Text

Initial Exam 2008-301 Draft RO Written Exam
	ML092940704
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	50-413/08-301, 50-414/08-301
	Download: ML092940704 (151)
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U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: CATAWBA Region: I C0 (i) III IV Reactor Type: (ij)

(vi) CE BW GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination Questio-n-B-an-k-#~K-A-_-sy-s*t-e-m---'-K-A-_-nu-m-b~er*--~

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1 D 507 EPE007 EK2.03

~;:l::;e-o;the Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7/ 7)D-R-ea-ct-or-tr-iP-st-at-us-p-an-el~~-~

45. 7) 0 Reactor trip status panel 41.7/45.

.......................................... ~~I Unit 1 is at 100% reactor power.

Four hours ago:

PZR Level Select Switch was in the 3-2 position

PZR level channel 1 failed HIGH

All actions required by Technical Specifications were completed to allow continued unit operation.

Following the receipt of several annunciators, the following items are noted:

1EDC has lost power

1FO-1, B/6 (PZR Hi Level RX Trip) is LIT and RED

DRPI indicates all control rods above insertion limits Which one of the following describes:

1. The current condition of the plant and

2. The correct operator action to take for the above evolution?

A. 1. Anticipated Transient Without Scram (A TWS)

2. Manually trip the reactor B. 1. Anticipated Transient Without Scram (A TWS)

2. Perform a shutdown per OP/1/A/61 00/003 (Controlling Procedure for Unit Operation)

C. 1. Reactor Protection System (RPS) failure

2. Manually trip the reactor D. 1. Reactor Protection System (RPS) failure

2. Perform a shutdown per OP/1/A/61 00/003 (Controlling Procedure for Unit Operation)

DRAFT Wednesday, October 08, 2008 Page 1 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 1 D General Discussion OMP 1-7 General Statements of Philosophy:

An ATWS (Anticipated Transient Without Scram) is defined in 10CFR50.62 as an anticipated operational occurrence followed by the failure of the reactor trip portion of the protective system. To have an ATWS there must be a transient followed by a failure of the reactor trip breakers.

Instrument failures, by themselves, are not necessarily transients. For example, if one channel of Pressurizer Pressure was out of service for preventive maintenance (bistable in tripped condition) and another Pressurizer Pressure channel failed (not the controlling channel), a reactor trip signal would be generated. If the reactor failed to trip, this would be a failure of the reactor trip breakers and the automatic trip features of the reactor protection system and not an ATWS event. (PPRB OPS-9283)

Also, OTDT runback would occur if rods are in AUTOMATIC Answer A Discussion Plausible: An invalid reactor trip is present as defined by OMP 1-7. To manually trip the reactor would be correct if it was a valid reactor trip.

Answer B Discussion Plausible: An invalid reactor trip is present as defined by OMP 1-7 This is not an ATWS. The shutdown would be correct due to being in TS required shutdown.

Answer C Discussion Plausible: This is a failure of the RPS system per OMP 1-7 To manually trip the reactor would be correct if it was a valid reactor trip.

Answer D Discussion

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~RRECT Job Level R_O ____~ _____

____ _____C__

Cognitive Level

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QuestionType

_____ L_ _ _M_O_D

_ L_ _ _ __IF_IE_D__~_________________

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__ ________________2_0_06 Question Source

__N_R_C_Q__

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__l_(_B_an_k_6_0_7_)______ ~~_

l_(_B_an_k_6_0_7_)________ -

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~ Developed Development References Student References Provided EPINTR013 D OPT Approved OMP 1-7 TS 3.3.1 D OPS Approved D NRC Approved ~-------------------------

QuestionBank # KA_system 507 EPE007 EK2.03 Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 / 45. 7) 0 Reactor trip status panel Wednesday, October 08, 2008 Page 2 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA QuestionBank # IKA system IKA number JI QUESTION 2 D 508 I EPE009 I EA2.10 I Unit 1 was in Mode 3 at full temperature and pressure with all control and shutdown banks inserted. Operators note the following:

1RAD-1 , B/3 "1EMF41 AUX BLDG VENT HI RAD" - LIT

1AD-13, A/1 "NO & NS ROOMS SUMP LEVEL EMERG HI" - LIT

"SAFETY INJECTION ACTUATED" status light - LIT Which one of the following states the correct procedure flowpath that will address this event?

A. AP/1/A/55001027 (Shutdown LOCA)

AP/1/A/55001019 (Loss of Residual Heat Removal System)

B. AP/1/A/55001027 (Shutdown LOCA)

AP/1/A/55001010 (Reactor Coolant Leak)

C. EP/1/A/5000/E-O (Reactor Trip or Safety Injection)

EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization)

D. EP/1/A/5000/E-O (Reactor Trip or Safety Injection)

EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

EP/1/A/5000/ECA-1.2 (LOCA Outside Containment)

Wednesday, October 08, 2008 Page 3 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 D General Discussion The EMF in alarm is the key to a LOCA outside containment with the sump level providing confirmation. Choices Band C are for LOCAs IN containment. Choices A and B are for shutdown conditions as stated in AP/27 which do not apply to this situation based on the stem.

Answer A Discussion He may interpret "shutdown" in the title as Mode 3. This is a common point of confusion. When AP/27 is used, it does transition for this situation to API 19 Answer B Discussion There is a transition to APII 0, however he should realize it's a LOCA outside containment based on EMF-41 and NDINS sump room.

Answer C Discussion This is a valid EP flowpath for a leak in the NCS. But not for a LOCA outside containment.

Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided OPIlIB161 0010 lOX o OPT Approved AP/lIAl55001027 EP/lIAl50001E-l OOPS Approved EP/lIAl5000IECA-1.2 o NRC Approved QuestionBank # JKA system KA number I 50SiEPE009 EA2.10 I

~K_A~d_e_s_c__________________________________________________________________________________ -------I Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 I 45.13)OAirborne activity I L"L"'_"_"'_"'L"_"'_"_"'_"_"'_"_"'_"'_"_

- - _** _***_** _._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~

Wednesday, October 08, 2008 Page 4 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA IKA_number number II QUESTION 3 A 509 I EPEOll JI 2.4.30 iI KA KA desc EPEOll GENERICDKnowiedge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.1 0/43.5 /45.11)

Given the following events:

A Large Break LOCA has occurred on Unit 2

All equipment functioned as designed

The OSM has declared an Alert

A signed Emergency Notification Sheet has been handed to you for transmittal Which of the following is a complete list of agencies required to be contacted within 15 minutes of the declaration of the Alert?

A. State and county warning points B. State warning points and NRC Operations Center C. County warning points and NRC Operations Center D. State and county warning points and the NRC Operations Center Wednesday, October 08, 2008 Page 5 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 3 A General Discussion 15 minute notifications do not include NRC, but are the state and county warning points.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2005 NRC Q75 (Bank 479)

Development References Student References Provided

~ Developed RP/OIA/50001006A rev30 D OPT Approved RP/OIA/50001001 rev 18 OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 5091EPEOIl 12.4.30 I1 KA desc

---~~--~~~~~--~~~~~~~----~~~~----~----~~~--~~--~----~--------------~

BPEOll EPEOll GENERICDKnowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11)

Wednesday, October 08, 2008 Page 6 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # [KA system [KA number [

QUESTION 4 A 510 I APE022 I AK1.02 I KA desc Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8 /41.10/

45.3)ORelationship of charging flow to pressure differential between charging and RCS ................................ .

Given the following initial conditions:

1NV-294 (NV Pmps A&B Disch Flow Ctrl) in MANUAL

1NV-309 (Seal Water Injection Flow) in MANUAL

pressurizer pressure is 2235 psig

total seal water flow is 32 gpm

charging line flow is 89 gpm If pressurizer pressure is increased to 2300 psig, which one of the following sets of system parameter changes is correct?

A. Charging line flow decreases and total seal water flow decreases B. Charging line flow decreases and total seal water flow remains the same C. Charging pump discharge header pressure increases and total seal water flow increases D. Charging pump discharge header pressure increases and total seal water flow remains the same Wednesday, October 08, 2008 Page 7 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 4 A General Discussion Lc_e_n_tr_ifi_ug_a_l_p_u_m_p_l_a_w_s_re_q_u_ir_e_t_ha_t_t_he_d_is_Ch_ar_ge_h_ea-",d,-e~r Lc_e_nt_r_ifi_ug_a_l_p_u_m_p_l_aw_s_re_q_u_ir_e_t_ha_t_t_he_d_is_ch_ar_ge_he_a--=dLe->r ~p_re_s_su_r_e_in_c-,re,,-as-,-es_a_n_d_fl_o_w_dLeLcrLe_as_e_s_as_sy_s_te_m_p_re_s_su_r_e_i_nc_r_ea_s_e_s._T_he_r_eD_o_re_chargiili]

,,-p_re_s_su_r_e_in_c-,roceas line flow and total seal flow will decrease while charging line discharge pressure increases.

___es_a_n_d_fl_o_w_d_e_cr_e_as_e_s_as_sy_s_te_m_p_re_s_su_r_e_i_nc_r_e_as_e_s._T_h_er_e_fo_r_e chargiili]

Answer A Discussion ICORRECT Answer B Discussion Incorrect: total seal flow decreases because INV-309 is in manual.

Answer C Discussion Incorrect: total seal flow decreases. May think higher discharge pressure = more seal flow.

Answer D Discussion Incorrect: total seal water flow decreases because INV-309 is in manual.

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2005 NRC Q6 (Bank 410)

~ Developed Development References Student References Provided THFFF 12 thru THFFF 15 o OPT Approved OOPS Approved o NRC Approved QuestionBank #jKA # IKA system IKA IKA number I

~_ 510lAPE022 IAK 1. 02 JI KA KA desc Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8 / 41.10 /

45.3)DRelationship of charging flow to pressure differential between charging and RCS ................................ .

Wednesday, October 08, 2008 Page 8 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA 511 I APE025 IKA number I 2.4.30 I

I QUESTION 5 c KA desc APE025 GENERlCOKnowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5 /45.11)

Unit 1 was in Mode 5 preparing to enter Mode 6.

Given the following:

Both trains of NO have been lost.

The crew entered AP/1/A/5500/019 (Loss of Residual Heat Removal System) but actions to restore cooling have failed.

The OSM has determined an immediate need to take an action per 10CFR50.54(X).

Per 10CFR50.54(x):

1. Is notification to the NRC Operations Center required prior to taking the action?

2. How many SROs (in total) are required to agree prior to taking the action?

A. 1. Yes

2. One B. 1. Yes

2. Two C. 1. No

2. One O. 1. No

2. Two Wednesday, October 08, 2008 Page 9 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 5 c General Discussion 50.72 "The licensee shall activate the Emergency Response Data System (ERDS)4 as soon as possible but not later than one hour after declaring an Emergency Class of alert, site area emergency, or general emergency".

OMP 1-73. The licensee shall notify the NRC Operations Center by ENS telephone of emergency circumstances requiring the licensee to take any protective action that departs from a license condition or technical specification as permitted by the preceding paragraphs. When time permits, the notification must be made before the protective action is taken; otherwise, the notification must be made as soon as possible thereafter. The Commission may require written statements from a licensee concerning its action. Also, the licensee should notify the Resident NRC Inspector as soon as practical.

Per 10cfr5054x, only one SRO is required to make the determination and take action per the CFR. OMP 1-7 says for situations not covered by procedure, 2 are required.

Answer A Discussion I

1 ________~

Answer B Discussion

~I_ _ _ _ _ _ _ _ _ _ _ _ _ _~~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I

~IAnswer

_1 C Discussion

__I Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided OMP 1-7 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 511 APE025 2.4.30 KA desc APE025 GENERICDKnowledge of events related to system operation/status that must be reported to internal organizations or external

_I' agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.) 0/43.5/45.) 1)

Wednesday, October 08, 2008 Page 10 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number JI QUESTION 6 A 512 I APE026 I AA2.03 I KA_desc KA desc Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/ 45.13)DThe valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition ..................

Unit 1 was operating at 100% with "A" Train KC in service. Given the following:

An 86N relay actuated on 1ETB two minutes ago

A major KC system piping leak has occurred in the Auxiliary Building non-essential header

1AD-1 0, N1 "KC SURGE TANK A LO-LO LEVEL" - LIT

1AD-10, N2 "KC SURGE TANK B LO-LO LEVEL" - LIT

The crew has entered AP/1/N5500/021 (Loss Of Component Cooling)

Assuming all automatic actions have occurred, which one of the following correctly lists the major KC headers that are currently being cooled?

A. KC Train A essential header only B. KC Train A essential header and the Reactor Building non-essential header C. KC Train A essential header and KC Train B essential header D. KC Train A essential header, KC Train B essential header and the Reactor Building non-essential header Wednesday, October 08, 2008 Page 11 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 6 A General Discussion An 86N locks out the essential bus, therefore, B train KC pumps are off and the B train header isolation vlaves will not close. The Reactor building header shares common piping with the AB non-ess header. Both non-essential headers are isolated based on low KC surge tank levels due to the piping rupture.

Answer A Discussion Answer B Discussion If student thinks that the Rx Building header is not isolated since the leak is on the AB header. Although its diffvalves for purposes of leak isoaltion they are identical.

Answer C Discussion IIf student thinks the DIG re-energizes IETB Answer D Discussion IBoth Band C above for psychometric balance.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed 0

0 OPT Approved OPS Approved API 1/Al55001021 PSSKC

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0 NRC Approved L -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ ~_____________________j QuestionBank # IKA system IKA IKA number II 512IAPE026 5121APE026 IAA2.03 I KA desc Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 I 45.13)OThe valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition ................. .

Wednesday, October 08, 2008 Page 12 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system I~number I QUESTION 7 B 513 I APE027 I AAI.04 I KA desc Ability to operate and / or monitor the folIowing as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7/45.5/

45.6)DPressure recovery, using emergency-only heaters .....................

Given the following:

The SSF has been manned due to a fire in the cable spreading room.

During the course of SSF operations a head vent stuck in the open position for a short period of time and then reclosed.

You have been directed to increase NC pressure using heaters.

1. Why is pressure recovery slower from the SSF than from the Control Room?

2. How are the heaters available from the SSF secured should Pzr level drop below 17%?

A. 1. Only a portion of the D heaters are available from the SSF

2. Automatically B. 1. Only a portion of the D heaters are available from the SSF

2. Manually C. 1. Only A and B heaters are available from the SSF

2. Automatically D. 1. Only A and B heaters are available from the SSF

2. Manually Wednesday, October 08, 2008 Page 13 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 7 B General Discussion Only a portion ofD heaters are available from the SSF. The OP for SSF operations has numerous cautions about having to manually sercure those heaters should leve drop below 17%. A&B heaters are available from the ASP.

Answer A Discussion lfirst part is correct.

~. -- -- -- ------------------- -- ---- - - - - -- --------------------- -- ---- - - - -- --------------------- --

J Answer B Discussion iCORRECT ~

Answer C Discussion The A and B heaters would automatically secure but are available from the ASP not the SSF Answer D Discussion isecond part is correct Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided OP/O/B/610010 13 o OPT Approved PSILE OOPS Approved o NRC Approved QuestionBank # KA_system SI3APE027 AAI.04 Ability to operate and I or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 I 4S.S I 4S.6)OPressure recovery, using emergency-only heaters .................... .

Wednesday, October 08, 2008 Page 14 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKAIKA_number number II QUESTION 8 D 514 I EPE029 I 2.4.34 I KA desc EPE029 GENERlCDKnowledge ofRO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13)

Which one of the following is a complete list of breakers directed to be opened per EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATWS) to trip the reactor locally?

1. Reactor Trip Breakers RTA and RTB

2. Reactor Trip Bypass Breakers BYA and BYB

3. CRO/MG "Motor" Breakers

4. CRO/MG "Generator" Breakers A. 1 B. 1 and 2 C. 1,2 and 3 O. 1,2,3,and4 Wednesday, October 08, 2008 Page 15 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 8 D General Discussion Nonnally the OSM will directed the non affected Units BOP to go open these breakers to minimize the time the Reactor stays critical. RO's know it takes only opening one breaker to trip the reactor. ]

Answer A Discussion Incorrect: EP!1IA/SOOIFR-S.l requires opening all the breakers. Plausible: Students knows only one breaker needs to be open to trip the reactor.

Answer B Discussion Incorrect: EPI1!A/SOOIFR-S.l requires opening all the breakers. Plausible: Immediate actions ofEPI1!A/SOOO/E-O verify that Reactor Trip breakers and Reactor Trip Bypass Breakers are opened.

Answer C Discussion Incorrect: EPI1!A/SOOIFR-S.l requires opening all the breakers. Plausible: If opening the Reactor Trip and Bypass Breakers doesn't trip the Reactor then opening the MG set breakers will cause the rods to fall.

Answer D Discussion ICorrect Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed FR-S.l 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I S141EPE029 12.4.34 1 KA desc EPE029 GENERIC 0 Knowledge ofRO tasks perfonned outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10! 43.S! 4S.13)

Wednesday, October 08, 2008 Page 16 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system 515 I EPE038 IKA number I EK1.02 I

I QUESTION 9 c KA desc Knowledge of the operational implications ofthe following concepts as they apply to the SGTR: (CFR 41.8/41.10/ 45.3)DLeak rate vs.

pressure drop ...................................... ..

Given the following:

Unit 1 and 2 are operating at 100%

One single steam generator tube fully shears on each unit

The crews are responding per EP/1 (2)/A/5000/E-3 (Steam Generator Tube Rupture), preparing to perform the initial reactor coolant system cooldown to the required core exit thermocouple temperature using steam dumps.

Based on the differences between Unit 1 and Unit 2 steam generator design:

1. Which unit would have a lower primary system equilibrium pressure?

2. Which unit will have a faster cooldown rate?

(Assume identical cores and steam dump performance.)

A. Unit 1 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate.

B. Unit 1 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate.

C. Unit 2 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate.

D. Unit 2 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate.

Wednesday, October 08, 2008 Page 17 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 9 c General Discussion Unit 1 has smaller tubes and larger surface area, therefore the leakage would be less on Unit 1 causing Unit 2 to have a larger pressure drop to equilibrium and assuming dumps are fully opened for the initial NC cooldown, Unit 1 would cooldown faster.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2005 NRC Q69 (Bank 473)

~ Developed Development References Student References Provided STMSGIO o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 515EPE038 EK1.02 KA desc ======l

~~~~:dJ;o;f~~~.~:'~~~~~~~~I.. ~::.~~~~~~~ns of the following concepts as they apply to the SGTR: (CFR 41.8/41.10/ 45.3)OLeak~~

Wednesday, October 08, 2008 Page 18 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 10 B 516 I APE057 1 AA2.13 l

KA desc Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5 I 45.13)OVCT level and pressure indicators and recorders ., ....................

Unit 1 is operating at 100%. 1ERPA is lost. What effect does this have on VCT auto makeup capability and VCT level indication in the control room?

Auto Makeup Level Indication A. Available Available B. Unavailable Available C. Available Unavailable D. Unavailable Unavailable Wednesday, October 08, 2008 Pa!!:e 19 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 10 B General Discussion Vital has no effect on level indication. Lost ofERPA will cause the Rx MIU pumps to not start in auto or manual. This makes auto makeup be lost.

Answer A Discussion Incorrect for makeup but correct for indication Answer B Discussion

[CORRECT Answer C Discussion Incorrect for makeup and for indication.

Answer D Discussion Correct for makeup but incorrect for indication.

Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed API 1/Al55001029 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 5l6iAPE057 lAA2.l3 I KA desc Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5 I 45.l3)OVCT level and pressure indicators and recorders ..................... .

Wednesday, October 08, 2008 Page 20 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system IKA_number I QUESTION 11 c Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7 / 45.5/ 45.6)0 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector ............................ .

Given the following:

1ERPD has been de-energized due to a blown fuse on inverter 1EID.

The crew has implemented AP/1/A/55001029 (Loss of Vital or Aux Control Power).

The fuse has been replaced and the CRS wishes to re-energize 1ERPD from 1EID.

Which one of the following correctly states the minimum acceptable wait time prior to inverter restart and the sequence for operation of inverter 1EID DC input breaker and AC output breaker?

A. 1. 5 seconds

2. Close the DC input breaker and then close the AC output breaker B. 1. 5 seconds

2. Close the AC output breaker and then close the DC input breaker C. 1. 60 seconds

2. Close the DC input breaker and then close the AC output breaker D. 1. 60 seconds

2. Close the AC output breaker and then close the DC input breaker Wednesday, October 08, 2008 Page 21 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 11 c General Discussion Per OP L&P 60 sec wait must occur. 5 seconds is the requried precharge time.

Answer A Discussion ITime is incorrect.

Answer B Discussion

!Both time and order are incorrect.

Answer C Discussion Icorrect Answer D Discussion The order of the AC and DC breakers are reversed Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed EPL 0 OPT Approved API 1/Al55001029 OPIlIAl6350100S Al63501008 0 OPS Approved 0 NRC Approved QuestionBank # #[KA

[KA system IKA

[KA number I 5171APE05SjAA1.02 5171APE058 IAA 1. 02 I KA desc Ability to operate and I or monitor the following as they apply to the Loss of DC Power: (CFR 41.7 I 45.5 I 45.6)0 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector ............................ .

Wednesday, October 08, 2008 Pal!e 22 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 12 A 518 I APE062 I AK3.03 I

KA desc Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 ! 45.7 )OGuidance actions contained in EOP for Loss of nuclear service water ....

Both units were at 100% with 2A RN Pump in service when the following annunciators were received:

1AD-12, E/2 "RN PIT A SWAP TO SNSWP" - LIT

2AD-12, E/2 "RN PIT A SWAP TO SNSWP" - LIT

1AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL - LO" - LIT

2AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL - LO" - LIT During the recovery 2RN-48B (RN Supply X-Over Isol) was re-opened, however 1RN-48B (RN Supply X-Over Isol) could not be re-opened.

What is the minimum time the crew must wait following receipt of the above annunciators prior to securing any RN Pumps and what is the minimum number of RN Pump(s) required to ensure flow to both essential train headers on both units?

A. 2 minutes; 1 pump B. 2 minutes; 2 pumps C. 5 minutes; 1 pump D. 5 minutes; 2 pumps Wednesday, October 08, 2008 Page 23 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 12 A General Discussion AP/20 states that valves and pumps cannot be manipualted for 2 minutes following the autostart on pit level. (5 minutes is the time for the YV swap.) Only one ofthe B train crossovers is required to ensure flow to all essential headers, however, both close on the low pit level and student must remember that only one is required. Since normal alignment is all crossovers open, student may assume they are both required open to get flow to the opposite unit header.

Answer A Discussion ICORRECT Answer B Discussion ICorrect time, wrong number of pumps Answer C Discussion IWrong time, correct number of pumps Answer D Discussion Both incorrect - for psychoimetric balance

=

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided AP120 o OPT Approved RN lesson OOPS Approved NRC Approved QuestionBank # IKA system IKA IKA_number number JI 5181APE062 IAK3.03 I KA desc Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 145.7 )DGuidance actions contained in EOP for Loss of nuclear service water ....

Wednesday, October 08, 2008 Page 24 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA QuestionBank # IKA_system system IKA IKA number II QUESTION 13 B 519 II APE065 1I AK3.03 I

KA desc Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: (CFR 41.5,41.10 145.6/45.13)DKnowing effects on plant operation of isolating certain equipment from instrument air .....................................

Given the following:

One RL turnaround valve is manually pinned in place for mantenance

The crew has entered AP/O/A/55001022 (Loss of Instrument Air)

Operators have determined that the leak can be isolated but doing so will result in all RL turnaround valves losing VI.

The CRS has directed that the leak be isolated.

Which one of the following correctly states the effect that this will have on the RL turnaround valves and the equipment cooled by RL.

A. The unpinned RL turnaround valves will fail open resulting in more flow to the components supplied by RL.

B. The unpinned RL turnaround valves will fail closed resulting in more flow to the components supplied by RL.

C. The unpinned RL turnaround valves will fail open resulting in less flow to the components supplied by RL.

D. The unpinned RL turnaround valves will fail closed resulting in less flow to the components supplied by RL.

Wednesday, October 08, 2008 Page 25 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 13 B General Discussion The RL turnaround valves basically act as a false load to maintain header pressure. The valves fail closed which cause header pressure to increase and forces more flow through the other components. This is counterintuitive.

Answer A Discussion the valves fail closed. But logic would say that valves failing open woudlresult in> flow but nto the case due to system design.

Answer B Discussion J

iCORRECT Answer C Discussion iTrue ifthe valves DID fail open Answer D Discussion fail in right direction but the effect is reversed.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided RL D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA IKA number II 5191APE065 519iAPE065 AK3 .03

.iIAK3.03 iI KA desc Knowledge of the reasons for the following responses as they apply to the Loss ofInstrument Air: (CFR 41.5,41.10 / 45.6 /45.13)OKnowing effects on plant operation

__ ~~~

of isolating

__ ~~~

certain

__equipment from instrument

___ air ....................................

~~~~~~~--~~~---=~~--~~~~~~~~~--.~~-------------------------------------------.---

L-~~~~~~ ~~~_~~~~~ ~~ ________________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _

Wednesday, October 08, 2008 Page 26 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system

[KA system [KA number IKA_number I

[

QUESTION 14 D 520 II APE077 II AAl.OI I

KA desc Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CPR: 41.5 and 41.10/45.5, 45.7, and 45.8 )DGrid frequency and voltage .........................................................

Given the following:

Unit 1 is at 100% power with power factor at 0.99 lagging.

Operators are controlling power factor in manual due to the auto voltage regulator not controlling properly.

A major grid disturbance causes power factor to increase to slightly leading.

1. Which button on the voltage regulator is operated to bring power factor back to its original value?

2. What part of the generator is susceptible to overheating should power factor be erroneously adjusted to 0.8 lagging?

Reference provided A. 1. The "LOWER" button

2. The generator armature core end B. 1. The "RAISE" button

2. The generator armature core end C. 1. The "LOWER" button

2. The generator field D. 1. The "RAISE" button

2. The generator field Wednesday, October 08, 2008 Page 27 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 14 D General Discussion The RAISE button will cause power factor to decrease froma leading value to a lagging value. If the generator voltage is adjusted to severley lagging (.8) then it will be past the AB line on the Generator capability curve and field heating is a concern.

Answer A Discussion I.Both parts wrong, psychometric balance.

Answer B Discussion Wwrong gneerator component. This would be ifPF was severely LEADING.

Answer C Discussion LOWER will cause PF to go more lagging but lower seems logical, Correct generator aea Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided Generator Capability Curve (DataBook Curve 43) Databook Figure 43 (Generator Capability D OPT Approved RL Curve)

D OPS Approved D NRC Approved QuestionBank # \KA system \KA number \

520IAPE077 IAAl.OI IAAl.OI II KA desc Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10/45.5, 45.7, and 45.8 )OGrid frequency and voltage ........................................................ .

Wednesday, October 08, 2008 Page 28 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 15 D 521 I WE04 I EK2.2 I KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

(CFR: 41.7/ 45.7)DFacility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Unit 1 was operating at 100%. Given the following events and conditions:

0200 - reactor tripped due to a LOCA outside containment

0210 - crew enters ECA-1.2, (LOCA Outside Containment)

0220 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc)

0240 - The crew is at the step in ECA-1.1 to determine NC subcooling

Current conditions:

o NCS pressure is 1100 psig o 1B NC pump running o 1A, 1C, and 1D NC pumps secured o Reactor Vessel DIP is 20%

o 1 NI pump running, indicating 220 gpm o 1 NV pump running, indicating 385 gpm o Both ND pumps off o No NS pumps running o Subcooling is 35°F Which one of the following statements correctly describes the minimum required flow and which pump can be secured?

Reference provided A. 210 gpm, stop the running NV pump.

B. 210 gpm, stop the running NI pump.

C. 410 gpm, stop the running NI pump.

D. 410 gpm, neither pump may be secured at this time.

Wednesday, October 08, 2008 Page 29 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 15 D General Discussion Bank Question: 912.1 Time after trip is 40 minutes, graph starts at 10 minutes, flow required is 408 gpm Answer A Discussion Incorrect: required flow is 408 gpm Plausible: candidate misses the fact that the graph starts at 10 minutes; this is the 50 minute number Answer B Discussion ICorrect: required flow is 408 gpm, the NY pump is providing 410 gpm, and the NI pump may be stopped.

Answer C Discussion Incorrect: required flow is 408 gpm Plausible: candidate uses 30 minutes to determine required flow (time since diagnosis ofLOCA outside containment)

Answer D Discussion Incorrect: required flow is 408 gpm Plausible: candidate uses 20 minutes to detennine required flow (time since procedure entry)

Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2004 NRC Q26 (Bank 326)

~ Developed Development References Student References Provided Lesson Plan Objective: EP-EP2 SEQ 29 EP/IIAl50001ECA-l.l (Step 19)

D OPT Approved

References:

EP/IIAl5000IECA-I.1 (Enclosure 5)

1. ECA-l.l step 19 and Encl 5 - PROVIDED D OPS Approved D NRC Approved QuestionBank # IKA system IKA IKA number JI 5211WE04 !EK2.2 IEK2.2 I KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the foIJowing:

(CFR: 41.7 I 45.7)DFacility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Wednesday, October 08, 2008 Page 30 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA_number IKA number I QUESTION 16 D 522 WE05 EK3.1 I I I KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)

(CFR: 41.5! 4l.l0, 45.6, 45. 13) 0 Facility operating characteristics during transient conditions, includingDcoolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

A feedwater transient resulted in a reactor trip and the operating crew entered EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink) when all Auxiliary Feedwater flow was lost. Given the following:

S/G 1A wide range level- 31 %

S/G 1B wide range level - 20%

S/G 1C wide range level- 23%

S/G 1D wide range level - 28%

The BOP has just secured all the NC pumps

The OATC notes NC system pressure is increasing

1. Why have NC pumps been secured?

2. Why is NCS pressure increasing?

A. 1. To begin NCS bleed and feed

2. Due to NC temperature increase B. 1. To minimize heat input

2. Due to letdown being secured C. 1. To begin NCS bleed and feed

2. Due to letdown being secured D. 1. To minimize heat input

2. Due to NC temperature increase Wednesday, October 08, 2008 Pa!1e 31 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 16 D General Discussion There are 2 times NC pumps are secured in HI. First after CA cannot be reinitiated, and second is prior to commencing feed and bleed. S/G wide range levels are above the FIB critera (3<24% WR to establish) unless ACC conditoions (36%). NCPs are secured to minimize heat input causing the water in the S/G to last longer. Pressure inceeases due to the temperature increase prior to the establishment of natural circulation.

Answer A Discussion FIB criteria are not met but would be for ACC numbers (correct part 2)

Answer B Discussion Ipart I is correct, part 2 is not Answer C Discussion both part incorrect - psychometric baloance Answer D Discussion

[Correct Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed FR-h.l and basis 0 OPT Approved E-l and basis 0 OPS Approved 0 NRC Approved QuestionBank #JKA system IKA number I 5221WE05 IEK3.1 I KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)

(CFR: 41.5/41.10, 45.6, 45. 13) 0 Facility operating characteristics during transient conditions, including 0 coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

Wednesday, October 08, 2008 Pa{!e 32 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system 523 I WE 11 IKA number I EK2.1 I

I QUESTION 17 c KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:

(CFR: 41. 7/45. 7) 0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

~~==============================================================~.------

The crew implemented EP/1/A/5000/ECA-1.2 (LOCA Outside Containment),

determined the leak can not be isolated and transitioned to EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation). Given the following:

FWST level is 55%

Subcooling is +rF.

What actions, if any, are taken per EP/1/A/5000/ECA-1.1 to ensure the NV pumps maintain adequate suction until cold leg recirculation capability is restored?

A. Terminate safety injection and establish normal charging from the VCT.

B. Remove power from 1NI-184B (ND Pump 1B Cont Sump Suct) and 1NI-185A (ND Pump 1A Cont Sump Suct)

C. Use "DEFEAT" buttons used for "C-LEG RECIR TO CONT SUMP SWAP TRN A" and "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B" D. None, a swap to the containment sump is blocked when sump level is less than 3.3 feet Wednesday, October 08, 2008 Pa!JP :n of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 17 c General Discussion With FWST level at 55%, an attempt to swap hs not been made (37%).

Answer A Discussion This can be done if Subcooling is > 50 degrees. Normal SII termination criteria is subcooling >0 degrees. Swap to VCT is done in this procedure in that case.

Answer B Discussion This is an action that could be done to prevent these valves from opening and is done when it is trying to open them manually.

Answer C Discussion ICORRECT Answer D Discussion The procedure mentions sump levels being both> 2.5 feet and> 3.3 feet in several locations. The basis is to check for adequate suction source, but there are no actual interlocks to prevent the swapover at 37%.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed ECA l.l 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 5231WEll IEK2.1 I KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:

(CFR: 41. 7/ 45.7)0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Wednesday, October 08, 2008 Pal!e 34 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system 524 IKA system I

I WEl2 IKA_number IKA I

number EK1.3 I

I QUESTION 18 c KA desc Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators)

(CFR: 41.8 141.1 0 I 45.3)DAnnunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

The crew entered EP/1/A/5000/ECA-2.1 (Uncontrolled Depressurization of All Steam Generators) following a unit trip. Given the following:

Attempts to close any MSIV using its individual valve control board pushbutton have failed.

Safety Injection has not been reset.

1. What additional action is taken per this procedure to attempt to close any MSIV?

2. If an MSIV can be closed, what plant parameter is monitored to determine when this procedure can be exited?

A. 1. Maintenance is dispatched to isolate air to the MSIVs.

2. NC loop T-hots B. 1. Both trains of Main Steam Isolation are initiated.

2. NC loop T-hots C. 1. Maintenance is dispatched to isolate air to the MSIVs.

2. S/G pressure D. 1. Both trains of Main Steam Isolation are initiated.

2. S/G pressure Wednesday, October 08, 2008 Page 35 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 18 c General Discussion To exit, one steam generator presure must be increasing and SfI termination must not be in progress per ECA 2-1. NC Thots are monitored for other reasons in this procedure and they will increase once the MSIV is closed, but Enclsoure one specifies S/G Pressure. SM ISOL pushbuttons are depressed due to failed auto actions most likely during E-O in this scenario, but ECA-2.1 does not redo this action. It sends MAINT to isolate VI to the valves locally.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed EP/IIA/SOOO/ECA-2.1 0 OPT Approved 0 OPS Approved 0 NRC Approved IKA QuestionBank # jKA system IKA KA number JI 5241WEI2 i 1.3 EK1.3 EK Ii KA desc Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators)

(CFR: 41.8 I 41.10 I 45.3)DAnnunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

Wednesday, October 08, 2008 Pa!!e 36 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 19 D 525 I APEOOI I AAl.06 I KA desc Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.7 / 45.5 /45 .6)ORod transfer switches .............................................

Given the following events and conditions on Unit 1:

NC system is at full temperature and pressure.

"A" Shutdown Bank control rods are fully withdrawn.

CRD BANK SELECT switch is in the "SBB" position.

The OATC is withdrawing "B" Shutdown Bank control rods with the current bank position at 64 steps withdrawn.

The OATC releases the ROD MOTION switch but "B" Shutdown Bank control rods continue to withdraw.

1. What is the current plant Mode of Operation?

2. Which of the following describes the first required procedural action(s) for this situation?

A. 1. Mode 2

2. Immediately trip the reactor.

B. 1. Mode 3

2. Immediately trip the reactor.

C. 1. Mode 2

2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor.

D. 1 Mode 3

2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor.

Wednesday, October 08, 2008 Pal!e 37 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D General Discussion Per IRE lesson: '3.0Allows individual banks to be moved in bank select positions. No prescribed sequencing exists and Bank Overlap is defeated.' Immed action for AP/15.

Mode 2 occurs when the first CONTROL BANK begins withdrawal. Plant is currently in Mode 3 Answer A Discussion Iwrong mode, wrong action I Answer B Discussion I ~-----------------------------------------------I

~ong action, right mode ~

Answer C Discussion Iright action, wrong mode Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed AP/15 D OPT Approved IRE D OPS Approved D NRC Approved QuestionBank # IKA system KA number I 5251APEOOI AAl.06 I

KA desc Ability to operate and I or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.7 I 45.5 I 45.6)ORod transfer switches .............................................

Wednesday, October 08, 2008 Pa!!:e 38 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # [KA system [KA number I

[

QUESTION 20 B 526 I APE005 J I 2.4.6 1I KA desc I[

APE005 GENERICDKnowiedge ofEOP mitigation strategies. (CFR: 41.1 0/43.5/45.13)

I Unit 1 was operating at 100% power with Control Rod Bank 0 at 216 steps withdrawn on DRPI when an OTDT runback occurred for approximately 30 seconds and cleared.

When conditions stabilized, the following indications were noted:

Control Rod Bank 0 demand counters are indicating 190 steps.

Control Rod Bank 0 rod 04 indicates 216 steps withdrawn on DRP!.

All other Control Rod Bank 0 rods indicate 188 steps withdrawn on DRP!.

1. What is the first immediate action of the Abnormal Procedure that will address this issue?

2. What are the modes of applicability for the corresponding Technical Specification?

A. 1. Verify only one rod - MISALIGNED.

2. MODE 1, MODE 2 with keff ::: 1.0 B. 1. Verify only one rod - MISALIGNED.

2. MODE 1, MODE 2 C. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL.

2. MODE 1, MODE 2 with keff ::: 1.0 D. 1. Ensure "CRD BANK SELECT" switch - IN MANUAL.

2. MODE 1, MODE 2

. Wednesday, October 08, 2008 Pa!!:e 39 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 B General Discussion One CR is misaligned by >24 asteps. And AP/14 would be appropriate for this situation. CRD bank select to manual is not an immedaite action but is the next action of this AP. It IS an immediate action of AP/15 for continuous rod movement. Tech spec 3.1.4 applied for Rod Group alignment Limits. 3.1.6 does not apply because the control rods are above insertion limits.

Answer A Discussion

\wrong TS applicability Answer B Discussion

\CORRECT Answer C Discussion

\Both wrong (for psychometric balance.)

Answer D Discussion

\Wrong action Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided TS 3.1.6 o OPT Approved AP/14 AP/15 OOPS Approved TS3.1.4 o NRC Approved QuestionBank # KA system KA number 526APE005 2.4.6 KA desc APE005 GENERICDKnowledge ofEOP mitigation strategies. (CFR: 41.10/43.5/45.13)

Wednesday, October 08, 2008 Page 40 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 527 I APE024 I AKl.04 I

I QUESTION 21 c KA desc Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8 /41.10/ 45.3)OLow temperature limits for born concentration ....................

Given the following:

Unit 1 is in Mode 5

BAT temperature is 60° F.

FWST temperature is 70° F.

Assuming any required pumps are operable, which one of the following correctly states a combination of equipment which will satisfy the requirements of SLC 16.9-7 Boration System Flowpaths - Shutdown?

A. BAT to NV Pump B. FWST to NI Pump via 2 cold leg lines C. FWST to NV Pump O. FWST to NO Pump via 2 cold leg lines Wednesday, October 08, 2008 Page 41 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 21 c General Discussion Bat is inoperable due to <65 deg F. FWST is operable.

INI Pump requires 4 flow paths not 2 ND can only be used in Mode 6.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed TS 3.9.4 D OPT Approved SLC 16.9-7 SLC 16.9-11 D OPS Approved D NRC Approved IKA QuestionBank # IKA_system system IKA IK~number number II 527iAPE024 5271APE024 IAKl.04 I KA desc Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8 ! 41.10 ! 45.3)DLow temperature limits for born concentration ................... .

Wednesday, October 08, 2008 Pa!!e 42 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKAlKA system IKA number JI QUESTION 22 A 528 I APE033 I AK1.01 1I KA desc Knowledge of the operational implications of the following concepts as they apply to Loss ofIntermediate Range Nuclear Instrumentation:

CFR 41.8/41.10/ 45.3)0 Effects of voltage changes on performance ...........................

Given the following conditions and sequence of events:

During the last calibration of N-35, an IAE technician improperly adjusted the compensating voltage to a value slightly lower than required by procedure.

N-36 failed 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago, the crew entered AP/1 IA/55001016 (Malfunction of Nuclear Instrumentation), Case III (Intermediate Range Malfunction).

All actions required by AP/1/A/55001016 have been completed.

A feedwater transient occurs resulting in a reactor trip.

How does this adjustment error affect the reading on N-35 and how will this condition affect when the source range instruments automatically energize?

A. N-35 will indicate higher than the actual value.

The source ranges instruments will energize at a lower actual neutron flux.

B. N-35 will indicate higher than the actual value.

The source ranges instruments will energize at the same actual neutron flux.

C. N-35 will indicate lower than the actual value.

The source ranges instruments will energize at the same actual neutron flux.

D. N-35 will indicate lower than the actual value.

The source ranges instruments will energize at a higher actual neutron flux.

Wednesday, October 08, 2008 Pave 43 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 22 A General Discussion 2/2 IR instruments are required to clear P-6 and automatically energize the SR instruments. Compensating voltage set too low will cause IR indication to be higher than actual flux level, delaying automatic energizing of the SR. > P-lO removed SR voltage. If this is confuzed and student thinks that <p-lO will energize SR and with one IR already failed low, then "at the same time" is plausible.

Answer A Discussion Answer B Discussion

!N35 indication is correct Answer C Discussion Ipsychometric balance Answer D Discussion SR will energize at a lower value N35 will indicate higher. This would be corect if voltage was set higher Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed API 1/A/550010 16 0 OPT Approved ENB 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 528jAPE033 jAK1.01 j KA desc Knowledge of the operational implications of the following concepts as they apply to Loss ofInterrnediate Range Nuclear Instrumentation:

CFR 41.8 1 41.10 1 45.3)OEffects of voltage changes on performance .......................... .

Wednesday, October 08, 2008 Pal!e 44 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA system IKA_number QuestionBank # IKA_system IKA number I QUESTION 23 D 529 I APE037 I AA2.03 I KA KA desc Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 / 45.13)DThat the expected indication on main steam lines from the S/Gs should show increasing radiation levels ......................

Given the following:

Unit 1 is operating with a known 0.6 GPO S/G tube leak

1A CF pump tripped and results in a plant runback which has been successfully addressed using AP/1/A/5500/003 (Load Rejection)

The transient has caused the tube leak to increase to 12 GPO.

Which one of the following indications will provide the best indication (most sensitive and timely) that the S/G tube leak has increased?

A. Observing 1EMF-26, 27, 28 and 29 (Steamline 1A - 10)

B. Comparing S/G feed flow to steam flow mismatch C. Observing 1EMF-33 (Condenser Air Ejector Exhaust)

O. Observing 1EMF-71, 72, 73, 74 (S/G A-O leakage)

Wednesday, October 08, 2008 Pa2:e 45 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 23 D General Discussion Bank Question: 605.1 normally, EMF-71-74 are the most sensitive monitors. But these monitors detect N16 0 radiation that has a high energy (7 MeV) 0 that only is generated when the reactor is operating at power (requires a neutron flux).

Answer A Discussion This would be true at low power level or in mode 3 where N16 is not present or at low concentrations Answer B Discussion Incorrect: Not a sensitive method of comparison - requires large gpm leak rates before this is noticeable.

Plausible: This method will show gross SGTRs Answer C Discussion This EMF is not as senstive as the Stm line EMFs, also the Steam line EMF see the radiation first.

Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2003 NRC Q32 (Bank 232)

Development References Student References Provided

~ Developed SM lesson 0 OPT Approved NSD513 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 5291APE037 IAA2.03 I KA desc Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 / 45. 13)DThat the expected indication on main steam lines from the S/Gs should show increasing radiation levels .................... ..

Wednesday, October 08, 2008 Page 46 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system lKA system JKA_number IKA number II QUESTION 24 D 530 II EPE074 I EA1.01 lI KA desc Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7 / 45.5 / 45.6)ORCS water inventory S/G depressurization to atmospheric pressure has been performed in EP/1/N5000/FR-C.1 (Response to Inadequate Core Cooling).

1. What are the NC temperature and RVLlS level limits that allow the crew to transition out of this procedure?

2. Why are these limits so much more strict than earlier transition conditions?

A. 1. Two NC Thots less than 328 deg F, RVLlS level greater than 41%

2. To ensure a hard bubble does not block natural circulation flow B. 1. Two NC Thots less than 328 deg F, RVLlS level greater than 41 %

2. Due to the NC system being depressurized C. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 %

2. To ensure a hard bubble does not block natural circulation flow D. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 %

2. Due to the NC system being depressurized Wednesday, October 08, 2008 Page 47 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 24 D General Discussion 350 and 61 are correct and NC depressurized is correct. 328 and hard bubble are both from S/G depress for CLA to prevent N2 injection. 41 %

is the entry requirement and earlier kickout requirement.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed F-O 0 OPT Approved FR-C.l and basis 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 530lEPE074 iIEA1.01 EA 1.01 II KA desc Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7 / 45.5/ 45.6)ORCS water inventory Wednesday, October 08, 2008 Page 48 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 531 I APE036 I AK3.03 I

I QUESTION 25 c KA desc Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10 / 45.6 / 45.13)DGuidance contained in EOP for fuel handling incident ..................

Unit 1 was conducting refueling operations in mode 6. Given the following events and conditions:

The containment purge (VP) system is in operation in the REFUEL mode.

1VQ-10 (VQ Fans Disch to Unit Vent) is open to inspect the actuator for air leaks.

Both trains of SSPS are in "TEST".

The refueling crew dropped a fuel assembly into the refueling cavity.

1RAD-1 Al2 "1 EMF-39 CONTAINMENT GAS HI RAD" - LIT

1RAD-3 0/2 "1EMF-17 REACTOR BLDG REFUEL BRIDGE" - LIT

The crew has implemented AP/1/A155001025 (Damaged Spent Fuel).

As the crew reaches the appropriate steps in AP/1/A155001025, which one of the following statements correctly identifies the "as-found" state of the VP system and the position of 1VQ-10?

A. The VP system is running; 1VQ-10 is open B. The VP system is running; 1VQ-10 is closed C. The VP system is secured; 1VQ-10 is open D. The VP system is secured; 1VQ-10 is closed Wednesday, October 08, 2008 Page 49 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 25 c General Discussion THIS WAS A REPLACEMENT KA IVQ-lO closes based on EMF35,36 Trip 2, but not on EMF 39 (however EMF39 does isolate VQ flow via VQ2A and VQ3B. EMF39 secures VP using 2 separate signals one thru SSPS (Sh) and one directly from the EMF. With both trains of SSPS in test, the Sh will not work, however VP will be secured by EMF 39 directly. The status ofVP and VQ are both checked per AP25.

Answer A Discussion IVp is shutdown, partially correct 1VQ lOis open Answer B Discussion Iboth parts wrong Psychometric balance Answer C Discussion ICORRECT l Answer D Discussion partially correct VP is secured, but VQ lOis open Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED 2004 NRC Q86 (Bank 386)

Development References Student References Provided

~ Developed AP/25 D OPT Approved VQ CNT D OPS Approved VP D NRC Approved QuestionBank # IKA system IKA number I 531iAPE036 lAK3.03 KA desc Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10 I 45.6 1 45.13)DGuidance contained in EOP for fuel handling incident ................ ..

Wednesday, October 08, 2008 Page 50 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # #jKA

[KA system IKA number IKA_number JI QUESTION 26 A 532 WED3 EK2.1 I II II KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:

(CFR: 41.7/45. 7)0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Unit 1 was operating at 100% power when a small break LOCA occurred. Given the following events and conditions:

Cooldown and depressurization is in progress in ES-1.2 (Post Cooldown and Depressurization)

NC system pressure has stabilized at 410 psig

FWST level is 70% and slowly decreasing

The operators attempt to place 1A NO train in the RHR mode

1ND-1 Band 1ND-2A (NO Pump 1A Suct from Loop B) will not open Which one of the following statements correctly describes why 1ND-1 Band 1ND-2A will not open?

A. The NC system pressure is too high B. 1NI-185A (NO pump 1A Suctfrom CNMT Sump) is closed C. ECCS has not been reset D. 1NI-147B (NI Pumps Recirc to FWST Isol) is open Wednesday, October 08, 2008 Pal!e 51 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 26 A General Discussion (Bank Question: 1167 Answer A Discussion Correct: IfNC system pressure is> 385 psig, these valves will not open Answer B Discussion Incorrect: NI-I85A being closed will not prevent IND-IB and IND-2A from opening - the closed position makes up the interlock.

Plausible: Reverse logic - If INI-I85A were open, it would prevent IND-IB and IND-2A from opening Answer C Discussion Incorrect: ECCS does not have to be reset for IND-IB and IND 2A to open Plausible: Resetting ECCS is usually done as an operational matter before starting an ND train in RHR mode.

Answer D Discussion Incorrect: This is not a valve interlock with IND-IB and IND-2A Plausible: INI-147B being open is a valve interlock for ND-28A and NI-136B - if the candidate confuses the valve interlocks.

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2004 NRC Q50 (Bank 350)

Development References Student References Provided

~ Developed PS-ND 9 D OPT Approved NSD3.1.30 ND pages 8, 13 D OPS Approved D NRC Approved QuestionBank # IKA system IKA IKA_number number II 5321WE03 IEK2.1 IEK2.1 J!

KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:

(CFR: 41.7 ! 45.7) 0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Wednesday, October 08, 2008 Pa{!e 52 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA [KA_system system IKA number IKA_number I QUESTION 27 D 533 I

I WE09 J

I EK3.3 I

KA desc Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations)

(CFR: 41.5/41.10, 45.6, 45. 13) 0 Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

Given the following conditions and sequence of events:

One hour ago, a fault in the Unit 1 main generator resulted in a complete loss of offsite power.

The crew entered EP/1/A/5000/ES-0.2 (Natural Circulation Cooldown).

The OSM determined that a transition to EP/1/A/5000/ES-0.3 (Natural Circulation Cooldown With Steam Void in Vessel) was required.

The crew has transitioned to ES-0.3 and is preparing to depressurize the NC system.

Which one of the following describes:

1. A condition that would stop the depressurization of the NC system during this cooldown?

2. How S/G PORVs are being operated to support NC temperature control?

A. 1. PZR Level greater than 70%

2. Manually by NLOs stationed in the doghouses B. 1. RVLlS level less than 73%

2. Manually by NLOs stationed in the doghouses C. 1. PZR Level greater than 70%

2. In manual from the control room D. 1. RVLlS level less than 73%

2. In manual from the control room Wednesday, October 08, 2008 Pa2e 53 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 27 D General Discussion S/G PORVS can be operated with N2 backup from the control room. Local PORV operation is rquired in some accident scenarios where onsite power is lost (EDE, EDF) ESO.2 does have steps to operate locally but no indication that is required from stem.

70% is the PZR Hi Level Alarm. The actual value is 90%.

Answer A Discussion A is incorrect. PZR Level is > 90% PORVs are operated from the CR.

Answer B Discussion IRight limit. PORVS are operated from the CR Answer C Discussion Wrong level, see A above. Right location for PORV operation.

Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2006R NRC Q65 (Bank 142)

Development References Student References Provided

~ Developed ES-0.3 0 OPT Approved SM 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA IKA_number number II 5331WE09 IEK3.3 JI KA desc Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations)

(CFR: 41.5/41.10, 45.6, 45.13)OManipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

Wednesday, October 08, 2008 Pa!!e 54 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system 534 I SYSOO3 I

IKA number I A2.02 JI I

QUESTION 28 c KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45/13)DConditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP ...................

Unit 1 is in the process of performing a reactor startup. Given the following conditions and sequence of events:

Control Bank "A" is at 28 steps withdrawn

1AD-6, A15 "NCP HI VIBRATION" - LIT

1AD-6, B/5 "NCP HI-HI VIBRATION" - LIT

The BOP validates that the 1C NC Pump vibration level on the frame is at 6.5 mils using the NC Pump vibration monitor panel.

Which one of the following selections is the list of the correct actions based on this situation?

A. Reinsert Control Bank "A" rods.

Trip 1C NC Pump.

Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).

B. Trip 1C NC Pump.

Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).

C. Trip the reactor.

Trip 1C NC Pump.

Go to EP/1/A15000/E-O (Reactor Trip or Safety Injection).

D. Pump trip criteria is not yet met.

Go To AP/1/A155001008 (Reactor Coolant Pump Malfunction).

Wednesday, October 08, 2008 Paj!e 55 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 28 c General Discussion The correct action is to trip the reactor (based on being in Mode 2), trip the reactor coolant pump, and enter E-O due to the reactor trip.

Answer A Discussion Plausible: This would be correct response in Mode 3 with all control banks in.

Answer B Discussion Incorrect: With the plant in mode 2, E-O is the correct procedure.

Answer C Discussion ICorrect:

Answer D Discussion Incorrect: The pump trip criteria is > 5 mils on the frame.

Plausible: If trip criteria were not met, this would be the correct response.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2004 NRC Q64 (Bank 364) Bank Question: 1183 Development References Student References Provided

~ Developed PS-NCP 12 0 OPT Approved OPIl/B/6100101G lAD-6 B/5 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number II 5341SYS003 534!SYS003 IA2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5/45.3 I 451l3)OConditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP .................. .

Wednesday, October 08, 2008 Pa!!e 56 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA IKA number II QUESTION 29 D 535 I SYSOO4 I Al.OI I KA KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5/ 45.5)DActivity levels in primary system ...................................

Unit 1 is operating at 75% with some confirmed failed fuel. Given the following conditions and sequence of events:

Letdown flow is 75 gpm.

Mixed bed and cation bed demineralizers are in service attempting to maintain satisfactory levels of activity in the NC system.

1AD-07, F/3 "LETDN HX OUTLET HI TEMP" - LIT

The BOP notes that letdown temperature has trended to 132 of and appears to have stabilized.

1. What is the status of the demineralizers at the current time?

2. What is the applicability of Tech Spec 3.4.16 (RCS Specific Activity)?

A. 1. The demineralizers have been automatically bypassed.

2. Modes 1,2, and 3 B. 1. The demineralizers have been automatically bypassed.

2. Modes 1 and 2, Mode 3 with Tavg .::: 500°F.

C. 1. The demineralizers are still in service.

2. Modes 1,2, and 3 D. 1. The demineralizers are still in service.

2. Modes 1 and 2, Mode 3 with Tavg.::: 500°F.

Wednesday, October 08, 2008 Pa!!e 57 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 D General Discussion INVI73 diverst to VCT (bypasses Demins) at 136 degrees. The alarm comes in at 128 degrees.

Answer A Discussion Demins are not bypassed, wrong ts appl. - psychometric balance Answer B Discussion demins are not bypassed, second part correct Answer C Discussion

!first part correct, wrong appl Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed OPIl/B/61 0010 I OH D OPT Approved NV lesson TS3.4.I6 D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 535!SYS004 !A1.0I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5 1 45.5)DActivity levels in primary system .................................. .

Wednesday, October 08, 2008 Page 58 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system 536 I SYSOO4 IKA number I

I K1.34 I

I QUESTION 30 c KA desc Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: (CPR: 4l.2 to 4l.9 /

45.7 to 45.8)DInterface between evcs and reactor coolant drain tank; and PZR PCS ....

Unit 1 is operating at 100%. Given the following initial conditions and sequence of events:

Excess letdown is in service to repair a leak on the letdown line.

A PZR pressure channel failure causes 1 NC-32B (PZR PORV) and 1NC-36B (PZR PORV) to open.

1NC-36B does not re-close and the BOP closed its isolation valve.

Minimum NC pressure reached during the event was 1820 psig.

Current NC pressure is 2145 psig and increasing.

Assuming no operator actions other than isolating 1NC-36B:

1. What tank other than the VCT can excess letdown be directed to by 1 NV-125B (Excess Letdn Hx Otlt Ctrl)?

2. Is excess letdown currently flowing to the VCT?

A. PRT; no B. PRT; yes C. NCDT; no D. NCDT; yes Wednesday, October 08,2008 Pal!e 59 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 30 c General Discussion The tanks that can receive input from INV-125B are the VCT and the NCDT. Excess letdown cannot be aligned to the PRT, however, the PORVs in the stem will discharge to the PRT and the seal return (downstream of excess LID) goes to the PRT. The pressure drop stated in the stem results in a safety injection. Excess letdown (INV-I24B) does not isolate on an SI signal however nonnalletdown does. The seal return isolations close on an St signal but if they think that it is an Sp singla then it would be flowing to the VCT still.

Answer A Discussion

!Wrong tank, correct status.

Answer B Discussion

!Wrong tank, and status (balance)

Answer C Discussion

!Correct Answer D Discussion

!Correct tank, wrong status Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed APIIO D OPT Approved NV D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 536!SYS004 !K1.34 !

KA desc Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: (CPR: 41.2 to 41.9 /

45.7 to 45.8)OInterface between CVCS and reactor coolant drain tank; and PZR PCS ....

Wednesday, October 08, 2008 Pa!!e 60 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA lKA number I QUESTION 31 D 537 I SYSOO5 I K4.11 I KA desc Knowledge ofRHRS design feature(s) and/or interlock(s) which provide or the following: (CFR: 41.7)OLineup for low head recirculation mode (external and internal) ..........

1NO-1 B (NO Pump 1A Suct Frm Loop B) and 1NO-37A (NO Pump 1B Suct Frm Loop G) have been aligned to their alternate power supplies.

1. What impact (if any) will aligning the alternate power supply have on the interlocks associated with these valves?

2. How are these valves positioned electrically in the current alignment?

A. 1. Interlocks operate normally

2. From the main control boards B. 1. Interlocks operate normally

2. From the face of alternate MGG breaker G. 1. Interlocks are removed

2. From the main control boards O. 1. Interlocks are removed

2. From the face of alternate MGG breaker Wednesday, October 08, 2008 Paffe lil of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 31 D General Discussion On alt power all interlocks are bypassed. The reason is to allow ND to be aligned on a loss of one train of power. SSF power swaps are completed for items just not ND. Interlocks are normal and would be desired but not available Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed ND lesson 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 537lSYSOO5 IK4.11 I KA desc Knowledge ofRHRS design feature(s) and/or interlock(s) which provide or the following: (CFR: 41.7)OLineup for low head recirculation mode (external and internal) ......... .

Wednesday, October 08, 2008 Page 62 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system 538 I SYSOO6 IKA number I Al.05 I

I QUESTION 32 c KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/ 45.5)DCCW flow (establish flow to RHR heat exchanger prior to placing in service ................................................

At 1200, Unit 1 was addressing an NC system leak per AP/1/A/55001010 (Reactor Coolant Leak) when the leak began to increase. Given the following:

Time 1200 1206 1212 1218 1224 NC system pressure (psig) 2130 1950 5 5 5 Containment pressure (psig) 0.5 1.3 2.8 4.2 2.5 FWST level (%) 98 97 80 60 35 What is the earliest time that KC flow is established to the ND heat exchangers?

A. 1206 B. 1212 C. 1218 D. 1224 Wednesday, October 08, 2008 PaIJe tl~ of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 32 c General Discussion KC aligns to the ND Hx on an Sp signal (3 psig in cont) or on an Ss signal with 10 101 fwst level (37%)

Answer A Discussion An Ss signal is present but FWST level is too high to align KC Answer B Discussion An Ss signal occurs on NCS pressure. If student doesn not recognize Ss has already occurred on Cont pressure, this answer is plausible.

Answer C Discussion Answer D Discussion Ss with LoLo FWST is present, but KC was aligned on the SP at 1218.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed KC lesson D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I A 05 538iSYSOO6 5381SYSOO6 IAl.05 i l. II KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5 / 45.5)DCCW flow (establish flow to RHR heat exchanger prior to placing in service ............................................... .

Wednesday, October 08, 2008 Pal!e 64 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 33 D 539 I SYS007 I 2.4.6 I KA desc I SYS007 GENERICOKnowledge ofEOP mitigation strategies. (CFR: 4l.10 / 43.5/45.13)

Given the following sequence of events:

1600 A reactor trip occurs 1605 The crew entered EP/1/A/5000/FR-H.1 (Loss of Heat Sink).

1615 Bleed and feed is initiated.

1. What minimum SII pump configuration is required to ensure adequate feed?

2. What minimum number of open NC PORVs is required to ensure adequate bleed?

A. 1. One NV pump and one NI pump are running

2. One NC PORV B. 1. One NV pump and one NI pump are running

2. Two NC PORV C. 1. One NV pump is running

2. One NC PORV D. 1. One NV pump is running

2. Two NC PORV Wednesday, October 08, 2008 Pal!e 65 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 D General Discussion Per the background document one NV pump is the minimum flow required to ensure adequate feed if the reactor has been shutdown less than 90 minutes, however, the procedure attempts to start at least 1 NV and 1 NI. 2 PORVS are required open per the basis one many not be adequate depending on NC pressure (i.e. leak size) There is no LOCA mentioned in this question.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided FR-H.l D OPT Approved FR-H.l background D OPS Approved D NRC Approved QuestionBank # KA system KA number 539SYS007 2.4.6 KA desc SYS007 GENERICOKnowledge ofEOP mitigation strategies. (CFR: 41.10/43.5/45.13)

Wednesday, October 08, 2008 Pa!1e 66 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # #JKA IKA system IKA_number IKA number II QUESTION 34 B 540 I I SYS008 1I K3.03 II KA desc I Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:ORCP ........................................................... I Unit 1 is in Mode 3 with all shutdown banks withdrawn in preparation for startup when the following occur:

1AD-6 E/3 "NCP THERMAL BARRIER KC OUTLET HIILO FLOW" - LIT

OAC indicates KC flow to NCP 1C Thermal Barrier HX is 75 gpm.

What effects will this have on NCP 1C and what action should be taken to address the alarm?

A. NCP 1C seal cooling is being maintained. Verify 1KC-345A (NC Pump 1C Therm Bar Otlt) closes immediately.

B. NCP 1C seal cooling is being maintained. Verify 1KC-345A (NC Pump 1C Therm Bar Otlt) closes after a 30 second time delay.

C. All seal cooling to NCP 1C is lost. Open the #1 seal bypass valve for the 1C NCP to restore cooling.

D. All seal cooling to NCP 1C is lost. Trip NCP 1C to prevent seal failure.

Wednesday, October 08, 2008 P<>(JP (\'7 nf '?OO

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 34 B General Discussion The nonnal flow to the KC thermal barrier is 40 gpm per NCP. The high flow alann is set at 60 gpm per NCP.

Answer A Discussion Incorrect: I KC-345A does not close immediately.

Plausible: This would be correct except the valve closes after a 30 second delay Answer B Discussion Correct: NCP seal cooling is being maintained by NY. IKC-345A closes after a 30 second time delay.

Answer C Discussion Incorrect: All seal cooling is not lost. The seal bypass valve is on a common line from all 4 NCPs - not just the IC NCP.

Plausible: Ifhe thinks that seal cooling is lost, opening the seal bypass valve would enhance seal cooling to the NCP.

Answer D Discussion Incorrect: This would be correct if all seal cooling is lost in this mode.

Plausible: If the candidate does not understand that seal cooling is supplied by the NV with this alann.

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2004 NRC Q53 (Bank 353) Bank Question: 1170

~ Developed Development References Student References Provided

References:

o OPT Approved 1. OP-CN-PSS-KC page 12

2. OP-CN-PS-NCP pages 15-19 OOPS Approved o NRC Approved QuestionBank # KA system KA number 540SYS008 K3.03 KA desc Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:DRCP Wednesday, October 08, 2008 Page 68 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_systemIKA system IKA_number lKA_number II QUESTION 35 A 541 I SYSOO8 I K4.09 JI KA desc Knowledge ofCCWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)OThe "standby" feature for the CCW pumps ............................

Unit 2 is in Mode 5 with alignment of the KC system for parallel operations per OP/1/A/64001005 (Component Cooling System). Given the following conditions and events:

2A 1, 2B1, and 2B2 KC Pumps are in service.

Both 2ETA and 2ETB are aligned to Unit 1 offsite power

An 86S relay actuates on 2ETB

All systems respond appropriately in automatic.

Assuming no operator actions, which Unit 2 KC pumps are in service?

A. 2A 1 KC pump only B. 2A 1 and 2A2 KC pumps only C. 2A 1, 2B1, and 2B2 KC pumps only D. 2A1, 2A2, 2B1 and 2B2 KC pumps Wednesday, October 08, 2008 Page 69 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 35 A General Discussion REPLACEMENT KIA An 86S relay causes 2ETB to lockout. The blackout signal will not be overridden by the blackout signal, however, a LOCA signal would override the 86S relay and attempt to load LOCA loads. Therefore neither B train pump will re-start. On a normal LOCA or LOOP, both trains ofKC would actuate.

Answer A Discussion ICORRECT Answer B Discussion If the student thinks that either train BIO causes both trains to start (could be confused with RN which causes both units pumps to start on either unit LOCA or B/O) 2A2 will not start.

Answer C Discussion IIf student thinks that the B/O signal will override the 86S relay. This would be correct if a B train only were to occur.

Answer D Discussion If the student thinks that either train BIO causes both trains to start (could be confused with RN which causes both units pumps to start on either unit LOCA or B/O)

Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED 2007 NRC Q36 (Bank 836)

~ Developed Development References Student References Provided D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA

JKA system IKA IKA number I 54IISYS008 IK4.09 jI KA KA desc Knowledge ofCCWS design feature(s) andlor interlock(s) which provide for the following: (CFR: 41.7)OThe "standby" feature for the CCW pumps ...................... " .. ..

Wednesday, October 08, 2008 Page 70 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA IKA_number number I QUESTION 36 B 542 I I SYSOI0 I SYSOI0j 2.1.25 I KA desc I SYSOIO GENERICDAbiIity to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) I Given the following sequence of events and conditions:

A pressurizer PORV opens spuriously and will not close

5 minutes after the PORV opens, the block valve is closed.

NC pressure is 1500 psig

NC temperature is 550 of

PRT pressure is 45 psig What is the approximate pressurizer PORV tailpipe temperature?

Reference provided A. 270 of B. 290 of C. 310 of D. 320 of Wednesday, October 08, 2008 Page 71 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 36 B General Discussion Tailpipe temperature will be saturation temperature for PRT pressure which is 45psig or 60 psia (psia used for steam tables)

Answer A Discussion This temperature would be based on correct graph usage but with 45 instead of the correct 60 psia Answer B Discussion Answer C Discussion this is the temperaure iifthe student uses correct pressure but goes straight up the graph (constant entropy)

Answer D Discussion his is the temperaure iifthe student uses incorrect pressure and goes straight up the graph (constant entropy)

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided ASME Steam Tables o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 542SYSOlO 2.1.25 KA desc SYSOIO GENERlCDAbility to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12)

Wednesday, October 08, 2008 Page 72 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 37 D 543 I SYS012 I A2.02 I I

KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5 /45.3 / 45.5)DLoss of instrument power Given the following conditions and sequence of events:

Unit 1 was operating at 100% power.

The crew has entered AP/1 /A/5500/016 (Malfunction of Nuclear Instrumentation System) due to N-42 lower detector failing LOW

IAE has not yet placed the required bistables in the trip condition per AP/1/A/5500/016.

A complete loss of 1ERPD occurs What procedure takes priority for these conditions?

A. Continue in AP/1/A/5500/016 B. Enter AP/1/A/5500/029 (Loss of Vital or Aux Control Power)

C. Enter AP/1/A/5500/003 (Load Rejection)

D. Enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

Wednesday, October 08, 2008 Page 73 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 37 D General Discussion With N-42 failed, OTDT picks up. Loss of a vital bus will cause that channels bistables to pick up (in general) including OTDT. This caus~

2/4 situation on the OTDT runback and reactor trip. ~

Answer A Discussion This procedure will address the N42 failure but does not take priority.

Answer B Discussion This procdure will address ERPD failure but does not take priority.

Answer C Discussion There are 2/4 OTDT and if a reactor trip did not occur, a runback would.

Answer*D Discussion ICORRECT.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed ENB lesson 0 OPT Approved EPL lesson 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 5431SYS012 IA2.02 I

KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45.5)OLoss of instrument power Wednesday, October 08, 2008 Page 74 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA number IKA_number II QUESTION 38 D 544 JI SYS012 1I K5.01 I KA KA desc Knowledge of the operational implications ofthe following concepts as the apply to the RPS: (CFR: 41.5/45.7)DDNB Which one of the following selections correctly matches the reactor trip signals to their limiting accident?

Reactor Trip Signal Limiting Accident/Protection A. OPOT ONB OTOT Excessive fuel centerline temperature Pzr High Level NC system integrity Pzr Low Pressure ONB B. OPOT Excessive fuel centerline temperature OTOT ONB Pzr High Level ONB Pzr Low Pressure NC system integrity C. OPOT NC System integrity OTOT Excessive fuel centerline temperature Pzr High Level ONB Pzr Low Pressure ONB D. OPOT Excessive fuel centerline temperature OTOT ONB Pzr High Level NC system integrity Pzr Low Pressure ONB Wednesday, October 08, 2008 Page 75 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 D General Discussion Answer A Discussion IOPDT and OTDT are reversed Answer B Discussion Ipzr high and low pressure are reversed Answer C Discussion Ipsychometric balance Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2007 Audit Exam #2 Q39 (Bank 39)

Development References Student References Provided

~ Developed TS 3.3.1 and bases D OPT Approved IPX D OPS Approved D NRC Approved QuestionBank # \KA_system IKA system IKA number

\KA_number j 5441SYSOl2 iIK5.01 K5 .01 I KA desc Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5/ 45.7)ODNB Wednesday, October 08, 2008 Page 76 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA [KA system IKA [KA_number number I[

QUESTION 39 B 545 SYS013 K6.01 I I I KA KA desc Knowledge of the effect ofa loss or malfunction on the following will have on the ESFAS: (CFR: 41.7! 45.5 to 45.8)OSensors and detectors Initial Conditions:

Unit 1 was performing a heatup following a refueling outage

NC Temperature was 400 of

NC pressure was 1600 psig

"A" and "B" shutdown banks were withdrawn

Containment Pressure Channel II failed high Current Conditions:

1ERPD has lost power

Containment pressure channels read:

o Channell: 0 psig o Channel II: +5 psig o Channel III: 0 psig o Channel IV: -5 psig Which of the following statements explains the impact on the Engineered Safeguards Features (ESF) system and expected operator actions?

A. Only Train "A" safety injection actuates.

Implement EP/1/A/5000/E-O, Reactor Trip or Safety Injection.

B. Only Train "A" safety injection actuates.

Implement AP/1/A/5500/005, Reactor Trip or Inadvertent S/I Below P-11.

C. Train "A" and "B" safety injection actuates.

Implement EP/1/A/5000/E-O, Reactor Trip or Safety Injection.

D. Train "A" and "B" safety injection actuates.

Implement AP/1IA/5500/005, Reactor Trip or Inadvertent S/I Below P-11.

Wednesday, October 08, 2008 Page 77 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 39 B General Discussion ESFAS infonnation due to power failure: AP-29 Enclosure 17 Answer A Discussion Incorrect: Bistables for channels 2&4 are actuated and SSPS receives the input. Only A train actuates due to ERPD failure.

Answer B Discussion ICorrect Answer C Discussion Since both trains of input bay receive any signal from the process cabinets, he may assume that 2 press ch would satisfy both SSPS output bays.

E-O is not used in M4, AP-05 transfers to E-O only on valid indication of high cont press >200 F in the NCS.

Answer D Discussion Bistables for channels 2&4 are actuated and SSPS receives the input but only A train actuates .. Because the actuations were made in Mode 4, AP 05 is the correct mitigation procedure path.

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2005 NRC Q36 (Bank 440) SIMILAR

~ Developed Development References Student References Provided Lesson 0 OP-CN-ECCS-ISE o OPT Approved Objectives02 & 3 REFERENCESOAP/1/A/5500/029 Enclosure 17 OOPS Approved (lERPD load list) rev 013 o NRC Approved IKA QuestionBank # IKA system IKA IKA number I 545ISYS013 JK6.01 IK6.01 JI KA desc Knowledge of the effect ofa loss or malfunction on the following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8)OSensors and detectors Wednesday, October 08, 2008 Page 78 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA

IKA IKA number JI QUESTION 40 D 546 I SYS022 I K2.02 II KA desc I Knowledge of power supplies to the following: (CFR: 41.7)OChillers ....................................................... . I Unit 1 is operating at 100% power with the "YV/RN Cool Water Ctrl" switch in the "Local" position.

Which of the following describes what condition (if any) will result in a swap to the RN cooling water supply?

A. 5 minutes after a loss of MXE only B. 5 minutes after a loss of MXI only C. Immediately after a loss of both MXE and MXI D. No swap to RN supply at any time Wednesday, October 08, 2008 Page 79 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 D General Discussion Local - Containment Mechanical Equipment Building Control (Will block Auto Swap to RN if in this position Answer A Discussion This would occur with switch in CR position Answer B Discussion This would occur with switch in CR position Answer C Discussion This would occur with switch in CR position but its either OR not both, may think that both out requireds more urgency.

Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided RN lesson o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 546SYS022 K2.02 KA desc Knowledge of power supplies to the following: (CFR: 41.7)OChillers ...................................................... ..

Wednesday, October 08, 2008 Page 80 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 41 A 547 I SYS025 1I A4.01 I

KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)DIce condenser isolation valves Given the following:

1AD-13, 0/8 "GLYCOL EXPANSION TNK LO-LO LVL" - LIT

BOP notes that the Unit 1 NF containment isolation valves have closed Where does the bypass valve for pressure relief between the isolation valves relieve to and from what location may the Glycol Expansion Tank Lo-Lo Level interlock be bypassed?

A. Glycol Expansion Tank / local NF control panel B. Glycol Expansion Tank / main control room C. Glycol Mixing and Storage Tank / local NF control panel D. Glycol Mixing and Storage Tank / main control room Wednesday, October 08, 2008 Page 81 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 A General Discussion Bypass will allow excess pressure from within the pentration to excape INTO containment but not anything out of containment. Interlock Bypass is a key switch on the local panel.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion 1'---__________________________-----'

Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed NF lesson 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number II 547jSYS025 547!SYS025 jA4.01 IA4.01 II KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)OIce condenser isolation valves Wednesday, October 08, 2008 Page 82 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA number IKA_number A1.03 II QUESTION 42 c 548 I SYS026 I I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5/ 45.5) 0 Containment sump level ...........................................

Given the following:

A large break LOCA has occurred.

Containment pressure is 3.2 psig and slowly decreasing.

The crew has just transitioned to EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation)

What is the minimum containment sump level that will support operation of all ECCS pumps and the NS pumps?

A. 0.5 ft B. 2.5 ft C. 3.3 ft D. 5.0 ft Wednesday, October 08, 2008 Page 83 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 42 c General Discussion Per the anuciator response for Containemt sump levels on lAD20 & 21, 2.5 ft will support eccs operation, 3.3 ft will support eccs and NS operations. All levels in distractors are levels mentioned in ES-l.3 which can be assumed entered for large break locas.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed ES 1.3 D OPT Approved OP/l/A16100/007 D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 5481SYS026 IAl.03 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 / 45.5)OContainment sump level .......................................... .

Wednesday, October 08, 2008 Page 84 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA number IKA_number JI QUESTION 43 A 549 II SYS026 I I K1.01 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8)DECCS .......................................... ,...............

Given the following sequence of events:

1200 Unit 1 reactor tripped from 100% power due to a large break LOCA 1236 BOP reports:

FWST level is currently 36% and decreasing

Containment pressure is 3.8 psig and decreasing 1240 BOP reports that 1NI-185A (NO Pump 1A Cont Sump Suet) is not open and efforts to open it from the control room have failed.

1241 1A NO pump is secured.

1245 NLOs have been dispatched to manually open 1NI-185A.

1300 NLOs report 1 NI-185A is fully open.

1301 1A NO pump is started.

1305 BOP reports:

FWST level is currently 16% and decreasing

Containment pressure is 3.1 psig and decreasing Which one of the following states:

1. What was the status of the 1A NS pump at 1245?

2. What was the earliest time that any NO Aux Spray could be aligned if needed?

A. 1. 1A NS pump was running

2. 1250 B. 1. 1A NS pump was running

2. 1301 C. 1. 1A NS pump was off

2. 1250 O. 1. 1A NS pump was off

2. 1301 Wednesday, October 08, 2008 Page 85 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 43 A General Discussion for ND Aux spray must have 50 min since trip and 1 train ofND in CLR mode.

ND is secured if the cont sump valve does not open, but NS remains on till 11 % ifNS is required.

As long as NY SII and NI pump can be supplied from 1 train ofND alone, then after 50 minutes, can use ND aux spray from B train.

Answer A Discussion Answer B Discussion INS status is correct, time is not Answer C Discussion ITime is corect status is now Answer D Discussion both incorrect - psychomentric balance. Plausible because maybe think that NS is secured along with ND,and that both trains of CLR are needed to allow ND aux spay.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed NS lesson 0 OPT Approved ES 1.3 ES 1.3 background 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 5491SYS026 IK1.01 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)DECCS ........................................................ ..

Wednesday, October 08, 2008 Page 86 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 44 D 550 I SYS039 I K5.01 JI KA desc Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/ 45.7)ODefinition and causes of steam/water hammer ........................

Given the following conditions and sequence of events:

Unit 1 is manually tripped due to a loss of normal feedwater

Steam generator levels have recovered to normal levels and operators are attempting to throttle CA flow

"An train CA cannot be reset and attempts to close 1CA-58A (CA Pump A Disch To S/G 1B Isol) have failed

NLOs have been dispatched to manually isolate flow to 1B S/G

When CA flow is secured to 1B S/G, level is noted to be 96% on NR level gauges Which of the following consequences have increased risk for 1B S/G based on the current water level in that S/G?

1. Failure of S/G PORV and/or SM safety valves to actuate

2. Failure of S/G PORV and/or SM safety valves to reseat following an actuation

3. Water hammer upon initiation of steam flow

4. Mechanical failure of the main steam lines A. 1,2,3 B. 1,2,4 C. 1,3,4 D. 2,3,4 Wednesday, October 08, 2008 Page 87 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 44 D General Discussion 2, 3 and 4 are all potential consequences of a SO overfill.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed SM lesson 0 OPT Approved FR-H.3 Background 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 550lSYS039 IK5.01 I

KA desc Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/ 45.7)ODefinition and causes of steam/water hammer ...................... ..

Wednesday, October 08, 2008 Page 88 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA IKA_number number II QUESTION 45 B 551 I SYS059 I A4.11 I KA KA desc Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8)DRecovery from automatic feedwater isolation Unit 1 is at 75% power when a plant trip occurs due to P-14 actuation. Given the following events and conditions:

The plant is currently stable.

The steam dumps have just closed at no-load Tave.

Steam generator NR levels are 35% in unaffected steam generators and 80%

in the affected steam generator.

What action must the operator take to reset CF isolation?

A. Cycle the reactor trip breakers only.

B. Cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.

C. Lower the affected steam generator level and cycle the reactor trip breakers.

D. Lower the affected steam generator level, cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.

Wednesday, October 08, 2008 Page 89 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 45 B General Discussion Answer A Discussion Incorrect: must also depress FWI push buttons ifP-4lLow Tave FWI had not occurred. Cycling Rx trip breakers does clear auto S/I Plausible: would be true ifP-41L0w sir block following an SII.

S/!.

Answer B Discussion Correct: to clear the P-14, the trip breakers must be cycled. To clear the low tave/p-4 FWI, FWr, it must be reset.

Answer C Discussion Incorrect: not need to reduce S/G level on Unit 1 - must reset FWI FWr Plausible: partially correct - would be true on Unit 2 and Low Tave/P-4 Fwr FWI had not occurred.

Answer D Discussion Incorrect: no need to reduce S/G level Plausible: would be true on unit 2.

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2003 NRC Q55 (Bank 255) Old Bank Question: 970BH

~ Developed Development References Student References Provided Lesson Plan Objective: ISE Obj: 5 D OPT Approved

References:

1. OP-CN-ECCS-ISE page 21, 22, 23 D OPS Approved D NRC Approved IKA system QuestionBank # IKA_system IKA IKA_number number I L_ 5511SYS059 IA4.11 I KA desc Ability to manually operate and monitor in the control room: (CFR: 41.7 I 45.5 to 45.8)0 Recovery from automatic feedwater isolation Wednesday, October 08, 2008 Page 90 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 46 D 552 1 SYS061 1 A3.03 1

~ desc l Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/ 45.5)OAFW S/O level control on automatic start ............................ 1 Given the following:

Unit 2 was operating at 100% power.

2A steamline ruptured inside containment resulting in containment pressure rapidly increasing to 3.7 psig.

Current containment pressure is 2.4 psig and slowly decreasing.

The crew has just verified that total CA flow is greater than 450 gpm per step 18.a of EP/2/A/5000/E-0 (reactor Trip or Safety Injection).

Within what operating band should the BOP be attempting to control S/G N/R levels?

A. Between 11 % and 50%

B. Between 29% and 50%

C. Between 9% and 62%

D. Between 21% and 62%

Wednesday, October 08, 2008 Page 91 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 46 D General Discussion ACC values should be used since containment pressure exceeded 3 psig even though it has been redced below 3 psig.

Answer A Discussion

!Unit 1 non-ACC number Answer B Discussion

!Unit 1 ACC numbers Answer C Discussion

!Unit 2 non-ACC numbers Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided E-O o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 552 SYS061 A3.03 KA desc Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/ 45.5)OAFW S/O level control on automatic start ........................... .

Wednesday, October 08, 2008 Page 92 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA_number IKA number I QUESTION 47 B 553 I SYS062 I I A3.0I I KA desc Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7/ 45.5)DVital ac bus amperage Given the following:

2B DIG automatically started due to the incoming breaker to 2ETB spuriously opening.

While checking DIG operating parameters, the crew notes that DIG 2B "VOLTS" is 4300 V.

At the direction of the CRS, the BOP adjusts voltage to normal.

How will DIG 2B "AMPS" and "P/F" indications respond to this adjustment?

AMPS P/F A. increase less lagging B. increase stay the same C. decrease less lagging D. decrease stay the same Wednesday, October 08, 2008 Page 93 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 B General Discussion Students must understand that the DIG is not in parallel and that voltage must be adjusted DOWN. When vlotage is reduced, DIG lETA amps increases. This has no effect on Power Factor. This is OE from an NLO who was attempting to control PIF while operating isynchcronus.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed DG31esson 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 553[SYS062 [A3.0! [

KA desc Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7 I 45.5)OVita! ac bus amperage Wednesday, October 08, 2008 Page 94 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination

[KA_system QuestionBank # IKA 554 I system [KA_number SYS063

[KA number I K2.01 I[

II QUESTION 48 c KA desc I[

Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads I

Which of the following buses powers the Unit 1 Turbine Emergency Bearing Oil Pump (EBOP)?

A. 1EDB - 125V Vital Instrumentation and Control Power B. 1EMXF - 600V Unit Essential Power C. 1DPD - 250V Auxilary Power D. SMXD - 600V Shared Power Wednesday, October 08, 2008 Page 95 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 c General Discussion All power supplies listed are B train and there are 2 ac and 2 dc sources of plausible voltage.

Answer A Discussion IThiS is the only other DC power voltage.

Answer B Discussion IUnit 1 AC power many motors are 600V unit power Answer C Discussion Answer D Discussion shared AC 600 V power. May think that it is prudent to have power available to protect the main turbine bearings from either unit.

Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided EPL o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 554SYS063 K2.01 KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads ................................................ .

Wednesday, October 08, 2008 Page 96 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system lKA 555 I SYS063 J IKA_number I

number K3.01 JI I

QUESTION 49 c I

KA desc Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7 I 45.6) 0 ED/G Unit 1 was operating at 10% power preparing to roll the turbine. Given the following sequence of events:

0200 - 1A DIG Battery Charger 1DGCA fails.

0700 - DIG 1A Panel, E/5 "LOSS OF DC CONTROL POWER" - LIT 0900 - A tornado results in a complete loss of the switchyard.

Assuming no actions have been taken to address the failed charger, which one of the following statements correctly describes the operating status of the 1A DIG and the reason for this status?

A. The 1A DIG starts because the auto-start function is not dependent on DC control power.

B. The 1A DIG starts because the loads of the failed charger are supplied from vital power through auctioneering diode 1VADA.

C. The 1A DIG did not start because it has lost all control power.

D. The 1A DIG started but did not tie to the bus because the sequencer has lost all control power.

Wednesday, October 08, 2008 Page 97 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 49 c General Discussion Answer A Discussion Incorrect: DIG will not start. DC control power is required for the DIG to start.

Plausible: If the candidate thinks that the battery will carry DC control power loads for> 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Answer B Discussion Incorrect: DIG will not start.

Plausible: if student thinks that control power to the DIG is available thru VADA. This is reversed, the DGCA supplies power thru VADA to the sequencer.

Answer C Discussion ICorrect:

Answer D Discussion Incorrect: DIG will not start.

Plausible: The sequencer has normal power available thru lEDA (from vital power)

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2004 NRC Q74 (Bank 374) OLD Bank Question: 1212

~ Developed Development References Student References Provided Lesson Plan Objective: DG-DGI-14, 19 o OPT Approved

References:

1. OP-CN-DG-DGI pages 17-19,26 OOPS Approved o NRC Approved QuestionBank # IKA system IKA number I 5551SYS063 IK3.01 I KA desc Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7 145.6)OED/G Wednesday, October 08, 2008 Page 98 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA system IKA QuestionBank # IKA_system IKA_number number II QUESTION 50 B 556 II SYS064 1I A3.07 I KA~ I Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/ 45.5)OLoad sequencing ................................................. I Given the following conditions and sequence of events:

Unit 2 was operating at 100% power when a LOCA occurred

Containment pressure peaked at 2.6 psig and is slowly decreasing

1A CA Pump failed to start

"A" train ECCS and O/G load sequencer was reset

1A CA Pump was manually started

A complete loss of switchyard occurs Assuming no operator actions since the loss of the switchyard, which of the following is a complete list of the ECCS pumps currently in service?

A. 2A NV, 2A NI, 2A NO, 2B NV, 2B NI, 2B NO B. 2A NV, 2B NV, 2B NI, 2B NO C. 2B NV, 2B NI, 2B NO O. 2A NV, 2B NV Wednesday, October 08, 2008 Page 99 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 50 B General Discussion With sequencer reset, load groups 4 and 5 (NI, ND) will NOT start on a blackout. This is the situation on "A" train. All will restart on B train since the LOCA signal is still present and it overrides the BO Answer A Discussion this would be if neither train ofECCS/SEQ were reset Answer B Discussion Answer C Discussion This is plausibe if student thinks that all A train ECCS equipment does not restart on a blackout. NV does ...

Answer D Discussion This would occur if BOTH trains were reset Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided E-O and backgmd doc o OPT Approved EQB OOPS Approved o NRC Approved QuestionBank # KA system KA number 556SYS064 A3.07 KA desc Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/ 45.5)OLoad sequencing ................................................ .

Wednesday, October 08, 2008 Page 100 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 51 B 557 SYS064 K6.07 I I I KA desc Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7/ 45.7)OAir receivers Unit 1 is operating at 100% power. A plant operator reports the following:

DIG 1A Panel, B/8 "LOW VG AIR TANK PRESS" - LIT

VG receivers starting air pressure is stable at 149 psig Which one of the following statements correctly describes the state of readiness of the 1A DIG?

A. The DIG cannot be manually or automatically started until the VG receiver is repressurized.

B. The DIG can be manually started and is capable of one or two starts.

C. The DIG can be automatically started and is capable of one or two starts.

D. The DIG can be automatically started and is capable of five starts.

Wednesday, October 08, 2008 Page 101 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 51 B General Discussion Bank Question: 986 IfVG Pressure decreases to less than 150 psig, all automatic start signals are blocked. This conserves enough air for one or two manual start attempts after the cause of the start failure is corrected.

Answer A Discussion Incorrect: Can be started manually started Plausible: psychometric balance Answer B Discussion Correct: Can be started manually one or two times Answer C Discussion Incorrect: With starting air receiver pressure < 150 psig, auto starts are blocked.

Plausible: partially correct - capable of one or two manual starts.

Answer D Discussion Incorrect: Auto starts are blocked below 150 psig - can't make 5 starts at 150 psig.

Plausible: This is the FSAR requirement for the number of starts on a DIG Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2003 NRC Q64 (Bank 264)

Development References Student References Provided

~ Developed

1. DG 1 lesson D OPT Approved 2. Tech Spec Bases 3.8.3 El D OPS Approved D NRC Approved IKA QuestionBank # JKA system IKA jKA number Ij 557!SYS064 jK6.07

!K6.07 J!

KA KA desc Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 I 45.7)DAir receivers Wednesday, October 08, 2008 Page 102 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # [KA system [KA number [

QUESTION 52 B A2.02 558 I SYS073 I I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor- rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/ 45. I 3)ODetector failure .................................................

Unit 1 is operating at 8% power preparing to place the turbine online when 1EMF-39 "CONTAINMENT GAS HI RAD" detector fails causing a Trip 2 alarm.

1. What is the status of the Unit 1 Containment Evacuation alarm?

2. What is/are the minimum action(s) required to reset the safety signal generated as a result of this detector failure?

A. 1. The Containment Evacuation alarm has actuated.

2. Bypass the failed EMF detector and then RESET the safety signal.

B. 1. The Containment Evacuation alarm has NOT actuated.

2. Bypass the failed EMF detector and then RESET the safety signal.

C. 1. The Containment Evacuation alarm has actuated.

2. RESET the safety signal only.

D. 1. The Containment Evacuation alarm has NOT actuated.

2. RESET the safety signal only.

Wednesday, October 08, 2008 Page 103 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 52 B General Discussion EMF 39 Trip2 will give an SH signal. This will isolate containment ventilation (VPNQ).

To reset the SH the initiating signal must be cleared and the reset depressed unlike SP and ST which can be reset with the initiating signal present.

The containment evacuation alarm sounds on this EMF in trip 2 below P-6 (Low in source range) the reactor is currently below pol 0 (10%

power but well above P6)

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided OP/1/B/61 00/0 I 0 X o OPT Approved OOPS Approved o NRC Approved QuestionBank # IKA system IKA number II 55S[SYS073 [A2.02 [

KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor- rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 1 45. I 3) D Detector failure ............................................... ..

Wednesday, October 08, 2008 Page 104 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system

/KA IKA_number IKA number J I QUESTION 53 A 559 J I SYS076 I I K2.01 II KA desc I Knowledge of bus power supplies to the following: (CFR: 41.7)0 Service water .................................................. ..

I 1A RN pump is normally powered from:

A. 4160V bus 1ETA B. 4160V bus 1FTA C. 6900V bus 1TA long side D. 6900V bus 1TC short side Wednesday, October 08, 2008 Page 105 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 53 A General Discussion These are all A train power supplies for large motors.

Answer A Discussion Answer B Discussion '

Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided RN lesson o OPT Approved EPC lesson OOPS Approved o NRC Approved QuestionBank # KA system KA number 559 SYS076 K2.0l KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)DService water .................................................. ..

Wednesday, October 08, 2008 Page 106 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 54 B 560 I SYS078 I K3.02 I KA desc Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CFR: 41.7 / 45.6)0 Systems having pneumatic valves and controls ........................

Unit 2 is in Mode 3 at normal temperature and pressure with all systems in normal alignment preparing for reactor startup.

What affect does a total loss of VI have on the NV system?

A. Charging flow increases; letdown flow increases B. Charging flow increases; letdown flow decreases C. Charging flow decreases; letdown flow increases D. Charging flow decreases; letdown flow decreases Wednesday, October 08, 2008 Page 107 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 54 B General Discussion INV294 and INY309 INY294 INV309 fail open, letdown orifice vlaves fail closed on loss of air. Letdown isolation valves lNY-IA lNV-IA and INY-2A INV-2A fail close on Loss ofYI of VI Answer A Discussion Ipartially correct.

Answer B Discussion Answer C Discussion Ireversed - psychometric balance Answer D Discussion Ipartially correct.

Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided NV lesson INY D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 560lSYS078 IK3.02 I KA desc Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CFR: 41.7/ 45.6)0 Systems having pneumatic valves and controls ....................... .

Wednesday, October 08, 2008 Page 108 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA IKA_number number JI QUESTION 55 A 561 I SYSI03 I L K1.07 1I KA KA desc Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR:

41.2 to 41.9 / 45.7 to 45. 8)0 Containment vacuum system .......................................

Unit 1 is operating at 100% power with a routine containment air release in progress through 1VQ-10 (VQ Fans Disch To Unit Vent).

1. What is a potential negative consequence of 1VQ-1 0 failing to close automatically based on containment pressure as designed?

2. What EMFs in Trip 2 alarm send a closed signal to 1VQ-10?

A. 1. Non-compliance with technical specification on containment pressure

2. Unit Vent EMFs (35L, 36L)

B. 1. Unexpected opening of ice condenser inlet doors

2. Unit Vent EMFs (35L, 36L)

C. 1. Non-compliance with technical specification on containment pressure

2. Containment EMFs (38L, 39L)

D. 1. Unexpected opening of ice condenser inlet doors

2. Containment EMFs (38L, 39L)

Wednesday, October 08, 2008 Page 109 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 55 A General Discussion IF VQ 10 fails to close based on pressure, it can conceivably draw pressure to negative 2.8 psig which violated TS limits, however, that's not enough to open lower ice cond doors. (0.5 Ib/sqft) EMF 35 and 36 causes I VQ-l 0 to close. EMFs 38 and 39 will also terminate the release, but by closing the containment isoaltin vlaves, not 1VQ-l O.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References StUdent References Provided

~ Developed VQ lesson 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA IKA_system system IKA number IKA_number I 5611SYS103 IK1.07 I

KA desc Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR:

41.2 to 41.9 / 45.7 to 45.8)DContainment vacuum system ......................................

Wednesday, October 08, 2008 Page 110 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 56 A 562 I SYSOOI iI K2.02 I KA desc I Knowledge of bus power supplies to the following: (CFR: 41.7)DOne-line diagram of power supply to trip breakers ..................... I I

Unit 2 is operating at 100% power with Reactor Trip breaker RTA is out of service for PMs.

If Reactor Trip Bypass breaker BYB is racked in and closed, what will be the overall status of each the Reactor Trip and Reactor Trip Bypass breakers?

A. RTA-OPEN RTB-OPEN BYA- OPEN BYB-OPEN B. RTA-OPEN RTB-OPEN BYA-CLOSED BYB-CLOSED C. RTA-OPEN RTB -CLOSED BYA-OPEN BYB-CLOSED D. RTA-OPEN RTB-CLOSED BYA-CLOSED BYB-CLOSED Wednesday, October 08, 2008 Page 111 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 56 A General Discussion If both bypass breakers are closed, all breakers open.

Answer A Discussion Answer B Discussion Plausible. In some systems when alternate power is supplied the normal power supply trips open Answer C Discussion plausible if student thinks there is an interlock preventing both bypass breakers from being closed at the same time.

Answer D Discussion IIF student thinks the breaker will stay closed.

Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided IPX o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 562SYSOOI K2.02 KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OOne-line diagram of power supply to trip breakers .................... .

Wednesday, October 08, 2008 Page 112 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 57 D 563 I SYSOII I A1.02 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) 0 Charging and letdown flows ........................................

Initial conditions at 1300:

Unit 2 was at 50% power

Pressurizer level was at program level

2NV-312A (Chrg Line Cont Isol) spuriously closed and could not be reopened

Operators have taken the following actions per AP/21N55001012 (Loss of Charging or Letdown), Case I (Loss of Charging):

o Secured letdown o Total charging flow has been reduced to 32 gpm

Excess letdown can not be established At approximately what time will the pressurizer become inoperable per Tech Spec 3.4.9 (Pressurizer)?

Reference provided A. 1434 B. 1608 C. 1651 D. 1825 Wednesday, October 08, 2008 Page 113 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 57 D General Discussion With charging flow at 32 gpm and no letdown, a net of20 gpm is being added to the NC system. (Stating level is 40% based on 50% rx power)

Based on this and a conversion of -125 gallons/% level in the PZR, level will reach the hi level setpoint of 70% at 1434 hrs (T+ 188 minutes).

This is plausible since it is an alarm setpoint associated with abnormally high pressurizer level. The actual inoperability level is 92% which will occur at -1825 hrs (T+325 minutes).

The other valveus are based on level starting at 55% which is the nonnal PZR level at 100%.

Answer A Discussion if assume 100% power level and 70% inoperable Answer B Discussion lif assume 50 power and 70% level Answer C Discussion lif assume lOOp ower and 92 inoperable Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2005 SRO Q77 (Bank 481)

~ Developed Development References Student References Provided LessonDOP-CN-PS-ILE rev 23 Pressurizer volume (gal) to level (%) graph o OPT Approved REFERENCESDTS 3.4.9 PZR level to gallons graph (REF PROVIDED)

OOPS Approved o NRC Approved QuestionBank # IKA system IKA number I 5631SYSOIl lAl.02 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5 / 45.5)DCharging and letdown flows ...................................... ..

Wednesday, October 08, 2008 Page 114 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA system IKA QuestionBank # IKA_system IKA_number number II QUESTION 58 B 564 SYS016 K1.l2 I I I KA KA desc Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /

45.7 to 45.8)OS/G ............................................................

Unit 1 was operating at 70% when 1 C S/G MEDIAN SELECTED Wide Range (WR)

Level output to the Digital Feedwater Control System (DFCS) fails low.

How will the DFCS respond to this event?

A. DFCS will reduce S/G 1 C WR level to 50%.

B. DFCS will generate a "DFCS TROUBLE" alarm only.

C. DFCS will substitute another S/G's WR level input into "c" loop.

D. DFCS will switch 1C S/G CF reg valve and CF bypass reg valve to MANUAL.

Wednesday, October 08, 2008 Pae:e 115 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 58 B General Discussion WR level is only used at lower power <<25%) when it is used it it is median selected Answer A Discussion this occurs on unit 2 when a CF pump is lost at >65%

Answer B Discussion

[CORRECT Answer C Discussion This would be true for CF temperature which substitutes another S/Gs value.

Answer D Discussion Would need additional failures to cause it to go to manual but since this is the output of a median selected signal it is plausible.

Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK TASKMASTER IFE-002-A Development References Student References Provided

~ Developed IFE lesson D OPT Approved ARP D OPS Approved D NRC Approved IKA QuestionBank # IKA system IKA IKA number II 564[SYS016 564ISYSOI6 [K1.l2 IK1.l2 [

KA KA_desc desc Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /

45.7 to 45.8)OS/G ........................................................... .

Wednesday, October 08, 2008 Page 116 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA IKA number II QUESTION 59 B 565 II SYSOl7 I K3.01 I KA KA desc Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/ 45.6)DNatural circulation indications .....................................

Unit 1 was operating at 100% power when a loss of offsite power caused a reactor trip. The crew has verified natural circulation in ES-0.1 (Reactor Trip Response). Ten minutes later, the operator notes that the thermocouple input to both plasma displays is malfunctioning.

Which one of the following correctly describes a valid indication that natural circulation is continuing?

A. S/G saturation temperatures are decreasing and REACTOR VESSEL UR LEVEL indication is greater than 100%.

B. S/G pressures are decreasing and Tcold is at S/G saturation temperature.

C. S/G pressures are decreasing and REACTOR VESSEL DIP indication is greater than 100%.

D. S/G pressure is at saturation pressure for Tcold and REACTOR VESSEL DIP indication is greater than 100%.

Wednesday, October 08, 2008 Page 117 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 B General Discussion iBank Question: 911.1 Answer A Discussion Incorrect: There is no indication of coupling between primary and secondary. Plausible: These are important indications during natural circulation.

Answer B Discussion ICorrect:

Answer C Discussion Incorrect: Reactor Vessel DIP is unavailable during natural circulation.

Plausible: S/G pressure decreases during natural circulation and RVLIS is one of the other plasma display indications.

Answer D Discussion Incorrect:Reactor Vessel DIP is unavailable during natural circulation.

Plausible: S/G pressure will remain close to saturation for Tcold during natural circulation and RVLIS is one of the other plasma display indications.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 RO Q48 (Bank 248)

Development References Student References Provided

~ Developed HT D OPT Approved 1. ES-O.l page 15

2. ES-O.I Enclosure 3 page I D OPS Approved D NRC Approved QuestionBank # IKA system IKA IKA number I 5651SYSOl7 IK3.01

-'K3.01 -'I KA desc Knowledge of the effect that a loss or malfunction of the ITM system wiIl have on the following: (CFR: 41.7/ 45.6)ONatural circulation indications .. ,................................. .

Wednesday, October 08, 2008 Page 118 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA_system IKA_number lKA_number JI QUESTION 60 B 566 I SYS027 Il K5.01 1I KA desc Knowledge of the operational implications ofthe following concepts as they apply to the CIRS: (CFR: 41.7/ 45.7)DPurpose of charcoal filters Unit 1 was operating at 100% when a design basis LOCA occurred. Radiation monitoring teams at the site boundary report that projected Iodine 131 dose is 5 Rem.

Which one of the following statements correctly describes the condition of the VE filters that would result in the dose readings noted at the site boundary?

A. The HEPA filters are saturated B. The charcoal filters are saturated C. The prefilter/demisters are saturated D. The VE filter unit preheaters are energized Wednesday, October 08, 2008 Page 119 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 60 B General Discussion tBank Question: 834 Answer A Discussion Incorrect: HEPA filters do not remove radioactive Iodine Plausible: HEPA filter remove small particulates Answer B Discussion

)Correct:

Answer C Discussion Incorrect: Prefilter/demister do not remove Iodine.

Plausible: If the candidate does not know the prefilter function.

Answer D Discussion Incorrect: Heaters are supposed to be energized.

Plausible: If the candidate does not know the heater function.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 NRC Q41 (Bank 241)

~ Developed Development References Student References Provided

1. OP-CN-CNT-VE pages 5-6 o OPT Approved OOPS Approved o NRC Approved IKA QuestionBank # IKA system IKA IKA_number number II 566)SYS027 )KS.01 IK5.01 JI KA desc CrRS: (CFR: 41.7 I 4S.7)OPurpose Knowledge of the operational implications of the following concepts as they apply to the CIRS: 45.7)OPurpose of charcoal filters Wednesday, October 08, 2008 Page 120 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system

/KA system IKA_number

/KA number I

/

QUESTION 61 A 567 I SYS035 I 2.2.40 I I

KA desc SYS035 GENERICDAbility to apply Technical Specifications for a system. (CFR: 4l.I0 143.2/43.5/45.3)

Unit 1 is in Mode 5 following refueling. All S/Gs were drained and have just been refilled with condensate water per Chemistry request.

The following conditions existed during the filling operation and have been verified to be the current conditions:

Primary conditions:

1A NO Hx inlet temperature 185 OF of

1B NO Hx inlet temperature 185 of

NC pressure 218 psig Secondary conditions:

S/G 1A CF inlet temperature 71°F

S/G 1B CF inlet temperature 72 of

S/G 1C CF inlet temperature 68 of

S/G 10 CF inlet temperature 71°F

All S/Gs pressures are 0 psig.

Based on the reported conditions, what is the action required by Selected License Commitments?

A. Reduce NC pressure to less than or equal to 200 psig within 30 minutes.

B. Reduce NC pressure to less than or equal to 200 psig within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Increase 1C S/G secondary temperature to greater than 70 of within 30 minutes.

O. Increase 1C S/G secondary temperature to greater than 70 of within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Wednesday, October 08, 2008 Page 121 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 A General Discussion The correct action is to reduce NC pressure within 30 minutes to <200 psig.

All ACTIONS MUST BE COMPLETE if the CONDITION is entered. Therefore, cannot increase temperature to get out of the action.

THIS ONE NEEDS WORK Answer A Discussion Answer B Discussion Incorrect: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months will not meet the action.

Answer C Discussion Cannot increase temperature to revent having to do the actions. Correct time Answer D Discussion Cannot increase temperature to revent having to do the actions.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2005 NRC Q86 (Bank 490)

~ Developed Development References Student References Provided Lesson 0 OP-CN-CF-SG o OPT Approved ObjectivesD25 REFERENCESDSLC 16.5-7 OOPS Approved o NRC Approved QuestionBank # KA system KA number 567 SYS035 2.2.40 KA desc SYS035 GENERICDAbility to apply Technical Specifications for a system. (CFR: 41.10/43.2/43.5 /45.3)

Wednesday, October 08, 2008 Page 122 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system IKA system .IKA_number IKA number II QUESTION 62 B 568 II SYS045 II A3.05 II KA KA desc Ability to monitor automatic operation of the MT/G system, including: (CFR: 4117 / 45.5)DElectrohydraulic control Unit 1 was operating at 100% power. Given the following sequence of events and conditions:

1AD-01, Fig "EHC Emergency Manual Mode" - LIT

1B CFPT trips

1. How was the EHC Emergency Manual Mode selected?

2. How do the control valves respond to a manual runback under the above conditions?

A. 1. automatically

2. the control valves will operate per the valve curves B. 1. automatically

2. the control valves will NOT operate per the valve curves C. 1. manually

2. the control valves will operate per the valve curves D. 1. manually

2. the control valves will NOT operate per the valve curves Wednesday, October 08, 2008 Page 123 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 B General Discussion Emerg manual mode cannot be manually selected. When the valves are operated (in manual using CV lower), all valves will stroke simultaneously without regard for the programmed valves curves Answer A Discussion

!first lfirst part true second part false.

Answer B Discussion Answer C Discussion

!both Iboth parts false - psychometric balance Answer D Discussion lfirst part is wrong, second part is true

!first Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed OPIIIB16 I 0010 lOB 0 OPT Approved EHC lesson 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA KA number JI 5681SYS045 iAA3.05 3 .05 II KA desc Ability to monitor automatic operation ofthe MT/G system, including: (CFR: 4117 I 45.5)DElectrohydraulic control Wednesday, October 08, 2008 Page 124 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 63 A 569 I SYS071 I K4.01 II KA desc Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41. 7)0 Pressure capability of the waste gas decay tank .......................

Which one of the following Waste Gas Decay Tanks (WGDTs) is maintained at a low pressure per the limits and precautions of OP/O/A/65001003A (Gaseous Waste System (Normal Operations)) to allow it to receive discharge from the relief valves of the other WGDTs and what maximum pressure does it specify?

A. WGDT A; less than 5 psig B. WGDT A; less than 30 psig C. WGDT B; less than 5 psig D. WGDT B; less than 30 psig Wednesday, October 08, 2008 Page 125 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 63 A General Discussion A WGDT pressure is normally limited to 5 psig per the OP to allow it to receive relief from other tanks. B tank has a different function- it is used to store nitrogen for shutdown. The hydrogen recombiner operation limit and precaution requires 30 pisg minimum for proper operation.

Answer A Discussion ICORRECT ~

Answer B Discussion IRight tank, wrong pressure Answer C Discussion IWrong tank, correct pressure Answer D Discussion IBoth wrong, psychometric balance.

Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed WG lesson plan page 6 D OPT Approved OP/0IAl65001003 BLIP OP/0IAl65001003 A LIP D OPS Approved D NRC Approved QuestionBank # IKA system KA number I 5691SYS07l K4.01 I

KA desc Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)DPressure capability of the waste gas decay tank .......................

Wednesday, October 08, 2008 Page 126 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 570 I SYS079 I A4.01 I

I QUESTION 64 c KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) DCross-tie valves with lAS VI system pressure is 98 psig.

Which one of the following statements correctly describes the sequence and position of VI system valves in response to a loss of VI header pressure as pressure decreases?

A. VI-500 (VI supply to VS) opens VS-78 (VS supply to VI) opens B. VI-500 (VI supply to VS) opens VS-78 (VS supply to VI) closes C. VI-500 (VI supply to VS) closes VS-78 (VS supply to VI) opens D. VI-500 (VI supply to VS) closes VS-78 (VS supply to VI) closes Wednesday, October 08, 2008 Page 127 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 64 c General Discussion iBank Question: 282.2 Answer A Discussion Incorrect: VI-500 closes - not opens Plausible: partially correct - VS-78 opens Answer B Discussion Incorrect: valve operations are reversed Plausible: psychometric balance Answer C Discussion Answer D Discussion Incorrect: VS-78 opens - does not close Plausible: partially correct - VI-500 closes.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 NRC Q7 (Bank 207)

~ Developed Development References Student References Provided OP-CN-SS-VI page 21 OPT Approved Lesson Plan Objective: VI Obj: 5, 8, 28, 30 AP-22 OOPS Approved o NRC Approved QuestionBank # IKA IKA system JKA_number

/KA_system number I 570lSYS079 IA4.01 I KA desc

~--~~-----------------------------------------------------------------------------------------~

r*--~~---~---------------------------------------------------------------------------------------4 Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) 0 Cross-tie valves with lAS Wednesday, October 08, 2008 Page 128 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA system JKA_number QuestionBank # IKA_system IKA number II QUESTION 65 A 571 I SYS086 I K6.04 I KA KA desc Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7 I 45.7)OFire, smoke, and heat detectors .....................................

Given the following conditions and sequence of events:

2A DIG auto-started due to a blackout on 2ETA

The control room crew notes all loads were sequenced on as required

A fuel oil line leak occurs resulting in a major fire in the 2A DIG room Assuming no operator actions since the DIG auto-started:

1. How long will it take for the Cardox system to discharge once the fire is detected?

2. What is the status of the 2A DIG emergency ventilation after the Cardox system discharges?

A. 1. 6.5 minutes

2. Running due to sequencer actuation B. 1. 6.5 minutes

2. Secured due to Cardox actuation C. 1. 1.5 minutes

2. Running due to sequencer actuation D. 1. 1.5 minutes

2. Secured due to Cardox actuation Wednesday, October 08, 2008 Page 129 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 65 A General Discussion The DIG ventilation will start following the autostart after the B/O signal, since the sequencer has not been reset, they will continue to run. The cardox actuation would normally shutdown the ventialtion system. There is a 5.0 electronic time followed by a 1.5 min pneumatic timer. Were there a loss of power to the cardox system, the 5 min electronic timeer would not work and the card ox would dump at 1.5 minutes.

Answer A Discussion Answer B Discussion

[correct time, but fans run Answer C Discussion

[incorrect time, fan status is correct Answer D Discussion IBoth incorrect pyschometric balance Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed RFY lesson 0 OPT Approved DG 1 lesson VD 0 OPS Approved 0 NRC Approved IKA QuestionBank # \KA system IKA

\KA number I

\

5711SYS086 IK6.04 I KA desc Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7 I 45.7)OFire, smoke, and heat detectors ....................................

Wednesday, October 08,2008 Page 130 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKAIKA system IKA IKA_number number II QUESTION 66 D 572 GEN2.1 2.1.45 I I I KA KA desc Conduct of Operations DAbility to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7/43.5/

45.4)

During a control board walkdown, the crew notes that over the last 10 minutes turbine load has decreased from 1209 MWto 1207 MWwhile reactor power has increased from 99.87% to 100.05%. They suspect a steam leak.

Which set of the following indications could be used to confirm their suspicions?

1. % Steam flow

2. Steam pressure

3. Containment pressure

4. Containment humidity A. 1,2,3 B. 1,2,4 C. 1,3,4 D. 2,3,4 Wednesday, October 08, 2008 Page 131 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 66 D General Discussion Based on simulator modelling, a steam leak of IE4 #/hr would cause MW and Rx power indications as shown. Containment pressure would increase as well as humidity. This is less than 11100th of I % steam flow to any given S/G (3.73E6 #/hr) and would not be useful in diagnosing a steam leak.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided

~ Developed AP/28 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA IKA number JI 572IGEN2.1 12 .1.45 12.1.45 I I

KA desc Conduct of OperationsO Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7/43.5/

45.4)

Wednesday, October 08, 2008 Page 132 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKAIKA_system systemlKA IKA_number number I QUESTION 67 B 573 I GEN2.1 I 2.1.8 I KA desc I Conduct of OperationsDAbility to coordinate personnel activities outside the control room. (CFR: 41.10/45.5 /45.12/45.13) I Terrorists have broken through the security fence and set both Unit 1 main transformers on fire. Security has notified the operating crew that several terrorists are enroute to the control room.

What instructions are provided to the NLO dispatched to the 1ETA switchgear room and which procedure provides that guidance?

A. Perform a partial transfer to the SSF per AP/1/AJ55001017 (Loss of Control Room)

B. Transfer control to the SSF per AP/1 IA/55001017 (Loss of Control Room)

C. Perform a partial transfer to the SSF per AP/OIAJ55001045 (Plant Fire)

D. Transfer control to the SSF per AP/O/A/55001045 (Plant Fire)

Wednesday, October 08, 2008 Page 133 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 67 B General Discussion API17 is used due to being a security event. A full transfer is done for a security event.

Answer A Discussion Partial transfer is done in AP/45 for plant fires but not per AP/17 Answer B Discussion Answer C Discussion Partial transfers are done per AP/45 when fires exist in certain vital area (this is not) and there is a fire, however the security event takes priority.

Answer D Discussion Full control is not transferred to the SSF in AP/45.

Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided AP/17 ENCL 11 o OPT Approved AP/45 API17 Symptoms OOPS Approved API17 step Sc o NRC Approved QuestionBank # KA system KA number 573 GEN2.1 2.1.S KA desc Conduct of OperationsDAbility to coordinate personnel activities outside the control room. (CFR: 4l.l 0 I 45.5 145.12 I 45.13)

Wednesday, October 08, 2008 Page 134 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 68 D 574 I GEN2.2 I 2.2.2 I KA desc Equipment ControlOAbility to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2)

During a power increase to 100% power per OP/1/A/61 001003 (Controlling Procedure for Unit Operation), the "C" Heater Drain Pumps are placed in service at a minimum power level of . The purpose of this is to prevent the potential for _ _ __

A. 50% I excessive main feedwater pump discharge pressure B. 70% I excessive main feedwater pump discharge pressure C. 50% I deadheading of hotwell and booster pumps D. 70% I deadheading of hotwell and booster pumps Wednesday, October 08, 2008 Page 135 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 68 D General Discussion C Heater drain pumps are placed in service at >70% to prevent the possibility of deadheading the hotwell and CBPs under certain transient conditions. Since the C heater drain pumps pump to the suction of the CFPs, the student may think that the increases suction pressure might increase discharge pressure too high. The second CFP is placed in serivice at 50%

Answer A Discussion Iboth parts false, psychometric balance Answer B Discussion lfirst part is true Answer C Discussion Isecond part is true Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided

~ Developed CM Lesson plan 0 OPT Approved OP/lIN61001003 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number I 5741GEN2.2 12 .2 .2 I KA desc Equipment ControlDAbility to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 4l.6 I 4l.7 I 45.2)

Wednesday, October 08, 2008 Page 136 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA IKA number

-'I QUESTION 69 A 575 I GEN2.2 I 2.2.39 I

KA desc Equipment Control oKnowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 4 1.7 ! 4 1.10 !

43.2! 45.13)

Unit 1 is at 4% power, conducting a plant startup. Given the following events and conditions:

One control bank "A" rod drops fully into the core

NCS temperature decreases to 550°F Which one of the following statements correctly describes an action that is required within 30 minutes by Technical Specifications?

A. Be in mode 2 with Keff less than 1.0.

B. Restore rod group within alignment limits.

C. Verify shutdown margins within the limits specified in the COLR.

D. Adjust power range Nils to increase reactor power so that reactor power and thermal power best estimate are equal.

Wednesday, October 08, 2008 Page 137 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 69 A General Discussion Answer A Discussion ICORRECT Answer B Discussion Required per 3.1.4 but not within 30 minutes Answer C Discussion Required per 3.1.6 but not within 30 minutes Answer D Discussion Thermal power would indicate lower not higher due to increased thermalization of the neutrons. While NI adjustment is a problem, this action does not comply with action 3.4.2.

Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2003 NRC Q30 (Bank 230) Bank Question: 600 Development References Student References Provided

~ Developed Lesson Plan Objective: NC SEQ 10 OPT Approved

References:

1. OP-CN-PS-NC page 33 D OPS Approved

2. Tech Spec 3.4.2 page 1 D NRC Approved TS 3.1.4, 3.1.6 QuestionBank # IKA system IKA number I 5751GEN2.2 12.2.39 I KA desc Equipment ControlOKnowledge ofless than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/

43.2/45.13)

Wednesday, October 08, 2008 Page 138 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 576 I GEN2.31 GEN2.3 I 2.3.11 I

JI QUESTION 70 c KA desc I Radiation ControlOAbility to control radiation releases. (CPR: 41.11/43.4/45.10)

I A Unit 1 containment purge is in progress using OP/1/N64501015. Given the following events and conditions:

1EMF-39(L) (CONTAINMENT GAS (LO RANGE)) spiked to a Trip 2 condition then cleared Which one of the following statements correctly describes the action required?

A. The VP release may not be reinitiated until RP draws a new containment air activity sample.

B. The VP release may be reinitiated after the spike clears. If 1EMF-39 spikes a second time, the release cannot be reinitiated without RP sampling containment air for activity.

C. The VP release may be reinitiated after the spike clears. If 1EMF-39 spikes a second time, the release may also be reinitiated.

D. The VP release may be reinitiated if grab samples are taken of Unit Vent activity during subsequent reinitiation.

Wednesday, October 08, 2008 Page 139 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 c General Discussion Answer A Discussion Incorrect: the OP allows the VP release to be reset twice if due to EMF spike.

Plausible: This is a conservative answer.

Answer B Discussion Incorrect: the OP allows the VP release to be reset twice if due to EMF spike.

Plausible: a new sample may be required if the EMF actuates prior to initiating the release.

Answer C Discussion Correct: the OP allows the VP release to be reset twice if due to EMF spike.

Answer D Discussion Incorrect: the OP allows the VP release to be reset twice if due to EMF spike.

Plausible: grab samples are required ifEMF-39 is inoperable when the release occurs.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 NRC Q54 (Bank 254) Bank Question: 968.3

~ Developed Development References Student References Provided Lesson Plan Objective: VP Obj: 8,9 D OPT Approved

References:

1. OP/l/N6450/015, limits and precautions page 2 OPS Approved rev44 D NRC Approved 2. OP-CN-CNT-VP page 15 QuestionBank # KA system KA number 576GEN2.3 2.3.11 KA desc Radiation ControlDAbility to control radiation releases. (CFR: 41.11 /43.4/45.10)

Wednesday, October 08, 2008 Page 140 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system JKA_number 577 I GEN2.3 I 2.3.4 I

I QUESTION 71 c KA desc I Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10)

I While performing a valve lineup in the boric acid mixing room, an air line failure caused a severe airborne beta contamination problem. A worker received both internal and external contamination that was detected upon attempting to exit the RCA.

Which one of the exposures would exceed the 10CFR20 limit for the worker's annual shallow dose equivalent (SDE) exposure?

A. 55 Rem external dose to the lens of the eye.

B. 17 Rem internal dose equivalent to the lens of the eye.

C. 55 Rem external dose to the leg below the knee.

D. 17 Rem internal dose to the right forearm.

Wednesday, October 08, 2008 Page 141 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 c General Discussion Answer A Discussion Incorrect: skin dose equivalent Plausible: 50 Rem is correct limit for SDE - may confuse with LDE eye dose Answer B Discussion Incorrect: SDE is an external skin or extremity dose not an internal dose Plausible: this is the correct LDE limit (lens of the eye).

Answer C Discussion Correct: 50 Rem SDE limit to the extremities (below forearm and below knee) or skin.

Answer D Discussion Incorrect: SDE is an external dose not an internal dose Plausible: the right forearm is the correct part of the anatomy for an SDE - based on confusion of external/internal Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2004 NRC Q16 (Bank 316)

~ Developed Development References Student References Provided HP lesson D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system KA number 577GEN2.3 2.3.4 KA desc Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10)

Wednesday, October 08, 2008 Page 142 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 72 A 578 I GEN2.3 I 2.3.7 I KA~

KA desc Ii Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10) II A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

The worker's present exposure is 1938 mrem for the year

The RWP states:

o General area dose rate = 30 mrem/hr o Airborne contamination concentration =10.0 DAC The job will take 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the worker wears a full-face respirator. It will only take 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the worker does not wear the respirator.

If the RP Manager grants all applicable dose extensions, which one of the following choices for completing this job would maintain the worker's exposure within the station administrative requirements?

A. The worker should not wear the respirator.

The calculated TEDE dose received will be less than if he does wear one.

B. The worker should not wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits.

C. The worker should wear the respirator.

The calculated TEDE dose received will be less than if he does not wear one.

D. The worker should wear the respirator.

He could exceed DAC limits.

Wednesday, October 08, 2008 Page 143 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 72 A General Discussion Radiation exposure comparison:

Without respirator DDE = 30 mremlhr x 1 hr = 30 mrem From airborne contamination:

CEDE = 10 DAC 1 hr x 2.5 mremIDAC-hr = 25 mrem TEDE = 30 + 25 = 55 mrem from job Total exposure for year = 1938 + 55 = 1993 mrem With respirator DDE = 30 mremlhr x 2 hr = 60 mrem CEDE = 0 TEDE = 60 mrem Total exposure for year = 1938 + 60 = 1998 mrem (With respirator) (Without respirator)

TEDE = 60 mrem > 55 mrem = do not use a respirator Answer A Discussion ICorrect answer Answer B Discussion Incorrect: the dose will not exceed the 2000 mrem limit based on calculation.

Plausible: If the candidate miscalculates the dose Answer C Discussion Incorrect: The calculated exposure will be greater if you wear the respirator. Plausible: If the candidate incorrectly computes the exposure - this was the correct answer on a previous exam Answer D Discussion Incorrect: DAC limits are not direct ALARA controls.

Plausible: If the candidate does not understand the concept of derived airborne concentrations.

Job Level Cognitive Level QuestionType Question Source

.4-----~~----------~----------~--~--------------------------------------------------~

RO Comprehension BANK 2003 NRC Qll (Bank 211) Bank Question: 353.3

~ Developed Development References Student References Provided Lesson Plan Objective: HP Obj: 2, 4 D OPT Approved I. OP-CN-RAO-HP pages 14-15 D OPS Approved D NRC Approved QuestionBank # KA system KA number 578GEN2.3 2.3.7 KA desc Radiation ControlOAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10)

Wednesday, October 08, 2008 Page 144 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 579 I GEN2.4 I 2.4.13 I

I QUESTION 73 c KA desc J Emergency Procedures / PlanDKnowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12) I Per OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines), which control room crew position, by title, has primary responsibility for monitoring Critical Safety Function (CSF) status trees during EOP usage?

A. The OSM has responsibility, but he can delegate the task if necessary.

B. The OSM has responsibility and he can not delegate this task.

C. The STA has responsibility, but the OSM can reassign the task if necessary.

D. The STA has responsibility and this task can not be reassigned.

Wednesday, October 08, 2008 Page 145 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 c General Discussion Iper OMP 1-7, C is correct Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided OMP 1-7 o OPT Approved OMP 1-8 OOPS Approved o NRC Approved QuestionBank # KA system KA number 579GEN2.4 2.4.13 KA desc Emergency Procedures / Plan 0 Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12)

Wednesday, October 08, 2008 Page 146 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 74 B 580 I GEN2.4 l 2.4.22 I

KA desc Emergency Procedures 1 PianO Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CPR: 41.71 41.10/43.5/45.12)

Which one of the following sets of critical safety functions (CSFs):

is listed in the correct order per the CSF status trees from highest to lowest priority

forms the bases for protection of the fuel and fuel cladding?

A. 1. Heat Sink 2. Core Cooling 3. Integrity B. 1. Core Cooling 2. Heat Sink 3. NC Inventory C. 1. Heat Sink 2. Su bcriticality 3. NC Inventory D. 1. Subcriticality 2. Heat Sink 3. Integrity Wednesday, October 08, 2008 Page 147 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B General Discussion Answer A Discussion IIncorrect: Wrong order, wrong functions.

Answer B Discussion ICORRECT Answer C Discussion Iright functions wrong order Answer D Discussion Iwrong functions, right order Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW

~ Developed Development References Student References Provided LessonOOP-CN-EP-CSF o OPT Approved Objectives02 REFERENCES 0 Lesson plan information page 10 OOPS Approved o NRC Approved QuestionBank # IKA system IKA number I 5801GEN2.4 12 .4.22 1 KA desc Emergency Procedures / Plan 0 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7/

41.10/43.5/45.12)

Wednesday, October 08, 2008 Page 148 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # )KA system )KA number )

QUESTION 75 A 581 I GEN2.4 I 2.4.42 I KA desc )

Emergency Procedures I PlanO Knowledge of emergency response facilities. (CFR: 41.10 145.11)

I An offsite release is occurring due to a stuck open S/G PORV on 2C S/G which has a significant tube leak.

Which one of the following states:

1. The emergency facility that assumes responsibility for communications with offsite agencies including the NRC once it is activated?

2. What is the lowest classification level that requires this facility's activation?

A. 1. Technical Support Center (TSC)

2. Alert B. 1. Technical Support Center (TSC)

2. Unusual Event C. 1. Operations Support Center (OSC)

2. Alert D. 1. Operations Support Center (OSC)

2. Unusual Event Wednesday, October 08, 2008 Page 149 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 A General Discussion Answer A Discussion Answer B Discussion Correct location, wrong classification. The TSC can be activated at this level, but it is not REQUIRED.

Answer C Discussion Right level, wrong location. This is the center in Charlotte. The NRC and offsiote agency communications go thru the TSC Answer D Discussion IBoth wrong - psychometric balance.

.Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided SEP lesson o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system KA number 581 GEN2.4 2.4.42 KA desc KA_desc Emergency Procedures / Plan 0 Knowledge of emergency response facilities. (CFR: 41.10/45.11)

Wednesday, October 08, 2008 Page 150 of 200

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