/BLC/RF
A Unit 2 is in a refueling outage and the"A" Loop of RHR is in shutdown cooling.The following events occurred at the times listed
10:00 am: Fire brigade dispatched
following a fire reported to the control room in an unidentified
electrical
panel in the Southwest corner of Unit 2 Reactor Building 130'elev.10:10 am: Fire brigade leader arrives at the scene and contacts the control room to inform the SRO that a breaker was on fire.10: 12 am: Fire brigade leader reports to control room that the power supply to 2E11-F015A
RHR injection valve (600V MCC E-A Frame 3C)was burning.Which ONE of the following describes the emergency plan classification
requirements?
A.Declare an Unusual Event beginning at 10:00.Do not declare an Alert.B.Declare an Alert beginning at 10:12.Do not declare an Unusual Event.C.Declare an Unusual Event beginning at 10:00.Declare an Alert beginning at 10:12.D.Declare an Unusual Event at 10:10.Do not declare an Alert.Need to cover this question with licensee....E-Plan classification
is'Changing at Hatch, but question will still work.This KIA was changed from 6000000 G2.4.49[Ability to perform w/o reference to procedures
those actions that require immediate operation of system components
and controls]TO 6000000 G2.4.29[Knowledge
of the emergency plan]BECAUSE the Hatch Fire AOP does not include any immediate actions.SRO only because of link to 10CFR55.43
(5): Assessment
of facility conditions
and E-plan classification.
APE: 600000 Plant Fire On Site 2.4.29 Knowledge of the emergency.plan.(CFR: 43.5/45.11)IMPORTANCE
RO 2.6/SRO 4.0 References
Draft 73EP-EIP-001-0, EMERGENCY CLASSIFICATION
AND INITIAL ACTIONS EP-LP-2010 1-03, Initial/Terminating
Activities
Friday, September 28, 2007 9:24:39 AM 35
Tier: Keyword: Cog
Test: 1 E-PLAN HIGHER SRO QUESTIONS REPORT for SRO Group: 1 Source: MODIFIED BANK Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:39 AM 36
QUESTIONS REPORT for SRO 94.G2.1.14 00 1/3/1INOTIFICATIONSINEW
/FUND/HT2007
-30 I/SRO/BLC/RF
A Which ONE of the following identifies
a plant personnel notification (including
the specific procedure)
that is first required when the reactor is made critical and is AGAIN required when the mode switch is transferred
to RUN?A!'On-shift Lab foreman In accordance
with 34GO-OPS-001-2, Plant Startup B.Northern/Southen
Control Center In accordance
with 34GO-OPS-001-2, Plant Startup C.Plant Manager lAW Reactivity
Management
Program, 40AC-ENG-016-0
D.Reactor Engineer lAW Reactivity
Management
Program, 40AC-ENG-016-0
A.Correct.B.Incorrect because the procedure does not state this because at these points, the dispatcher
is not affected.Plausible if applicant perceives that impending tie-to-the-grid
activities
are being approached.
C.Incorrect because the procedure does not state this.Plausible if applicant reasons that these plateaus are important for the plant manager to be aware of.D.Incorrect because the procedure does not state this.Plausible if applicant reasons that these plateaus are important for the reactor engineer to aware of.SRO only because of link to 10CFR55.43
(5): procedures
2.1.14 Knowledge of system status criteria which require the notification
of plant personnel.(CFR: 43.5/45.12)IMPORTANCE
2.5/3.3 References
34GO-OPS-001-2, Plant Startup Tier: 3 Keyword:.NOTIFICATIONS
Cog Level: FUND Test: SRO Friday, September 28, 2007 9:24:40 AM Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A 37
QUESTIONS REPORT for SRO 95.G2.1.7 00 1/3/1/0PRM/NEW/HIGHERlHT2007
-30 l/SRO/BLC/RF
A Unit 2 is operating with the following conditions:
Core flow is 50.82 Mlbm/hr Reactor power is 780/0 OPRMs are OPERABLE Given these plant conditions, which ONE of the following is correct?A':I The OPRMs are NOT armed at this point on the power-to-flow
map.Tech Specs require only the period based algorithm for the OPRM operability.
B.The OPRMs are armed at this point on the power-to-flow
map., Tech Specs require only the period based algorithm for the OPRM operability.
C.The OPRMs-are NOT armed at this point on the power-to-flow
map.Tech Specs require both the amplitude and period algorithms
for the OPRM operability.
D.The OPRMs are armed at this point on the power-to-flow
map.Tech Specs require both the amplitude and period algorithms
for the OPRM operability.
A.Correct B.Incorrect because this point is outside the OPRM armed region of>250/0 power and<600/0 core flow.Plausible if applicant does not know when the OPRMs auto-arm themselves.
C.Incorrect because only the period based algorithm is required by tech specs.Plausible if applicant does not know basis for OPRM trip function or reasons that two o.ut of three algorithmsarerequired
operable.D.Incorrect because this point is outside the OPRM armed region of>25°ft>>power and<600/0 core flow.Also incorrect because only the period based algorithm is required by tech specs.Plausible if applicant does not know when the OPRMs auto-arm themselves
or does not know the bases for the OPRM'trip function.SRO only because of link to 10CFR55.43
(2): Tech Specs bases 2.1.7 Ability to evaluateplantperformance
and make operational
judgments based onoperating
characteristics
/reactor behavior/and instrument
interpretation.(CFR: 43.5/45.12/45.13)IMPORTANCE
3.7/4.4 References
34GO-OPS-005-2, Power Changes, Attachment
1, Power-to-flow
map Tech Spec 3.3.1.1., RPS Instrumentation (including
bases)Friday, September 28,20079:24:40
AM 38
Tier: Keyword: Cog Level: Test: 3 OPRM HIGHER SRO QUESTIONS REPORT for SRO Group: 1 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:40 AM 39
QUESTIONS REPORT for SRO 96.G2.2.19 00 1/3/2/WORK/NEW
/FUND/HT2007
-30 l/SRO/BLC/RF
A In accordance
with 50AC-MNT-001-0, Maintenance
Program, which ONE of the following describes how"minor work" and"tool pouch work" are classified, including when a maintenance
work order (MWO)is required?At:I Minor work and tool pouch work are BOTH classified
as"minor maintenance." Minor Work is documented
with a CR or an MWO.Tool pouch work outside the power block does not require documentation.
B.Minor work and tool pouch work are BOTH classified
as"minor maintenance." Tool pouch work is documented
such as a CR or an MWO.Minor work outside the power block does not require documentation.
C.Tool pouch work is ONLY classified
as"elective maintenance." Minor work is ONLY classified
as"other maintenance." Minor Work is documented
with a CR or an MWO.Tool pouch work outside the power block does not require documentation.
D.Tool pouch work is ONLY classified
as"elective maintenance." Minor work is ONLY classified
as"other maintenance." Tool pouch work is documented
with a CR or an MWO.Minor work outside the power block does not require documentation.
A.C*orrect.B.Incorrect because minor work requ*ires documentation;
whereas tool pouch work sometimes doesn't require documentation.
Plausible if applicant does not know the titles of minor maintenance
sub-categories.
C.Incorrect because both tool pouch and minor work can be classified
as either corrective, elective, or"other." Plausible if applicant does not know that minor maintenance
can be involved with the three major categories
of maintenance
activities;
i.e.corrective, elective, or other.D.Incorrect because both tool pouch and minor work can be classified
as either corrective, elective, or"other." Also incorrect because minor work requires documentation;
whereas tool pouch work sometimes doesn't require documentation.
Plausible if applicant does not know that minor maintenance
can be involved with the three major categories
of maintenance
activities;
i.e.corrective, elective, or other OR also plausible if applicant does not know the titles of the sub-categories
of minor maintenance.
Friday, September 28, 2007 9:24:40 AM 40
Group: 2 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO SRO-only because of job/task requirements
for Work Control Center.2.2.19 Knowledge of maintenance
work order requirements.(CFR: 43.5/45.13)IMPORTANCE
2.1/3.1 References
50AC-MNT-001-0, Maintenance
Program (Section 8.1.6.2)NMP-GM-006, Work Management (Section 4.10)Tier: 3 Keyword: WORK Cog Level: FUND Test: SRO Friday, September 28, 2007 9:24:40 AM 41
QUESTIONS REPORT for SRO 97.G2.2.34 00 1/3/2/CRDM/NEW
/HIGHERlHT2007
-30 I/SRO/BLC/RF
A Unit 2 was operating at 1000/0 power with the following conditions:
The following 10 rods have been declared"slow": (see attached map)22-31,26-15, 26-39, 26-47, 30-15, 30-23, 34-39, 38-15, 38-23, 38-31,42-27.
Which ONE of the following identifies
the, minimum required actions if HCU accumulator
26-27 develops a nitrogen leak which cannot be repaired?[Reference
provided]A.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 />, i.e., all rods inserted.B.Declare rod 26-27"slow" within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.No further LCO actions are required.Declare rod 26-27 inoperable
within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Insert the rod within the following 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarm (either electrically
OR hydraulically)
the rod within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.D.Declare rod 26-27 inoperable
within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Insert rod 26-27 within the following 3 h0l:lrs and disarm (ONLY hydraulically
-electrically
not allowed)the rod within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.A.Incorrect because none of these rods areconsideredadjacent.
Plausible if applicant determines
TS 3.1.4 Action A applies.B.Incorrect because the TS LCO 3.1.4 requirements
are no longer met when the nitrogen leak developed.
Plausible if applicant determines
that TS LCO 3.1.5 Action A is allowed.C.Correct.D.Incorrect because TS 3.1.3 bases allow either dis-arming
method.Plausible if applicant does not know bases allowances
for reactivity
control methods.SRO only because of link to 10CFR55.43
(2): Tech Specs 2.2.34 Knowledge of the process for detennining
the internal and external effects on core reactivity.(CFR: 43.6)IMPORTANCE
2.8/3.2*References
34SV-CII-003-1, Attachment
3, CRD Signoffmap (marked up with the 10 rods)Tech Spec 3.1.3, Control Rod Operability (including
bases)Tech Spec 3.1.4, Control Rod Scram Times (including
bases)Tech Spec 3.1.5, Control Rod Scram Accumulators (including
bases)DISTRIBUTEONLY
THE TECH SPECS TO STUDENTS WITH CORE MAP DO NOT DISTRIBUTE
THE BASES TO ANY OF THE TECH SPECS.Friday, September 28, 2007 9:24:40 AM 42
Tier: Keyword: Cog Level: Test: 3 CRDM HIGHER SRO QUESTIONS REPORT for SRO Group: 2 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A Friday, September 28, 2007 9:24:40 AM 43
QUESTIONS REPORT for SRO 98.G2.3.9 00 1/3/3/CONT
AINMENT/NEW/HIGHER/HT2007
-30 l/SRO/BLC/RF
A A unit shutdown was just completed to facilitate
identification
of dryweilleakage.
Curre'nt plant conditions
are:Reactorpressure
450 psig Mode Switch in SHUTDOWN Given these conditions, which ONE of the following describes the containment
purge procedure and when the minimum requirements
have been met for Shift Supervisor
authorization
for the initial drywell entry?A.Drywell and torus purging are NOT allowed to be performed concurrently.
02 concentration
is>10%as indicated on 2P33-R601A(B), and/or 2P33-R603 recorder(s)
and confirmed>
19.50/0 by only ONE lab sample.Drywell and torus purging are NOT allowed to be performed concurrently.
02 concentration
is>100/0 as indicated on 2P33-R601A(B), and/or 2P33-R603 recorder(s)
and confirmed>
19.50/0 by at least TWO lab samples.C.Drywell and torus purging can be performed concurrently.
02 concentration
is>100/0 as indicated on 2P33-R601A(B), and/or 2P33-R603 recorder(s)
and confirmed>
19.50/0 by only ONE lab sample.D.Drywell and torus purging can be performed concurrently.
02 concentration ,is>100/0 as indicated on 2P33-R601A(B), and/or 2P33-R603 recorder(s)
and confirmed>
19.5%by at least TWO lab samples.A.Incorrect because two lab samples are required.Plausible if applicant does not know procedure requirement.
B.Correct.C.Incorrect because concurrent
purging has the potential to bypass the torus feature in Mode 3 if a LOCA occurs.Also incorrect because two lab samples are required.Plausible if applicant does not know the restriction
on concurrent
purging operations
in Mode 3 or does not know the drywell entry authorization
requirements.
D.Incorrect because concurrent
purging has the potential to bypass the torus feature in Mode 3 if a LOCA occurs.Plausible if applicant does not know the restriction
on concurrent
purging operations
in Mode 3.Friday, September 28, 2007 9:24:40 AM 44
QUESTIONS REPORT for SRO SRO only because tied to 10CFR55.43(4):
KIA G2.3.9 SRO only because tied to Shift Supervisor
responsibilities.
2.3.9 Knowledge of the process for perfonning
a containment
purge.(CFR: 43.4/45.10)IMPORTANCE
2.5/3.4 References
31 GO-OPS-005-0, Primary Containment
Entry procedure 34S0-T48-002-2, CAC/CAD system operating procedure Tier: 3 Group: Keyword: CONT AINMENT Source: Cog Level: HIGHER Exam: Test: SRO Author/Reviewer:
Friday, September 28, 2007 9:24:40 AM 3 NEW HT2007-301
BLC/RFA 45
QUESTIONS REPORT for SRO 99.G2.4.11 00 1/3/3/SHUTDOWN
CLGINEW/HIGHER/HT2007
-30 l/SRO/BLC/RFA
Unit 2 was in Mode 4 with the following conditions: "A" loop of RHR operating in shutdown cooling, Coolant temp 180 deg F Both Recirc pumps under clearance out of service Following a trip and reset of an RPS MG set, the control room operator is unable to re-open the outboard shutdown cooling isolation valve (2-E11-F009).
All local efforts to manually open this valve have not been succesful.
Given these conditions, which ONE of the following identifies
the required actions, if any, in accordance
with Tech Spec 3.4.8, RHR Shutdown Cooling.System-Cold Shutdown and a-Iso defines the term"boil off time" in accordance
with 34AB-E11-001-2, Loss of Shutdown Cooling?At:!"Boil-off time" is the time from when the loss of shutdown cooling occurred until the time water level reaches T AF.Verify an alternate method of decay heat removal is available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.Ambient heat losses can be cons.idered
as, or contributing
to, the alternate method.B."Boil-off time" is the time from when the loss of shutdown cooling occurred until thetime212 deg F is reached.Verify an alternate method of decay heat removal is available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.Ambient heat losses can b.e considered
as, or contributing
to, the alternate method.C."Boil-off time" is the time differential
between the time of complete loss of shutdown cooling and the time water level reaches T AF.No tech spec action is required, LCO conditions
are currently met.D."Boil-off time" is the time differential
between the time of complete loss of shutdown cooling and the onset of boiling.No tech spec action is required, LCO conditions
are currently met.Friday, September 28, 2007 9:24:40 AM 46
Group: 3 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A QUESTIONS REPORT for SRO A.Correct.B.Incorrect because this is the definition (according
to the AOP)for"saturation
time." Plausible if applicant does not know the AOP terminology.
C.Incorrect because the LCO cO.nditions
are not met and required action A and B must be met.Plausible if applicant mis-interprets
the allowance for both RHR subsystems
and recirc pumps to be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.D.Incorrect because this is the definition (according
to the AOP)for"saturation
time." Also incorrect because the LCO conditions
are not met and required action A and B must be met.Plausible if applicant does not know the AOP terminology
or mis-interprets
the-allowance
for both RHR subsystems
and recirc pumps to be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.SRO-only due to the link to 10CFR55.43
(2): Tech Specs G2.4.11 Knowledge of abnormal condition procedures.(CFR: 41.10/43.5/45.13)
IMPORTANCE
3.4/3.6 References
Tech Spec 3.4.8, RHR Shutdown Cooling System-Cold Shutdown (including
bases)34AB-E11-001-2, Loss of Shutdown Cooling AOP Tier: 3 Keyword: SHUTDOWN CLG Cog Level: HIGHER Test: SRO Friday, September 28, 2007 9:24:40 AM 47
QUESTIONS REPORT for SRO 1 00.
00l/3/4/FIRE
BRIGADE/NEW/FUND/HT2007-301/SRO/BLC/RFA
Which ONE of the fo'liowing
describes the MINIMUM required number of fire brigade members, including their assignment
limitations?
A.4 members+1 leader (total of 5)Person.nel
assigned to the fire brigade CAN also be used to fulfill the minimum shift crew composition
requirements
as defined by plant Tech Specs.4 members+1 leader (total of 5)A minimum of three of these persons must have competent knowledge of safety-related
systems and.components.
C.5 members+1 leader (total of 6)Personnel assigned to the Fire Brigade can NOT be used to fulfilltheminimum
shift crew composition
requirements
as defined by Tech Specs.D.5 members+1 leader (total of 6)A minimum of three of these persons must have competent knowledge of safety-related
systems and components.
A.Incorrect because fire brigade members cannot be used to fulfill tech spec crew composition
req'ts.Plausible since system operators can be fire brigade members;only 3 required by tech specs for system operators only..normal shift may have 6 or 7 system operators.
B.Correct.C.Incorrect because only 5 total are required.Plausible if applicant thinks that the fire brigade leader is'in addition to the fire brigade.D.Incorrect because only 5 total are required.Plausible if applicant thinks that the fire brigade leader is in addition to the fire brigade.SRO only because of tie to 10CFR55.43(1):
Conditions
and limitations
in the facility license.2.4.26 Knowledge of facility protection
requirements
including fire brigade and portable fire fighting equipment usage.(CFR: 43.5/45.12)IMPORTANCE
2.9/3.3 References
30AC-OPS-003-0, Plant Operations
40AC-ENG-008-0S, Fire Protection
Program 10CFR50.48, Fire Protection.
Tier: 3 Keyword: FIRE BRIGADE Cog Level: FUND Test: SRO Friday, September 28, 2007 9:24:40 AM Group: 4 Source: NEW Exam: HT2007-301
Author/Reviewer:
BLC/RF A 48