ML080460189

Dec. 2007 Exam 05000321-07-301, 05000366-07-301 Draft SRO Written Exam

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

DECEMBER 3 - 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?

A~ 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. Plausible since the 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 incorrect because the

34GO-OPS-013-2 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 trip and reset 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) A2.05 Reactor Scram

4.1*/4.1

SRO-only (tie to 10CFR55.43(5): Assessment of facility conditions and selection ofappropriatae procedures during

norrmal, abnormal, and emergency situations.

References

34GO-OPS-013-2, Normal Plant Shutdown

34AB-C71-001-2, 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. 204000G2.1.2 001/2/2/RWCU/BANK-MOD/HIGHER/HT2007-30 l/SRO/BLC/RFA

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° F

RWCU HX room differential temperature (N022C/N023C) 105°F ~T

RWCU HX room differential temperature (N022D/NO*23D) 105°F ~T

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 not re'quired~

B~ An 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 into secondary containment 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, 2007 9:24:39 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 ofplant 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. 211000G2.1.14 002/2/1/E-PLANINEW/HIGHER/HT2007-30I/SRO/BLC/RFA

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 a site evacuation 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 ofplant 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 ofEmergency 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/RFA

Friday, September 28, 2007 9:24:39 AM

6

QUESTIONS REPORT

for SRO

79. 212000A2.20 001/2/1/RPS/NEW/HIGHERJHT2007-30 l/SRO/BLC/RFA

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/RFA

QUESTIONS REPORT

for SRO

A. Correct.

B. Incorrect because the bypass 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 ofA2 K&A and 10CFR55.43 (2): Facility operating limitations in the technical specfications and

their bases.

A2. Ability to (a) predict the impacts ofthe following on the REACTOR PROTECTION SYSTEM; and (b) based

on those predictions, use procedures to correct, control, or mitigate the consequences ofthose 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?

A. Core alterations must now be suspended.

B~ 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 becaus~ 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/RFA

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 ofvarious internal and external effects

on core reactivity. Also linked to Tech specs 3.3.1.2

A2. Ability to (a) predict the impacts ofthe following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and

(b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose 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 . 245000A2.07 001/2/2/EHC/NEW/HIGHER/HT2007-30 l/SRO/BLC/RFA

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 Shutdown

C~ Steam 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 ofreactor/turbine

pressure control system: Plant-Specific 3.8 / 3.9

References

34AB-N61-002-1, 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 & Low Low 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. 262001A2.08 003/2/1/4160VACINEW/FUND/HT2007-30 l/SRO/BLC/RFA

While performing an electrical tagout, a system operator inadvertently opened breaker

1. 1 in 125VDC Cabinet 1D (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.

C~ 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 the 1C RHR SW pump.

B. Incorrect because only a few breakers have this auto-open feature and they are

only located on 4160VAC emergency bus 1F. 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 renders the switch on the outside of the

cubicle door inoperable. Also incorrect because the switch 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 ofDC Buses AOP

Tier:

2

Keyword:

4160VAC

Cog Level:

FUND

Te~:

SRO

Friday, September 28, 2007 9:24:39 AM

Group:

1

Source:

NEW

Exam:

HT2007-301

Author/Reviewer:

BLC/RFA

14

QUESTIONS REPORT

for SRO

83. 295003AA2.04 00 l/l/l/TRANSFORMERINEW/HIGHERlHT2007-30 l/SRO/BLC/RFA

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/RFA

QUESTIONS REPORT

for SRO

Note: Both SATs 1C 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-02701, 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.

C~ 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 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.

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

H11-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 ATTS 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 ofpartial or complete loss ofD.C. power.... 3.5/3.9

References

TRM Section 11.0, Loss ofFunction Diagrams

34AB-R22-001-2, Loss ofDC 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. 295014G2.4.31 001/1/2/RODS/NEW/HIGHER/HT2007-30l/SRO/BLC/RFA

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 movement control switch 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.

C~ 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/RFA

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 ofthe 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 annunciator 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. 295020AA2.04 001/1/2/HPCI/RCIC/NEW/HIGHER/HT2007-30l/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.

B~ 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 Depressurization

D~ RC 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 applica~t 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

[N0 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/RFA

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

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

C~ 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 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

34AR-657-072-1, Multipoint Rcdr 1T47-R611 Temp High annunciator procedure

34AR-654-009-1, Multipoint Rcdr 1T47-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/RFA

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.

D~ "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, 2007 9:24:39 AM

27

Group:

1

Source:

NEW

Exam:

HT2007-301

Author/Reviewer:

BLC/RFA

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. 295033G2.4.50 001/1/2/REFUEL/NEW/HIGHER/HT2007-30l/SRO/BLC/RFA

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 1D11-K611 A-D are causing the valid EXHAUST

rad alarm and the refueling floor 1D21-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.

D~ 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

1D21-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 linked to 10CFR55.43 (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-O14-1, Unit 1 Secondary Containment Control flowchart

73EP-EIP-00I-0, Section 18, Fuel Damage By Fuel Handling Accident

34AR-601-409-1, Refueling Floor Vent Exhaust Radiation High annunciator procedure

34AR-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/RFA

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 annunciator 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 is required to 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 is required to 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/RFA

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 PSWIRBCCW 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 PSWIRBCCW 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

Tie~

.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/HIGHERlHT2007-30l/SRO/BLC/RFA

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 b~low:

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 ofthe 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-20101-03, Initial/Terminating Activities

Friday, September 28, 2007 9:24:39 AM

35

Tier:

Keyword:

Cog Leve~:

Test:

1

E-PLAN

HIGHER

SRO

QUESTIONS REPORT

for SRO

Group:

1

Source:

MODIFIED BANK

Exam:

HT2007-301

Author/Reviewer:

BLC/RFA

Friday, September 28, 2007 9:24:39 AM

36

QUESTIONS REPORT

for SRO

94. G2.1.14 001/3/1INOTIFICATIONSINEW/FUND/HT2007-30I/SRO/BLC/RFA

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 ~e aware of.

SRO only because of link to 10CFR55.43 (5): procedures

2.1.14 Knowledge of system status criteria which require the notification ofplant 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/RFA

37

QUESTIONS REPORT

for SRO

95. G2.1.7 001/3/1/0PRM/NEW/HIGHERlHT2007-30 l/SRO/BLC/RFA

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 algorithms are required 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 oflink to 10CFR55.43 (2): Tech Specs bases 2.1.7 Ability to evaluate plant performance 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, 2007 9:24:40 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/RFA

Friday, September 28, 2007 9:24:40 AM

39

QUESTIONS REPORT

for SRO

96. G2.2.19 001/3/2/WORK/NEW/FUND/HT2007-30 l/SRO/BLC/RFA

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/RFA

QUESTIONS REPORT

for SRO

SRO-only because ofjob/task requirements for Work Control Center.

2.2.19 Knowledge ofmaintenance 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. G2.2.34 001/3/2/CRDM/NEW/HIGHERlHT2007-30 I/SRO/BLC/RFA

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.

C~ 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

hours 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

hours.

A. Incorrect because none of these rods are considered adjacent. 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 ofthe 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)

DISTRIBUTE ONLY 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/RFA

Friday, September 28, 2007 9:24:40 AM

43

QUESTIONS REPORT

for SRO

98. G2.3.9 001/3/3/CONTAINMENT/NEW/HIGHER/HT2007-30 l/SRO/BLC/RFA

A unit shutdown was just completed to facilitate identification of dryweilleakage.

Curre'nt plant conditions are:

Reactor pressure 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.

B~ 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 ofthe process for perfonning a containment purge. (CFR: 43.4/ 45.10) IMPORTANCE 2.5 / 3.4

References

31GO-OPS-005-0, Primary Containment Entry procedure

34S0-T48-002-2, CAC/CAD system operating procedure

Tier:

3

Group:

Keyword:

CONTAINMENT

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. G2.4.11 001/3/3/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-offtime" is the time from when the loss of shutdown cooling occurred until the

time water level reaches TAF.

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 the

time 212 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 TAF.

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/RFA

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

hour 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

100. G2~4.26 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.

B~ 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 fulfill the minimum 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 oftie 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/RFA

48