ML14241A706

2014-02 - Draft Written Exam

ML14241A706
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/27/2014
From:	Vincent Gaddy Operations Branch IV
To:	Entergy Operations
References
Download: ML14241A706 (110)

Text

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 11925 I Rev:

Search looCE02K103

[QJ Rev Date: 19/26/2013 3:30:49 1 QID #:

Lie Level: [}] Difficulty: [)) Taxonomy :[EJ Source:

I t0CFR55:

System

Title:

\Reactor Trip Recovery 141.8 I 41.10 I 45.3 \

I Safety Function I System Number \

Author:

\

NEW E02

\

\ KIA \

foster EKl.3 Tier: OJ Group: OJ RO Imp: CTI] SRO Imp: ~ L. Plan: \ A2LP-RO- ERTR \ OBJ ~I-~

the (Reactor Trip Descriptio n: Knowledge of the operational implications of the following concepts as they apply to Recovery): - Annunciators and conditions indicating signals, and remedial actions associated with the (Reactor Trip Recovery)

Question:

Consider the following :

- Unit 2 is operating at 60% power

- "A" MFP has been tagged out for bearing replacement

- Annunciator 2K03 A-11 "Feed Pump Trip" is in alarm for "B" MFP

- CRS directs tripping the Reactor

- All components operate as designed

- SPT As have been completed

- The Control Room has been informed that "B" MFP was tripped inadvertently by maintenance personnel

• During implementation of OP-2202.002, Reactor Trip Recovery EOP, the CRS would direct starting

~~~~

~~~~

~-

to restore Steam Generator Levels to 60% .

A. 2P-7A Emergency Feedwater Pump B. 2P-7B Emergency Feedwater Pump C. 2P-75 Auxiliary Feedwater Pump D. 2P-1B Main Feedwater Pump Answer:

C. Correct Notes:

C. Correct: based on OP-2202.0 02 step 12.A levels OP-2202.002 step A. B. and D. Incorrect due to procedural guidance to place the AFW pump in service to restore S/G 12.A References :

176 OP-2203.012C, Annunciator Corrective Actions 2K03 window A-10, Rev 030, pages 134 and 135 of Main Feedwater Pump AOP, Rev 013 , step 3, contingenc y 3.E. l) and 2) page 2of11 OP-2203.027, Loss of Reactor Trip Recovery EOP, OP-2202.0 02, Rev 0 I 0, step 12.A, contingency A. I) page 6 of 17 Reactor Trip Recovery Tech Guide, EOP-2202. 002, Rev 010, step 12., page 19 of33

• Historical Comments :

Form ES-401-5 Written Exam Question Workshee t 1

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 11926 I Rev: [}] Rev Date: 19/26/2013 3:30:42 j QID #:

Lie Level: CKJ Difficulty: ITJ Taxonomy:Q J Source: I Search looo008A230 j toCFRSS : j4 I. 7 I 41.1 OI 43.5 I 45 I 2

Safety Function System

Title:

jPressurizer (PZR) Vapor Space Accident (Relief! System Number I Author:

j NEW 3

008 j

foster I KIA I AA2 .30 Tier: [JJ Group: [JJ RO Imp: 8IJ SRO Imp: @] L. Plan: I A2LP-RO-ELOCA j OBJ I 17 er Vapor Space Accident: -

Descripti on: Ability to determine and interpret the following as they apply to the Pressuriz Inadequate core cooling Question :

Consider the following :

- Unit 2 has been taken off line due to indications of a LOCA inside Containment

- SPTAs are complete and OP-2202.003, Loss of Coolant Accident EOP, has been entered

- Pressurizer level 90% and trending up

- Pressurizer pressure I 055 psia and trending up

- Tc 468°F and lowering

- Th 552°F and rising

- Average CET temperature 558°F and rising

- Containment Pressure 25 psia established .

The RCS leak is in the Pressurizer _ _ _ _ _ space and natural circulation ____

• A. water; is B. water; is not C. steam; is D. steam; is not Answer:

D. Correct Notes:

will cause PZR heaters to energize A steam space leak will cause PZR level to rise (venting off of the steam space) the insurge and the RCPs will be secured (directed by (colder water entering into the PZR from the RCS) Containment Spray will actuate head region, combined with low RCS pressure, procedure , section 1, step 16, page 11) cooling flow is lost to the reactor vessel

>50°F delta between Th and Tc]

a void will form. Natural Circulation is not established [<30°F MTS and

References:

A.2) d), page 31 of 67 OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 3, step 7.A. contingency EOP-2202.003, Loss of Coolant Accident Tech Guide, Rev 014, section 3, step 7, page 90of140 Historica l Commen ts:

New Question

• Form ES-401-5 Written Exam Question Workshe et 2

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 11927 I Rev: [}] Rev Date: 19/25/2013 10:27:2 Lie Level: ITJ Difficulty: [}] Taxonomy:[![] Source: I Search 10000112120 I 10CFRSS:

System

Title:

!Large Break LOCA 141.10 / 43 .5 / 45 .12 I QID #: 3 SafetyFu nction I System Number Author:

I I

NEW 3

011 I

foster I K/A I 2.1.20 Tier: QJ Group: QJ RO Imp: ~ SRO Imp: 8IJ L. Plan: I A2LP-RO-ELOCA I OBJ !~-~

Descripti on: !conduct of Operations -Ability to interpret and execute procedure steps.

Question :

Consider the following:

- Unit 2 has experienced a LOCA

- OP-2202.003 , Loss of Coolant Accident EOP, is being implemented

- Pressurizer pressure is 1450 psia

- Pressurizer level is 32% and trending up

- Margin to Saturation (MTS) is 32°F and stable

- Reactor Vessel Level Monitoring System (RVLMS) indicates level 01

- Containment Temperature 210°F and trending down

- Containment Pressure is 22.3 psia and trending down 25%

- Emergency Feed Actuation Signal (EFAS) has actuated and "A" and "B" S/G Levels are

- "A" and "B" Emergency Feedwater (EFW) pumps are running on recirculat ion due to

• Terminate /Throttle criteria has NOT been met for High Pressure Safety Injection [HPSI]

A. Pressurizer level is too low B. Containment pressure is too high C. Margin To Saturation (MTS) is too low D. Feedwater flow to the S/Gs is too low Answer:

A. Correct Notes:

used to determine HPSI Containment is in a "Harsh Environment" condition [>200°F] which changes the values to be 50% or greater with the Terminate/Throttle criteria. [numbers to be used are bracketed] pressurizer level is required given conditions

References:

OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 3, step 15, page 35 of67 f140 EOP-2202.003, Loss of Coolant Accident Tech Guide, Rev 014, section 3, step 15, pagel01o Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 3

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: /1928 / Rev:

Lie Level:

Search /ooOOI5Kl01

[I]

~ Difficulty: ~

Rev Date: i9/25/2013 12:43:1 / QID #:

Taxonomy: =:c Source:

10CFRSS: !41.8 I 41.10 I 4_5_

System

Title:

Jo17 Reactor Coolant Pump (RCP) M-a-lfun

.3_~

4

---~=----NE Safety Function

- c-ti-o-ns- System Number J Author:

/

_W 4

015

/

foster

/ KIA i AKI.QI Tier: CI] Group: [1= RO Imp: ~ SRO Imp: ~ L. Plan: ' A2LP-RO-CIRC / OBJ / 4

Description:

jKnowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions: - Natural circulation in a nuclear reactor power plant Question:

Consider the following:

- Unit 2 has been tripped from I 00% power

- The Reactor Coolant Pumps (RCPs) have been secured due to a power issue

- SPT As are complete

- OP-2203.013, Natural Circulation AOP is being implemented OP-2203.013, Natural Circulation AOP directs maintaining a MINIMUM Margin to Saturation (MTS) of _ _ _ to minimize reactor vessel head voiding. The Reactor Coolant System (RCS) is checked to be void free if Pressurizer level _ __ __

with pressurizer spray in service.

A. >30°F; goes up B. >30°F; is stable C. >50°F; goes up D. >50°F; is stable Answer:

D. Correct Notes:

The Natural Circulation AOP requires a higher MTS [>50°F] step 5 and has the operator verify stable pressurizer level when Pzr spray is in service to check the RCS is void free.

References:

OP-2203.013, Natural Circulation AOP, Rev 014, step 5, page 3 of32 and step 32 pagel8 of32 AOP-2203.013, Natural Circulation Tech Guide, Rev 014, step 5, page 4 of34 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 5

21-Dec- 13 Data for 2014 NRC RO/SR O Exam

• Bank: 11929 I Rev: [ ] ] Rev Date: 19/27/2013 8:19:52 1 QID #:

Lie Level: [}] Difficulty : [}] Taxonom y:[ ] ] Source:

Search loo0022K 103 j IOCFR55 : j4 I.8 I 41.10 I 45.3 System

Title:

jLoss of Reactor Coolant Makeup I

I Safety Function 5 Author:

j NEW I System Number I 022 I KIA I AKl.03 2 I foster Tier: OJ Group: OJ RO Imp: [}I] SRO Imp: ~ L. Plan: j A2LP-RP -ACCP I OBJ j 2 they apply to Loss of Reactor Coolant Descripti on: Knowledge of the operational implications of the following concepts as Makeup: - Relationship between charging flow and PZR level Question :

(Reference Provided)

Consider the Following:

- Unit 2 is operating at I 00% power

-Annunci ator 2K12 B-3 "Header Flow LO" comes into alarm

- Charging Header Flow (2FIS-486 3) is reading 15 gpm

- Letdown Flow (2FIS-4802) is reading 26 gpm

- Pressurizer level is 60.0%

first backup Charging Pump (CCP)

Assuming no further changes in charging or letdown flow and NO operator action, the would reach its auto start setpoint in approximately _ _ _ minutes .

• A. 9.5 B. 7 C. 11 D . 15 Answer:

C. Correct Notes:

by 15 gpm with the stated Student should know that Pzr level setpoint is 60% at 100% power. Pzr level would decrease out [from controlled Bleedoft] ) equals conditions. 15 gpm in [from charging] minus (26 gpm out [from letdown] plus 4 gpm x 3.1 % = 165.85 gallons required to be lost a -15 gpm from the primary. Pzr level is 53.5 gallons per percent. 53.5 gal/%

11.06 minutes]

from the system to reach the 1st CCP auto start setpoint. [165.85 gals I 15 gpm =

g for RCP controlled A. Incorrect: Number is based on using the VCT gallons per percent and not accountin letdown] ]= -11 gpm from the Bleedofff low: 15 gpm in [form charging] minus [(26 gpm out [from x 3.1  % = 104.78 gallons required to be lost primary. VCT level is 33.8 gallons per percent. 33 .8 gal/%

from the system to reach the 1st CCP auto start setpoint. [104.78 gals I 11 gpm = 9.5 minutes RCP controlled B. Incorrect: Number is based on using the VCT gallons per percent and accounting for Bleedofff low: 15 gpm in [form charging] minus [(26 gpm out [from letdown] plus 4 gpm out [from primary. VCT level is 33.8 gallons per percent. 33.8 gal/% x controlled Bleedoft] )] = -15 gpm from the Jost from the system to reach the 1st CCP auto start setpoint.

3.1 % = 104.78 gallons required to be

[104.78 gals I 15 gpm = 6.98 minutes for RCP controlled D. Incorrect: Number is based on using the Pzr gallons per percent and not accounting gpm in [form charging] minus (26 gpm out [from letdown] = -11 gpm from the primary.

Bleedofff low: 15 Form ES-401-5 Written Exam Question Workshe et 5

21-Dec-13 Data for 2014 NRC RO/SRO Exam

• Pzr level is 53.5 gallons per percent. 53 .5 gal/% x 3.1% = 165.85 gallons required to be lost from the system to reach the 1st CCP auto start setpoint. [165.85 gals I 11 gpm = 15.07 minutes

References:

OP-2305.002 , Reactor Coolant Leak Detection, Rev 024, exhibit 1, page 39 of 54 [PROVIDED to STUDENT]

OP-2203 .0121, Annunciator Corrective Actions 2K12 window B-3, Rev 044, page 36of116 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 6

20-Dec-J 3 Data for 2014 NRC RO/SRO Exam m

• Bank: j1 930 Rev:

1 Rev Date: ;12/9/2013 2:53:03 l QID #: 6 Author: foster Lie Level: IT] Difficulty: ; 3 i Taxonomy: ~ Source:

1 NEW Search loo0025AI03 I 10CFR55: !41.7 I 45.5 I 45.6 Safety Function I 4 i System

Title:

!Loss of Residual Heat Removal System (RHRS) ! System Number I 025 I KIA I AAl.03 Tier: ITJ Group: ITJ RO Imp: 3.4 SRO Imp: @J L. Plan: I A2LP-RO-SDC I OBJ I 3 Removal System: -

Descriptio n: Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat LPI pumps Question:

Consider the following:

- Unit 2 is in Mode 5

- RCS level is currently 24" from the bottom of the hot leg

- "A" Low Pressure Safety Injection (LPSI) pump [2P-60A] is in service

- "B" Low Pressure Safety Injection (LPSI) pump [2P-60B] is in standby

- Annunciator 2K 12 A-8 "lnstr Air Press HI/LO" comes into alarm

- Annunciator 2K07 C-7 "LPSI Pump Motor Amps HI/LO" is in alarm

- The ATC reports "A" LPSI pump amperage and flow rate is oscillating

- The CRS has entered OP-2203.029, Loss of Shutdown Cooling AOP Using OP-2203.029, Loss Of Shutdown Cooling AOP, the CRS would direct _ _ _ _ _ _ _ _ _

• A. placing HIC for flow control valve 2CV-5091 in MANUAL to lower flow B. throttling flow control valve 2CV-5091 bypass valve 2SI-5091-3 to lower flow C. placing the "B" Low Pressure Safety Injection (LPSI) pump [2P-60B] in service D. securing "A" SDC pump [2P-60A] and transition to OP-2202.011, Lower Mode Functional EOP Answer:

D. Correct Notes:

D. Correct: With a Loss ofIA, the flow control valve will fail open causing high system flowrate . The Loss ofSDC AOP, step 12 contingency C. I) and 2) will direct securing the in service SDC pump and entering the Lower mode Functional EOP not A. Incorrect: placing the HIC in MANUAL would try and send a signal to the valve, but the valve will response due to the Loss of Instrument Air Pressure is B. Incorrect: Normal configuration for 2SI-5091-3 is closed (the temperature control valve bypass valve normally throttled open when on SDC]

C. Incorrect: The AOP would not direct placing the standby pump in service with signs of pump cavitation

References:

OP-2203.0 120, Annunciator Corrective Actions 2K07 window C-7, Rev 031, page 52 of71 OP-2203 .012L, Annunciator Corrective Actions 2Kl2 window A-8, Rev 044, page 85ofI16

• OP-2203 .029 Loss of Shutdown Cooling Rev 016, step 12, page 8 of I 8 Technical Guideline OP-2203 .029, Loss of Shutdown Cooling, Rev 016, step 12, page 13of19 Historical Comments :

Form ES-401-5 Written Exam Question Workshee t 8

Data for 2014 NRC RO/SR O Exam 20-Dec-13

• Bank: ~ Rev: I 0 ' Rev Date: [9126/2013 3:05:02 : QID #:

Lie Level: ~ Difficulty: ~ Taxonom y:[ [ ] Source: :

7 Search [oo0026K302 i 10CFR55 : 14 I .5 I 41 . 10 I 45.6 I 45 . ' Safety Function System

Title:

[Loss of Component Cooling Water (CCW)  : System Number Author:

NEW 8

026 foster I K/A i AK3.02 Tier: =:I] Group: I I J RO Imp: I 3.6 1 SRO Imp: I 3.9 1

L. Plan: 1 A2LP-RO-SWACW I OBJ I 11 Descripti on: Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: -

The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS Question :

The PURPOSE for the Component Cooling Water (CCW) Heat Exchanger Service Water Return Isolation Valves (2CV-1543-l/2CV-1542-2) to automatically ___ on a Main Steam Isolation Signal (MSIS) is to A. open; ensure cooling to the RCP seals is maintained B. open; cross-tie Loop I and Loop 2 Service Water returns C. close; separate Loop I and Loop 2 Service Water returns D. close; isolate seismic Category I piping from seismic Category 2 piping Answer:

• D. Correct Notes:

D. Correct: MSIS and SIAS will CLOSE the inlets and outlets to CCW system to separate Service Water system.

A. Incorrect: MSIS will close the isolation valves it from the 8 . Incorrect: MSIS will close the isolation valves C. Incorrect: Loop l and 2 Service Water return headers will still be crossed tied with the CCW outlet isolations valves closed.

Referenc es:

System Training Manual (STM) 2-42, Rev 35 , section 3.5.12, pages 37 and 37, and section 3.6.15.1, page 46, Simplified Service Water drawing, page 61 Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et JO

20-Dec-13 Data for 2014 NRC RO/SRO Exam foster Bank: II 932 I Rev: [QJ Rev Date: j9/27/2013 10:53 :3 I QID #: 8 Author:

Lie Level: ~ Difficulty:[D Taxonomy: ~ Source: Modified NRC BANK QID # 1497 1

! 10CFR55: 141.7 I 45 .7 I Safety Function 3 I Search loo0027K203 I

System

Title:

!Pressurizer Pressure Control (PZR PCS) Malfun System Number 027 I KIA ! AK2 .03 Tier: [JJ Group: [JJ RO Imp: ITIJ SRO Imp: ~ L. Plan: : A2LP-RO-PZR I OBJ I 5 Control Malfunctions and the following: -

Description:

Knowledge of the interrelations between the Pressurizer Pressure Controllers and positioners Question:

restored , the Pressurizer Pressure Controller If AC power is lost to the SELECTED Pressurizer Pressure Controller and then would return in the Mode of operation with a output demand.

A. Manual; 0%

B. Auto; 0%

C. Manual ; 100%

D. Auto; 100%

Answer:

A. Correct Notes:

demand on the controller A. Correct: The controller will regain power with a manual signal and no output B. Incorrect: The controller will not come back in AUTO C. Incorrect: The controller will have no output demand when power is restored D. Incorrect: The controller will not come back in AUTO

References:

2.2.2, pages 5 and 6 STM 2-03-1 , Pressurizer Pressure & Level Control Systems , Rev 16, section Historical Comments:

NRC BANK QID # 1497 used on 2008 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 11

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 1933 1Rev: ~ Rev Date: 9/27/2013 10:59:2 Lie Level: [I] Difficulty::

Search !oo0029Al 12 2 1 I 10cFR55:

Taxonomy: ~ Source:

141.7 I 45 .5 I 45.6 System

Title:

!Anticipated Transient Without Scram (ATWS)

QID #:

I 1

9 Safety Function Author:

NRC Bank QID # 1495 System Number ~9 ~ KIA I EAl.12 foster Tier: [JJ Group: ~ RO Imp: ' 4.1 1 SRO Imp: ; 4.0 ~ L. Plan: I A2LP-RO-DSS f OBJ I 4

Description:

!Ability to operate and/or monitor the following as they apply to a ATWS: - MIG set power supply and reactor trip breakers Question:

Consider the following:

- Unit 2 is operating at 20% power

- Pressurizer Transmitters 2PT-4600-2 AND 2PT-4600-4 that supply signals to the Diverse Scram System (DSS) have failed HIGH What would be the direct effect of these conditions on Unit 2?

A. These conditions would cause two reactor trip circuit breakers to open AND NO Reactor trip B. These conditions would cause four reactor trip circuit breakers to open AND a Reactor trip

• C. These conditions would cause only the 'B' CEA MG Set output contactor to open AND NO Reactor trip D. These conditions would cause the 'A' and 'B' CEA MG Set output contactors to open AND a Reactor trip Answer:

D. Correct Notes:

D. Correct: These conditions would cause the 'A' and 'B' CEA MG Set output contactors to open AND a Reactor Trip.

A. Incorrect: These pressure transmitters are independent of the pressure transmitters that feed RPS and Reactor trip breakers would not open initially but all 8 circuit breakers eventually would trip open due to LPD and DNBR trips.

B. Incorrect: Same reason as above C. Incorrect 2 out of 4 ATWS pressure transmitters failing high will give a full output opening both disconnect contactors causing a Reactor trip

References:

STM 2-63 -1, Diverse Scram System, section 2.1, pages 3 and 4 Historical Comments:

NRC Bank QID # 1495 used on 2008 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 12

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: jI 934 j Rev:

Lie Level:

IT] Rev Date: j9/30/2013 I :48:42 IT] Difficulty: [JJ Taxonomy:((]

Search joo0038A144 j IOCFRSS: j4I.7/45.5 / 45.6 System

Title:

jsteam Generator Tube Rupture (SGTR)

I Source:

QID #:

I 10 Author:

I SafetyFunction I 3 I NEW I System Number I 038 I K/A I EAl.44 foster Tier: [JJ Group: [JJ RO Imp: [E) SRO Imp: [El L. Plan: I A2LP-RO-ESGTR I OBJ I 15

Description:

!Ability to operate and/or monitor the following as they apply to a SGTR: - Level operating limits for S/Gs Question:

Consider the following:

- Unit 2 is off line due to an 80 gpm tube leak in the "B" Steam Generator (S/G)

- All plant equipment is operating as designed

- OP-2202.004, Steam Generator Tube Rupture (SGTR) EOP, is being implemented

- The "B" S/G has been isolated

- The CRS has directed the A TC to cool down and depressurize the "B" S/G by backflowing to the RCS Per OP-2202.004, Steam Generator Tube Rupture EOP, what is the MINIMUM Steam Generator level allowed during backflow?

• A. 49.0%

B. 38.0%

C. 22.0%

D. 10.0%

Answer:

D. Correct Notes:

D. Correct: per procedure A. Incorrect: 49% is where the feedring is located and is used to reduce flowrate to the S/Gs when feeding during a Loss ofFeedwater Event B. Incorrect: this is the top of the procedure level band for backflow C. Incorrect: This is close to the EFAS setpoint and S/G levels are verified pre cooldown/isolation of the ruptured S/G

References:

OP-2202.004, Steam Generator Tube Rupture EOP, Rev 014, step 50. A. l) page 31 of 48 EOP-2202.004, Steam Generator Tube Rupture Tech Guide, Rev 013, step 50, page 69 of 81 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 12

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11935 I Rev:

Lie Level:

[Il Rev Date: 112/4/20133:1 8:40

@] Difficulty: Li] Taxonomy: [}[]

I Source:

Search !oocE05A20 2 i 10CFR55: 141.7 / 41.10 / 43.5 / 45 . ,

System

Title:

!Excess Steam Demand QID#:

I II Author:

NRC Bank QID #0458 Safety Function i 4 I I System Number : E05 I KIA I EA2.2 foster Tier: OJ Group: OJ RO Imp: [8 SRO Imp: [ill L. Plan: I A2LP-RO-EESD I OBJ I 8

Description:

!Ability to determine and interpret the following as they apply to the (Excess Steam Demand): - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Question:

Consider the following:

- A Steam Line Break has occurred on the "B" Steam Generator (S/G) outside Containment

- Main Steam Isolation (MSIS) has automatically actuated

- OP-2202.005, Excess Steam Demand EOP, has been entered

- "B" Steam Generator (S/G) level indicate O" (zero) wide range

- RCS Tcold has been stabilized at 400°F using the "A" SIG

- Average CET temperature indicates 400°F To prevent pressurized thermal shock (PTS) from causing brittle fracture of the Reactor Vessel, RCS pressure should be reduced below psia using spray .

• A. 1800; Aux B. 1800; Main C. 1540; Aux D. 1540; Main Answer:

D. Correct Notes:

200 degrees MTS is the License basis that will ensure brittle fracture does not occur after a rapid cooldown. Current RCS temperature 400°F + 200°F (max allowed MTS) = 600°F. The saturation pressure for 600°F is 1543.2 psia. Also Main spray is not available due the RCPs being secured when Containment Spray Actuated in SPTAs (Containment building pressure >23.3#).

References:

OP-2202.005, Excess Steam Demand EOP, Rev 014, step 30 page 12 of41 EOP-2202.005, Excess Steam Demand Tech Guide, Rev 014, step 30 page 41 of76 OP-2202.010, Standard Attachments, Rev 022, Attachment I page 5 of204 Historical Comments:

NRC Bank QID #0458 used on 2005 NRC exam

• Form ES-401-5 Written Exam Question Worksheet 14

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: 11936 I Rev:

Lie Level: 0

[QJ Rev Date: 112/2/2013 11 :22:4 1 QID #:

Difficulty: IT] Taxonomy:[I!J Search looCE06K201 I rncFR55: 141.7 I 45 .7 System

Title:

!Loss ofFeedwater Source:

12 Safety Function I System Number I Author:

~~-=====---~~~---==========:

I NEW

~~~~~~---;:::====::::;-~~~~~

I 4 E06 I

foster I KIA I EK2.l Tier: [JJ Group: [JJ RO Imp: Q}J SRO Imp: [}TI L. Plan: I A2LP-RO-ELOSF I OBJ I 3

Description:

Knowledge of the interrelations between the (Loss ofFeedwater) and the following: - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Question:

Consider the following :

- Unit 2 has tripped due to a steam leak inside Containment

- Containment Building pressure is 24 psia and trending up

- Annunciator 2KO 1 8-7 "LO relay Trip" for 2A 1 is in alarm

- Neither Emergency Feedwater (EFW) pump is available

- "A" Steam Generator (S/G) Level is 200" (WR) and trending down 11

- 8 11 Steam Generator (S/G) Level is 21 % (NR) and trending down slowly

- SPTAs have been completed RCS cooling would be accomplished by starting ___ Condensate Pump and feeding _ _ _ Steam Generator.

A. "A" (2P-2A); "B" B. "B" (2P-2B); "B" C. "A" (2P-2A); "A" D. "B" (2P-2B) ; "A" Answer:

B. Correct Notes:

B. Correct: For the given conditions, a SIAS, CCAS, EFAS, CSAS, and a MSIS are all present. The CSAS and MSIS signals, along with the MFWIS, will isolate feed and steam to/from the containment to minimize the energy release into containment. OP-2202.009, Functional Recovery EOP, would be entered due to 2 events in progress (ESD and Loss ofFeedwater) Normally the EFW pumps would supply feedwater for RCS heat removal but they are unavailable. AFW pump is powered from 2A 1 is 11 11 unavailable. The Functional would direct over riding the MFWIS signal on either the 8 or "C" condensate pumps so they can be started and available to feed the S/Gs through the main Feedwater Headers. Only "B" S/G would be fed after starting a condensate pump due to indications of a steam leak in the "A" S/G (low level)

A. Incorrect: The MFWIS signal is not capable of being overridden for the "A" condensate pump (2P-2A)

C. Incorrect: 2P-75 does not have power (2A 1 Lockout) and is unavailable for feeding

• D. Incorrect: S/G levels are above the OTC criteria and feedwater is available

References:

Form ES-401-5 Written Exam Question Worksheet 14

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• OP-2203.012A, Annunciator Corrective Actions 2K01 window B-7, Rev 045, page 98of179 OP-2202.009, Functional Recovery EOP, Rev 016, HR-lstep 35 page 26 of95 OP-2202.010, Standard Attachments, Rev 022, Attachment 57 step 2 page 176 of204 OP-2202.010, Standard Attachments, Rev 022, Attachment 50 step 3 page 146 of204 EOP-2202.009, Functional Recovery Tech Guide, Rev 016, HR-1 step 35 page 205 of342 STM 2-20, Condensate System, Rev 14 section 2.3.4 page 15 ,

STM 2-70, Engineered Safety Features Actuation System, Rev 18, section 2.2.4.l pages 5 and 6, MFWIS table page 55 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 15

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11937 f Rev: [ [ ] Rev Date: 10/ 1/2013 8:39:42 Lie Level: =:!] Difficulty: rr= Taxonomy:[}]

Search Joo0055K302 f tOCFR55: 141.5 I 41 .1OI 45 .6 I 45 .

QID #:

Source: J 1

13 Safety Function System

Title:

fLoss ofOffsite and Onsite Power (Station Black J System Number I Author:

I NEW 6

055 I

foster I KIA I EK3.02 Tier: [ [ ] Group: ~ RO Imp: 8L SRO Imp: ~ L. Plan: 1 A2LP-RO-ESBO , OBJ I 11.b

Description:

Knowledge of the reasons for the following responses as they apply to the Station Blackout: - Actions contained in EOP for loss of offsite and onsite power Question:

OP-2202.008, Station Blackout EOP, directs securing the Safety Parameter Display System (SPDS) inverter (2Y26) ifthe Blackout conditions exceed minutes, and this action is performed to _ _ __ _ _ _ _ __ _ __ __

A. 60; reduce load on the vital battery bank B. 60; reduce load on the non-vital battery bank C. 90; reduce load on the vital battery bank D. 90; reduce load on the non-vital battery bank Answer:

D. Correct Notes:

D. Correct: EOP step 18. SPDS [Safety Parameter Display System] is used by operators and the EOF organization to monitor the plant during e-plan situations. The inverter is powered by non vital AC and DC sources. Direction is given in the EOP to secure the SPDS inverter within 90 minutes to preserve battery life.

A. Incorrect: 60 minutes is the time the PMS [plant monitoring system] inverter is secured. SPDS inverter is non vita l powered B. Incorrect: 60 minutes is the time the PMS [plant monitoring system] inverter is secured.

C. Incorrect: 90 minutes is the correct time to secure the SPDS inverter but the SPDS inverter is non vital powered

References:

OP-2202.008, Station Blackout EOP, Rev 012, section I step 18, page 20 of79 EOP-2202.008, Station Blackout Tech Guide, Rev 012, section I step 18, page 24of103 STM 2-76, Safety Parameter Dip lay System (SPDS), Rev 11 , section 1.0, pages 3 and 4 Historical Comments:

• Form ES-401 -5 Written Exam Question Wo rksheet 17

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: /1938 ~ Rev: I 0 , Rev Date: 111 /27/20131:49:£] QID#:

Lie Level: [IJ Difficulty: OJ Taxonomy: [}[]

Search /oo0056A24 7 System

Title:

/Loss ofOffsite Power 1

Source:

/ IOCFR55: 41. 7 I 41.10 I 43 .5 I 45 .

14 Author:

~--'====~~~~--=======~

NRC Bank QID # 1537

~~~~~------;:::====::;---~~~------"

Safety Function I System Number I L6~

056 I KIA /

foster AA2.47 Tier: ~ Group: [ [ ] RO Imp: [TI] SRO Imp: J:TI L. Plan: / A2LP-RO-EDG I OBJ / 2

Description:

Ability to determine and interpret the following as they apply to the Loss ofOffsite Power: - Proper operation of the ED/G load sequencer Question:

Consider the following:

- Unit 2 has tripped from I 00% power due to a Loss of Offsite Power (LOOP) concurrent with a Safety Injection Actuation Signal (SIAS)

Which ONE (1) of the following list the major pump starts on the safety busses in the correct order beginning with the first pump start AND the reason why they sequence onto the vital buses at various times?

A. Service Water Pumps, HPSI Pumps, LPSI Pumps, Charging Pumps; to ensure RCS inventory and cooling are provided in the correct order B. Service Water Pumps, HPSI Pumps, LPSI Pumps, Charging Pumps; to limit the amount of current drawn from the EDGs during pump starts C. HPSI Pumps, Service Water Pumps, Charging Pumps, LPSI Pumps; to ensure RCS inventory and cooling are provided in the correct order D. HPSI Pumps, Service Water Pumps, Charging Pumps, LPSI Pumps; to limit the amount of current drawn from the EDGs during pump starts Answer:

B. Correct Notes:

The Service Water pumps supplies cooling for the EDG, HPSI and LPSI pumps so it is the first motor to start. The HPSI then LPSI then Charging are next to address the RCS inventory concerns. The large amount of counter EMF exhibited during large motor starts will be seen as a large current draw on the EDG degrading voltage and frequencies so the motors are sequenced onto the diesel to limit the current generated if all the motors started at once.

References:

STM 2-31 , Emergency Diesel Generator, Rev 33, section 3.2 page 54 Unit 2 FSAR, EDG System Description, Diesel Load Table Historical Comments:

NRC Bank QIDs were used on the 2008 (# 1537) and the 2002 (0382) NRC Exams

• Form ES-401-5 Written Exam Question Worksheet 18

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11939 I Rev: ~ Rev Date: li 2/9/2013 2:28:30 ' QID #:

Lie Level: [TI Difficulty: [Ij Taxonomy: ~

Search loo0057A204 I tocFR55:

Source: I 15 141.7 I 41.10 I 43 .5 I 45. f Safety Function System

Title:

fLoss of Vital AC Electrical Instrument Bus f System Number Author:

I I

NEW 6

057 I

foster f KIA I AA2.04 Tier: =:cJ Group: [I] RO Imp: ~ SRO Imp: ~ L. Plan: I A2LP-RO-ESFAS f OBJ I 6

Description:

Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: - ESF

,system panel alarm annunciators and channel status indicators Question:

Consider the following:

- Unit 2 is operating at 100% power

- 2RS-I , 120 Vital AC Electrical Bus, is inadvertently DE-ENERGIZED In the Engineering Safety Features Actuation System (ESF AS), the loss of 2RS- l power would cause _ __ _ _ _ Solid State Relay(s) to deenergize.

A. none of the Trip Path B. only Trip Path- I

• C. only Trip Path-3 D. Trip Path- I and Trip Path-3 Answer:

D. Correct Notes:

2RS- l powers the RED train (channel l) components. Each Matrix has 2 individual l 2v power supply, powered by a different vital bus. A failure of one matrix power supply will de-energize 2 of the 4 matrix relays (refered to as a halfleg trip). The ESF system will remain energized and none of the actuation subgroup relays will de-energize.

References:

STM 2-70, Engineered Safety Features Actuation system, Rev 18, section 2.0 pages 2-4, section 3.2.8 pages 20-21 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 19

20-Dec-13 Dat a for 2014 NRC RO/ SRO Exa m foster Bank : 11940 I Rev: LQJ Rev Date: 111125 /2013 3:55:1 J QID# : 16 Auth or:

Modified NRC Bank QID #0462 Lie Level: ~ Difficulty: ~ Taxonomy: ~

Sourc e: :

I 45.6 I 45. Safet y Funct ion :

1 6 I Searc h !oo0058K302 ! IOCFRSS: 41.5 I 41.10

System Numb er ! 058 I KIA I AK.3.02 System

Title:

!Loss of DC Power L. Plan: I A2LP-RO-Al25V I OBJ I 3 Tier: OJ Grou p: ~ RO Imp: @] SRO Imp: ~

- Actions ing responses as they apply to the Loss of DC Power:

Descr iption : Knowledge of the reasons for the follow contained in EOP for loss of de power Quest ion:

Consider the following:

- Unit 2 is operating at I 00% power tagged OPEN in preparations

- The RED battery (2Dl 1) disconnect, 2D-5 l , has been for a battery cell change out

- Battery Charger, 2D3 l A, is supplying 2DO 1

- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later Volt" comes into alarm

- Annunciator 2KOI A-10 "Cont Center 2D01 Under l A has 0 VDC output

- The IAO reports Battery Charger 2D3 te as design ed

- All other systems and components opera AOP

- The CRS has entered OP-2203 .037, Loss of 125 VDC

• In accordance with OP-2203 .037, Loss of 125 VDC

_ _ _ _ _ _ _ _ _ _ _ in bypass to prevent were to trip.

AOP, the CRS would direct placing ALL points on EITH inadvertent actuat ion of Train PPS comp ER onent s ifthe reactor A. channel 1 (2C23 -l) OR channel 2 (2C23-2); RED N

B. channel 1 (2C23- l) OR channel 2 (2C23-2); GREE C. channel 1 (2C23-1) OR channel 3 (2C23-3); RED N

D. channel l (2C23 -I) OR channel 3 (2C23-3); GREE Answ er:

D. Correct Notes:

sing all points in either Channel I or Channel 3 to D. Correct: The Joss of 125Vdc AOP will direct bypas

s. Inadvertent actuations of Red train prevent inadvertent actuations of Green train component r available for breaker operation.

components is not a concern due to no DC control powe prevent bypassing the same point in two different A. Incorrect: Interlocks within the ESF AS cabinets Red train components is not a concern due to no channels at the same time. Inadvertent actuations of DC control power available for breaker operation prevent bypassing the same point in two different B. Incorrect: Interlocks within the ESF AS cabinets channels at the same time .

onents is not a concern due to no DC control C. Incorrect: Inadvertent actuations of Red train comp power available for breaker operation Writt en Exam Quest ion Work sheet 20 Form ES-401-5

20-Dec-13 Data for 2014 NRC RO/SRO Exam

References:

OP-2203 .0 I 2A, Annunciator Corrective Actions 2KO I window A-10, Rev 045, OP-2203 .037, Loss of 125 V DC AOP, Rev 009, section 2, step 5 page 6 of AOP-2203.037, Loss of 125 V DC Tech Guide, Rev 009, section 2, step 5 page STM 2-32-5, 125 Vdc Electrical Distribution, Rev 19, section 2.7.2 page 15, 57 and page 125 of 179 6 of 57 simplified drawing page 24 Historical Comments:

NRC Bank QID #0462 used on the 2005 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 21

20-Dec-13 Data for 2014 NRC RO/SRO Exam 17 Author: foster Bank: 11941 : Rev: [ ] ] Rev Date: 110/1 /20133 :20:04 : QJD#:

Lie Level: [I] Difficulty: I 4 , Taxonomy: ~ Source: ! Modified from NRC Bank QID #0617 Search !ooo065K303  : 10CFRSS: 14 I.5 I 41.I 0 I 45.6 I 45. I Safety Function 8 I System

Title:

!Loss oflnstrume nt Air  : System Number 065 J KIA I AK3.03 Tier: ITJ Group: [JJ RO Imp: I 2.9 I SRO Imp: @] L. Plan:  ! A2LP-RO-ALIA I OBJ I 3 nt Air: - Knowing Descriptio n: Knowledge of the reasons for the following responses as they apply to the Loss oflnstrume effects on plant operation of isolating certain equipment from instrument air Question:

Consider the following:

- Unit 2 is operating at 100% power

- Annunciator 2Kl2 A-8, "INSTR AIR PRESS HI/LO" is in alarm

- Unit 2 Instrument Air Header pressure 68 psig and trending down

- Unit 1 Instrument Air Header pressure 72 psig and trending down

- OP-2203 .021, Loss oflnstrume nt Air AOP, has been entered

- CNTMT Chill Water Isolation Valves 2CV-3581-I and 2CV-3852-I have failed CLOSED

- I&C has commenced monitoring CEDM coil temperatures and reports that CEA # I coil temperature indicates 461 °F and is slowly trending up

- Restoration of Instrument Air is NOT IMMINENT and OP-2203.021, Loss oflnstrume nt Air AOP, directs _ _ _ _ ___ due to the low IA header pressure

• _ __ _ _ ___ due to the current # 1 CEA coil temperature.

A. closing the IA cross tie valves to/from Unit I; tripping the reactor B. closing the IA cross tie valves to/from Unit I; commencing a plant shutdown C. manually align Service Water to the Containment Coolers; tripping the reactor D. manually align Service Water to the Containment Coolers; commencing a plant shutdown Answer:

D. Correct Notes:

D. Correct: Loss oflA AOP, step 15 directs manually aligning SW to the Containment coolers ifIA header pressure is <65# [stem gives IA pressure at 64#] and Commence a plant shutdown is directed by step 16 contengiency actions A. Incorrect: first statement is correct but procedure does not direct tripping the Reactor until after Coil temperature rises above 500°F B. Incorrect: Procedure does not direct un-cross tying IA headers until pressure on Unit 1 IA pressure drops to 60#

C. Incorrect: for reasons stated above

References:

OP-2203 .012L, Annunciator Corrective Actions 2Kl2 window A-8, Rev 044, page 85of116 OP-2203.021, Loss oflnstrume nt Air AOP, Rev 015, step 15, page 6of108 and step 16, pages 7 and 8of108 Historical Comments :

Form ES-401-5 Written Exam Question Workshee t 22

20-Dec-/3 Data for 2014 NRC RO/SRO Exam

• Used on 2006 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 23

Data for 2014 NRC RO/SRO Exam 20-Dec-13 Bank: 11942 1Rev: m Rev Date: 111 /5/2013 2:47:20 I Q~ID_#_:---==18=::::'.__A_u_t_ho_r_: _ _'.=::==£=0s=te=r=~

• Lie Level: CI] Difficulty: CI] Taxonomy: [}[] Source: I NEW

'--~~~~------;:::====::;-----~~~~

Search loo0077KI03 I 10CFRSS: l4t.4 I 41.5 I 41.7 I 41.1 1 Safety Function I 6 I System

Title:

!Generator Voltage and Electric Grid Disturbance! System Number I 077 I KIA I AKl.03 Tier: ITJ Group: ITJ RO Imp: [ITI SRO Imp: [}I] L. Plan: I ASLP-RO-CMP05 I OBJ I 17

Description:

Knowledge of the operational implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances: - Under-excitation Question:

Consider the following:

- Unit 2 is operating at 100% power

- Main Generator output is 1044 MWe

- Main Generator MYARS are 0

- A Grid disturbance causes Grid Voltage to Rise

- No operator actions are taken As Grid Voltage goes UP, Main Generator MVARs would become more _ _ _ _ _ _ and Main Generator Exciter is protected by the _ __ _ _ _ _ _ __

A. positive (OUT); Under-Excitation Amperage Limit (URAL) circuit B. positive (OUT); Generator Maximum Excitation relay C. negative (IN); Under-Excitation Amperage Limit (URAL) circuit D. negative (IN); Generator Maximum Excitation relay Answer:

C. Correct Notes:

With no operator action, the MTG exciter field voltage is normally controlled in Automatic to hold MTG output voltage constant. As grid voltage goes up, the reactive load (MY ARs) on the Grid would be transferred to the MTG (capacitive load or IN). With MVARs starting at zero, the overall effect would be MYARs becoming more negative (capacitive load or IN) when Generator field voltage lowers, the URAL sets a minimum voltage to ensure there will be no pole slipage. The Maximum excitation limit is used to prevent field overheating.

References:

General Physics Corporation, Rev 4, chapter 5, Motors and Generators, pages 113 and 114 of 170 STM 2-30, Main Generator Constrction and Controls, Rev 9, section 2.7 page 27, section 3.2.13 page 31 , and section 4.2 page 34 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 24

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: t 1943 I Rev: ~ Rev Date: I 0/2/2013 I 0:48:2 I QID #: 19 Author: foster

~~-======------~~~----============;'

Lie Level: IT] Difficulty: I 3 I Taxonomy: ~ Source: i

~~~~~~=====::;-~~~~

NEW Search looooo3Al05 I rncFR55: 141.7 I 45.5 I 45.6 Safety Function  ; I System

Title:

loropped Control Rod System Number I 003 I KIA I AAl.05 Tier: lIJ Group: IT:: RO Imp: ~ SRO Imp: ~ L. Plan: : ASLP-RO-RXT14 I OBJ I 21

Description:

!Ability to operate and/or monitor the following as they apply to the Dropped Control Rod: - Reactor power -

turbine power Question:

Consider the following:

- Unit 2 is operating at 100% power

- Main Turbine Generator (MTG) output 1040 MW

- CEA 22 drops to the bottom of the core

- NO operator actions are taken

- 10 minutes have elapsed Compared to before the CEA dropped into the core, reactor power would be _ _ _ __ and MTG output would be A. the same; the same B. lower; slightly lower C. lower; the same D. the same; slightly lower Answer:

8. Correct Notes:

The rod worth (negative reactivity) of the inserted CEA will cause overall reactor power and RCS temperature to go down, which will lower steam pressure, lower Main Steam header, less energy to turn the turbine, less megawatts

References:

ASLP-RO-RXT14, Reactor Operational Physics, Chapter 8, Rev 4, General Physics Corp.

Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 25

20-Dec-13 Data for 2014 NRC RO/SRO Exam Bank: [1944 Rev: ~ Rev Date: [1012/2013 10:28:1 ~ QID #: 20 Author: foster J

CI] Difficulty: : 3 : Taxonom y: =:BJ Source: ~:_ _ _ _ _N_R _C_ B_a_nk _ #_0_2_3_1 _ _ _ _~

_ Q_ID Lie Level:

Search [oo0024K204 I 10CFR55 : \~ 7 _/ 4_5_.7_ _ _~ Safety Function 1._

4_ I I

_n_ _ _ _ _ _ _ _ _ _! System Number at-io y_B_o_r-ge_n_c_ i 024 [ KIA I AK2 .04 System

Title:

~[E_m_e_r-Tier: ~ Group: ~ RO Imp: [}1J SRO Imp: ~ L. Plan: [ A2LP-RO-BORON [ OBJ I 7 following : - Pumps Descripti on: !Knowledge of the interrelations between the Emergency Boration and the Question :

Consider the following:

- Unit 2 has tripped due to a Loss of Offsite power

- #2 EDG failed upon starting withdrawn

- ATC reports CEA 12 is not fully inserted as indicated by CEAC 1 and 2 reading 112"

- SPTAs have been entered

_ _ _ _ _ _ to the charging During SPTAs, the ATC would commence emergency boration by aligning._ _ _ __

pump suction.

A. the Refueling Water Tank B. gravity feed from the Boric Acid Makeup Tanks

• C. 2P-39A, "A" Boric Acid Makeup Pump D. 2P-39B, "B" Boric Acid Makeup Pump Answer:

B. Correct Notes:

The BAM pumps B. Correct: with a LOOP and #2 EDG failing to start, there is no Green train vital power.

therefore not available for emergenc y boration.

and the RWT outlet valve are green vital powered A. Incorrect: R WT outlet has no power to open C. Incorrect: "A" BAM pump has no power D. Incorrect: "B" BAM pump has no power Referenc es:

161 of 186 OP-2202.010, Standard Attachments exhibit I , Emergency Boration, Rev 12-22-10, page STM 2-04, Chemical and Volume Control System, Rev 29, pages 23 , 28 and 32 Historica l Commen ts:

NRC Bank question 0231, not used on any previous exams

• Form ES-401-5 Written Exam Question Workshe et 26

20-Dec-13 Data for 2014 NRC RO/SRO Exam Bank: I1945 I Rev: IT] Rev Date: I12/9/2013 l ll i i ] QID #: 21 Author: foster Lie Level: CI] Difficulty: 3 Taxonomy: [ E Source: I NRC Bank QID # 1728 Search ;oo0033K301 i 10CFR55: 141.5 / 41.10 1 45.6 145. : Safety Function 1 7

System

Title:

!Loss of Intermediate Range Nuclear Instrumenta I System Number '. 033 I KIA I AK3 .0I Tier: [}] Group: [D RO Imp: [II] SRO Imp: [ill L. Plan: ~------~

OBJ I

~-~

Description:

Knowledge of the reasons for the following responses as they apply to the Loss oflntermedia te Range Nuclear Instrumentation: - Termination of startup following loss of intermediate-range instrumentation Question:

Consider the following:

- Unit 2 is in Mode 2 with a Reactor Startup in progress

- Annunciator 2K 10 K-4 "STARTUP CHANNEL 1 TROUBLE" comes in alarm

-Annunciato r 2K10 K-5 "STARTUP CHANNEL 2 TROUBLE" comes in alarm

- The CRS declares Startup Channels # 1 and #2 INOPERABLE The Reactor Startup procedure, OP-2102.016 , _ _ __ _ allow the reactor startup to continue due to A. would ; the Startup channels are not required in this mode

• B. would; boron samples are being taken every 15 minutes C. would not; the loss of power to all Log power channels D. would not; no longer meeting initial conditions Answer:

D. Correct Notes:

D. Correct: OP-2102 .016 limit and precaution 5.9 that states if unexpected conditions arise the reactor should be place in a safe condition. This is also covered during the pre-job brief.

A. Incorrect: this is a correct statement but L&P 5.9 directs aborting the Reactor Startup B. Incorrect: monitoring boron concentration is not a requirement ifthe start up channels are lost C. Incorrect: All log channel power indication has not been Jost the safety channels are still available.

References:

STM 2-67-1 , Excore Nuclear Instrumentation, Rev 11 section 2.1page2 and section 2.3.3 page 8 OP-2102.016 , Reactor Startup, Rev 021 section 5.0, step 5.9 page 5 of 31 and Attachment C section 1.0 page 28 of 31 OP-2203 .012J, Annunciator Corrective Actions 2K10 window K-4, rev 039 page 54 of84 T.S. 3.3.3.5, Remote Shutdown instrumentation OP-2203 .0121, Annunciator Corrective Actions window 2K10 K-5 , rev 039 page 61 of84 Tech Spec 3.9.2, refueling instrumentation Historical Comments:

• NRC Bank QID # 1728, used on 2011 NRC Exam. Original QID 121 was used on the 1998 NRC Exam Form ES-401-5 Written Exam Question Worksheet 27

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11946 1Rev:

Lie Level: [D Search !oooo36Kl02

[TI Rev Date: 112/ 16/2013 5:26:3 1 QID #:

I 10cFRSS:

System

Title:

!Fuel Handling Incidents 141.8 I 41.10 I 45.3 22 Safety Function I System Number I Author:

-~=====--~~~---=========:

Difficulty: [}] Taxonomy: [ [ ] Source: '---1_ _ _ _ _ _ _ _NE I

_ W 8

foster 036 I

I KIA I AKl.02 Tier: [JJ Group: [}] RO Imp: [}I] SRO Imp: ~ L. Plan: I A2LP-RO-FH I OBJ I 8

Description:

Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents: -

SDM Question:

During normal operations (Mode 1) a MINIMUM Boron concentration in the Spent Fuel Pool (SFP) of greater than

_ _ __ _ _ _ is to assure the fuel assemblies will maintain a subcritical array in the event ofa postulated accident.

A. 1600 ppm B. 1800 ppm C. 2000 ppm D. 2500 ppm Answer:

C. Correct

• Notes:

T.S.3.9.12 bases

References:

T.S.3.9.12.c and bases Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 28

21-Dec-13 Dat a for 2014 NRC RO/ SRO Exam

• Bank : 11947 I Rev: [TI Rev Date: 1121912013 10:56:0 Lie Level: [ ] ] Difficulty: [}] Taxo nomy :[ ]

Searc h looo037A211 I rncFR 55: 141.7 141.10 System

Title:

!steam Generator (SIG) Tube Leak I

] Sourc e: I QID #: 23 1 43.5 145 I Safet yFun ction I System Numb er Auth or:

I I

NEW 3

037 I

foster I KIA I AA2. I I

[]}] L. Plan: I A2LP-RO-APSEC I OBJ I 3

Tier: [IJ Grou p: [JJ RO Imp: ~ SRO Imp:

Leak: - When to following as they apply to the Steam Generator Tube Descr iption : Ability to determine and interpret the isolate one or more SIGs Quest ion:

Consider the following:

"A" Steam Generator (SIG)

- Unit 2 has shutdown due to a I gpm tube leak in the

- SPTAs are complete a common problem with the RCPs

- A natural circulation cooldown is in progress due to is being implemented

- OP-2203.038, Primary to Secondary Leakage AOP,

- "A" SIG hot leg temperature is 537°F

- "A" SIG cold leg temperature is 508°F on _ _ _ leg 03.038, Primary to Secondary Leakage AOP, based "A" SIG _ _ _ _ meet isolation criteria of OP-22 temperature .

• A. does; hot B. does not; hot C. does; cold D. does not; cold Answ er:

B. Correct Notes:

plant in natural when Thot is <535°F. The given conditions place the OP-2203.038 AOP directs isolating the leaking SIG know both isolati on critier ia is based on Thot, differential. Student has to circulation which will have a large loop temperature not Tcold and <535°F.

Refer ences :

Rev 014, step 25, page 17 of32 OP-2203.038, Primary to Secondary Leakage AOP, Tech Guide, Rev 014, step 25, page 25 of81 AOP-2203.038, Primary to Secondary Leakage Histo rical Comm ents:

• Form ES-401-5 Writt en Exam Quest ion Work sheet 28

21-Dec-13 Data for 2014 NRC RO/S RO Exam

• Bank: 11948 1Rev:

Lie Level: 0 Search loo0067243 l m Rev Date: 110/3/2013 10:07:5 1 QID #:

Difficulty: [JJ Taxonomy: 0 I rncFRS S:

System

Title:

!Plant Fire on Site 14 I. l OI 45 .3 Source :

24

~-------;::::=:::::=

Safety Functio n I System Numbe r Author :

~~-'=====---~~~---=========~

I I

I NEW 9

067 foster

~----~

I K/A I 2.4.31 Tier: [I] Group: OJ RO Imp: ~ SRO Imp: @] L. Plan: I A2LP-RO AFIRE I OBJ I 2 alarms, indications, or response procedures.

Descrip tion: !Emergency Procedures/Plan - Knowledge of annunciator Questio n:

Consider the following :

- Unit 2 is operating at 100% power

- The Control room gets a report of a fire at the cooling tower

- OP-2203 .034, Fire and Explosion AOP, has been entered For this event, the would respond to the fire and, at a MINIMUM, a _ _ _ _ _ __

the Control Room .

must be dispatched to the scene as a communicator to coordinate with A. ANO Fire Brigade ; knowledgeable member of plant staff B. ANO Fire Brigade ; on watch Waste Control Operator (WCO)

• C. London Fire Department; knowledgeable member of plant staff D. London Fire Department; on watch Waste Control Operator (WCO)

Answe r:

C. Correct Notes:

IA W OP-2203 .034, Fire and Explosion AOP section 4

References:

5, page 24 of36 OP-2203 .034, Fire and Explosion AOP, Rev 015, section 4, steps 2 and steps 2, page 37 of 44, and step 5, page 39 of 42 AOP-2203 .034, Fire and Explosion Tech Guide, Rev 015, section 4, Histori cal Comme nts:

• Form ES-401 -5 Written Exam Q uestion Worksh eet 29

20-Dec-13 Data for 2014 NRC RO/S RO Exam foster Bank: 11949 I Rev: [JJ Rev Date: 112/9/2013 1: 16:20 j QID #: 25

~~-=====--~~~----=======~

Author:

Difficulty: ~ Taxonom y: [][_ Source: J'--_ _ _ _ _ _ _ _NE _ _ _ _ _ _ _~

Lie Level: [TI __W Search looo068K318  ! 10CFR5 5: 141.5 I 41.10 I 45 .6 I 45 . 1 Safety Functio n  ! 8 I

. System Number J 068 I KIA J AK3 . l 8 System

Title:

!control Room Evacuation Tier: [JJ Group: ITJ RO Imp: [4.21 SRO Imp:  ! 4.5 : L. Plan: ; A2LP-RO-ARS I OBJ J 1&2 J Room Evacuation: - Actions Descrip tion: Knowledge of the reasons for the following responses as they apply to the Control contained in EOP for control room evacuation emergency task Questio n:

Consider the following:

- Unit 2 is operating at I 00% power

- Unit 1 Halon system is inadvertently discharging into the Control Room envelope

- The Unit 2 Shift Manager directs the Unit 2 Control Room to be evacuated

- OP-2203 .030, Remote Shutdown AOP has been entered and manually Prior to exiting the control room, OP-2203.030, Remote Shutdown AOP directs Generato rs (S/Gs) by placing the EFAS actuating the Emergency Feedwater system to established feedwater to the Steam handswitches on panel 2C03 _ _ 2C14 to "Actuate".

A. tripping both Main Feedwater pumps; AND

• B. closing the Main Steam Isolation Valves (MSIVs) ; AND C. tripping both Main Feedwater pumps; OR D. closing the Main Steam Isolation Valves (MS!Vs); OR Answer:

A. Correct Notes:

becoming inhabitable A. Correct: the remote shutdown AOP would be entered due to the Control Room d, and control of the plant from the discharging Halon. The Reactor would be tripped and CR evacuate actuating EFW by placing all established from the Remote Shutdown panel. The CRS would direct and then return them to normal handswitches on 2C03 AND 2Cl4 (8 total) to their actuated positions feedwate r available to the S/Gs .

(step 6) and tripping both MFW pumps (step 7) to ensure (MSIVs) prior to exiting the control room is and action B. Incorrect: Closing the Main Steam isolation Valves specified by the Alternate Shutdown AOP not the Remote Shutdow n AOP C. Incorrect: All 8 handswitches are required to be operated Steam isolation Valves D. Incorrect: All 8 handswitches are required to be operated . Closing the Main e Shutdown AOP not the (MSIVs) prior to exiting the control room is and action specified by the Alternat Remote Shutdown AOP Referen ces:

section 1 steps 6 and 7 page 2 of 48 OP-2203 .030, Remote Shutdown AOP, Rev 013, entry section page I of 48, page 4 of25, section I pages 8 and 9 of25 AOP-2203 .030, Remote Shutdown Tech Guide, Rev 012, AOP Introduction, Historic al Comme nts:

Form ES-401-5 Written Exam Questio n Worksh eet 31

Data for 2014 NRC RO/SR O Exam 21-Dec-13

• Bank: 11950 I Rev: [ ] ] Rev Date: II0/3/2013 1:36:08 1 QID #:

Lie Level: IT] Difficulty: ITJ Taxonomy:[ [ ]

Search loo0074Al 27 Source: I I 10CFRSS: 141.7 I 45 .5 I 45.6 System

Title:

!Inadequate Core Cooling I

26 Safety Function Author:

I NEW 4 I foster I System Number I 074 I KIA I EAl.27 Tier: [}] Group: [TI RO Imp: 82] SRO Imp: GI] L. Plan: I A2LP-RO-ELOSF I OBJ I 5

Description:

Ability to operate and/or monitor the following as they apply to an Inadequate Core Cooling:

- ECCS valve control switches and indicators Question:

Consider the following :

- Unit 2 has tripped from I 00% power due to loss of all feedwater

- OP-2202.006, Loss ofFeedwat er EOP, is being implemented

- The CRS has directed to commence Once Through Cooling (OTC)

The ATC would open the _ _ _ _ __ _ vent valves using the control switches on panel _ _ __

A. Emergency Core Cooling System (ECCS); 2C09 B. Emergency Core Cooling System (ECCS); 2C336- l

• C. Pressurizer High Point; 2C09 D. Pressurizer High Point; 2C336-l Answer:

A. Correct Notes:

The Loss of Feed EOP direct opening the ECCS vents to commence OTC and the handswitches are located on control room panel 2C336-l

References:

OP-2202.006, Loss ofFeedwat er EOP, Rev 011 , step 15. Hand I. pages 7 and 8 of25 EOP-2202.006, Loss ofFeedwat er Tech Guide, Rev 009, step 20, page 32 of62 Historical Comments :

• Form ES-401-5 Written Exam Question Workshee t 31

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: [!2ill Rev: [}]

Lie Level:

Search looCE09K I 02 Rev Date: 110/11/2013 9:59:2 IT] Difficulty: [}] Taxonom y:CEJ I rncFRSS :

System

Title:

!Functional Recovery 14 I.8 I 41.1 OI 45.3 I

Source:

QID #:

I I

27 Safety Function I System Number Author:

I I

NEW O

E09 I

foster I KIA I EKI.2 Tier: [JJ Group: OJ RO Imp: Q}J SRO Imp: [ill L. Plan: I A2LP-RO-EFRP I OBJ I 1&4 (Functional Descripti on: Knowledge of the operational implications of the following concepts as they apply to the y operating procedure s associated with (Function al Recovery)

Recover): - Normal, abnormal and emergenc Question :

Consider the following:

- Unit 2 has tripped from 100% power

- "A" Steam Generator has a 0.12 gpm tube leak

- Containment Pressure, Temperature and Humidity are trending up

- Containment Low Range Rad monitors are trending up

- SPTAs are complete direct performing The CRS would diagnose _ _ _ _ _ _ _ _ EOP and once implemented, he would

_ _ _ _ _ _ _ _ _ _ _ _ _ _ to control secondary contamin ation .

• A. Steam Generator Tube Rupture; Standard Attachment 10, SG Isolation B. Steam Generator Tube Rupture; Standard Attachment 17, LOCA Isolation C. Functional Recovery ; Standard Attachment 10, SG Isolation D. Functional Recovery ; Standard Attachment 17, LOCA Isolation Answer:

C. Correct Notes:

for the FRP. Standard Conditions given indicate 2 events in progress (SGTR and LOCA) which is an entry condition secondary contamination.

Attachment 10 is directed by the FRP (HR-2 step 16) to isolate the "A" SIG and control

References:

OP-2202.009, Functional Recovery EOP, Rev 017, section HR-I, step 13 page 10 of95 of341 EOP-2202.009, Functional Recovery Tech Guide, Rev 016, section HR-I, step 16 page 239 nts, Rev 021, Att. 10 pages 26 and 27 of204 and Att. 19, pages 62-66of1 86 OP-2202.010, Standard Attachme Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 33

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: j 1952 ~ Rev: ~ Rev Date: j 101312013 3: 11 :38 Lie Level: ~ Difficulty: LIJ Taxonomy: L}] Source: '.

Search [003000K302 [ tOCFR55: j41.7 I 45 .6 System

Title:

[Reactor Coolant Pump System (RCPS)

I QID #: 28

[ Safety Function

System Number Author:

I

[

NEW 4

003 I

[ KIA [

foster K3.02 Tier: [ [ ] Group: =:!] RO Imp: ~ SRO Imp: ~ L. Plan: I ASLP-RO-CMP06 ! OBJ I 10

Description:

!Knowledge of the effect that a Joss or malfunction of the RCPS will have on the following: - SIG Question:

Consider the following:

- Unit 2 has been tripped from 100% power

- All Reactor Coolant Pumps (RCPs) have been secured Securing RCPs would cause Reactor Coolant System (RCS) flowrate through the Steam Generators to _ _ __ _ _ and would cause differential temperature across the Steam Generators to _ _ __

A. stop; rise B. stop; stay the same C. lower; rise D. lower; stay the same Answer:

C. Correct Notes:

This is applying generic fundamentals of heat transfer with a change in Mass flow rate. In the S/Gs, there is less heat being added due to the reduced flowrate caused by the securing all RCPs. With a lower mass flowrate, a larger delta Twill develop across the SIG.

References:

ASLP-RO-CMP06, Heat Exchanger and Condensers, Rev 4, General Physics Corp.

Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 34

Data for 2014 NRC RO/SRO Exam 21-Dec-l3

• Ba nk: ~ 953 ]

Lie Level: 0 Rev: m Rev Date: 112/ 18/2013 12:17:

Oifficulty: ITJ T axonomy:[ D Source: I Search loo4000K530 I 10CFRSS: 141.5 / 45.7 I Q ID #: 29 Author :

I Safety F unction [

System

Title:

jChemical and Volume Control System (eves) j System Number I 004 NEW

~-;::===::::;-~~~~~

J foster j KIA I K5.30 T ier: [JJ Group: OJ RO Imp: [ill SRO Imp: ~ L. Pla n: ! A2LP-RO-CVeS I O BJ I 2

Description:

Knowledge of the operational implications of the following concepts as they apply to the eves: - Relationship between temperature and pressure in eves components during solid plant operation Q ues tion :

Consider the following:

- Unit 2 is tripped due to a Loss ofeoolant Accident (LOeA)

- OP-2202.003, Loss of Coolant Accident AOP, is being implemented

- The Reactor Coolant System (RCS) is water solid During water solid operations, placing letdown in service would cause - - - - - - to RAPIDLY lower.

A. Pressurizer level B. Pressurizer pressure C. RCS temperature D. Reactor Vessel Level Monitoring System (RVLMS) level Answer :

B. Correct Notes:

In a solid plant condition small changes in either temperature or level will cause a large change in pressure.

References:

OP-2202.003, Loss ofeoolant Accident EOP, Rev 014, section 2 page 14 of67 Ilistorical Comments:

• Form ES-401-5 Written Exa m Question Wor ksheet 34

Data for 2014 NRC RO/SRO Exam 2 I-Dec-I 3

• Bank: 11954 1Rev:

Search loosoooK201 m

Lie Level: [ [ ] Difficulty:

Rev Date: 111129/2013 12:25:

[JJ Taxonomy:[ [ ]

I 10cFRSS: 141.7 System

Title:

!Residual Heat Removal System (RHRS)

I Source:

QID #:

. _ I_

30 Safety Function I System Number I Author:

~~-====='--~~~-=========~

I N_E_W 4

005 I

I KIA I foster K2.0l

_J

'-----;::=:=::::

Tier: [I] Group: [JJ RO Imp: [IQ] SRO Imp: [}TI L. Plan: I A2LP-RO-ECCS I OBJ ~-12_

Description:

!Knowledge of bus power supplies to the following: - RHR pumps Question:

Consider the following:

- Unit 2 is in Mode 6

- Startup #3 Transformer is supplying plant 'in-house' loads

- Startup #2 Transformer handswitches are OUT of Pull-to-Lock (PTL) for 2Al and 2A2

- The Alternate AC Diesel Generator (AACDG) is Available

- #2 EDG is OOS for maintenance

- "A" Spray pump (2P-35A) is aligned for Shutdown Cooling and is in service

- Annunciator 2K01 A-3 "L.O. Relay Trip" for Startup #3 comes into alarm

- NO operator actions have been taken OP-2203 .029, Loss of Shutdown Cooling AOP, entry conditions _ __ _ _ and the "A" Spray pump (2P-35A) _ __

running .

A. have been met; is B. have not been met; is C. have been met; is not D. have not been met; is not Answer:

B. Correct Notes:

The "A" Spray Pump is powered off of the RED vital AC train (2A3) which is supplied by 2A 1 non vital switchgear. Offsite power to the site during an outage is supplied by the Startup #3 transformer with the Startup #2 transformer in standby (available for fast transfer) to both RED and GREEN buses. A Startup #3 Lockout will initiate a fast transfer of2Al to Startup #2. The safety bus will not see a Joss of power and the Spray pump will continue to run. The Loss ofSDC Entry conditions are not met and the control room staff would respond to the Startup #3 Lock out per the ACA.

References:

OP-2107.001 , electrical System Operations, Rev. 104, Note before section 7 .0 step 7 .2 page 26 of 311 STM 2-14, Shutdown Cooling System, Rev 11, section 2.2.2 page 12 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 36

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 1955 Rev:

Lie Level:

Search R

006000K409 0 Rev Date: I 0/712013 2:32:47 Difficulty: 2 Taxonomy: H I OCFRSS: 41. 7 System

Title:

Emergency Core Cooling System (ECCS)

QID #:

Source:

31 Safety Function System Number Author:

NEW 2

006 KIA foster K4.09 Tier: 2 Group: RO Imp: 3.9 SRO Imp: 4.2 L. Plan: A2LP-RO-ECCS OBJ 13

Description:

Knowledge ofECCS design feature(s) and/or interlock(s) which provide for the following: - Valve positioning on safety injection signal Question:

Consider the following:

- Unit 2 has tripped from I 00% power due to a LOCA 15 minutes ago

- RCS pressure is 1400 psia and slowly trending down

- All systems operate as designed Low Pressure afety Injection system (LPSI) _ _ _ be injecting into the RCS and the Low Pressure Safety Injection pump recirculation flow path would be aligned to _ _ _ _ _ _ _ __

A. would; Refueli ng Water Tank (RWT)

B. would not; Refueling Water Tank (RWT)

C. would; ECCS pump suction piping D. would not; ECCS pump suction piping Answer:

B. Correct Notes:

A Safety Injection Actuation {SIAS) occurs when RCS pressure drops below 1650#. The SIAS wil l start the LPSI pumps and open the injection MOVs. Shutoff head of the LPSI pump is approximately 200# therefore no flow would be provide to the RCS. The LPSI pump recirc tlowpath is aligned to the RWT, ifa Recirc Actuation Signal (RAS) occurred the LPSI pump is tripped and the recirc flowpath valves would go closed, isolating the LPSI recirc tlowpath from the R WT. A RAS is not actuated based on the time given [ 15 minutes] the RWT holds enough inventory to supply the ECCS pumps for 30 minutes during a OBA. The given conditions does not indicate a OBA in progress [RCS pressure 1400# and slowly trending down] therefore the LPSI recirc flowpath is still aligned to the RWT.

References:

STM 2-05, Emergency Core Cooling System, Rev 27, section 3.2, page 16, section 4.2, pages 30 and section 4.5 page 38 STM 2-08, containment Spray System, Rev 22, section 3.1.1 pages 7 and 8 Historical Comments:

• Form ES-401 -5 Written Exam Question Worksheet 37

21-Dec-13 Data for 2014 NRC RO/SRO Exam

• Bank: jl956 I Rev:

Lie Level: 0 Search joo6000A213

[2J Rev Date: jl0/ 11/2013 9:14:2 Difficulty: [}] Taxonomy:[!IJ Source: I I 10CFR55:

I j41.5 / 43.5 / 45.3 / 45.

System

Title:

jEmergency Core Cooling System (ECCS)

QID #:

I 32 SafetyFu nction I System Number Author:

I I

NEW 2

006 I

foster I KIA I A2 .13 Tier: [JJ Group: [JJ RO Imp: [I[] SRO Imp: @ ] L. Plan: I A2LP-RO-INAD I OBJ I 1&2 s on the ECCS and (b) based on

Description:

Ability to (a) predict the impacts of the following malfunctions or operation malfunctions or those predictions, use procedures to correct, control, or mitigate the consequences of those operations: - Inadvertent SIS actuation Question:

Consider the following :

- Unit 2 is operating at 100% power

-Annunci ator 2K07 A-1 "SIAS ACT" is in alarm

- The Reactor did not trip

- RCS pressure 2200 psia and steady

- Containment parameters are normal and steady The CRS has entered the appropriate AOP and would direct the CBOT to override and _

• A. open Service Water (SW) to Aux Cooling Water (ACW) supply isolation valves B. open the Component Cooling Water (CCW) isolation valves to the containment building C. close the ECCS Containment Sump isolation valves inside the containment building D. close the ECCS Containment Sump isolation valves outside the containment building Answer:

A. Correct Notes:

Action is in accordance with the Inadvertent SIAS AOP

References:

OP-2203.012G, Annunciator Corrective Actions 2K07 window A-1, Rev 030, page 4 of70 OP-2203 .018, Inadvertent SIAS AOP, Rev 010, entry section, page 3 of 52 AOP-2203 .018, Inadvertent SIAS Tech Guide, Rev 009, page 6 of60 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 38

Data for 2014 NRC RO/SRO Exam ZO-Dec-13 Bank: I 957 Rev: 0 Re** Dale: I0/712013 11 :28:4 QID #: 33 Author: fostc;:---i Lie Lcnl: IR Difficulty: 3 Taxonomy: F Source: L NRC Bank QIO #1742 Search 1

007000Al02 IOCFRSS: 41.5 :' 45.5 Safely Function I 5 System

Title:

Pressurit.er Rcllcf 'l'a nk!Quench Tank System (P System Number 007 I KIA /\ 1~

Tier: 2 Croup: _ 1_ RO lmp: 1.:2..._ SRO Imp: 2.9 J L. Piao: /\2Ll>-RO-R.CS I OBJ I ~

Description:

Ability oo predict and/or monitor changes in parameters (to pre**ent exceeding design limits) associated wilh opera1ing the PRTS controls including:* Maintaining quench tank pressure Question:

Consider the following:

• Uni! 2 is operating al I 00% power

• Am1unciator 2K I0 D-4 Qu~nch Tank Pressure Hl is in alarm

• 2PIS-4694, Quench Tank Pressure, is 4 2 psig and slowly trending up

• 2LIS-4694, Quench Tank Level. is 78% and slowly trending up A possible source of inleakage to lhe Quench Tank is from - - -- -- _ __ and lhe Quench Taok would be drained to the to clear the alann.

A. RCS High Point Yonts; Containment Sump R. RCS High Point Vents; Reactor Drain Tank C. Pressurizer Spray Valve Stem leakoff; Rcacror L>rain Tank D. l'res5Uri7a Spray Valve Stem leakoff; Containment Sump Answer:

B. Correct Noh:s:

B. Correct: RCS high point vents di;charge into the quench t mk and Lhc quench tank is vented to the Reactor Drain Taok

/\, lncolTeCt: RCS high points venl< do go to the Quench Tank but venting 10 the containment sump is not an option in the OP-2103.007. The quench iank vent path could be aligned co die containment atmosphere lhru the high point vent header but is not procedurnlly driven in the given mode.

C. lncotrecr: Pressurizer Spra) Valve Stem lcakofl'is not directed to the Qoench tank but the RcaclOI' Drain Tank.

D. Incorrect: Pressurizer Spray Valve Stem leakoff is noc directed to the Quench tank bur the Reactor Drain Tank.

Rcfcrcoce.;:

OP* 2203.0J2J, Annunciator Corrective Actions 2K10 window D-4, Rev 039, page 48 of 84 STM 2-52, Liquid Radwaste/Boron MlillagcmcnLS)-Stem, Rev 17, seetion 3.1, page 13 STM 2-03, Reacwr Coolant System, Rev 22, section 2.3, pages 23 and 24 OP-2103.007, Quench Tank and Reactor Drain Tanl OPS. Rev 023, section 7.6. pagelO of30

• His to ri c~I Comments:

used on 2012 !'RC Exam Forni ES-401-5 Written Exam Question Worksh.eet 39

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11958 1Rev:

Lie Level:

Search loo8000K105

[QJ Rev Date: '. 1017/2013 4:03 :37] QID #:

10CFR55: 41.2 to 41.9 I 45.7 to 4 System

Title:

\Component Cooling Water_S_y-st_e_m_(_C_C_W_sLJ 34 Safety Function

_)_~ System Number Author:

~~======-~~~----============:

~ Difficulty: 2 Taxonomy: ~ Source: :'----_ _ _ _ _ _ _N_E_W_ _ _ _ _ _ ____,

I 1~_8_~1 008 I KIA I foster Kl.05 L___-;:::====='.

Tier: ~ Group: JJ RO Imp: I 3.0 I SRO Imp: ; 3.1 I L. Plan: A2LP-RO-CCW OBJ '-I_4~

Description:

Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems: - Sources of makeup water Question:

The system supplies normal makeup to the Component Cooling Water (CCW) surge tanks and the level control valves will fail on a loss of power.

A. Domestic Water; closed B. Domestic Water; open C. Condensate Transfer; closed D. Condensate Transfer; open Answer:

C. Correct Notes:

Makeup is supplied by the condensate transfer system and the makeup valve is an air actuated to open by energizing the air supply solenoid

References:

STM 2-43, Component Cooling Water System, Rev 13, section 2.8, pages 9 and 10 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 40

20-Dec-13 Data for 2014 NRC RO/S RO Exam

• ITJ Author: foster Bank: j1959 i Rev: Rev Date: jl0/31 /20138: 18:0 I QID #: 35

~~======'---~~~----=============:

Lie Level: CK] Difficulty: [}] Taxonomy:[}] Source: I

~--------

NEW

---

~

Search 10080002244 I 10cFR5 5: 141.10 / 43.5 / 45.12 Safety Functio n I 8 I System

Title:

icompon ent Cooling Water System (CCWS) '. System Number '. 008 I KIA I 2.2.44 Tier: ((j Group: ~ RO Imp: ~ SRO Imp: 4.4 L. Plan: I A2LP-RO-CCW I OBJ I 2 ns to verify the status and operation of a system, Descrip tion: Equipment Control - Ability to interpret control room indicatio ns.

and understand how operator actions and directives affect plant and system conditio Questio n:

Consider the following:

- Unit 2 is operating at 100% power chemist request

- "C" Coolant Charging Pump (CCP) 2P-36C, has been placed in service upon the output of the Main Feedpump Lube Oil The output of the Letdown temperature controller would _ _ __ ___ and temperature controller would A. go up; go up B. go up; go down

• C. go down; go down D. go down; go up Answer :

B. Correct Notes:

raising letdown flow from the RCS. As letdown When a second CCP is places in service, the letdown system will response by er and the letdown Hx temperature control valve flow goes up, there is a greater demand for cooling of the letdown heat exchang for cooling goes up, so does CCW flow through will throttle open more. The letdown Hx is cooled by CCW and as the demand CCW cooled components [i.e. MFP LO the letdown Hx. As CCW flow goes up, there will be less available flow to other goes up, the valve will open] the MFP LO coolers] the letdown Hx temperature control valve is a direct acting [as demand down, the valve will open] therefore , as the flow cooler temperature control valve is reverse acting [as controller demand goes valve would open.

has increased in the letdown Hx, the MFP LO cooler temperature control

References:

EN-WM-105, work order Standard Tl 1123 pages 4 of8 and 6 of8 Historic al Comme nts:

NRC Exam Bank QID # 17 44 used on 2011 NRC Exam

• Form ES-401-5 Written Exam Questio n Worksh eet 41

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: 11960 I Rev: [ ] ] Rev Date: 110/31/2013 9:28:5 1 QID #:

Lie Level: 0 Search lo10000K60l Difficulty: [I] Taxonomy:[![]

I 10cFR55: 141.7 I 45 .7 Source: ~I I

36 Safety Function System

Title:

!Pressurizer Pressure Control System (PZR PCS) I System Number Author:

___M_o_d-ifi-1e_d_NR I

I C_B_a_nk 3

010

_ Q_I_D_ # _l I

I KIA I foster 5_2_3--~

K6.0l Tier: OJ Group: [JJ RO Imp: [DJ SRO Imp: QI] L. Plan: I A2LP-RO-PZR I OBJ I 4&5 I

Description:

Knowledge of the effect ofa loss or malfunction of the following will have on the PZR PCS: - Pressure detection systems Question:

Consider the following:

- Unit 2 is operating at 100% power

- The "A" Pressurizer Pressure Control Channel is in service

- Annunciator 2Kl2 E-6 "CNTRL CH 1 Pressure HI/LO" comes into alarm

- "A" Pressurizer Pressure instrument (2PS-4626A) has failed low

- No Operator action has been taken The Pressurizer backup heater breakers would _ _ _ __ _ _ and the Proportional Heaters would go to a _ _ __ __

firing rate.

A. open; maximum B. close; maximum C. open; minimum D. close; minimum Answer:

B. Correct Notes:

The pressure control system would see the false low pressure and with the control channel indicating <25 psia below setpoint (2200 psia@ 100% power) the backup heaters breakers will close and energize all Backup Heaters and send a maximum fire command to the proportional heaters.

References:

OP- 2203 .012J, Annunciator Corrective Actions 2Kl0 window E-6, Rev 039, page 68 of84 STM 2-03-01 , Pressurizer Pressure and Level Control, Rev 16, section 2.0 pages 8, 11 and 12 Historical Comments:

NRC Bank QID #1523 used on 2008 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 41

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: J1961 J Rev:

Lie Level:

Search Jo12000A403

[I]

System

Title:

~JR-e-ac_t_o_

r-Rev Date: J10/ 18/2013 11:14: J QID#:

CI] Difficulty: ~ Taxonomy:[ [ ]

J 10CFR55: J41.7 I 45.5 to 45.8 Pr-o-te_c_t-io_n_S_y_s-Source:

37 Safety Function te-m-------~J System Number J Author:

.---~-'====='---~~~-=========::;'

J I

NEW

~~~~~------;::::====::;-----~~~~

7 012 J

J KIA :

foster A4.03 Tier: [JJ Group: [JJ RO Imp: Q}] SRO Imp: [))] L. Plan: J A2LP-RO-RPS J OBJ J 10

Description:

jAbility to manually operate and/or monitor in the control room: - Channel blocks and bypasses Question:

Consider the following:

- Unit 2 is performing a plant cooldown As the RCS is cooled down, the Low RWT Level/Low PZR Pressure Operating Bypasses are _ _ _ _ _ bypassed and the HI/Low S/G Level Operating Bypasses are bypassed.

A. manually; automatically B. automatically; manually C. manually; manually

• D. automatically; automatically Answer:

C. Correct Notes:

There is no automatic function to go into bypass but either will automatically come out of bypass. The Low R WT Level/Low PZR Pressure Operating Bypass will come out of bypass when RCS pressure is >436 psia and the HI/Low S/G Level Operating Bypass will automatically come out of bypass when RCS Th is > l 95F

References:

OP-2102.010, Plant Cooldown, Rev 049, section 9.6 page 23 of54 and section 9.18 page 30 of54 STM 2-63, Reactor Protection system, Rev 11, section 6.2.2.2 and section 6.2.2.3 page 44 Historical Comments:

• Form ES-401 -5 Written Exam Question Worksheet 43

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11962 ! Rev:

Lie Level:

Search lo13000K301 3J Rev Date: ;121212013 10:31 :3 ; QID#:

IT] Difficulty: [}] Taxonomy: [TI

! t0CFR55: 141.7 I 45.6 Source: !

38 Safety Function System

Title:

!Engineered Safety Features Actuation System (E I System Number :

Author:

I NEW 2

013 I Kl A I foster K3.01 Tier: OJ Group: [JJ RO Imp: ~ SRO Imp: @] L. Plan: [ i fLP-RO-ECCS I OBJ I 4

Description:

!Knowledge of the effect that a loss or malfunction of the ESFAS will have on the following : - Fuel Question:

To limit the peak cladding temperature of the fuel, the Emergency Safety Features Actuation Signal (ESFAS) is used to actuate components in the Emergency Core Cooling System (ECCS) and together they are designed for a loss or malfunction of:

A. a single failure of an active component during the injection mode OR a single failure of an active or passive component during the recirculation mode B. a single failure of an active component during the injection mode OR a single failure of an active and passive component during the recirculation mode C. a single failure of an active or passive component during the injection mode OR a single failure of an active or passive component during the recirculation mode D. a single failure of an active or passive component during the injection mode OR a single failure of an active and passive component during the recirculation mode Answer:

A. Correct Notes:

Design bases for ECCS

References:

STM 2-05, Emergency Core Cooling System, Rev 27, section 1.1 pages 1 and 2 Tech Spec 3.5.2 and 3.5.3 bases STM 2-70, Engineerd Safety Features Actuation system, Rev 18, section 2,2, 1 page 5, Table on page 8 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 44

21-Dec -l 3 Data for 2014 NRC RO/S RO Exam

• Bank: II 963 I Rev: [ ] ] Rev Date: I10/8/2013 2:41: 17 I QID #:

Lie Level: 0 Search lo26000K408 Difficulty: [)) Taxon omy:[ EJ Source: !~_ _ _ _ _

I 10cFR SS: 141.7 System

Title:

!contain ment Spray System (CSS) 39 R_

N_

Safety Functio n I System Numbe r C_B Author :

I I

_Q

_a_nk 5

026 D_#_1_7_4_

_I_

I foster 9----~

I K/A I K4.08 Tier: [D Group: DJ RO Imp: ~ SRO Imp: @] L. Plan: I A2LP-RO-SPRA Y I OBJ I 4 which provide for the following: -Autom atic Descrip tion: Knowledge ofCSS design feature(s) and/or interlock(s) swapover to containment sump suction for recircul ation phase after LOCA (RWST low-low level alarm)

Questio n:

Consider the following:

- Unit 2 has tripped due to a Design Based Accident (DBA) LOCA

- One ( 1) hour has elapsed (ECCS) pumps is the _ _ _ _ _ _ _ _ and The suction source for the running Emergency Core Cooling Systems adequate core heat removal would be verified using _ _ _ _ __

A. Refueling Water Tank (RWT); Exhibit 2, HPSI Flow Curve B. Refueling Water Tank (RWT); Exhibit 3, LPSI Flow Curve

• C. Containment sump; Exhibit 2, HPSI Flow Curve D. Containment sump; Exhibit 3, LPSI Flow Curve Answe r:

C. Correct Notes:

in approximately 30 minutes following the Design The RWT inventory will be transferred into the containment building n setpoint) the ECCS suction header automatically Based Accident (DBA) LOCA. When RWT level reaches 6% (RAS actuatio to prevent pump damage and cavitation of the HPSI swaps to the containment sump. The LPSI pumps will trip on the RAS expected flow for given RCS pressure that is required for and Spray pumps due to the LPSI high flowrate. Exhibit 2 shows the Inventory and Heat Removal.

Referen ces:

of204 EOP 2202.010, Standard Attachments, Rev 022, exhibit 2, page 181 1.3, pages 2 and 3 STM 2-05, Emergency Core Cooling System, Rev 27 , section 3.1.1, pages 7 and 8 STM 2-08, Containment Spray System, Rev 22, section Histori cal Comme nts:

NRC Bank QID #749 used on the 2006 NRC Exam

• Form ES-401-5 Written Exam Questio n Worksh eet 46

Data for 2014 NRC RO/SRO Exam 20-Dec-13 1

Bank: 11964 ! Rev: 0 I Rev Date: [10/ 11/2013 7:55 :4 I QID #: 40 Author: foster Lie Level: ~ Difficulty: 3 Taxonomy: ~ Source: \'- - - -- - - -NE - -W - - - - - -- -----,

1 1 Search \022000K404 I t0CFRSS: \41.7 Safety Function I 5 I System

Title:

!containment Cooling System (CCS) I System Number L~ KIA \ K4.04 Tier: [JJ Group: =cJ RO Imp: ~ SRO Imp: 1 3.1 1 L. Plan: I A2LP-RO-CVENT I OBJ I 3&10 I

Description:

Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following: - Cooling of control rod drive motors Question:

Cooling Water to the CEDM Coolers is normally supplied by _ _ _ _ _ _ and if Containment Building pressure rose to 20.0 psia the CEDM cooling would be _ _ __ _ __

A. Main Chilled Water; isolated B. Main Chilled Water; supplied by Service Water C. Component Cooling Water; isolated D. Component Cooling Water; supplied by Service Water Answer:

A. Correct Notes:

Normal supply is Main Chilled Water. It comes into containment and flows through the Containment Coolers (for preheat) and then to the CEDM coolers. With Containment building pressure > 18.3 psia, a Containment Isolation Actuation Signal (CIAS) will occur. The CIAS wi ll isolate chill water to the containment. This pressure will also cause an Containment Cooling Actuation Signal (CCAS) which will align SW to the Containment cooler. also, the distractor ofCCW is valid due to the CCW system supplying loads inside the reactor building.

References:

STM 2-09, Containmnet Cooling and Purge Systems, Rev 18, section 2.2 pages 4 and 5, section 2.5 pages 6 and 7, section 2.7 page 10 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 46

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11965 1Rev: [ ] ] Rev Date: ll0/9/2013 12:14:5 I QID #: 41 Author: foster Lie Level: ~ Difficulty: ~ Taxonomy: =-:[J Source: NEW 1

Search lo26000Kl02 I 10CFR55: j4 I.2 to 41.9 I 45.7 to 4 I Safety Function I 5 I System

Title:

!containment Spray System (CSS) I System Number ! 026 I KIA I Kl.02 Tier: ; 2 : Group: ~ RO Imp: =:DJ SRO Imp: 4 .1 L. Plan: i A2LP-RO-SPRA Y I OBJ I 3

Description:

Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: - Cooling water Question:

For a Containment Spray pump to be considered OPERABLE, Service Water _ __ _ required to be aligned to the seal cooler and the Auto Start feature of the ESF room coolers ___ required .

A. 1s; is B. is; is not C. is not; is D. is not; is not Answer:

B. Correct Notes:

Pump seal water cooling is required but the Auto start feature is not. 2 room coolers have to be operable with SW aligned and capable of either auto starting or manually started from the Control room. The requirement for seal water cooling is plausable based on the LPSI pumps only required when RCS temperature is > l 60°F and it is not required for the HPSI pumps.

References:

STM 2-08, Containment Spray System, Rev 22, section I 0.0 page 33 OP-2104.005, Containment Spray, Rev 069, section 5.0 page 7of192 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 47

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• I Bank: 11966 Rev: [ ] ] Rev Date: !10/10/2013 10:46:

Lie Level: CE] Difficulty: OJ Taxonomy:[][]

Search lo39000A404 j IOCFRSS: j41.7 I 45.5 to 45.8 System

Title:

!Main and Reheat Steam System (MRSS)

J Source:

QID #:

I I

42 Safety Function System Number Author:

I I

NEW 4

039 I

KIA I foster A4.04 m

J J Tier: Group: [JJ RO Imp: [}I] SRO Imp: [I[! L. Plan: I A2LP-RO-ELOSF I OBJ I 3&4

Description:

jAbility to manually operate and/or monitor in the control room: - Emergency feedwater pump turbines Question:

Consider the following:

- Unit 2 is recovering from a complete Joss offeedwater event

- "A" S/G level 12% trending down

- "B" S/G level 19% trending down

- The WCO just reported she has reset 2P-7A and it is ready for start OP-2202.006, Loss ofFeedwater EOP directs controlling the initial feed rate to the Steam Generators to prevent

_ _ _ __ _ _ _ _ and this would be accomplished by _ _ __ _ _ _ _ _ __

A. damaging the feed ring; throttling the injection valves

• B. damaging the feed ring; controlling pump speed C. overcooling the RCS ; throttling the injection valves D. overcooling the RCS; controlling pump speed Answer:

B. Correct Notes:

With S/G level <49%, the feed ring is uncovered and the water will flash to steam. There is a possibility of collapsing the feed ring when cold feed water is restored. The EOP direct controlling feedwater flow to <150 gpm to minimize the chance of feed ring damage. 2P-7 A is the steam driven EFW pump and its S/G feed injection valves are not throttlable. The EOP directs controlling pump speed to control feed rate.

References:

OP-2202.006, Loss ofFeedwater EOP, Rev 011, step 12 page 5 of25 OP-2202.0 I 0, Standard Attachment, Rev 022, Att. 54 step 3 page 1 of 3, step 9 page 3 of 3 EOP-2202.006, Loss ofFeedwater Tech Guide, Rev 009, step 12 pages 19 and 20 of62 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 49

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• IT]

Bank: J1967 J Rev: Rev Date: Jl 1122/2013 4:50:0 J QID #: 43 Author: foster Lie Level: CK] Difficulty: CI} Taxonomy:[EJ Source: : Modified NRC BANK QID #0669 Search J059000K303 J toCFR55: [4G I 45.6 Safety Function I 4 System

Title:

JMain Feedwater (MFW) System J System Number J 059 J KIA J K3.03 Tier: [IJ Group: C::C: RO Imp: ~ SRO Imp: 02] L. Plan: J A2LP-RO-FWCD J OBJ J 14

Description:

!Knowledge of the effect that a loss or malfunction of the MFW System will have on the following: - S/Gs Question:

Consider the following:

- Unit 2 is operating at 80% power

- The "A" Feed Water Control System (FWCS) Master Controller, 2FIC-1029, has been placed in MANUAL due to a malfunction

- The Unit now trips

- No Operator actions are taken The "A" Steam Generator level would _ _ _ _ __ _ rise and operator action _ _ __ required to prevent a High Level Override (HLO) from occurring.

A. continuously; is

• B. continuously; is not C. initially shrink then slowly; 1s D. initially shrink then slowly; is not Answer:

C. Correct Notes:

With the Master controller in manual the response to a reactor trip are unaffected allowing Steam Generator levels to be maintained by the RTO signal. When the RTO condition has cleared [level >55% after 60 seconds] operator action would be required to prevent S/G levels from continually rising as set by the manual demand on the master controller pre trip.

References:

STM 2-69, Feedwater Control System, Rev 13, section 2.1 page 3, section 2.7 page 31, and section 3.3 page 39 Historical Comments:

NRC Bank QID #0669 used on the 2003 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 49

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: ~ Rev: ; 0 I Rev Date: I10/1 0/2013 10:21: : QID #: 44 Author: foster Lie Level: IT] Difficulty: rr= Taxonomy:[E J Source: ; NEW Search lo59000A207  : IOCFRSS: 141.5 I 43 .5 I 45.3 I 45.1 j Safety Function I 4  :

System

Title:

!Main Feedwater (MFW) System I System Number ! 059 I KIA I A2.07 Tier: [ [ ] Group: [JJ RO Imp: I 3.0 J SRO Imp: I 3.3 I L. Plan: I A2LP_RO-AMFP I OBJ i 3

Description:

Ability to (a) predict the impacts of the following malfunctions or operations on the MFW System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Tripping of MFW pump turbine Question:

Consider the following:

- Unit 2 has completed a plant startup and is raising power

- Current power is 3% and trending up

- "A" and "C" Condensate Pumps (2P-2A and 2P-2C) are running

- "A" Main Feed Pump (2P-1A) is in operation

- "B" Main Feed Pump (2P-1B) is idling for oxygen control

-Annunciator 2K03-A8 "Feed Pump Trip" is in alarm for "A" MFP

- OP-2203 .027, Loss of Main Feedwater Pump AOP has been entered Using OP-2203 .027, Loss of Main Feedwater Pump AOP, the FIRST pump the CRS would direct placing in service to recover Steam Generator levels would be the _ _ _ _ _ _ _ _ __

A. "A" Main Feed Water pump (2P-1A)

B. "B" Main Feed Water pump (2P-I B)

C. Aux Feed Water (AFW) pump (2P-75)

D. "B" Emergency Feed Water pump (2P-7B)

Answer:

B. Correct Notes:

IA W the AOP, step 3 contingency column 3.A. the steps are lettered not bulleted so they would be performed in order.

References:

OP-2203 .012C, Annunciator Corrective Actions 2K03 window A-8 , Rev 029, page 97of176 OP-2203 .027, Loss of Main Feed Water Pump AOP, Rev 013 step 3 page 2of11 AOP-2203.027, Loss of Main Feed Water Pump Tech guide, Rev 013 step 3 page 5of18 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 50

21-Dec-13 Dat a for 2014 NRC RO /SR O Exam

• 45 Auth or: foster Bank : 11969 1Rev: CI] Rev Date : 112/16/2013 9:51:5 1 QID #:

Lie Level: [TI Difficulty: CI] Tax onom y:((] Sour ce: I NEW I Safet y Func tion I 4 I Searc h lo6JOOOK502 I toCF R55: 141.5 I 45.7 I System Num ber I 061 I KIA I K5.02 Syste m

Title:

!Auxiliary I Emergency Feedwater (AFW) Syste

[JJ Group: [ [ ] RO Imp: []}] SRO Imp: [il l L. Plan:

I A2LP-RO-ESPTA I OBJ I 11 Tier:

m: -

following concepts as they apply to the AFW Syste Desc riptio n: Knowledge of the operational implications of the Decay heat sources and magnitude Ques tion:

gpm from the Emergency Feed Water (EFW )

15 minutes post trip, the required flow of >485 heat from the Reactor Coolant System (RCS).

system is required to adequately remove decay decay from the Reactor system would be required to adequately remove 45 minutes later, - - - - flow from the EFW Coolant System (RCS).

A. to each Steam Generator; more B. to each Steam Generator; less C. total flow to the Steam Generators; more th_e_s_t_ea_m__G_e_ne_r_a_to_rs_;_l_e_ss____ ____

__to- - ____ ____ ____ ____________________

• ___D_._t_o_ta_l _fl_ow Answ er:

D. Correct Notes:

to each S/G remove decay heat.

Total required EFW flow post trip is >485 gpm Refer ences :

14, step 8 contingency A.2, page I 0 of 17 OP-2202.00 I, Standard Post Trip Actions, Rev.

Guide, Rev. 014, step 8, page 19 of 42 EOP-2202.001, Standard Post Trip Actions Tech section F.3, page 111 EOP Setpoint Document Setpoint F.3, Rev 13, Histo rical Com ment s:

• Form ES-401 -5 Writ ten Exam Ques tion Work sheet 52

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: 11970 I Rev:

Lie Level:

Search joo5000A101 m Rev Date: jJ0/8/2013 12:11 :5 ITJ Difficulty: [I] Taxonomy:[ [ ] Source: I I 10cFRSS: 141.5 I 45.5 System

Title:

jResidual Heat Removal System (RHRS)

I QID #:

I 46 Safety Function Author:

I I System Number I 005 NEW 4 I I KIA I foster Al.01 Tier: [}] Group: [JJ RO Imp: ~ SRO Imp: O]J L. Plan: I A2LP-RO-TS I OBJ ~I~

Description:

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: - Heatup/cooldown rates Question:

Consider the following:

- Unit 2 is in Mode 5

- A loss of Shutdown Cooling (SDC) has occurred with an initial Reactor Coolant System (RCS) temperature at 1402 is 174°F

- At 1404, RCS temperature has risen to l 77°F IfNO operator actions are taken, at what time will the RCS reach the temperature requirement to enter Mode 4?

A. 1405 B. 1410

c. 1417 D. 1422 Answer:

C. Correct Notes:

C. Correct: With a Loss ofSDC a Heatup will occur. the heatup rate for above conditions is l.5 °F/minute

( J 77°F - 17 4°F = 3°F divided by 2 minutes = 1.5 °F) The lower temperature for entry into mode 4 is 200°F.

time difference, 200°F - 177°F = 23°F divided by l.5 °F/min = 15.3 minutes. 1402 + 15.3 minutes = 1417 A. Incorrect: number based on the difference between I 77°F but dividing by 3°F/minute (if they did not take into account for the 2 minutes between temperature readings)

B. Incorrect: number based on 174°F vs. 177°F and dividing by 3°F/min D. Incorrect: number based on l 74°F vs. l 77°F

References:

T.S. Table 1.1 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 53

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: ~ Rev:

Lie Level:

Search lo63000K201

[QJ Rev Date: 110/8/2013 10:39:3 1 QID #:

IT] Difficulty: [I] Taxonomy:Q J I 10CFRSS: 141. 7 System

Title:

ID.C. Electrical Distribution System 47 Author:

~~--'=====--~~~----=========~

Source: I NEW

'--~~~~-----;:::====;---~~~---'

Safety Function I System Number I I 6 063 I

I KIA I foster K2.0l Tier: []_] Group: OJ RO Imp: rm SRO Imp: OJ] L. Plan: I A2LP-RO-ED12 5 I OBJ I 4

Description:

!Knowledge of bus power supplies to the following: - Major DC loads Question:

The trip circuit control power for Trip Circuit Breakers TCB-3 and TCB-7 is supplied by _ _ _ __

A. 2RA- l , l 25V DC panel B. 2RA-2, 125V DC panel C. 2D-35, Battery Eliminator D. 2D-36, Battery Eliminator Answer:

C. Correct

• Notes:

C. Correct: The flowpath from the RED DC bus; through a vital inverter 2Y-13 or swing inverter 2Yl 113, to 2RS-3 , 2035 battery eliminator to the Yellow or channel 3 TCB control power A. Incorrect: Supplies control power to TCB-1 and 5 B. Incorrect: Supplies control power to TCB-2 and 6 D. Incorrect: Supplies control power to TCB-4 and 8

References:

STM 2-02, Control Element Drive Mechanism Control System, Rev 20, section 5.3.1 , pages 39 and 40 STM 2-32-5, 125Vdc Electrical Distribution, Rev 18, section 8.0 simplified drawing Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 54

Data for 2014 NRC RO/SRO Exam 20-Dec-13 Bank: i1972 I Rev: [ [ ] Rev Date: !10/3112013 1 :h lj Q.- 8 ==_A_ut_h_o_r:_-'=====fo=s=te=r==~

ID_ #_: -'===4=

• . Lie Level: ~ Difficulty: [ l j Taxonomy: ~ Source: I NEW

'----~~~~--;::::====::;--~~~~

Search !o62000A212 I 10cFRSS: 141.5 I 43.5 I 45.3 I 45 .1 J Safety Function 6 System

Title:

A.C. Electrical Distribution System ] System Number 062 I KIA I A2.12 Tier:  ! 2 I Group: [JJ RO Imp: 1 3.2 ! SRO Imp: j3.6 L. Plan: j A2LP-RO-SPRA Y I OBJ I 8& 13 I

Description:

Ability to (a) predict the impacts of the following malfunctions or operations on the A.C. Distribution System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Restoration of power to a system with a fault on it Question:

Consider the following:

- Unit 2 has tripped from 100% power due to a large break LOCA

- Annunciator 2K09 B-3 "2A4 L.O. Relay Trip" is in alarm

- Containment Pressure is 25 psia and trending up

- Annunciator 2K06 A-1 "2P-35A failure on ESFAS" is in alarm

- All other components operate as designed "A" Spray pump (2P-35A) and breaker ___ required to be investigated prior to start due to _ _ _ __ __

A. are; # 1 EOG running B. are; possible electrical fault on the 4160V Bus C. are not; the safety function not being met D. are not; no other alarms associated with the pump are in Answer:

C. Correct Notes:

C. Correct: Annunciator 2K06 A-1 "2P-35A failure on ESF AS" comes into alarm 45 seconds after it receives an auto start command (CSAS) With 2A4 bus locked out, the "B" Spray pump is unavailable along with the Green Train containment coolers. With containment building pressure trending up starting the "A" spray pump is needed to meet the containment safety function . 1 start attempt is allowed by the ACA if an emergency condition exists and the bus is powered from offsite. The Red bus (2A 1/2A3) is aligned to offsite with the given conditions.

A. Incorrect: The ACA would require the pump to investigated prior to a start attempt ifthe bus was powered from a EOG. The # I EOG is running (started by the SlAS @ 18.3#) but is not tied to the bus.

B. Incorrect: is not required to be investigated prior to a start attempt per the ACA D. Incorrect: The ACA does not allow a start attempt solely based on no other associtated pump alarms are in, i.e. an investigation of the pump prior to start would be required even without any other associtated pump alarms if2P35B was running.

References:

OP-2203.012F, Annunciator Corrective Actions 2K06 window A-1 , Rev 037, page 4 of79 COPD-032, Transient Conduct of Operations, Rev 003, section 9.3 page 18 of 41 Historical Comments:

Form ES-401-5 Written Exam Question Worksheet 54

21-Dec-13 Data for 2014 NRC RO/ SRO Exam

• 4 J QID #: 49 Autho r: foster Bank: Ji973 J Rev: [ ] ] Rev Date: J!0/8/2013 10:01: ,--~__'::==:==~~~~-=========

~

~ _ _ _ N _C

_R _ A B_ _N _

_K _

Q_ID #_ _

l_75_8 _ _ _ ~

Lie Level: IT] Difficulty: [D Taxon omy: ITJ Sourc e: J _

Safety Funct ion J 6 J Searc h J063000K402 J toCFR 55: J41.7 J System Numb er J 063 J KIA J K4.02 System

Title:

JD.C. Electrical Distribution System DI25 J OBJ J~~

Tier: [D Group : [JJ RO Imp: ~ SRO Imp: [}TI L. Plan: J A2LP -RO-E ing : -

feature(s) and/or interlock(s) which provide for the follow Descr iption : Knowledge ofD.C . Electrical System design Breaker interlocks, permissives, bypasses and cross-ties Quest ion:

Consider the following:

- Unit 2 is operating at l 00% power V bus

- DC control power has been lost to the 2A2 non-vital 4160 the breakers on 2A2?

Which of the following would describe the operation of possible by local manual A. Breakers would trip open and operation would only be means atic trip functions would not be B. Breakers would remain remotely operable but autom

• functional C. Breakers will remain in their "as is" condition and operat manual means D. Automatic breaker trips would remain functional but ion would only be possible by local remote operation of breakers would not be possible Answ er:

C. Correct Notes:

for remote breaker operations and perrnissives, C. Correct: 125 VDC power provides the motive power manual operations and automatic and breaker bypass interlocks. This would prevent any remote breaker cycles.

power A. Incorrect: Tripping breakers open requires 125 VDC remote operat ions withou t DC control power B. Incorrect: There are no D. Incorrect: For both reason s above Refere nces:

on 26, Section 6.2.2, page 63 STM 2.32-2 , High Voltage Electrical Distribution, Revisi Histor ical Comm ents:

NRC BANK QID # 1758 used on 2009 NRC Exam

• Form ES-401-5 Writt en Exam Quest ion Work sheet 57

21-Dec-13 Data for 2014 NRC RO/SRO Exam

• Bank: 11974 I Rev:

Lie Level: 0 Search lo64000K608 m Rev Date: 11018/2013 9:39:21 I QID #:

Difficulty: [}] Taxonomy: [!!] Source: ~I I 10CFRSS: 141.7 I 45.7 System

Title:

!Emergency Diesel Generator (ED/G) System 50 Author:

_ C M_o_d-ifi-1e_d_NR Safety Function I System Number I I 6 064 I

foster

_ _ Q_I_D_#_l_6_59_ __

_ B_A_NK I KIA I K6.08 Tier: 0 Group: [JJ RO Imp: []}] SRO Imp: cm L. Plan: I A2LP-RO-ED G I OBJ I11&12 1

Description:

Knowledge of the effect ofa loss or malfunction of the following will have on the ED/G System: - Fuel oil storage tanks Question:

Consider the following :

- Unit 2 is operating at 100% power

- #2 EDG monthly surveillance, OP-2104.036, supp. 2B, is in progress

- #2 EDG is currently tied to the grid and is consuming 2.4 gallons of fuel oil each minute

- #2 EDG fuel oil transfer pump (2P-16B) is running and filling #2 EDG fuel oil day tank (2T-30B)

- Annunciator 2K08 K-1, "Fuel System Trouble" comes into alarm

- The EDG watch reports 2Kl28 "Fuel X-Fer Pump Inoperable" is in alarm

- Both indicating lights are out on the local panel for 2P- I 6B

- #2 EDG fuel oil day tank (2T-30B) level is 480 gallons

- NO operator action is taken

• #2 EDG can continue to operate for _ _ _ _ minutes until the Tech Spec Minimum Day Tank Volume is reached.

A. 37 B. 75

c. 125 D. 200 Answer:

B. Correct Notes:

B. Correct: T.S. Minimum Day Tank Volume is 300 gallons. 480 - 300 gallons divided by 2.4 gpm is equal to 75 minutes A. Incorrect: number based on current level to the low level alarm value 391.3 gallons (480-391.3 =

88.7 gallons divided by 2.4gpm = 36.95 min, rounded up to 37 minutes)

C. Incorrect: based on T.S. min 300 gallons divided by 2.4 gpm = 125 min D. Incorrect: based on 480 gallons divided by 2.4 gpm = 200 minutes

References:

OP-2203.012H, Annunciator Corrective Actions 2K08 window K-1, Rev 037, page 12 of50 OP-2203 .012U, Annunciator Corrective Actions 2Kl28, Rev 020, page 25 of33

• T.S 3 .8.1.1 part b Historical Comments:

NRC BANK QID # 1659 used on 2009 NRC Exam. Question has been modified by changing which EDG (B vs. A), changed Form ES-401-5 Written Exam Question Worksheet 58

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• volume of day tank (from 500 gallons to 480 gallons), and changed fuel oil consumption rate (2.4 gpm vs. 2.2 gpm)

• Form ES-401-5 Written Exam Question Worksheet 59

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11975 I Rev: [ ] ] Rev Date: 112111/2013 2:33 :1 : QID #:

Lie Level: m Search !o39000A205 Difficulty: ~ Taxonomy: ~ Source: :

J tOCFR55: J41.5 I 43.5 I 45.3 I 45.I System

Title:

IMain and Reheat Steam System (MRSS) i 51 Safety Function I System Number I Author:

I NEW 4

039 I

I KIA [

foster A2.05 Tier: ITJ Group: OJ RO Imp: 1 3.3 : SRO Imp: : 3.6 i L. Plan: ~ A2LP-RO-ESPTA I OBJ '-I-~

Description:

Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Increasing steam demand, Question:

Consider the following:

- Unit 2 is at 20% power and rising after an outage

- 2CV-0402, "A" MSR Reheat Steam Low Load Valve (RSLLV), controller has been placed in Manual IA W OP-2106.009 Att. F to balance MSR temperatures When "A" RSLL V position is being adjusted , this _ _ _ __ be considered a reactivity manipulation because--- -- - -- - -- - - -- - - -- - -

A. would; MSR 2nd stage heating is supplied from main steam

• B. would; the change in MSR 2nd stage steam flow has significant impact on feedwater temperature C. would not; MSR 2nd stage heating is supplied from HP Turbine exhaust D. would not; the change in MSR 2nd stage steam flow has negligible impact on feedwater temperature Answer:

A. Correct Notes:

MSR 2nd stage heating is supplied from main steam system and opening the RSLL V will raise steam flow therefore raise reactor power (change reactivity)

References:

OP-2106.009, Turbine Generator Operations, Rev 071, Att. F step 4.0 page 86of143 STM 2-16, Reheat Steam, Rev 8 section 3 .3 .1.3 pages 5 and 6, simplified drawing page 17 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 58

Data for 2014 NRC RO/SRO Exam 20-Dec-13 Bank: 11976 J Rev: ; 0 I Rev Date: lt0/31 /2013 3:16:4 ; Q.- ID_ # :_ -'===

52==~-A_u_th_o_r_:_--====fo=s=te=r==~

• Lie Level: [ [ ] Difficulty: ~ 2 I Taxonomy:[![] Source: : NRC Bank QID # 1538

~~~~~-;:::====::;--~~~~

Search lo73000Kl01 I t0CFR55: J41.2to41.9 / 45.7to4 : Safety Function I 7 I System

Title:

JProcess Radiation Monitoring (PRM) System I System Number I 073 I KIA I Kl.01 Tier: ITJ Group: [JJ RO Imp: QI] SRO Imp: 1 3.9 I L. Plan: I A2LP-RO-RMON I OBJ I 9

Description:

Knowledge of the physical connections and/or cause-effect relationships between the PRM System and the following systems: - Those systems served by PRMs Question:

Consider the following:

- Unit 2 is operating at I 00% power

- Preparations are being made to release Boric Acid Condensate Storage Tank, 2T-69B In accordance with OP-2104.014, Supplement 1, Unit 2 Liquid Radwaste Release Permit, placing the selector switch for Process Liquid radiation monitoring instrument 2RJTS-2330 in would cause its meter output to exceed the dump permit high alarm setpoint and close the 2T-69B tank isolation valves, 2CV-2330A and /or 2CV-2330B.

A. HY (High Voltage)

B. PULSE CAL C. CHECK SOURCE D. LEVELCAL Answer:

B. Correct Notes:

The LRW/BMS Process Radiation Monitor, 2RJTS-2330, provides an automatic closure of2CV-2330A and/or 2CV-2330B.

This automatic feature occurs on a high alarm that is determined by the Unit 2 Liquid Radwaste Release Permit (OP-2104.014, Supp I). Going to PULSE Cal will raise the detector radiation output above the alarm setpoint causing the valves to go closed.

Testing of this interlock will prevent discharging liquid waste above the design limits.

References:

OP-2104.014, LR W and BMS Operations, Rev 054, supplement I section 7 .0 steps 7 .3 and 7.4 STM 2-62, Radiation Monitoring System, Rev 20, section 2.2.6.1 page 20 STM 2-52, Liquid Radwaste I Boron management System, Rev 17, simplified LRW/BMS drawing page 35 Historical Comments:

QID #1538 used on the 2008 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 59

Data for 2014 NRC RO/SRO Exam 21 -Dec-13

• Bank: j1977 I Rev: [ ] ] Rev Date: jl0/10/2013 9:27:3 I QID #:

Lie Level: 0 Search j076000A302 Difficulty: [D Taxonomy: CK]

I IOCFRSS: j41.7 I 45.5 System

Title:

jservice Water System (SWS)

Source: ~I_ _ _ __

53 Author:

_ _ _N Safety Function I

_ E_W 4 I I System Number I 076 I KIA I A3.02 foster Tier: [}] Group: [JJ RO Imp: ITIJ SRO Imp: [ID L. Plan: I A2LP-RO-ESPTA I OBJ I 11

Description:

jAbility to monitor automatic operation of the SWS, including: - Emergency heat loads Question:

Consider the following :

- Unit 2 has tripped from 100% power

- Annunciator 2K08 A-3 "Load Center 2B5 Undervolt" is in alarm

- ATC reports the lights above 2A301 , feeder to 2B5, are out

- All plant equipment operates as designed At the end ofSPTAs, #1 EDG _ _ _ _ _ be running and 2A3 _ _ _ _ _ be energized.

A. would; would B. would not; would

• C. would; would not D. would not; would not Answer:

D. Correct Notes:

The UV alarm on 2B5 will open the normal supply breaker (2A309) to 4160v vital bus 2A3 and give the #1 EDG a auto start command. When the EDG reaches near rated speed and voltage its output breaker will close powering the 4160V (2A3) bus.

During SPTAs, the CRS will direct securing the #1 EDG due to no cooling water being supplied (SW valve and EDG auxiliaries are powered from the 480v bus 2B5) to prevent overheating and damaging the #IEDG. 2A309 will remain open thus 2A3 will be de-energized. SPTAs do not address re-energizing 2A3 since the redundant safety bus (2A4) is energized. Restoring 2A3 will be directed when RTR is entered and implemented.

References:

OP-2203 .012H, Annunciator Corrective Actions, 2K08 window A-3 , Rev 037, page 25 of 50 OP-2202.001 , Standard Post Trip Actions EOP, Rev 014, step 4.G contingency colume, page 5 of 19 EOP-2202.001, Standard Post Trip Actions Tech Guide, Rev 014, step 4.F and 4.G, page 11 of 42 STM 2-32-2, High Voltage Electrical Distribution, Rev 26, section 5.4, page 51 STM 2-32-2, High Voltage Electrical Distribution, Rev 26, section 5.5.1 , page 52 STM 2-32-3, 480v Distribution System, Rev 15, section 2.2.2, page 10 Historical Comments:

Form ES-401-5 Written Exam Question Worksheet 60

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11978 I Rev:

Lie Level:

Search 10780002130 0

[QJ Rev Date: !11 / 13/20132:04:1 Difficulty: ~ Taxonomy: ~ Source: i~-------NE I toCFR55:

System

Title:

!Instrument Air System (IAS) 141.7 I 45.7 I QID #: 54 Safety Function I System Number I Author:

I 8

W-------~

078 I

I KIA I foster 2.1.30 Tier: [ [ ] Group: [JJ RO Imp: ~ SRO Imp: ~ L. Plan: I A2LP-AO-SWACW  ! OBJ I 16

Description:

!conduct of Operations -Ability to locate and operate components, including local controls.

Question:

Consider the following:

- Instrument Air is being isolated to 2CV-1460, Cooling Tower Basin Level Control Valve (Squeeze valve) for maintenance The Squeeze valve is located in the Auxiliary Building, 335' elevation, on the end.

To allow for local manual operation of the Squeeze valve, the handwheel would be rotated to A. south; engage the jacking sleeve with the valve stem and inserting a pin into the alignment hole B. north; engage the jacking sleeve with the valve stem and inserting a pin into the alignment hole

• C. south; align the disengaging lever with the keyway and rotate locking lever into the keyway D. north; align the disengaging lever with the keyway and rotate locking lever into the keyway Answer:

C. Correct Notes:

C. Correct: The squeeze valve is located on the 335' Auxiliary Building south end by the WCO work area. A handwheel is provided for manual operation but is normally disengaged. A "L" shaped lever is provided to engage or "lock" the handwheel to the valve stem for manual operations by pulling a pin out of the lever (hold it up and out of the way during normal operations) rotating the handwheel until the "slot" is aligned, then inserting the lever.

A. Incorrect: The method described to take manual control is used for manually controlling the Main Feed Reg Bypass Valves.

B. Incorrect: The squeeze valve is located on the 335' Auxiliary Building south end by the WCO work area. The method described to take manual control is used for manually controlling the Main Feed Reg Bypass Valves.

D. Incorrect: The squeeze valve is located on the 335' Auxiliary Building south end by the WCO work area.

References:

STM 2-42, Service Water & Auxiliary Cooling Water Systems, Rev 36, section 3.6. I 5.2, page 47, and simplified drawing, page 67 OP-2104.029, Service Water System Operations, Rev 095, Ehibit 2, section 2.0, page 186 of 314

_o_P_-2_2_0_3_.0_2_1_, _L_os_s_o_f_in_s_tr_um

__e_nt_ A

__ir_A_o_P_,_R_e_v_o_1_5_, _A_tt_ac_hm

__e_n_t _"A

__",_P_a_ge__l8__

of__

Io_8______________________ _______

• Historical Comments:

Form ES-401-5 Written Exam Question Worksheet 61

21-Dec-13 Data for 2014 NRC RO/S RO Exam

• Bank: 11979 1 Rev:

Lie Level:

Search !103000A101 m Rev Date: !1211012013 3:44:4 CK] Difficulty: [JJ Taxonomy:[} ]

I t0CFR SS:

System

Title:

!contain ment System 141.5 I 45.5

~~~~~~

~~~

I Source :

QID #:

~~~~~~

55 Safety Functio n I System Numbe r Author :

~~--=====-~~~______'.::========~

I ~~~~~~

I I

NEW 5

103 I

I KIA I foster

~~~~~~

Al.01 Tier: [I] Group: OJ RO Imp: [I2J SRO Imp: @] L. Plan: ~2LP-RO-ELOCAES tj OBJ I~~

(to prevent exceeding design limits) associated with Descrip tion: Ability to predict and/or monitor changes in parameters pressure, temperature, and humidity operating the Containment System controls including: - Containment Questio n:

Consider the following:

- Unit 2 has tripped due to a large break LOCA e, temperature and humidity, a MINIM UM Containment To prevent exceeding Containment Building design limits for pressur gpm post RAS.

Spray header flow of gpm is required prior to the Recirc Actuation Signal (RAS) and A. 1650; 2200 B. 1875; 2000 C. 2200; 1650 D. 2000; 1875 Answer :

B. Correct Notes:

are lower due to the spray pump recirc flowpath is Minimum spray flow [flow to the containment] pre RAS requirements g a higher pump tlowrate to accommodate the loss of aligned to the RWT. Post RAS, the recirc tlowpath is isolated , requirin the recirc flow.

Referen ces:

8 contiengency 18.E. page 8 of67 and section 3 step OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 1step1 22.C 1 step 18 page 32of14 0 and section 3 step 22.C EOP-2202.003 , Loss of Coolant Accident Tech Guide, Rev 014, section 10 AN0-2 EOP Setpoint Bases Document, Rev 13, Attachment 1 page Histori cal Comme nts:

• Form ES-401-5 Written Exam Questio n Works heet 65

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: J1980 ! Rev: ~ Rev Date: 111120/2013 1:09:5 1 QID #: I 56 Author: foster Lie Level: 0 Difficulty: ((] Taxonomy:[E l Source: I Modified ANO Bank QlD# ANO-OPS2-7851 Search 10020002411 i 10CFR55: J41.10 / 43 .5 / 45 .13 :=J Safety Function 2 I System

Title:

JReactor Coolant System (RCS)  ! System Number I 002 I KIA I 2.4.11 Tier: [ ] ] Group: [ ] ] RO Imp: [IQ] SRO Imp: @= L. Plan: I A2LP-RO-RCP I OBJ I 8

Description:

!Emergency Procedures/Plan - Knowledge of abnormal condition procedures.

Question:

In accordance with OP-2203 .025, RCP Emergencies AOP, which one of the following set of conditions for a single Reactor Coolant Pump (RCP) would require an immediate reactor trip and securing the affected RCP?

A. Failure of the lower and upper seals B. RCP motor vibrations 21 mils and rising C. RCP upper thrust bearing 200°F D. RCP controlled bleedoffflow 3.5 gpm and rising Answer:

B Correct

• Notes:

Attachment "D" requirements

References:

OP-2203 .025, RCP Emergencies AOP, Rev 015, Attachment D page 28 of30 Historical Comments:

Modified ANO Bank QID# ANO-OPS2-7851 not used on any previous NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 63

Data for 2014 NRC RO/SRO Exam 20-Dec-13 Bank: ~ Rev: [I] Rev Date: i12/16/2013 1: 11 :3 I QID #: 57 Author: foster

• Lie Level: 0 Difficulty: CI] Taxonomy: [ I J Source: I NEW Search lol 1000K202 I 10cFR55: j4 l. 7 I Safety Function I 2 I System

Title:

!Pressurizer Level Control System (PZR LCS) I System Number I 011 I KIA I K2 .02 Tier: [}] Group: [}] RO Imp: [IO SRO Imp: @] L. Plan: I A2LP-RO-RCS I OBJ I 10&12

Description:

!Knowledge of bus power supplies to the following: - PZR heaters Question:

Pressurizer proportional heaters are powered from _ _ __ _ _ _ _ _ _ and the Pressurizer backup heaters are powered from. _ __ _ _ _ _ __ _ _ _ __ _~

A. Non-Vital buses 289/ IO; Vital Buses 2B5/6 B. Non-Vital buses 289/ 10; Non-Vital buses 2B9/ 10 C. Vital Buses 2B5/6; Non-Vital buses 289/10 D. Vital Buses 285/6; Vital Buses 285/6 Answer:

C. Correct

• Notes:

The PZR Proportional are required by Tech Spec and are vital powered (2B5 and 6). The backup heaters are not Tech Spec related and are powered from non vital load centers (289 and 10)

References:

STM 2-03, Reactor Coolant System, Rev 22, section 2.2.2 pages 13 and 14 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 64

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: J1982 ; Rev: ~ Rev Date: 111129/2013 11:34: I QID #: 58 Author: foster Lie Level: IT] Difficulty: I 2 I Taxonomy: C[J Source: I ANO Bank QID# ANO-OPS2-378 Search J015000K519 J toCFR55: ~45.7 =1 Safety Function 7 System

Title:

JNuclear Instrumentation System J System Number 015 J KIA J K5 .19 Tier: OJ Group: [IJ RO Imp: L3:IJ SRO Imp: [ID L. Plan: J A2LP-RO-COLSS I OBJ J 16

Description:

JKnowledge of the operational implications of the following concepts as they apply to the NIS : - Heat balance Question:

Consider the following:

- Unit 2 is operating at 100% power During an NI calibration, which of the following inputs in the secondary heat balance, ifrecorded lower than actual value, would cause indicated power to read higher than actual power?

A. RCS hot leg temperature B. Feedwater temperature C. Feedwater flow D. Steam flow Answer:

B. Correct Notes:

Based on basic heat balance equation

References:

General Physics Corporation, Rev 4, chapter 4, Thermodynamis processes, page 12 of70 Historical Comments:

ANO Bank QID# ANO-OPS2-378 not used on any previous NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 65

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11983 I Rev: ~ Rev Date: 111 /29/2013 11 :27:

Lie Level: ITJ Difficulty: ((_, Taxonomy:[ ] ] Source: '.

Search loI6000K302 I tOCFR55: 141.7 I 45.6 System

Title:

!Non-Nuclear Instrumentation System (NNIS)

J QID #: 59 Safety Function I System Number I Author:

ANO Bank QID #ANO-OpsUnit2-l 121 I I 7 016 I

I KIA I foster K3.02 Tier: [JJ Group: [JJ RO Imp: ~ SRO Imp: ~ L. Plan: : A2LP-RO-PRZ I OBJ 13&10 I

Description:

!Knowledge of the effect that a loss or malfunction of the NNIS will have on the following: - PZR LCS Question:

Consider the following :

- Unit 2 is operating at 100% power

-Annunciator 2KIO F-7 "Level CH 1 LO/LO" is in alarm

- Channel 1 Pressurizer Level, 2LI-4627- l , is reading 0 %

- Channel 2 Pressurizer Level, 2Ll-4627-2, is reading 60%

- Pressurizer Level Control Channel Selector switch, 2HS-4626, is selected to the "A" position

- Low Level Cutoff switch, 2HS-4624, is selected to the "A/B" position

- NO operator actions are taken The Pressurizer Backup Heater breakers would be _ _ _ _ and Letdown flow controller output would go to _ _ __ _

A. open; maximum B. open; minimum C. closed; maximum D. closed; mimmum Answer:

B. Correct Notes:

With the Level Channel Select switch selected to "AIB" , either Pzr Level indicating <29% will deenergize all of the pressurizer heaters by opening their breakers and Letdown.would go to minimum flow (band is 26 to 32 gpm)

References:

OP-2203 .0121, Annunciator Corrective Actions, 2K10 window F-7, Rev 039, page 80 of84 OP-2103 .005, Pressurizer Operations, Rev 033 , section 6.0 page7 and 8 of37 STM 2-03-01, Pressurizer Pressure and Level Control, Rev 16, section3.2.1page16, section 3.2.2 pages 16 and 17, section 3.2.3 pages 17 and 18, section 3.2.6 pages 18 and 19, section 3.2.7 pages 19 and 20, section 3.2.7. l page 20 Historical Comments:

ANO Bank QID #ANO-OpsUnit2-11211 not used on any previous NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 66

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11984 I Rev: [ } ] Rev Date: 110/9/2013 2:45 :55 ; QID #:

Lie Level: CK] Difficulty: ((} Taxonomy: [EJ Search lo28000A203 Source: I System

Title:

!Hydrogen Recombiner and Purge Control Syste I System Number I 60 Author:

• NRC BANK QID # 1487 I 10cFR55: 141.5 I 43.5 I 45.3 I 45.1 1 Safety Function I 5 028 I

foster I KIA I A2.03 Tier: [ } ] Group: [ } ] RO Imp: ~ SRO Imp: @] L. Plan: I A2LP-RO-CONH2 I OBJ I 2&4

Description:

Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - The hydrogen air concentration I excessof limit flame propagation or detonation with resulting equipment damage in containment Question:

The Hydrogen analyzers are placed in service within minutes of the beginning of an accident to ensure a representative sample is obtained. A VIOLENT reaction inside the containment building is likely to occur if hydrogen concentration reaches A. 70; 4 B. 70; 18 C. 90; 4 D. 90; 18

• Answer:

B. Correct Notes:

The Hydrogen analyzers have a 20 minute transport time from when started to when an representative air stream is being sampled. Actions in the EOPs (LOCA, ESD, Functional Recovery) required the start of the analyzers within 70 minutes for this reason. 4% hydrogen concentration is right at the flammability limit inside containment. At 18% hydrogen concentration a detonation would occur.

References:

STM-2-06, Containment Combustible Gas Control System, Rev 12, section 1.5 pages 5 and 6 and section 4.2 page 24 Historical Comments:

NRC BANK QID # 1487 not used on any previous NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 67

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Lie Level: m Bank: 11985 1Rev:

Search lo29000K403 System

Title:

I~C-o-

[2J Rev Date: 110/9/2013 1:54:35 1 QID #:

Difficulty: [}] Taxonomy :((] Source: -

nt_a_

I 10cFR55: 1~4_1.7_ __

_e_

inm tP n_

_ _~

- ge- Sy-s-te-m- (C_P_S_)_ _ __ _

- ur 1 --

61 Safety Function I System Number Author:

_C M- o-d-ifi-1e_d_N_R I

I 8 029

_ B_A_NK Q I

D

_I_ _#

I KIA I

_l_

foster 54_ 6_ __

K4.03 Tier: OJ Group: OJ RO Imp: [ITI SRO Imp: []}] L. Plan: I A2LP-RO-C VENT I OBJ I 13

Description:

Knowledge of Containment Purge System design feature(s) and/or interlock(s) which provide for the following: - Automatic purge isolation Question:

Consider the following:

- Unit 2 is in Mode 6

- Refueling is in progress

- Containment Building Purge System is in service

- An inadvertent CIAS has occurred What is the status of the Containment Building Purge System?

A. Only two purge isolation valves close; supply fan tripped due to HIGH pressure in the supply duct; exhaust fan tripped I 0 seconds later B. Only two purge isolation valves close; exhaust fan tripped due to LOW pressure in the exhaust duct; supply fan tripped 10 seconds later C. All six purge isolation valves close; supply fan tripped due to HIGH pressure in the supply duct; exhaust fan tripped 10 seconds later D. All six purge isolation valves close; exhaust fan tripped due to LOW pressure in the exhaust duct; supply fan tripped I 0 seconds later Answer:

D. Correct Notes:

If an SIAS or a CIAS is received, all six purge isolation valves automatically close compared to only 2 isolation valves on a high radiation signal. When this happens, the exhaust fan draws down the pressure in the exhaust duct to less than -5.0 inches water gauge tripping the exhaust fan. Ten seconds later the supply fan trips.

References:

STM 2-09, Containment Cooling and purge Systems, Rev 16, section 7.8 pages 41 and 42 simplified drawing page Historical Comments:

Modified NRC BANK QID #1546 used on 2008 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 71

Data for 2014 NRC RO/SRO Exam 20-Dec-13 m

• Bank: 11986 I Rev: Rev Date: 112/ 11 /20139:35:4 1 QID#: 62 Author: foster Lie Level: IT] Difficulty: ~ Taxonomy: T Source: j~-------NE --W-------~

Search lo34000A401 I 10cFR55: ,41.7 I 45.5 to 45.8 Safety Function I 8 J System

Title:

l~F-ue_l_H d_

_a_n_ ng li- _ q-E_ p_

ui_ te_m_

nt_S_y_s-m_e- _S_)_ _~; System Number J (F_HE 034 I KIA I A4.0l

[D Group: I ~ SRO Imp: [}2=

1 Tier: 2 RO Imp: L. Plan: I A2LP-RO-RMON I OBJ I 7

Description:

JAbility to manually operate and/or monitor in the control room: - Radiation levels Question:

The Spent Fuel Pool Area Radiation monitors are type detectors and are verified Operable prior to commencing fuel movement in the SFP area from control room panel _ _ __ _

A. Geiger-Mueller; 2C14 B. Geiger-Mueller; 2C25 C. scintillation; 2C 14 D. scintillation; 2C25 Answer:

B. Correct

• Notes:

Area radiation detectors utilize Geiger-Mueller tubes for sensitivity and the operator interface (meter read out) is located behind the back panels in the control room (2C25)

References:

OP-2105.016, Radiation Monitoring and Evacuation System, Rev 029, section 3.0 page 2 of 36 STM 2-07, Spent Fuel Systems, Rev 22, section 2.1.5 page 7 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 69

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: 11987 1Rev:

Lie Level:

Search lo41000A301 ITJ Rev Date: 111/19/2013 3:38:1 ITJ Difficulty: [I] Taxonomy:[£] Source: I I toCFRSS: 141.7 I 45.5 I QID #: 63 Safety Function System

Title:

!steam Dump System (SDS) and Turbine Bypass I System Number I Author:

I NEW 4

041 I

foster I KIA I A3.0l Tier: [IJ Group: [IJ RO Imp: @] SRO Imp: o:IJ L. Plan: I A2LP-RO-SDBCS I OBJ I 20

Description:

jAbility to monitor automatic operation of the SDS, including: - RCS T-ave. meter (cooldown rate)

Question:

Consider the following:

- Unit 2 has tripped due to a loss of condenser vacuum

- A consistent 55°F/hour cooldown has been established over the last hour on the DOWNSTREAM atmosphere dump valves with SDBCS in automatic

- Annunciator 2Kl2 A-8 "IA Pressure HI/LO" comes into alarm

- Instrument Air header pressure is reading 0 psig

- NO operator actions are taken The RCS Cooldown ~~~~~

be exceeded due to ~~~~~~~~~~~~~~

A. would; the downstream atmosphere dump valves failing open

• B. would; the upstream atmosphere dump valves failing open C. would not; the downstream atmosphere dump valves failing closed D. would not; the upstream atmosphere dump valves failing closed Answer:

C. Correct Notes:

The downstream atmosphere dump valves fail closed on a loss of Instrument Air stopping the cooldown and the upstream atmosphere dump valves do fail open on a loss oflnstrument Air but are normally manually isolated from the Main Steam header, therefore would not affect the RCS

References:

Tech Spec 3.4.9, Pressure/Temperature Limits STM 2-23 , Steam Dump & Bypass Control System, Rev 16, section 1.2 pages 1 and 2 , section 1.2.2 pages 4 and 5, section 4.0 page 31 OP-2203.021 , Loss of instrument Air AOP, Rev 015, Attachment "A", page 18of108 OP-2203 .012L, Annunciator Corrective Actions, 2Kl2 window A-8, Rev 036, page 85of116 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 70

20-Dec-13 Data for 2014 NRC RO/SRO Exam

• Bank: jl988 j Rev: [I] Rev Date: !11119/20 1311:31 : I QID#: 64 Author: foster Lie Level: ((] Difficulty: ~ Taxonomy: ~ Source: i NEW I 45.7 to 4 : Safety Function I 4 I Search i045000K l06 1 10CFR55 : !41.2 to 41.9 System

Title:

jMain Turbine Generator (MT/G) System  ! System Number I 045 I KIA I Kl.06

-TURBC I OBJ I 32 Tier: I 2 Group: 2 ! RO Imp: ~ SRO Imp: I 2.6 I L. Plan: A2LP-RO i

1 J System and the Descripti on: Knowledge of the physical connections and/or cause-effect relationships between the MT/G following systems: - RCS, during steam valve test Question :

Consider the following :

- Unit 2 is operating at 97% power

- OP-2106.009, Supplement 3, Turbine Generator Valve Stroke Test surveillance is in progress Turbine Stop Intercept valves closed During the Turbine Generator Valve Stroke testing, when stroking the Low Pressure (LP) effect on RCS parameter s and when stroking the High Pressure (HP) Turbine one at a time, the ATC would see a see a effect on RCS parameter s.

Control Valves closed one at a time, the ATC would A. small; small B . small; large C. large; small D. large; large Answer:

B. Correct Notes:

is conservatively lowered to <99% as Base on actual plant data. MTG Stroke Valve Test performed 11115/2013. Reactor power Stage Feedback is placed in service for the Control Valve stroke test. As one part of the initial condition of supplement 3. First ts, RCS parameters will "swing" as CV goes closed, the other CVs will reposition (open) to compensate. During valve movemen As the Combined Stop/Intercept steam flow changes (due to the time for the CV s to stroke closed and adjust for the closure).

Stop/Intercept valves and steam valves are stroked, there is much less affect on the RCS due to the stroke time of the Combined on the RCS during the Combined flow is not being interrupted to the LP turbine. Therefore, there is a much smaller effect Stop/Intercept valve stroke test than the Control Valves Stroke test.

Referenc es:

PDS (Plant Data System) Data from 11/ 15/2013 Unit 2 Station Log for 11/15/2013 116, and 119of14 3 OP-2106.009, Turbine Generator Operations, Rev 071 , Supplement 3 pages 110, 112, 115, Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 72

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• [I]

Bank: 11989 I Rev: Rev Date: 111 /29/2013 8:53:4 I QID #: 65 Author: foster Lie Level: CIJ Difficulty: ~ Taxonomy: Q J Source: : NEW Search lo86000A405 i 10CFR55: 141.7 I 45.5 to 45.8 ~ Safety Function I 8 i System

Title:

!Fire Protection System (FPS) System Number I 086 I KIA I A4.05 Tier: [D Group: ~ RO Imp: [}I] SRO Imp: ~ L. Plan: ~ A2LP-RO-FPROT I OBJ I~-~

Description:

!Ability to manually operate and/or monitor in the control room: - Deluge valves Question:

The #1 EDG room is protected by a Firewater _ _ _ _ _ _ Sprinkler System which _ _ ___ be remotely actuated from Fire Protection Panel 2C343.

A. Preaction; can B. Preaction; can not C. Deluge; can D. Deluge; can not Answer:

A. Correct

• Notes:

The #1 EDG room is supplied by a Preaction Sprinkler valve triggered by smoke and flame detectors and the Control room does has the ability to manually actuate the Preaction Sprinkler valve from the Fire Protection Panel 2C343.

References:

STM 2-60, Fire Protection System, Rev 012, section 8.0 page 18, and Table 3 page 27 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 73

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11990 I Rev: [I] Rev Date: !11 / 19/2013 1:37:4 1 QID #: 66 Author: foster Lie Level: =:I::] Difficulty: [)) Taxonomy: =:IJ Source: I NEW Search 11940012105  ! t0CFR55: 141.10 I 43.5 I 45.12 1 Safety Function System

Title:

!Generic J System Number !GENERIC ! KIA I 2.1.5 Tier: OJ Group: ~ RO Imp: ~ SRO Imp: ~ L. Plan: A2LP-RO-TS ____, OBJ j 12

Description:

Conduct of Operations -Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Question:

[REFERENCE PROVIDED]

Consider the following:

- Unit 1 and Unit 2 are operating at I 00% power

- Shift turnover has been completed

- The following individuals on Unit I have signed into eSOMs as watchstanders:

- Shift Manager

- Shift Technical Advisor

- Control Room Supervisor

- 2 Control board Operators

- 2 Auxiliary Operators (Fire Brigade Members)

- I Waste Control Operator (Fire Brigade Leader)

- 2 Communicators

- The following individuals on Unit 2 have signed into eSOMs as watchstanders:

- Shift Manager

- Shift Technical Advisor

- Control Room Supervisor

- 2 Control board Operators

- 2 Auxiliary Operators (Fire Brigade Members)

- I Waste Control Operator (Fire Brigade Leader)

- Alternate Shutdown Operator The MINIMUM shift complement _ __ met for Unit I and the MINIMUM shift complement _ __ met for Unit 2.

A. is; is B. is; is not C. is not; is D. is not; is not Answer:

A. Correct Notes:

• Conduct of Operations, Attachment 9.1 , note 5 allows the required communicators to be either unit specific or both from the same unit.

Form ES-401-5 Written Exam Question Worksheet 74

Data for 2014 NRC RO/SRO Exam 20-Dec-13

References:

EN-OP-115, Conduct of Operations, Rev 014, Attachment 9.1 page I of 1 [PROVIDED to STUDENT]

Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 75

Data for 2014 NRC RO/SRO Exam 20-Dec-13 m

• Bank: [IEO Rev: Rev Date: 111 12012013 2:23: I Lie Level: ~ Difficulty: ITJ Taxonomy:[}J Source:

Search 11940012119 System

Title:

!Generic

! 10CFR55: 141.10 / 45.12 I QID #:

I 67 SafetyFunction I System Number Author:

NEW

!GENERIC ! KIA i foster 2.1.19 Tier: =:I] Group: [ [ ] RO Imp: J}] SRO Imp: ~ L. Plan: ; A2LP-RO-SPDS I OBJ I 5

Description:

conduct of Operations - Ability to use plant computers to evaluate system or component status.

Question:

Consider the following:

- Unit 2 has tripped from 100% power

- Annunciator 2K04 G-9 "MSSV Valve Open" is in alarm The CRS would direct the CBOT to determine which Main Steam Safety Valve is open by using the _ _ _ _ __ _ _

screen on the - - - - - -

A. Inadequate Core Cooling (ICC); Safety Parameters Display System (SPDS)

B. Primary to Secondary Heat Transfer (PSHT); Safety Parameters Display System (SPDS)

C. Inadequate Core Cooling (ICC); Plant Monitoring System (PMS)

D. Main Steam mimic; Plant Monitoring System (PMS)

Answer:

A. Correct Notes:

A. Correct: ICC on SPDS mimics the RCS and Secondary system to the MSIVs and the MSSVs will change colors to show if open or not B. Incorrect: does not have MSSV status C. Incorrect: ICC on PMS mimics the RCS and Secondary system to the MSlVs (similar to SPDS) but the MSSVs do not change colors D. Incorrect: does not have MSSV status

References:

STM 2-76, Safety Parameter Display System (Common Unit), Rev 11 , section 2.3 .7 page 22 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 76

21-Dec-13 Dat a for 2014 NRC RO /SR O Exam foster Bank : 11992 I Rev: ITJ Rev Date : 111 / 19/2013 9:57:2 I QID #: 68 Auth or:

Lie Level: m Diffi culty : [}] Taxo nomy : [][] Sourc e: I NRC Bank QID #177 6 Safet y Func tion Searc h 11940012144 I tOCF R55: 141.10 I 43 .6 I 45.6 I Syste m Num ber IGEN ERIC j KIA I 2.1.44 Syste m

Title:

!Generic I OBJ 4

[JJ Group: [JJ RO Imp: [}I] SRO Imp: [}T I L. Plan: I A2LP -RO- SDC I Tier:

ing, such as responding of RO duties in the control room during fuel handl Desc riptio n: Cond uct of Operations - Knowledge ty, system s operated from the tion with the fuel storage facili to alarms from the fuel handling area, communica tion.

and supporting instrumenta control room in suppo rt of fueling operations, Ques tion:

Consider the following:

- Unit 2 is in Mode 6

- "A" SDC Train is in operation

- Fuel handling is in progress closure

- An event has occurred requiring Containment nt Evacuation alarm from Containment building by actuating the Containme The Control Room would alert personnel in the n _ _ minutes.

control panel and Containment closure is required to be set withi A. 2Cl4 ; 30 B. 2Cl4 ; 60 C. 2C22; 30 D. 2C22; 60 Answ er:

C. Correct Notes:

OP- I 015. 008, Attachment F, by a handswitch on control panel 2C22 and per The Containment Evacuation alarm is actuated n 30 minutes Containment closure is required to be set withi Refer ences :

ngency G page 15 of 18 Rev 016, step 4 page 3 of 18 and step 21 conti OP-2203.029, Loss of Shutdown Cooling AOP, 18 of 19 Guide, Rev 016, step 21 page AOP-2203 .029, Loss of Shutdown Cooli ng Tech tiona l Reco very EOP, Rev 011 step 3.A page 3 of 46 OP-2202.011, Lower Mode Func Tech guide, Rev 010 step 3 page 9 of38 4 EOP-2202.011, Lower Mode Functional Recovery hment F pages 65 and 66of 102 OP-1015.008, Unit 2 SDC Control, Rev 044, Attac Attachment 32 step 5 .F page 106 of 204 OP-2202.0 I 0, Standard Attachments, Rev 022, Histo rical Com ment s:

NRC Bank QID #0496 used on 2005 NRC Exam NRC Bank QID # 1776 used on 2011 NRC Exam Writ ten Exam Ques tion Work sheet 76 Form ES-401-5

Data for 2014 NRC RO/SRO Exam 20-Dec-13

- Bank: 11993 ; Rev: ~ Rev Date: ) 1115/2013 12:06: I QID #: -'==6=9=:'._l_ A_ut_h_o_r:_---'===fi=os=te=r=~

• Lie Level: ITJ Difficulty: [)) Taxonomy: L}J Source: i NRC Bank QID #40 Search 11940012206 I 10CFRSS: 141.10 / 43.3 / 45 .13 I Safety Function System

Title:

!Generic J System Number !GENERIC ! KIA J 2.2.6 Tier: [JJ Group: OJ RO Imp: [IQ] SRO Imp: [}I] L. Plan: : ASLP-RO-PRCON I OBJ '--_ j ___,

Description:

[Equipment Control - Knowledge of the process for making changes to procedures.

Question:

Which one ( 1) of the following is NOT an example of a procedure INTENT change?

A. Minor alterations to the purpose for clarification B. Reducing the margin to nuclear safety C. Deleting a portion of the acceptance criteria D. Changing the Scope of the procedure Answer:

A. Correct Notes:

OP-1000.006 step 4.9.1 minor changes to the purpose section ofa procedure is permitted as long as it does not allow the procedure to accomplish a function it was not intended for. B, C, and D are Incorrect, per the procedure, all are definitions of an INTENT change

References:

OP- I 000.006, Procedure Control, Rev 065, step 4.9 Historical Comments:

NRC Bank QID #40 used on 1998 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 79

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: !1994 I Rev: [2:J Rev Date: !11 /1 4/2013 2:34:4 1 QID #: 70 Author: foster Lie Level: ~ Difficulty: ~ Taxonomy:[ l ] Source:  ! NEW Search 11940012207  ; 10CFR55: 141.10 I 43 .3 I 45 .13 Safety Function System

Title:

Joeneric ] System Number !GENERIC ! KIA ~I_2_.2_.7_~

. r-:;-1 ,----, ~ ~ I I Tier: L2_J Group: ~ RO Imp: ~ SRO Imp: L2i__j L. Plan: I ASLP-RO-PRCON , OBJ 16

Description:

!Equipment Control - Knowledge of the process for conducting special or infrequent tests.

Question:

You have been assigned a task that has been classified as an IPTE (Infrequently Performed Tests or Evolutions).

JAW EN-OP-116, lnfrequently Performed Tests or Evolutions procedure, during an IPTE brief, ALL of the items on the IPTE Pre Job Checklist (i.e. Tech. Specs., TRM, ODCM, Fire Protection, FME, etc .. .) are required to be discussed _ __ _ _ _

they are applicable to the evolution. Likewise, an IPTE Post Job Brief Checklist required to be performed for ALL infrequently performed tasks and evolutions.

A. only if; is B. whether or not; is C. only if; is not

• D. whether or not; is not Answer:

A. Correct Notes:

As described in procedure which makes B, C, and D incorrect.

References:

EN-OP-116, Infrequently Preformed Tests or Evolutions, Rev 012, section 5.3, page 16 of35 and section 5.2.5, page 14 of35 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 80

Data for 2014 NRC RO/SRO Exam 20-Dec-13 Bank: ~t-9?? Rev: ~-0  : Rev Date: '}i"i7i2~1}) !=~?:5- ! QID #: L~- 7j .-~.l Author:

( foster

'-~ Lie Level: : R ; Difficulty: , 2 Taxonomy: . H ' Source: ~** --- . Modified NRC Bank QID #0587 - ----i

- . ..... .. ~* --* ,,} *--*----- ....... --...-........... *- . *-* -**------'

Search

• 19400 1~~~~- __i IOCFR5S: 41_.7 I ~i)o.'/4_~:2*~~i~ Safety Function L.. **-*** -*-*;

System

Title:

iGeneric System Number ~~N.E_~IC,~ KIA ,~:__2;?A_2 :. ;

Tier: L. ~--Group: '. . .. RO Imp: 3.9 SRO Imp: :. 4~~ , L. Plan: _:~ ~~~~R.~~P.C -~ OBJ ~- ~--

Description:

Equipment Control - Ability to recogni~ system p~et;,;*th~t*;;~ntry-l~vel ~~~-ditl~~s f~;Teem;~-:

Specifications. .. ... _ _ _ . *- __ _ __ _

• Question:

Consider the following:

- Unit 2 is in Mode 6

- RCS level is 90"

- Reactor Vessel Head Installation is in progress

- "B" SOC train is in service with "B" LPSI pump thru the "B" SOC heat exchanger

- "A" SOC train is in standby

- "B" Service Water pump, 2P-4B, is OOS for maintenance

- Annunciator 2K06 B-5 "2P4A Breaker Trip" comes into alarm

- OAO reports burnt odor from the 2P-4A motor The Technical Specification for required Shutdown Cooling loops in Mode 6 met based on RCS inventory being

- - -- -- - - - - - 23 feet above the active fuel region in the core and _ __ Operable SOC loop(s) is(are) available.

A. is not; greater than; only one B. is; greater than; two C. is not; less than; only one D. is; less than; two Answer:

C. Correct Notes:

C. Correct: based on T.S. 3.9.8.2 A. Incorrect: The T.S. is not being met, RCS level is less than 23 feet above the active fuel region not greater than B. Incorrect: The T.S. is not being met, RCS level is less than 23 feet above the active fuel region not greater than, and two SDC loops is required D. Incorrect: The T.S. is not being met, RCS level is less than 23 feet above the active fuel region which requires two SDC loops

References:

OP-2203.012F, Annunciator Corrective Actions, 2K06 window B-5, Rev 037, page 38 of79

..- Tech Spec 3.9.8.2 action a, Shutdown Cooling-Two loops OP-I 015.008, Unit 2 SOC Control, Rev 043, Attachment B general description, page I of 13 and section 1.0 step 1.7 page 2 of 13 Form ES-401-5 Written Exam Question Worksheet 81

Data for 2014 NRC RO/SRO Exam 20-Dec-/3 Historical Comments:

NRC Bank QID #0587 used on the 2006 NRC Exam

(

Form ES-401-5 Written Exam Question Worksheet 82

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: 11996 1 Rev: [}] Rev Date: j11/13/2013 3:00:0 I QID #: ~7_2~1 Author: foster Lie Level: IT] Difficulty: =:I] Taxonomy:[ [ ] Source: ~,_ _ _ _ _N_R _ Q_I_D_#_l_6_8_1_ __ _

_ B_a_nk

_C ~

Search 11940012311  ! tOCFR55: 141.11 / 43.4 / 45.10 Safety Function System

Title:

!Generic I System Number !GENERIC ! KIA I 2.3 .11 Tier: OJ Group: LIJ RO Imp: IT!] SRO Imp: ~ L. Plan: i A2LP-RO-APSEC I OBJ I 5&9 :

Description:

!Radiological Controls - Ability to control radiation releases.

Question:

Consider the following:

- Unit 2 has tripped from I 00% power

- A 20 gpm tube leak in "B" Steam Generator occurs upon the trip

- OP-2203.038, Primary to Secondary Leakage AOP, is being implemented

- The CRS has directed the IAO to perform OP-2202.010, Standard Attachment 19, Control of Secondary Contamination To prevent an inadvertent radiological release, OP-2202.0 I 0, Standard Attachment I 9, Control of Secondary Contamination, would direct ---------------~

A. aligning Steam Generator Slowdown to the SU/BO Dls

• B. starting all available Auxiliary Building Exhaust fans (2VEF-8s)

C. securing the turbine building sumps to the Unit I Oily Water Separator D. isolating the discharge tlowpath from the Unit I Oily Water Separator to the lake Answer:

C Correct Notes:

Att. I 9 directs securing the Turbine building sump pumps to prevent an inadvertent release and to monitor a release through this tlowpath

References:

OP-2203.038, Primary to Secondary Leakage AOP, Rev 014, step 7 page 4 of32 EOP-2203.038, Primary to Secondary Leakage Tech guide, Rev 014, step 7 page 10 of33 OP-2202.0 I 0, Standard Attachments, Rev 022, Attachment I 9 pages 61 thru 64 of204 Historical Comments:

NRC Bank QID # 1681 used on the 2009 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 83

20-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 11997 I Rev: [}] Rev Date: !1211012013 3:06:0 I QID #: 73 Author: foster Lie Level: CK] Difficulty: =:IJ Taxonomy:[ [ ] Source: I Modified NRC Bank QID # 1782 Search iI 940012313  : 10CFR55 : ;4u2 I 43.4 I 45 .9 I 45 . j Safety Function I r-'=====::::.,

System

Title:

!Generic  ; System Number !GENERIC ! KIA I 2.3.13 Tier: IT] Group: [JJ RO Imp: ~ SRO Imp: ~ L. Plan: ! ASLP-RO-RADP I OBJ I 7 to licensed operator duties, such Descripti on: Radiological Controls - Knowledge ofradiolo gical safety procedures pertaining as response to radiation monitor alarms, containment entry requireme nts, fuel handling responsibilities, access to locked high-radiation areas, aligning filters , etc.

Question :

Consider the following :

- Unit 2 is in Mode 6

- "A" SDC train is in service

- RCS cleanup is in progress following Hydrogen peroxide addition

- General area dose rate in the "A" ESF pump Room is 700 mr/hour

- The WCO is investigating a noise in the room and calls for assistance

- The CRS has sent the CBOT into the Auxiliary Building to help the WCO posting for this area, Radiation The "A" ESF pump room would be posted as a _ _ _ __ _ __ Area and, due to the Protection (RP) Personnel CONTINUOUS coverage required for the CBOT .

• A. High Radiation Area; is B. High Radiation Area; is not C. Locked High Radiation Area; is D. Locked High Radiation Area; is not Answer:

B. Correct Notes:

A High Radiation area has a dose rate The room should be posted as a High Radiation Area due to the dose rate is <1000 mrem.

> I 00 to < I rem. Access to a High Radiation area does not required continuous RP coverage Referenc es:

Tech Spec 6.7.1, Administration Controls EN-RP-100, Radiation Worker Expectations, Rev 8, section 5.3 [18] page 12 of38 and [ 17] page 8 of 43 EN-RP-10 I, Access Control for Radiologically Controlled Areas, Rev 8, section 3 .0 [ 16]

Historica l Commen ts:

NRC Bank QID # 1782 used on 2011 NRC Exam

• Form ES-401-5 Written Exam Question Workshe et 84

20-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 11998 \ Rev: ITJ Rev Date: !12/ 19/2013 3:13 :0 \ QID #: 74 Author: foster Lie Level: ~ Difficulty: ((} Taxonom y:[ [ ] Source: I Modified ANO Bank QID #ANO-OPS2-13018 Search \1940012405 1

toCFRSS : j41.IO I 43 .5 I 45 .13 Safety Function  ! \

System

Title:

\Generic  ! System Number IGENERIC I KIA I 2.4.5 Tier: [JJ Group: ~ RO Imp: IT2J SRO Imp: ~ L. Plan: I A2LP-RO-ESPTA  ! OBJ  ! 3 procedures network for normal, Descripti on: Emergency Procedures/Plan - Knowledge of the organization of the operating abnormal , and emergency evolution s.

Question :

give direction to "GO TO" another Abnormal operating procedures (AOPs), and Emergency operating procedures (EOPs) will AOP, EOP or normal operating procedure (NOP).

Which of the following describes the term "GO TO"?

A. Continue with the controlling procedure and perform the procedure that you are directed to "GO TO" in conjunction with it B. Complete the controlling procedure and then enter the procedure that you were directed to "GO TO" C. Immediately exit the controlling procedure and then enter the procedure that you were directed to "GO TO" D. With Shift Technical Advisor (STA) concurrence, exit the controlling procedure and then enter the procedure that you were directed to "GO TO" Answer:

C. Correct Notes:

or step in the procedure and enter AN0-2 EOP/AOP User Guide uses the term "GO TO" to depart from the current procedure procedure altogether . It is used when the current procedure or step is either another step in the current procedure or a different that will help.

not working and will help the implementer with plant conditions and direct entry into a procedure

References:

4.40.10 page 11 of73 OP-1015 .021 , AN0-2 EOP/AOP User Guide, Rev 011 , section 4.4 page 3 of73 , and section Historica l Commen ts:

ANO Bank QID #ANO-OPS2-13018

• Form ES-401-5 Written Exam Question Workshe et 85

Data for 2014 NRC RO/SRO Exam 20-Dec-13 Bank: J1999 I Rev: lIJ Rev Date: :10/22/2013 10:12: I Q~ID_#_:---'==75=::::'.___A_u_th_o_r_: _-===fo=s=te=r===:

• Lie Level: 0 Difficulty: CIJ Taxonomy:[][] Source: J'---_ _ _ _ _ _ _ _NE __W_ _ _ _ _ _ _~

Search J1940012432 I toCFRSS: !41.10 / 43.5 / 45.13 I SafetyFunction System

Title:

!Generic I System Number jGENERic l KIA J 2.4.32 Tier: ITJ Group: DJ RO Imp: @] SRO Imp: ~ L. Plan: J A2LP-RO-PANN J OBJ J 8

Description:

1Emergency Procedures/Plan - Knowledge of operator response to loss of all annunciators.

Question:

Consider the following:

- Unit 2 is operating at I 00% power

- An Annunciator check is being performed for the shift turnover checklist

-Alarm panels 2K01through2K07 do not alarm

- OP-2203 .042, Loss of Annunciators AOP, has been entered The CRS would direct _ __ _ __ _

A. maintaining steady state plant conditions B. performing a one (1) hour rapid plant shutdown

• C. performing a two (2) hour normal plant shutdown D. tripping the plant and entering SPT As Answer:

A. Correct Notes:

Plant maneuvers are not recommended or required without remote monitoring capability (annunciators) steady state plant operation is preferred.

References:

OP-2203 .042, Loss of Control Room Annunciators AOP, Rev 006, step 3 page 2 of20 AOP-2203.042, Loss of Control Room Annunciators Tech Guide, Rev 005 , step 3 page 6of12 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 86

Data for 2014 NRC RO/SR O Exam 21-Dec-13

• Bank: 12000 I Rev:

Lie Level: m m Rev Date: 11114/2013 3:11:39 Difficulty: [}] Taxonomy :[ [ ] Source:

I QID #:

I Search loooo09A206 j IOCFR55: j41.7 I 41.10 I 43.5 I 45 I Safety Function I System

Title:

jsmall Break LOCA 76 Author:

NEW 3 I I System Number I 009 I KIA I EA2.06 foster Tier: [}] Group: [}] RO Imp: []}] SRO Imp: @] L. Plan: I A2LP-RO-ELOCA I OBJ I 6 Descriptio n: Ability to determine and interpret the following as they apply to a small break LOCA: -

Whether PZR water inventory Joss is imminent Question:

(REFERENCE PROVIDED)

Consider the following:

- Unit 2 is operating at 100% power

- "A" HPSI pump (2P-89C) is OOS for maintenance

- "C" CCP (2P-36C) is aligned to Green

- ATC reports Containment parameters are trending up (pressure, temperature, and humidity)

- Pressurizer level is 60%

- Volume Control Tank (VCT) level is 72%

3 minutes later:

- Pressurizer level is 59%

- VCT level is 71%

Unit 2 now trips due to a Loss of Offsite Power (LOOP)

- Annunciator 2K08 C-2 "Engine I Exciter Shutdown" for #1 EDG is in alarm

- CBOT reports "B" HPSI pump is running without discharge pressure

- RCS Leakrate does not change post trip Based on conditions above, the Reactor Coolant System (RCS) inventory (Pressurizer level) _ _ _

recover (trend up) and after performing SPT As, the CRS would diagnose entry into _ _ __ _ _ _ _ _ _ _ _ __

A. would; OP-2203.016, Excess RCS Leakage B. would; OP-2202.003 , Loss of Coolant Accident C. would not; OP-2203.016, Excess RCS Leakage D. would not; OP-2202.003, Loss of Coolant Accident Answer:

B. Correct Notes:

The leakrate is based on 55.3 gallons per percent in the pressurizer x I% change in level= 55.3 gallons 33 .8 gallons per percent in the VCT x 1% change in level= 33 .8 gallons, 55.3 + 33.8 = 89.2 gallons I 3 minutes (time frame the leakrate data was taken)= 29.7 gallon/minutes RCS leakage. SIAS would be actuated due to the RCS leakage and with the loss of offsite power (LOOP) and the # 1 EDG not supplying the bus (exciter shutdown) only Green Train components will be available for makeup sources. With the "C" HPSI (swing) pump OOS and the failure of the "B HPSI pump the 2 CCPs would be available to makeup to the Pressurizer (the "B" LPSI pump would be running but RCS pressure would be to high for injection (RCS Form ES-401-5 Written Exam Question Workshee t 88

Data for 2014 NRC RO/SRO Exam 21 -Dec-13

• makeup > RSC leakage) therefore Pressurizer level would trend up at approximately 1%

leak with a LOOP.

References:

[PROVIDED] OP-2305 .002, Reactor Coolant System Leak Detection, Rev 024 Exhibit I minute. With a leakrate of 29. 7 gpm entry conditions for OP-2203.016, Excess RCS Leakage. Exhibit 8 will direct the CRS to diagnose LOCA due to a RCS 1 page 39 of 54 OP-2203 .012H, Annunciator Corrective Actions, 2K08 window C-2, Rev 037, page 15 of 50 OP-2202.010, Standard Attachments, Rev 022, Exhibit 8 page 193 of204 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 89

Data for 2014 NRC RO/S RO Exam 21-Dec-13 Bank: !2001 I Rev: [ ] ] Rev Date: 112/ 11/2013 10:52: j QID #: 77 Autho r: foster Lie Level: [}] Difficu lty: [D Taxo nomy :[)) Source

I Modified NRC Bank QID #1566 Search !o000402402 / toCFR 55: 141.7 I 45.7 I 45.8 Safety Functi on 4 System

Title:

!steam Line Rupture j System Numb er I 040 J KIA I 2 .4.2 Tier: [ [ ] Group : [ [ ] RO Imp: 8lJ SRO Imp: 8IJ L. Plan: I A2LP-RO-COLSS I OBJ I 17 Descri ption: E~ergency Procedures/Plan - Knowledge of system set points, interlocks and automa with EOP entry conditions. tic actions associated Questi on:

Consider the following:

- Unit 2 is operating at 100% power

- The IAO reports a steam leak by the chemistry Jab

-Annu nciator 2K10 A-2 "COLSS Power Margin Exceeded" comes into alarm

- ATC reports reactor power is IO 1.9% and rising

- RCS Tave 576°F and trending down

- RCS Margin to Saturation (MTS) is 47°F and trending up

-ATC reports reactor power is 102.1%

The CRS would find the direction in for reduce turbine load AND the criteria for

• tripping the reactor when the MTG output has been reduced by at least _ __ megawatts.

A. 2K 10 A-2, COLSS POWE R MARG IN EXCE EDED , ACA; 25 B. 2Kl 0 A-2, COLSS POWE R MARG IN EXCE EDED , ACA; 50 C. OP-2203.050 , Overcooling Event in Mode 1 or 2 AOP; 25 D. OP-2203 .050, Overcooling Event in Mode 1 or 2 AOP; 50 Answe r:

C. Correct Notes:

The student is given indications of an excess steam demand on the reactor. The COLSS Power Margin Exceed ed alarm would be in and the ACA does have directions for reducing turbine load below 100%, but, with indicated reactor power so high

[101 .9%] entry conditions for the Overco oling Event in Mode 1or2 AOP are met. The ACA does direct entry into the Overcooling Event in Mode 1 and 2 AOP (OP-2203 .050). In the AOP, Trip criteria is given for a steam leak that is large enough to cause a MTG load to be reduced by >25 MW.

Refere nces:

OP-2203.0121 , Annunciator Corrective Actions, 2Kl0 window A-2, Rev 039, pages 18-20 of84 OP-2203 .050, Overcooling Event in Mode 1 or 2 AOP, Rev 001 entry section page 1 of 10, step 3.B and C page 3of10 Histor ical Comm ents:

NRC Bank QID # 1566, used on the 2008 NRC Exam Form ES-401 -5 Writte n Exam Questi on Works heet 90

21-De c-l 3 Data for 2014 NRC RO/S RO Exam

• Bank: 12002 I Rev:

Lie Level: m Search loo0055A201

[I] Rev Date: 112/ 16/2013 1:29:4 Diffic ulty:[ }] Taxo nomy :[IJ Source : I I 10CFR 55:

I QID #: 78 141.7 I 41.10 I 43.5 I 45. 1 Safety Functi on System

Title:

ILoss ofOffs ite and Onsite Power (Station Black Autho r:

I NEW 6 I I System Numb er I 055 I KIA I EA2.0l foster Group : [I] RO Imp: [}I] SRO Imp: ITIJ L. Plan:

I A2LP-RO-ESPTA I OBJ I 17 Tier: [I]

as they apply to a Station Blackout: - Existing valve positioning Descri ption: Ability to determine and interpret the following on a loss of instrument air system Questi on:

Consider the following:

- Unit 2 is operating at I 00% power nance

- The Alternate AC Diesel Generator (AACDG) is OOS for mainte

- A Loss of Offsite Power (LOOP ) now occurs running

- Upon the trip neither Emergency Diesel Generator (EDG) is

- IAO is unable to start either EDG

- SPTAs are complete lled Bleedo ff (CBO) Flow would be aligned to the Due to the given conditions, Reactor Coolant Pump (RCP) Contro entry into _ _ _ _ _ _ _ _ _ _ __

_ _ _ _ _ _ _ _ _ _ and the CRS would diagnose

• A. Quench Tank (QT); OP-2202.007, Loss ofOffs ite Power B. Volume Control Tank (VCT) ; OP-2202.007, Loss ofOffs C. Quench Tank (QT); OP-2202.008, Station Blackout EOP EOP ite Power EOP ut EOP D. Volume Control Tank (VCT); OP-2202.008, Station Blacko Answe r:

C. Correct Notes:

(due to the LOOP, AACDG OOS and neither EDG starting) The The student should recognize a Station Blackout is in progress to attachments Exhibit 8, Diagnosis Flow Chart. Without power CRS would diagnose the Station Blackout EOP using standard (valves fail and the CBO flowpath to the VCT would isolate the non-vital buses, there would be no Instrument Air pressure close) which will align CBO to the QT.

Refere nces:

2.1pag e21 and simplified drawing page 62 STM 2-04, Chemical and Volume Control System, Rev 29, section 193 of204 OP-2202.010 , Standard Attachments, Rev 022, Exhibit 8 page Histor ical Comm ents:

• Form ES-401-5 Writte n Exam Questi on Works heet 88

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 12003 I Rev: CT]

Lie Level: [}] Difficulty:

Search loo0058A203 Rev Date: II0/23/2013 8:53:2 I QID #:

CI] Taxonomy:[ ] ]

I 10CFRSS:

System

Title:

ILoss of DC Power Source: I 79 141. 7 I 41.1 OI 43.5 I 45 . I Safety Function Author:

I System Number I 058 I

NEW 6 I I KIA I foster AA2.03 Tier: ITJ Group: ITJ RO Imp: Q}J SRO Imp: [ill L. Plan: I A2LP-RO-ED125 I OBJ I 11 of DC Power: - DC loads lost; impact Descripti on: Ability to determine and interpret the following as they apply to the Loss on ability to operate and monitor plant systems Question :

Consider the following:

- Unit 2 is operating at l 00% power

- 2D02 Green Battery disconnect has been opened for maintenance

- Battery charger, 2D-32B, is in service

- Now 2D-32B the output breaker trips open be maintained by cycling Coolant The CRS would diagnose _ __ _ __ _ __ _ _ _ _ and Pressurizer level would Charging Pump (CCP) due to letdown isolation valve failing closed.

A. OP-2202.001 , Standard Post Trip Action EOP; 2CV-4820-2, inside containment

• B. OP-2202.001 , Standard Post Trip Action EOP; 2CV-4823-2 outside containment C. OP-2203 .037, Loss of 125V DC AOP; 2CV-4820-2, inside containment D. OP-2203 .037, Loss of 125V DC AOP; 2CV-4823-2, outside containment Answer:

D. Correct Notes:

all green DC loads. When the chargers With the Green Battery disconnected from its bus [2D02] the battery charger is supplying a trip with a loss of DC so the unit will breaker trips open, a loss of green DC will occur. The Unit has been modified to prevent isolation valve [2CV-4823-2] is air stay on line and the Loss of DC AOP would be entered. The outside containment letdown the valve will fail closed isolating operated and the air supply is controlled by a green DC solenoid. When green DC is lost, letdown and cause Pzr level to be maintained by cycling CCPs.

Referenc es:

33 of 57 OP-2203 .037, Loss of 125V DC AOP, Rev 009, entry page l of 57, section 3 step 2.A. page OP-2203 .037, Loss of 125V DC Tech Guide, Rev 009, section 3 step 2entry page 45 of75 Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 89

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: f2004 Rev:

Lie Level: m f

Search [0000622132

[2] Rev Date: 11 /1 4/2013 8:36 :3 f

Difficulty: ((] Taxonomy: [![] Source:

[ toCFR55: [41.10 / 43 .2 / 45 .12 System

Title:

[Loss of Nuclear Service Water f QID #: 80

[ System Number [

Author:

~~--=====---~~~---===========:;

I

[

NEW

~------;::=====::::;-----~

SafetyFunction 4 062

[

[ KIA [

foster 2.1.32 Tier: [ [ ] Group: [ [ ] RO Imp: @] SRO Imp: IT-2] L. Plan: [ A2LP-RO-SWACW [ OBJ f13&15 [

Description:

[conduct of Operations - Ability to explain and apply system limits and precautions.

Question:

Service Water Systems Operations procedure, OP-2104.029, has Limits and Precautions associated with the Emergency Cooling Pond (ECP) Level and Temperature Tech Spec 3.7.4. 1 Tech Spec 3.7.4.1 Bases, a MlNIMUM indicated ECP level of _ _ feet, based on soundings and includes measurement, calculation and other uncertainties (equivalent to 0.15 ft), ensures an adequate heat sink based on worst case initial conditions during a simultaneous shutdown of Unit I and emergency shutdown of Unit 2 following a Unit 2 LOCA.

Also, Operator action credited to initiate makeup to ECP upon a loss of Dardanelle Reservoir to maintain the minimum water volume required for a 30 day supply of cooling water to safety related components without exceeding their design basis temperature.

A. 5.2; is B. 5.2; is not

c. 5.5; is D. 5.5; is not Answer:

A. Correct Notes:

Aligns with T.S. 3.7.4.1 bases for the minimum indicated ECP level of 5.2 feet. This requirement is based on soundings and includes measurement, calculation and other uncertainties (equivalent to 0.15 ft) to ensure a minimum contained water volume of 70 area-feet crediting operator action to initiate makeup to ECP upon loss of Dardanelle Reservoir. The additional water added to the ECP during the time between first swapping the returns to the ECP and then later swapping the suctions to the ECP will maintain the ECP >70 area-feet and provide adequate supply of water for a 30 day supply of cooling water to ECCS components to operate without exceeding their design base temperature.

References:

OP-2104.029, Service Water Systems Operations, Rev 094, section 5.0 step 5.25 and 5.26 page 8 of 312 Tech Spec 3.7.4.1 , ECP Level and Temperature requirements Tech Spec Bases B3 .7.4.1, ECP Level and Temperature requirements OPS-B3 l , Unit 2 outside AO Logs, Rev 46, ECP Level reading, page 9 Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet 92

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• I Rev: [TI 1 Bank: 12005 Rev Date: 12/ 12/2013 10:59: I QID #: 81 Author: foster Lie Level: [ ] ] Difficulty: : 3 : Taxonomy: ~ Source: l~--A -N_O_B_a_nk

_Q_l_

D_#_A_N

_O_ _O_P_S_2_-7_0_3_5 -~

Search 10000772236 I rncFR55: 141.10 / 43.2 / 45.lL J SafetyFunction I 6  ;

System

Title:

!Generator Voltage and Electric Grid Disturbance! System Number I 077 I KIA I 2.2.36 Tier: ~ Group: [C RO Imp: JI) SRO Imp: l 4.2 : L. Plan: ; A2LP-RO-EDHVD I OBJ I 9

Description:

Equipment Control - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Question:

Consider the following:

- Unit 2 is operating at 100% power

- #2 EDG is out of service for its 18 month overhaul

- The Unit 2 control room has just been informed that Startup #2 (SU2) Transformer is Inoperable What action, listed below, is required?

A. Enter T.S. 3.0.3 due to being outside the LCO and allowable action statements B. Perform OP-2107.001, Electrical System Operation, Supp. 4 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

• C. Demonstrate the operability of # I EDG within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. Place the Unit in HOT STANDBY within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Answer:

B. Correct Notes:

T.S. 3.8.1.1 covers a varity of combinations ofloss of power sources. Action 'c' covers a loss of an offsite source (SU2) alone with the #2 EDG being unavailable due to planned maintenance. 3.8.1.1.c. l. required performance of OP-2107.001, Electrical System Operation, Supp. 4 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

A. Incorrect: The stated condition is not outside T.S.3.8. l. l LCO C. Incorrect: If an offsite power source was inoberable first, then a EDG became unavailable, then within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> oberalbility of the remaining EOG would have to be demonstrate D. Incorrect: No requirements to place the Unit in HOT STANDBY within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

References:

T.S. 3.8.1.1 , Electrical Systems Modes 1-4 Historical Comments:

ANO Bank QID #ANO-OPS2-7035

• Form ES-401-5 Written Exam Question Worksheet 93

21-Dec-13 Data for 2014 NRC RO/S RO Exam

• Bank: 12006 I Rev:

Lie Level: m Search loo00052222

[I]

Difficulty:

Rev Date: 111 / 15/2013 11:15 :

ITJ I tOCFRSS: 141.5 I 43.2 I 45.2 System

Title:

!Inoperable/Stuck Control Rod I QID #:

I

~~==

Taxon omy:[ [ ] Source : I'---ANO

===~

82

~~--

Autho r:

-'==

Bank QID #ANO-OPS2

~~~-=-;=

Safety Functi on I System Numb er I I

==

1 005

==

=:;-

I I KIA I foster

==

-6094

-~~~

==:

2.2.22

_J I OBJ I Tier: [I] Group : [ [ ] RO Imp: 8:IJ SRO Imp: ~ L. Plan: I A2LP-RO-ACEA 2 ons for operations and safety limits.

Descri ption: !Equipment Control - Knowledge of limiting conditi Questi on:

, OP-2203.003 , CEA Malfunction AOP, directs After realignment of an Inoperable control element assembly (CEA) ing a power escalation.

maintaining reactor power constant for one (1) hour prior to perform hour hold is Per the CEA Malfunction Tech Guide, the reason for this one(!)

~

~~~

~~~

~~~

of core power from the A. to prevent pellet-clad interactions caused by the redistribution misaligned control element assembly (CEA)

(Az Tilt) caused by the redistribution B. to prevent exceeding the Tech Spec limits on Azimuthal Tilt assemb ly (CEA) of core power caused by the misaligned control element 0.27 when performing the power C. to prevent exceeding the COLSS ASI operational limit of +/-

escalation after realignment of the control element assembly (CEA)

• D. to allow ASI to stabilize prior to performing the power escalat control element assembly (CEA)

Answe r:

A. Correct ion after realignment of the Notes:

for one hour to prevent pellet-clad interactions caused by the Per the AOP tech guide, reactor power is maintained constant t assembly (CEA) redistribution of core power from the misaligned contro elemen Refere nces:

13 of27 OP-2203 .003, CEA Malfunction AOP, Rev 020, step 33 page step 33 page 27 of34 AOP-2203 .003 , CEA Malfunction Tech Guide, Rev 020, Histor ical Comm ents:

ANO Bank QID #ANO-OPS2-6094

• Form ES-401-5 Writte n Exam Questi on Works heet 95

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: f2007 f Rev:

Lie Level:

Search f000024A201 m

j Rev Date: fl2/ 12/2013 9:25:4 f QID#: 83 10CFRSS: j4J.7 / 41.10 / 43 .5 / 45 f SafetyFunction System

Title:

jEmergency Boration [ System Number Author:

~~-=====-~~~----=========~

ITJ Difficulty: ITJ Taxonomy:[}[] Source: ~f_ _ _ _ _N_R_C_ B_a_n_k _Qc_I_D_#_1_5_6_9_ _ _ _

I I 1 024 I

I KIA [

foster AA2.01

___j Tier: OJ Group: 0 RO Imp: ITIJ SRO Imp: 8IJ L. Plan: [ A2LP-RO-EFRP I OBJ [ 4

Description:

Ability to determine and interpret the following as they apply to the Emergency Boration: - Whether boron flow and/or MOVs are malfunctioning, from plant conditions Question:

Consider the following:

- Unit 2 is operating at 100% power

-Annunciator 2K12 B-2 "Header Press LO" for the Coolant Charging Pumps (CCPs) comes into alarm

- Annunciator 2K 12 B-3 "Header Flow LO" for the CCPs comes into alarm

- Volume Control Tank (VCT) level is 58% and lowering

- The WCO reports a rupture in the CCP suction header downstream of the RWT supply valve, 2CV-4850-2

- OP-2203 .036, Loss of Charging AOP, has been entered and the CRS directs tripping the Unit

- The ATC reports 3 CEAs did not fully insert on the trip and reactor power is 0.2% and steady

- SPT As have been completed

• The CRS would diagnose _ _ _ __ _ _ _ _ __ _ _ and Emergency Boration would be accomplished by A. OP-2202.009, Functional Recovery EOP; aligning CCP discharge to the #1 HPSI header B. OP-2202.009, Functional Recovery EOP; lowering RCS pressure and starting a HPSI pump C. OP-2203.032, Emergency Boration AOP; aligning CCP discharge to the #1 HPSI header D. OP-2203 .032, Emergency Boration AOP; lowering RCS pressure and starting a HPSI pump Answer:

B. Correct Notes:

With the given conditions entering Functional Recovery and depressurizing the RCS to allow using HPSI to emergency borate is correct. The location of the charging suction header rupture is unisoable from the rest of the system rendering all CCPs incapable of adding inventory to the RCS. With > 1 CEA not fully inserted and reactor power >. l % and stable requires the addition of boron to meet shutdown margin. The Emergency Boration AOP does contain direction to depressurize and use a HPSI pump but it is not addressed on the exhibit 8 as an option to enter post SPTAs with the reactivity safety function not met.

References:

OP-2203.012L, Annunciator Corrective Actions, 2Kl2 window B-2, Rev 044 page 18of116

• OP-2203.012L, Annunciator Corrective Actions, 2K 12 window B-3 , Rev 044, page 36of116 OP-2203.036, Loss of Charging AOP , Rev 011 , step 8, contingency 8.2) page 7 of24 OP-2202.010, Standard Attachments, Rev 022, Exhibit 8 page 193 of204 OP-2202.009, Functional Recovery, Rev 017, entry section step I I.A page I 0 of 45 Form ES-401-5 Written Exam Question Worksheet 97

Data for 2014 NRC RO/SRO Exam 21-Dec-J 3

• OP-2202.009, Functional Recovery, Rev 017, section RC, Reactivity Control Decision Tree page 1 of 11 and section RC-3 step 4 contingency colume Historical Comments:

NRC Bank QID #1569 used on the 2008 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 98

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• [I]

Bank: !2008 ! Rev: Rev Date: !I0/29/2013 9:48:5 1 QID #: 84 Author: foster Lie Level: ~ Difficulty: [IJ Taxonomy:[ TI Source: I NRC Bank QID #0469 Search !ooo069A202  ! 10cFR55: i41.7 I 41.10 I 43 .5 I 45. j Safety Function I 5 System

Title:

!Loss of Containment Integrity  : System Number / 069 I KIA AA2.02 Tier: OJ Group: [TI RO Imp: [IE SRO Imp: ~ L. Plan: I A2LP-RO-CVENT I OBJ I 15

Description:

Ability to determine and interpret the following as .they apply to the Loss of Containment Integrity: -

Verification of automatic and manual means of restoring integrity Question:

Consider the following:

- Unit 2 is in Mode 4 and heating up

- Control Board panel walkdowns are being performed in preparations to enter Mode 3

- The CBOT reports the Containment Purge system isolation valves are open with keys inserted be The required action to comply with Tech Spec, 3.6.1.6 and restore the Containment Purge system to an Operable status would to verify the containment purge isolation valves closed with keys removed _ _ _ _ _ _ _ _ __

A. immediately B. within 5 minutes C. within 15 minutes D. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Answer:

D. Correct Notes:

Technical Specification 3 .6.1.6 requires all three Containment Purge Isolations in the supply and exhaust ducts to remain closed and keys removed during modes 1-4. These valve are only opened in Modes 5 and below to ensure Containment Integrity is maintained in Modes 1-4

References:

Technical Specification 3 .6.1 .6, Containment Ventilation System Historical Comments:

NRC Bank QID #0469, used on 2005 NRC Exam

• Form ES-401-5 Written Exam Question Worksheet 97

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: !2009 I Rev:

Lie Level: m

[Q] Rev Date: !10/29/2013 9:06:5 1 QID #:

Difficulty: [}] Taxonomy:[ [ ] Source: I Search looCA11A201 ! tocFRSS: 141.7 / 41.10 / 43.5 / 45 1 SafetyFunction System

Title:

!RCS Overcooling 85 Author:

Modified NRC BANK QID #0522 I 4 I System Number I Al 1 I KIA I EA2.1 foster Tier: [ [ ] Group: [D RO Imp: [I2J SRO Imp: [J.TI L. Plan: I A2LP-RO-ACOOL I OBJ I 1&3

Description:

Ability to detennine and interpret the following as they apply to the (RCS Overcooling): - Facility conditions and selection of appropriate procedures during abnonnal and emergency operations Question:

Consider the following:

- Unit 2 has tripped due to a rupture in the EH system

- SPT As have been completed

- IAO reports steam in the Turbine Building Basement

- "A" S/G pressure is 900 psia and slowly trending down

- "B" S/G pressure is 890 psia and slowly trending down The CRS would diagnose entry into _ _ _ _ _ _ _ _ _ and direct _ _ _ _ _ _ _ _ __

A. OP-2203 .011 , RCS Overcooling AOP; closing the Main Steam Isolation Valves (MSIVs)

B. OP-2203.011 , RCS Overcooling AOP; actuating Main Steam Isolation Signal (MSIS)

C. OP-2202.005 , Excess Steam Demand EOP; closing the Main Steam Isolation Valves (MSIVs)

D. OP-2202.005, Excess Steam Demand EOP; actuating Main Steam Isolation Signal (MSIS)

Answer:

A. Correct Notes:

A. Correct: OP- 2202.0 I 0, Standard Attachment diagnostics will direct entry into RCS Overcooling AOP unless the overcooling is excessive causing a Main Steam Isolation signal, then the Excess Steam demand EOP would be entered.

B. Incorrect: Entry conditions are met and actuating MSIS is directed in step 2 if SIG pressure is below the MSIS setpoint, but S/G pressures are above the MSIS setpoint.

C. Incorrect: the entry conditions for ESD are not met per the dianositic flow chart (exhibit 8) due to the MSIS setpoint has not been reached (<751 psia) closing the MSIVs is not directed D. Incorrect: the entry conditions for ESD are not met per the dianositic flow chart (exhibit 8) due to the MSIS setpoint has not been reached (<751 psia) actuating MSIS is directed in step 5.

References:

OP-2202.0 l 0, Standard Attachments, Rev 022, exhibit 8 page 193 of 204 OP-2203.011 , RCS Overcooling AOP, Rev 005, Entry Conditions page I of9 and step 3 page 2 of9 AOP-2203 .011, RCS Overcooling Tech Guide, Rev 005 Entry Conditions page 3 of 15 and step 3 page 6 of 15

• Historical Comments:

NRC Bank QID #0522 used on 2005 NRC Exam Form ES-401-5 Written Exam Question Worksheet 100

Data for 2014 NRC RO/SR O Exam 21-Dec-13 Bank: 12010 I Rev: m Rev Date: jI0/28/2013 3:58:2 I Lie Level: m Difficulty: [JJ Taxonomy:[}] Source:

QID #:

I 86 Author:

NEW foster Search jOI2000A203 / toCFR55 : j4 I.5 I 43.5 I 45.3 I 45. I Safety Function I 7 I System

Title:

jReactor Protection System ISystem Number I 012 j KIA I A2.03 Tier: [I] Group: [IJ RO Imp: ~ SRO Imp: [ID L. Plan: I A2LP-RO-RPS I OBJ I 10 Descripti on: Ability to (a) predict the impacts of the following malfunctions or operation s on the RPS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Incorrect channel bypassing Question :

[REFERENCE PROVIDED]

Consider the following :

- Unit 2 is operating at I 00% power

- Channel 1 Pressurizer [PZR] pressure transmitter [NR], 2PT-4601 -l , has failed LOW

- The CBOT bypasses ONLY point 5 [Pzr pressure - HIGH] for the Pzr pressure measurem ent channel A failure of another Pzr pressure [NR] transmitter would cause a reactor trip on

. This trip could of been prevented by applying Tech Spec 3 .3 .1.1 to bypass additional points in Channel 1.

A. Linear Heat Rate [LPD] and Departure form Nucleate Boiling Ratio [DNBR]; action 2

B. Linear Heat Rate [LPD] and Departure form Nucleate Boiling Ratio [DNBR]; action 3

C. Pressurizer pressure LOW; action 2 D. Pressurizer Pressure LOW; action 3 Answer:

A. Correct Notes:

With one channel failed low [Pzr pressure] channel I LPD and DNBR wilJ also be in a tripped condition on channel 1.

T.S.3.3.1 .1 action b requires points 3, 4, and 5 in either tripped or bypass within I hour.

Without placing points 3 and 4 in bypass for channel I the reactor trip logic is in a 2 out of 4 logic with I point already tripped, therefore it would on~y take I more Pzr pressure channel to fail low [which would also trip LPD and DNBR for that channel]

to cause a reactor tnp.

References:

STM 2-63, Reactor Protection System, Rev 11, section 6.2.1, pages 41 and 42 T.S. 3.3.1.1 STM 2-03, Reactor Coolant System, Rev 22, section 2.2.5.1, page 17 Historica l Commen ts:

• Form ES-401-5 Written Exam Q uestion Workshe et JOO

20-Dec-13 Data for 2014 NRC RO/SRO Exam 0 ~ Rev Date: :11 /4/2013 12:32:5 foster Bank: 12011 I Rev: i QID #: 87 Author:

Lie Level: ITJ Difficulty: ~ Taxonomy:ITJ Source: I NEW Search 10130002222 1 IOCFR55: 141.5 I 43.2 I 45.2 I Safety Function I 2 I System

Title:

!Engineered Safety Features Actuation System (E ! System Number I 013 I KIA I 2.2.22 Tier: [2J Group: [JJ RO Imp: 8IJ SRO Imp: ~ L. Plan: ! A2LP-RO-RCS I OBJ I 16 safety limits.

Description:

!Equipment Control - Knowledge of limiting conditions for operations and Question :

pressurized above its Safety Limit of Pressurizer Code Safety Tech Spec 3.4.3 LCO is based on preventing the RCS from being occurring at the first Reactor Protection System

_ _ _ ___ psia with a loss of the Main Turbine load with the reactor trip operation .

(RPS) setpoint and the Steam Dump Bypass Control System (SDBCS)

A. 2500; in B. 2750; in C. 2500; not in D. 2750; not in Answer:

D. Correct Notes:

T.S. 3.4.3 bases

References:

T.S 3.4.3, Safety Valves Operating and bases Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et JOO

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 12012 I Rev:

Lie Level: m Search 10260002120

[QJ Rev Date: 110/29/2013 2:55:5 Difficulty: [}] Taxonom y:[][] Source:

I rncFRSS : j41.10 I 43 .5 I 45.12 System

Title:

jcontainment Spray System (CSS)

I QID #:

I 88 Safety Function I System Number Author:

I I

NEW 5

026 I

foster I KIA I 2.1.20 Tier: [2J Group: [JJ RO Imp: GlJ SRO Imp: @] L. Plan: I A2LP-RO-ELOCA I OBJ 6

Description:

!conduct of Operations - Ability to interpret and execute procedure steps.

Question :

Consider the following :

- Unit 2 is operating at I 00% power

- l&C is performing maintenance in 2C-39, the Engineered Safety Features Auctuation System (ESF AS) actuation cabinet

- Annunciator 2K07 D-1 "CSAS ACT" is in alarm

- Containment parameters are normal The CRS would enter ~~~~

~~~~

~~~~

~

and would direct ~~~~

~~~~

A. OP2202.001 , Standard Post Trip Action EOP; secure all Reactor Coolant Pumps (RCPs)

• B. OP2202.001, Standard Post Trip Action EOP; place the "A" Spray Pump (2P-35A) in Pull to Lock (PTL)

C. OP2203.041, Inadvertant CSAS AOP; secure all Reactor Coolant Pumps (RCPs)

D. OP2203 .041 , lnadvertant CSAS AOP; place the "A" Spray Pump (2P-35A) in Pull to Lock (PTL)

Answer:

B. Correct Notes:

needed and direct placing the "A" the Inadvertant Spray Actuation will cause a reactor trip and SPTAs will verify spray is not the unit and secure the RCPs Spray pump in PTL. Pre power uprate, an lnadvertant CSAS would have the operators trip

References:

OP2202.001, Standard Post Trip Action EOP, Rev 014, step 9.B page 16of19 Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 102

21-Dec-13 Data for 2014 NRC RO /SR O Exa m

• 89 Auth or: foster Bank : 12013 I Rev: [QJ Rev Date : 11114/2013 11:08 :4 1 QID #:

N_E_W-------~

Difficulty: ((] Taxo nomy :[ [ ] Sour ce: ~I_

Lie Level: [I] _

I 10CFRSS: 141.5 I 43 .5 I 45.3 I 45. I Safety Func tion I 4 I Searc h lo61000A204 (AFW) Syste I System Num ber I 061 I KIA I A2.04 System

Title:

!Auxiliary I Emergency Feedwater QI] SRO Imp: [}TI L. Plan: I A2LP-RO-EFW I OBJ I I 0 Tier: OJ Grou p: [JJ RO Imp:

AFW System and (b) of the following malfunctions or operations on the

Description:

Ability to (a) predict the impacts the conse quenc es of those ct, control, or mitigate based on those prediction s, use procedures to corre per operation malfunctions or operations : - pump failure or impro Ques tion:

Consider the following:

- Unit 2 has tripped due to a disturbance on the Grid ed

-The 500kV and the 161kV lines are de-energiz Diese l Gene rators (EDG s) are running

- Both Emergency B-3 "2A3 L.O. Relay Trip" is in alarm

- Annunciator 2K08

- #1 EDG feede r to 2A3 (2A3 08) is open Trip" is in alarm

- Annunciator 2K05 A-9 "2P7 A Turb Overspeed ing down

- "A" Steam Generator (S/G) level is 223" and trend ing down

- "B" Steam Generator (S/G) level is 123" and trend

- SPTAs are complete

• The CRS would enter - - - - - - - - - - -

remove core heat.

A. Loss ofFee dwat er, OP-2202 .006; resetting EOP and direct - -- -- - - - - - - - - -- -

"A" EFW pump (2P-7 A) and feeding the S/Gs to 2A3 with the #1 EDG and feeding the S/Gs with B. Loss ofFee dwat er, OP-2202.006 ; energizing the "B" EFW pump (2P-7B) 2Al with the AACDG and feeding the S/Gs with C. Functional Recovery, OP-2202.009; energizing the Auxiliary Feedwater pump (2P-75) success path HR-3 , Once Through Cooling D. Functional Recovery, OP-2202.009; implement Answ er:

A. Correct Notes:

the "A" EFW pump and which will direct resetting the overspeed trip on OP-2202.006 implment Satadard Attactment 54 restoring feed to the S/Gs at <150 gpm

References:

2K08 window B-3 , Rev 037, page 26 of 50 OP-2203 .0l2H , Annunciator Corrective Actions, 2K05 window E-9, Rev 039, page 77 of86 OP-2203.0l2E, Annunciator Corrective Actions, step 12 page 5 of25 OP-2202.006, Loss ofFee dwat er EOP, Rev 010, 54 step 6.A page 2 of3 and step 9 page 3 of3 OP-2202.010, Standard Attachment, Rev 022, Att.

Rev 009, step 12 page 19 of62 EOP-2202.006, Loss ofFee dwat er Tech Guide, 104 Form ES-401-5 Writ ten Exam Ques tion Work sheet

Data for 2014 NRC RO/SRO Exam 21-Dec-13

• Bank: 12014 I Rev:

Search lo64000A20 1 m

Lie Level: [}] Difficulty:

Rev Date: 110/23/2013 11 :56:

[I] Taxonomy:[ ] ]

I 10CFRSS:

I Source:

141.5 I 43.5 I 45.3 I 45.

System

Title:

!Emergency Diesel Generator (ED/G) System QID#:

I I

90 Safety Function I System Number I Author:

I NEW 6

064 I

I K/A I foster A2.0l Tier: [}] Group: OJ RO Imp: [2IJ SRO Imp: [}TI L. Plan: I A2LP-RO-ESPTA I OBJ I 2&11 I

Description:

Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Failure modes of water, oil, and air valves Question:

Consider the following:

- Unit 2 is operating at 100 power

- A 3 gpm Reactor Coolant System (RCS) leak has been detected

- A Loss of Offsite Power now occurs

- SPT As have been entered

- Annunciator 2K09 D-1 "Potential Engine Failure" comes into alarm for #2 Emergency Diesel Generator (EDG)

- !AO has been dispatched and reports local alarm is "Service Water Pressure LO"

- IAO reports Savaging Air Temperature is 160°F and rising

-ATC reports both lights above the #2 EDG Service Water supply, 2CV-1504-2, are out

• At the end of SPTAs, 2A4 Vital bus _ _ ___ be energized and the CRS would enter _ _ _ _ __ _ _ __ _ __

A. would; OP-2202.003 , Loss of Coolant Accident EOP B. would not; OP-2202.003, Loss of Coolant Accident EOP C. would; OP-2203 .016, Excess RCS Leakage AOP in conjunction with OP-2202.007, Loss of Offsite Power EOP D. would not; OP-2203 .016, Excess RCS Leakage AOP in conjunction with OP-2202.007, Loss ofOffsite Power EOP Answer:

B. Correct Notes:

The #2 EOG would be secured during SPTAs due to indications of no service water available due to aligned. If the LOOP or LOCA procedure were being implmented when the service water failure occurred, both LOOP and LOCA would direct aligning service water to the EOG and the securing critieria is based on scavaging air temperature > l 70°F. The Excess RCS Leakage AOP entry conditions are meet prior to the plant trip but it is not design to handle a Loss ofOffsite Power. Per the EOP/AOP User guide, if in the Excess RCS Leakage AOP with a LOOP, then go to the LOCA EOP.

References:

OP-2202.001 , Standard Post Trip Actions EOP, Rev 014, step 4.G page 5of19 EOP-2202.001 , Standard Post Trip Actions Tech Guide, Rev 012, step 4.G page 11 of 42 OP-1015.021 , AN0-2 EOP/AOP User Guide, Rev 011 , section 5.1.2, page 14 of73 Form ES-401-5 Written Exam Question Worksheet 106

Data for 2014 NRC RO/SR O Exam 21-Dec-13

• Bank: 12015 I Rev:

Lie Level:

Search

[JJ Rev Date: 110/29/2013 12:37:

ITJ Difficulty: CI] Taxonomy: ffi] Source: I I QID #: 91 loo1000A218 I toCFR55 : 141.5 I 43.5 I 45.3 I 45.1 1 Safety Function I System

Title:

!control Rod Drive System Author:

NEW I

I System Number I 001 I KIA I A2.18 foster Tier: 0 Group: 0 RO Imp:@ ] SRO Imp: QIJ L.Plan: I A2LP-RO-CEDM I OBJ 114&15 1 Descripti on: Ability to (a) predict the impacts of the following malfunctions or operation s on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Incorrect rod stepping sequence Question :

[REFERENCE PROVIDED]

Consider the following:

- Unit 2 is in mode 2

- A Reactor Startup in Progress

- Shutdown Bank A , B are fully withdrawn

- CEA Reg Groups are being withdrawn in Manual Sequential

- Reg Groups land 2 have reached the fully withdrawn position

- Reg Group 3 is l 02" withdrawn

- Reg Groups 4 and 5 are 1O" withdrawn

- Annunciator 2K l 0 E-1 "Reg Group Out of Sequence" is in alarm

• - Reactor is subcritical Control Element Assembly (CEA) motion would be stopped _ _ __ _ _ and the CRS Group 5 CEAs in manual mode to clear the alarm.

would direct inserting Regulating A. automatically; sequential B. manually; sequentia l C. automatically; group D. manually; group Answer:

C. Correct Notes:

CEAs are monitored for proper overlap during rod withdrawn. If proper overlap is not maintaine d, the alarm [Reg Group Out of Sequence] would alert the operations staff and CEA motion is automatically stopped. Using the ACA, CEA motion can recommence in manual group or individual CEA.

Referenc es:

OP-2203.0121, Annunciator Corrective Actions, 2Kl0 window E-1Rev0 39, pages 9 and 10 of84 [PROVIDED to STUDENT]

STM 2-02, Control Element Drive Mechanism Control System, Rev 21, section 4.2.1.4 page 27

• Historica l Commen ts:

Form ES-401-5 Written Exam Question Workshe et 104

21-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: 12016 I Rev: [JJ Lie Level: [ ] ] Difficulty:

Search 10160002107 Rev Date: I11113/2013 9:09:3

[JJ Taxonom y:[}[]

I 10CFRSS:

I Source:

141.5 I 43 .5 I 45.12 I 45 System

Title:

!Non-Nuclear Instrumentation System (NNIS)

QID #:

I I

92 Safety Function I System Number Author:

I I

NEW 7

016 I

foster I KIA I 2.1.7

-CVCS I OBJ I 4&8 Tier: [}] Group: [}] RO Imp: ~ SRO Imp: @] L. Plan: I A2LP-RO operational judgments based on Descripti on: Conduct of Operations - Ability to evaluate plant performance and make operating characteristics, reactor behavior, and instrumen t interpreta tion.

Question :

Consider the following:

- Unit-2 is operating at 100% power

-Annunci ator 2Kl2 G-5 "VCT 2T4 Level LO LO" comes into alarm

- 2LIS-4857, Volume Control Tank (VCT) level on 2C09 reads 68%

- 2LR-4857 , Volume Control Tank (VCT) chart recorder on 2C09 reads 68% and steady

- VCT level computer point, L486 l, reads 0%

- It has been determined 2LT-4861 has failed low

- Reactor power is approximately 99.5 % and trending down slowly

- RCS Tave 578°F and trending down

- Pressurizer level is 59% and trending down slowly in progress and the CRS would initiate The Control room staff would determine there is a - -- -- - - - - - event actions referencing _ _ _ __ _ _ _ _ __ _ __ _ _

A. loss of charging; OP-2203.036, Loss of Charging AOP B. boration; COPD-032, Transient Conduct of Operations C. loss of inventory ; OP-2203 .016, Excess RCS Leakage AOP D. Pressurizer control system; OP-2203 .028, Pressurizer System Malfunction AOP Answer:

B. Correct Notes:

and 2CV-4950-2, CCP suction Due to the false low VCT level signal, CV-4873-1, VCT outlet, would automatically close to the RCS . Once aligned, reactor source from the R WT would automatically open aligning an Emergency Boration flowpath steam demand not changing (MTG is temperature will trend down, reactor power will maintain somewhat constant due to manual control of the VCT and RWT valves controlled in manual). The CRS should recognize this and secure CCPs (or take operator actions to take manual control of systems and realign CCP suction to the VCT) referencing COPD-032 which allows that are malfunctioning.

Referenc es:

OP-2203 .012L, Annunciator Corrective Actions, 2Kl2 window G-5, Rev 044, page 58of116 simplified drawing page 63 STM 2-04, Chemical and Volume Control system, Rev 29, section 2.1.21.1p age19 and COPD-032, Transient Conduct of Operations, Rev 003, section 8.0 page 17 of 41 Historica l Commen ts:

Form ES-401 -5 Written Exa m Q uestion Workshe et 109

20-Dec-13 Data for 2014 NRC RO/SR O Exam

• Bank: J20n J Rev: ITJ Rev Date: J10/22/2013 8:52:2 J QID #: 93 Author: foster Lie Level: ITJ Difficulty: ITJ Taxonomy: ITJ Source: ! NEW Search Jo34000K40 I J toCFR55 : 141. 7 I Safety Function [ 8 I System

Title:

JFuel Handling Equipment System (FHES) [ System Number i 034 I KIA I K4.0l Tier: [TI Group: [I] RO Imp: ~ SRO Imp: [EJ L. Plan: J A2LP-RO-FH I OBJ I 2 which provide for the following: -

Descripti on: Knowledge of Fuel Handling System design feature(s) and/or interlock(s)

Fuel protection from binding and dropping Question :

Consider the following:

- Unit 2 is in Mode 6

- Refueling is in progress and

- The crane operator on the Main Refueling Machine Bridge has grappled onto a fuel assembly raised it into the Upper Grapple Operating Zone (UGOZ)

- The crane operator now inadvertently takes the Grapple Handswitch to OPEN The fuel assembly will NOT become ungrappled due to _ _ _ __ _ __ _ __

A. a mechanical interlock between the grapple and the hoist box

• B. a mechanical interlock between the hoist box and the upper end fitting on the fuel C. an electrical interlock betweem the hoist box and the bridge positioned over the core D. an electrical interlock between the grapple and the hoist height in the UGOZ with weight on the crane Answer:

D. Correct Notes:

the grapple form rotating. In the The mechanical interlock is when the Grapple is inside the Hoist box which physically prevents UGOZ the grapple is out of the hoist box to allow rotation.

Referenc es:

11 , section 2.2.6.2 pages 20 and 21 STM 2-51-1, Main Refueling Bridge and Reactor Building Fuel Handling Equipment, Rev Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 109

Data for 2014 NRC RO/SRO Exam 20-Dec-13

• Bank: [2018 : Rev: ~ Rev Date: :12/10/2013 2:01 :0 [ QID #:

Lie Level: LD Difficulty: ~ Taxonomy: LBJ Source:

Search [1940012139 System

Title:

[Generic

[ 10CFR55: ~ 1.10 / 43 . 5 / 45 . 12 L_.__

94 Author:

NEW

~~~~-:::::====:::---~~~~~

[ SafetyFunction

~ System Number [GENERIC [ KIA i 2.1.39 foster Tier: =2J Group: ~ RO Imp: I 3.6 , SRO Imp: 43 L. Plan: ; A2LP-RO-NIMAL I OBJ [ 3

Description:

[conduct of Operations - Knowledge of conservative decision making practices.

Question:

In accordance with EN-OP-115 , Conduct of Operation, which of the following would be considered a NON-conservative decision making practice?

A. Reducing reactor power after a loss of the plant computer B. Re-energizing a Vital switchgear during an EOP after a potential fire on the bus C. An implementation plan being changed due to degrading trends D. Validating available information prior to taking any time critical actions Answer:

B. Correct

• Notes:

Based on EN-OP-115, Conduct of Operation, section 5.3 which describes the thought process utilized for making conservative decisions. Re-energizing a deranged electrical bus, even during implmentation of an EOP, would not be a prudent action without having the bus inspected first.

References:

EN-OP-115 , Conduct of Operation, Rev 014, section 5.3 page 22 of89 Historical Comments:

• Form ES-401 -5 Written Exam Question Worksheet 110

21-Dec-13 Data for 2014 NRC RO/S RO Exam

• Bank: 12019 I Rev:

Lie Level: m Search j1940012101

[2J Rev Date: 112/10/2013 12:58: I QID #:

Difficulty:

System

Title:

jGeneric OJ Taxonomy:((] Source: I I 10cFR5 5: j41.10 I 45.13 95 Author:

NRC Bank QID #I 71 I I Safety Functio n I System Number jGENERIC I KIA I foster 2.1.1

[ID L. Plan: I A2LP-RO-ARCSA I OBJ ~-5~

Tier: [}]Gro up: [}] RO Imp: []}] SRO Imp:

ents.

Description:

jconduc t of Operations - Knowledge of conduct of operations requirem Questio n:

Consider the following:

- Unit 2 is operating at 100% power

- A Loss of Stator Water Cooling has occurred

- Main Turbine Generator (MTG) runback is in progress and the brief must be The CRS would perform the Reactivity Brief as directed by ~~~

~~~

~~~

~~~

performed initiation of the maneuver. .

A. COPD-030, ANO Reactivity Management Program; before B. COPD-030, ANO Reactivity Management Program; following

• C. COPD-032, Transient Conduct of Operations; before D. COPD-032, Transient Conduct of Operations; following Answer:

D. Correct Notes:

20.0, step 20.3 page 28 of 41]

COPD-032 contains guidance for briefs requirements during transients [section

References:

41 and 20.0 page 28 of 41 COPD-032, Transient Conduct of Operations, Rev 003 section 6.0 page 10 of Historic al Comme nts:

NRC Bank QID # 1711 not used on a NRC Exam

• Form ES-401-5 Written Exam Questio n Worksh eet 112

20-Dec-/3 Data for 2014 NRC RO/SR O Exam

• [TI foster Bank: 12020 I Rev: Rev Date: 112/1 9/2013 5:25:3 I QID #: 96 Author:

Lie Level: ~ Difficulty: I 3 l Taxonomy:[ [ ] Source: l NEW Search 11940012214 I t0CFR55: 141.10 I 43 .3 I 45 .13 Safety Function System

Title:

JGeneric  ! System Number JGENERIC I KIA l 2.2.14 Tier: ITJ Group: [JJ RO Imp: ~ SRO Imp: ~ L. Plan: l A2LP-RO- ESPT A J OBJ l 3 or status.

Descriptio n: !Equipment Control - Knowledge of the process for controlling equipment configuration Question:

by use of the normal During an off normal event (AOP or EOP), plant configuration control _ _ required to be maintained prior to exiting, to ensure eSOMs programs (i.e. ESL, Station log, etc ...). A review of the AOP or EOP is performed, configuration control _ __ _ _ __

A. 1s; was maintained B. is; has been regained C. is not; was maintained D. is not; has been regained Answer:

D. Correct Notes:

the implementation of Configuration control is desired at all times but the formal tracking of components is not required during review of procedures ACAs, AOPs, or EOPs. Configuration control will be re-established post event by performing a detailed used and actions taken.

References :

OP-1015.02 1 , AN0-2 EOP/AOP User Guide, Rev 011 , section 9. 1.6, page 47 of73 22 of 41 COPD-032 , Transient Conduct of Operations , rev 003 , section 11 .0 page 21 of 41 , and section 12.0 page Historical Comments :

• Form ES-401-5 Written Exam Question Workshee t 112

20-Dec-13 Data for 2014 NRC RO/SRO Exam

• Bank: J2021 : Rev: [ ] ] Rev Date: 110/22/2013 11:28: j QID #: 97 Author: foster Lie Level: [}] Difficulty: OJ Taxonomy: ~ Source: 1 NEW Search 11940012217 j toCFRSS : 141.7 / 41.10 / 43.5 / 45 . l SafetyFu nction System

Title:

jGeneric  : System Number :GENERIC I KIA I 2.2.17 Tier: [JJ Group: LIJ RO Imp: ~ SRO Imp: QI] L. Plan: i ASLP-RO-MNTC J OBJ J 13 activities during power operations,

Description:

JEquipment Control - Knowledge of the process for managing maintenance operator.

such as risk assessments, work prioritization, and coordination with the transmission system Question :

[REFERENCE PROVIDED]

Consider the following :

- Unit 2 is operating at 100% power

- 2P-35A, "A" Spray pump, is OOS for maintenance

- Annunciator 2K04 K-2 "EFS Process System INOP" is in alarm

/D

- The lights are OUT for 2CV-1510-2, Service Water to Containment Fan Coolers 2VSF-1C

- IAO reports 2B63-E5, 480 V AC vital breaker for 2CV- l 5 l 0-2, is tripped

- The EOOS computer program has been taken out of service by the Safety Analysis Group Which of the following Risk Categories would apply to these conditions?

• A. Green; Minimal Risk B. Yellow; Acceptable Risk C. Orange; High Risk D. Red; Unacceptably High Risk Answer:

C. Correct Notes:

containment cooling train) as a COPD-024 Att. 2 table 7 designates this configuration (1 containment spray train and one ORANGE risk level

References:

COPD 24, Risk Assessment Guidelines, Attachment 2, Table 7 page 32 of 82 OP-2203 .012D, Annunciator Corrective Actions, 2K04 window K-2, Rev 036, page 23 of94 Provide COPD 24 Attachment 2 as a reference Historica l Commen ts:

• Form ES-401-5 Written Exam Question Workshe et 113

20-Dec-13 Data for 2014 NRC RO/SRO Exam

• Bank: 12022 : Rev: 1 o : Rev Date: !1011112 01311 :12: I QID#: ~LJ Author : foster Lie Level: [TI Difficu lty: I 3 I Taxono my:[E J Source : I NEW Search 119400 I 23 I 4 [ 10CFR 55: 141.12 I 43 .4 I 45 .10 I Safety Functio n

! System Numbe r :GENE RIC ! K/A I 2.3 .14 System

Title:

!Generic Tier: [ [ ] Group: [JJ RO Imp: ~ SRO Imp: I 3.8 I L. Plan: I ASLP-RO-RADP I OBJ ! -~ L_

that may arise during normal, Descrip tion: Radiological Controls - Knowledge ofradia tion or contamination hazards abnormal, or emergency conditions or activities.

Questio n:

g crew to log onto the Emergency Radworker Permit What is the LOWE ST Emergency Classification that requires the operatin (RWP) ?

A. Notification of Unusual Event B. Alert C. Site Area Emergency D . General Emergency Answer :

B. Correct Notes:

OP-1903 .01 lM Referen ces:

046, form M section 6.0 OP-1903.011 , Alert emergency Direction and Control Checklist, Rev Histori cal Comme nts:

• Form ES-401 -5 Written Exam Questio n Worksh eet 114

2 l-Dec-1 3 Data for 2014 NRC RO/SRO Exam

• Bank: 12023 I Rev: [}] Rev Date: 110/22/2013 8:29:5 I QID #:

Lie Level: [}]Dif ficulty :[}] Taxono my:[![] Source: I Search 11940012423 System

Title:

!Generic j 10CFR5 5: 141.10 / 43.5 / 45.13 I 99 SafetyF unction I System Number Author:

NEW IGENERIC j KIA I foster 2.4.23 Tier: [JJ Group: [JJ RO Imp: [I3J SRO Imp: [ID L. Plan: I A2LP-RO-EFRP I OBJ I 3 ing emergency procedure implementation Descrip tion: Emergency Procedures/Plan - Knowledge of the bases for prioritiz during emergency operations.

Questio n:

Consider the following:

- An event has occurred on Unit 2

- OP-2202 .009, Functional Recovery EOP, entry section has been completed with the following status:

- Reactivity - SATISFIED

- Maintenance of Vital Aux (DC) - SATISFIED

- Maintenance of Vital Aux (AC) - SATISFIED

- RCS Inventory Control - CHALLENGED

- RCS Pressure Control - CHALLENGED

- RCS/Core Heat Removal - SATISFIED

- Containment Isolation - JEOPARDIZED

• - Containment Temp/Press Control - JEOPARDIZED Which list is the correct order the CRS would address each safety function?

RCS/Core Heat A. Reactivity, Maintenance of Vital Aux (DC), Maintenance of Vital Aux (AC),

Control, Containm ent Isolation ,

Removal, RCS Inventory Control, RCS Pressure Containment Temp/Press Control ent B. RCS Inventory Control, RCS Pressure Control, Containment Isolation, Containm Reactivi ty, Mainten ance of Vital Aux (DC), Mainten ance of Vital Temp/Press Control, Aux (AC), RCS/Core Heat Removal RCS/Core Heat C. Reactivity, Maintenance of Vital Aux (DC), Maintenance of Vital Aux (AC),

Inventor y Control, Removal , Containment Isolation, Containment Temp/Press Control, RCS RCS Pressure Control Control, D. Containment Isolation, Containment Temp/Press Control, RCS Inventory RCS Pressure Control, Reactivity, Maintenance of Vital Aux (DC), Mainten ance of Vital Aux (AC), RCS/Core Heat Removal Answer :

D. Correct Notes:

e safety functions in an order of most After completing the entry section, the Functional Recovery procedure will prioritiz e: Reactivity is SAT; Maintenance of Vital endangered Ueopardized) With the above conditions the student should determin CHALLENGED; RCS Pressure Control Aux (DC) SAT; Maintenance of Vital Aux (AC) SAT; RCS Inventory Control Form ES-401 -5 Written Exam Q uestion Worksh eet 117

21-Dec -l 3 Data for 2014 NRC RO/SRO Exam

• CHALLENGED; RCS/Core Heat Removal SAT; Containment Isolatio JEPORIDIZED.

References:

OP-2202.009, Functional Recovery, Rev 015, entry section step 13.C.,

OP-2202.009, Functional Recovery, Rev 015, Success Path Trackin g n JEPORIDIZED; Containment Temp/Press Control page 15 of 43 Page, page 28 of28 014, step 13.C., page 20 of372 EOP-2202.009, Functional Recovery Tech Guide, Rev section 5.7, pages 20 and 21 of73 OP-1015.021, AN0-2 EOP/AOP User Guide, Rev 011, Attachm ent A, page 50 of73 OP-1015.021 , AN0-2 EOP/AOP User Guide, Rev 011, Historical Comments:

• Form ES-401-5 Written Exam Question Worksheet ))8

Data for 2014 NRC RO/SR O Exam 21-Dec-13

• I Bank: 12024 Rev:[} ] Rev Date: !J0/3012013 10:00:

Lie Level: [}] Difficult y:ITJ Taxonom y:[![] Source:

Search ~940012428 System

Title:

jGeneric I QID#:

! JOCFR55: !41.10/43:.?._/45.13 I I

JOO Safety Function Author:

NEW ISystem Number [GENERICj KIA I foster 2.4.28 I Tier: [JJ Group: [JJ RO Imp: [IT] SRO Imp: @] L. Plan: [A2LP-R O.ASEC '] OBJ I 5&7 I

Description:

Emergency Procedures/Plan- Knowledge of procedures relating to a security event (non-safeguards infonnation).

Question :

Consider the foJlowing:

• Unit 2 is operating at I00% power

• Security has infonned the control mom that a Hostile Action is occurring WITHIN the Owners Controlled Area

- OP-2203.048, Security Event AOP has been entered

- Security has now infonned the control room that a Hostile Action is occurring WITHIN the Protected Area

- The Reactor has been tripped IA W section I of OP-2203.048, Security Event AOP At the end of SPTAs, the Core Heat Removal Safety Function is being accomplished by _ _ _

_ circulation and the emergency classification will be performed u s i n g - - - - - - -

A. natural; OP-2203.048, Security Event AOP, Attachment C B. forced; OP-2203.048, Security Event AOP, Attachment C C. natural; OP-1903.01 lY, Emergency Response/Notification fonn D. forced; OP-1903.011 Y, Emergency Response/Notification fonn Answer:

B. Correct Notes:

References:

OP-2203.048, Security Event AOP, Rev 025, section I page 7 !llld section 1page13 [With hold From Puplic Disclosure]

OP-2202.001, Standard Post Trip Actions, Rev 014, step 7.A page 8of19

• Historical Comments:

Form ES-401-S Written Exam Question Workshe et

/J9