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U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
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)
Date:
(vi)    CE     BW   GE Start Time:                                               Finish Time:
Facility/Unit: CATAWBA Region: I C0 III IV Reactor Type: (ij) 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 hours after the examination begins.
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 hours after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
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
Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent f~:*lJ. r:\\ F""7" l])j
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u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date:
Facility/Unit: CATAWBA Region: I (i) III IV Reactor Type: (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 hours 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*--~
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*--~  
Questlo-n-S-an-k-#-'-K-A-_-sy-s--te-m----,-K-A-_-nu-m-b~er--~
-~-..
    -~--.
507 EPE007 EK2.03 D
    -~-              ..
rQ. ~:LION 1
D~\{A~Y~:LION rQ.
~\\{A IF' Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7/45. 7) 0 Reactor trip status panel Unit 1 is at 100% reactor power.
                                                                              ~V{Ar
Four hours ago:
                                                                                      ~:LION IF',
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.
1                D 507                      EPE007  EK2.03
Following the receipt of several annunciators, the following items are noted:
~;: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~~-~
1 EDC 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:
: 45. 7) 0 Reactor trip status panel 41.7/45.
: 1. The current condition of the plant and
..........................................                                                                                    ~~I Unit 1 is at 100% reactor power.
: 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 D
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination Questlo-n-S-an-k-#-'-K-A-_-sy-s--te-m----,-K-A-_-nu-m-b~er--~  
-~--.
507 EPE007 EK2.03 D
rQ.  
~Y~:LION 1
~V{Ar,
D  
~;:l::;e-o;the interrelations between a reactor trip and the following: (CFR 41.7/ 45. 7)D-R-ea-ct-or-tr-iP-st-at-us-p-an-el~~-~
Unit 1 is at 100% reactor power.
Four hours ago:
Four hours ago:
* PZR Level Select Switch was in the 3-2 position
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.
* 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:
Following the receipt of several annunciators, the following items are noted:
* 1EDC has lost power
1 EDC 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:
* 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
: 1. The current condition of the plant and
: 2. The correct operator action to take for the above evolution?
: 2. The correct operator action to take for the above evolution?
A.               1. Anticipated Transient Without Scram (A TWS)
A.
: 2. Manually trip the reactor B.               1. Anticipated Transient Without Scram (A TWS)
: 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)
: 2. Perform a shutdown per OP/1/A/61 00/003 (Controlling Procedure for Unit Operation)
C.               1. Reactor Protection System (RPS) failure
C.
: 2. Manually trip the reactor D.               1. Reactor Protection System (RPS) failure
: 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)
: 2. Perform a shutdown per OP/1/A/61 00/003 (Controlling Procedure for Unit Operation)
DRAFT Wednesday, October 08, 2008                                                                                       Page 1 of200
DRAFT Wednesday, October 08, 2008 Page 1 of200  
~~I


FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination                                                                 QUESTION 1                                       D General Discussion OMP 1-7 General Statements of Philosophy:
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.
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)
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)
Line 62: Line 93:
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 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 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
Answer D Discussion  
~RRECT--~~--~~~~~~-~~~~~~~~~~~~-
~RRECT Job Level Cognitive Level QuestionType Question Source J
~RRECT Job Level R_O ____~ _____
R_O ____ ~ _____ C
____         _____C__
__ o_m_p_r_eh_e_ns_i_on ____ _L ___
Cognitive Level
M_O_D __
__o_m_p_re_h_en_s_io_n o_m_p_r_eh_e_ns_i_on____
IF_IE_D __ ~
QuestionType
_________________ 2_0_0_6_N_R_C_Q __
_____ L_ _ _M_O_D
l_(_B_an_k_6_0_7_) ______ ~~_  
_ L_ _ _  __IF_IE_D__~_________________
~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA_system 507 EPE007 Development References EPINTR013 OMP 1-7 TS 3.3.1 EK2.03 Student References Provided
M_O_D_I_F_IE_D
~-------------------------
__ ________________2_0_06 Question Source
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 QUESTION 1 D
__N_R_C_Q__
General Discussion OMP 1-7 General Statements of Philosophy:
2_0_0_6_N_R_C_Q
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.
__l_(_B_an_k_6_0_7_)______ ~~_
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)
l_(_B_an_k_6_0_7_)________  -
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.
J
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.
  ~       Developed                                           Development References                             Student References Provided EPINTR013 D      OPT Approved                                        OMP 1-7 TS 3.3.1 D      OPS Approved D      NRC Approved                                                                                          ~-------------------------
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.
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
Answer D Discussion
~RRECT--~~--~~~~~~-~~~~~~~~~~~~-
Job Level Cognitive Level QuestionType Question Source J
R_O ____ ~ _____ C __ o_m_p_re_h_en_s_io_n ____ _L ___
M_O_D_I_F_IE_D __ ~
________________ 2_0_06 __
N_R_C_Q __
l_(_B_an_k_6_0_7_)________
~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA_system 507 EPE007 Development References EPINTR013 OMP 1-7 TS 3.3.1 Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 QuestionBank # IKA system IKA number I
* 1RAD-1 , B/3 "1EMF41 AUX BLDG VENT HI RAD" - LIT
508 I
* 1AD-13, A/1 "NO & NS ROOMS SUMP LEVEL EMERG HI" - LIT
EPE009 I
        *  "SAFETY INJECTION ACTUATED" status light - LIT Which one of the following states the correct procedure flowpath that will address this event?
EA2.10 I
A.       AP/1/A/55001027 (Shutdown LOCA)
Unit 1 was in Mode 3 at full temperature and pressure with all control and shutdown banks inserted. Operators note the following:
1 RAD-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)
AP/1/A/55001019 (Loss of Residual Heat Removal System)
B.     AP/1/A/55001027 (Shutdown LOCA)
B.
AP/1/A/55001027 (Shutdown LOCA)
AP/1/A/55001010 (Reactor Coolant Leak)
AP/1/A/55001010 (Reactor Coolant Leak)
C.       EP/1/A/5000/E-O (Reactor Trip or Safety Injection)
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/E-1 (Loss of Reactor or Secondary Coolant)
EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization)
EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization)
D.     EP/1/A/5000/E-O (Reactor Trip or Safety Injection)
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/E-1 (Loss of Reactor or Secondary Coolant)
EP/1/A/5000/ECA-1.2 (LOCA Outside Containment)
EP/1/A/5000/ECA-1.2 (LOCA Outside Containment)
Wednesday, October 08, 2008                                                   Page 3 of200
Wednesday, October 08, 2008 Page 3 of200 D
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 QuestionBank # IKA system IKA number J
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:
1 RAD-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 D


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 D
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.
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 1 9 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 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
Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType 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
~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # JKA system 50SiEPE009 Development References OPIlIB161 0010 lOX AP/lIAl55001027 EP/lIAl50001E-l EP/lI Al5000IECA-1.2 KA number 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"_"'_"_"'_"_"'_"_"'_"'_"_
EA2.10 I
                                    ***_** _***_** _._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~
Question Source Student References Provided
Wednesday, October 08, 2008                                                                                                                               Page 4 of200
~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 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 1 9 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 RO Comprehension NEW
~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # JKA system 50SiEPE009 Development References OPIlIB161 0010 lOX AP/lIAl55001027 EP/lIAl50001E-l EP/lI Al5000IECA-1.2 KA number I
EA2.10 I
Question Source Student References Provided
~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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 3 A
QuestionBank # IKA system IKA number I
509 I
EPEOll I
2.4.30 I
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:
Given the following events:
* A Large Break LOCA has occurred on Unit 2
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?
* All equipment functioned as designed
A.
* The OSM has declared an Alert
State and county warning points B.
* 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?
State warning points and NRC Operations Center C.
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
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
QuestionBank # IKA system IKA_number I
509 I
EPEOll J 2.4.30 i
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 3 A
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)
General Discussion 15 minute notifications do not include NRC, but are the state and county warning points.
Development References                               Student References Provided
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)  
~ 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
~ Developed Development References Student References Provided 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 I
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)
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
Wednesday, October 08, 2008 Page 6 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)
~ Developed Development References Student References Provided 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 1
KA desc BPEOll 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                 [
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 4 A
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/
2008 SRO NRC Examination QuestionBank # [KA system
45.3)ORelationship of charging flow to pressure differential between charging and RCS ................................ .
[KA number
[
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:
Given the following initial conditions:
* 1NV-294 (NV Pmps A&B Disch Flow Ctrl) in MANUAL
* 1 NV-294 (NV Pmps A&B Disch Flow Ctrl) in MANUAL
* 1NV-309 (Seal Water Injection Flow) in MANUAL
* 1 NV-309 (Seal Water Injection Flow) in MANUAL
* pressurizer pressure is 2235 psig
* pressurizer pressure is 2235 psig
* total seal water flow is 32 gpm
* 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?
* 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
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 QUESTION 4 A
2008 SRO NRC Examination QuestionBank # [KA system
[KA number
[
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:
* 1 NV-294 (NV Pmps A&B Disch Flow Ctrl) in MANUAL
* 1 NV-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]
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 4 A
                                                                                        ,,-p_re_s_su_r_e_in_c-,roceas line flow and total seal flow will decrease while charging line discharge pressure increases.
General Discussion 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]
___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]
line flow and total seal flow will decrease while charging line discharge pressure increases.
Answer A Discussion ICORRECT Answer B Discussion Incorrect: total seal flow decreases because INV-309 is in manual.
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 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.
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)
Job Level Cognitive Level QuestionType RO  
  ~    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
~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension BANK Development References THFFF 12 thru THFFF 15 QuestionBank # IKA system 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 /
510lAPE022 IAK 1. 02 J
45.3)DRelationship of charging flow to pressure differential between charging and RCS ................................ .
KA desc Question Source 2005 NRC Q6 (Bank 410)
Wednesday, October 08, 2008                                                                                                                                                 Page 8 of200
Student References Provided 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 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,,-p_re_s_su_r_e_in_c-,roceas 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]
line flow and total seal flow will decrease while charging line discharge pressure increases.
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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension BANK Development References THFFF 12 thru THFFF 15 QuestionBank #jKA system IKA number I  
~_
510lAPE022 IAK 1. 02 I
KA desc Question Source 2005 NRC Q6 (Bank 410)
Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 5 c
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)
QuestionBank # IKA system IKA number I
511 I
APE025 I
2.4.30 I
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
QuestionBank # IKA system IKA number I
511 I APE025 I
2.4.30 I
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.
Unit 1 was in Mode 5 preparing to enter Mode 6.
Given the following:
Given the following:
* Both trains of NO have been lost.
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 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).
The OSM has determined an immediate need to take an action per 10CFR50.54(X).
Per 10CFR50.54(x):
Per 10CFR50.54(x):
: 1. Is notification to the NRC Operations Center required prior to taking the action?
: 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?
: 2. How many SROs (in total) are required to agree prior to taking the action?
A.         1. Yes
A.
: 2. One B.         1. Yes
: 1. Yes
: 2. Two C.         1. No
: 2. One B.
: 2. One O.         1. No
: 1. Yes
: 2. Two Wednesday, October 08, 2008                                                                               Page 9 of200
: 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".
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.
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.
Per 10cfr5054x, only one SRO is required to make the determination and take action per the CFR.
Answer A Discussion I
procedure, 2 are required.
1                                                                                                                  ________~
OMP 1-7 says for situations not covered by Answer A Discussion I
Answer B Discussion
________ ~
~I_ _ _ _ _ _ _ _ _ _ _ _ _ _~~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I
Answer B Discussion
~IAnswer
~I ______________ ~~
    -------------------------------------------------_1 C Discussion
I Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO
__I Answer D Discussion Job Level           Cognitive Level           QuestionType                                     Question Source RO                   Memory                    NEW
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 511 APE025 NEW Development References OMP 1-7 KA number 2.4.30
  ~   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 Question Source Student References Provided KA desc
_I' agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.) 0/43.5/45.) 1)
_I' APE025 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.) 0/43.5/45.) 1)
Wednesday, October 08, 2008                                                                                     Page 10 of200
Wednesday, October 08, 2008 Page 10 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.
procedure, 2 are required.
OMP 1-7 says for situations not covered by Answer A Discussion 1
________ ~
Answer B Discussion  
~I -------------------------------------------------_1 Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO  
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 511 APE025 NEW Development References OMP 1-7 KA number 2.4.30
__ I Question Source Student References Provided KA desc
_I' APE025 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.) 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 ..................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 6 A
QuestionBank # IKA system IKA number I
512 I
APE026 I
AA2.03 I
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 1 ETB 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
QuestionBank # IKA system IKA number J
512 I
APE026 I
AA2.03 I
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:
Unit 1 was operating at 100% with "A" Train KC in service. Given the following:
* An 86N relay actuated on 1ETB two minutes ago
An 86N relay actuated on 1 ETB 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)
* 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?
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
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.
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 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.
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
Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
  ~ Developed 0
~ Developed Development References Student References Provided API 1/ Al55001021 0
0 OPT Approved OPS Approved API 1/Al55001021 PSSKC
OPT Approved PSSKC 0
                                                                                                                                            ==!
OPS Approved 0
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 ................. .
NRC Approved QuestionBank # IKA system IKA number I
Wednesday, October 08, 2008                                                                                     Page 12 of200
512IAPE026 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 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
~ Developed Development References API 1/ Al55001021 0
OPT Approved PSSKC 0
OPS Approved


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 .....................
Student References Provided 0
NRC Approved L-__________________________ ~
~_____________________j QuestionBank # IKA system IKA number I
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 QUESTION 7 QuestionBank # IKA_system I~number I
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:
Given the following:
* The SSF has been manned due to a fire in the cable spreading room.
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.
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.
You have been directed to increase NC pressure using heaters.
: 1. Why is pressure recovery slower from the SSF than from the Control Room?
: 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%?
: 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
A.
: 2. Automatically B.         1. Only a portion of the D heaters are available from the SSF
: 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 B.
: 2. Automatically D.         1. Only A and B heaters are available from the SSF
: 1. Only a portion of the D heaters are available from the SSF
: 2. Manually Wednesday, October 08, 2008                                                                                   Page 13 of 200
: 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 B
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 7 QuestionBank # IKA_system I~number I
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 B


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.
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.
Answer A Discussion lfirst part is correct.
~. -- -- -- -------------------     -- ---- - - - -   -- ---------------------       -- ---- - - - -- ---------------------       --
J
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
Answer B Discussion iCORRECT
  ~   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
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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA_system SI3APE027 NEW Development References OP/O/B/610010 13 PSILE AAI.04 Question Source Student References Provided 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 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 RO  
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA_system SI3APE027 NEW Development References OP/O/B/610010 13 PSILE AAI.04 Question Source Student References Provided 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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 8 D
QuestionBank # IKA system IKA_number I
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 BY A 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
QuestionBank # IKA system IKA number I
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?
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
: 1. Reactor Trip Breakers RTA and RTB
: 2. Reactor Trip Bypass Breakers BYA and BYB
: 2. Reactor Trip Bypass Breakers BY A and BYB
: 3. CRO/MG "Motor" Breakers
: 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
: 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.                                                                                     ]
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 8 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 A Discussion Incorrect: EP!1I A/SOOIFR-S.l requires opening all the breakers.
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.
needs to be open to trip the reactor.
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 B Discussion Plausible: Students knows only one breaker  
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)
Incorrect: EPI1!A/SOOIFR-S.l requires opening all the breakers.
Wednesday, October 08, 2008                                                                                       Page 16 of 200
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
~ Developed Development References Student References Provided 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 D 2008 SRO NRC Examination QUESTION 8 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!1I A/SOOIFR-S.l requires opening all the breakers.
needs to be open to trip the reactor.
Answer B Discussion Plausible: Students knows only one breaker
]
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  
~ Developed Development References Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 9 c
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.
2008 SRO NRC Examination QuestionBank # IKA system IKA number I
pressure drop ...................................... ..
515 I
EPE038 I
EK1.02 I
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:
Given the following:
* Unit 1 and 2 are operating at 100%
Unit 1 and 2 are operating at 100%
* One single steam generator tube fully shears on each unit
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.
* 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:
Based on the differences between Unit 1 and Unit 2 steam generator design:
: 1. Which unit would have a lower primary system equilibrium pressure?
: 1. Which unit would have a lower primary system equilibrium pressure?
: 2. Which unit will have a faster cooldown rate?
: 2. Which unit will have a faster cooldown rate?
(Assume identical cores and steam dump performance.)
(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.
A.
B.         Unit 1 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate.
Unit 1 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate.
C.         Unit 2 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate.
B.
D.         Unit 2 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate.
Unit 1 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate.
Wednesday, October 08, 2008                                                                             Page 17 of 200
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 QUESTION 9 c
2008 SRO NRC Examination QuestionBank # IKA system IKA number I
515 I
EPE038 I
EK1.02 I
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 c 2008 SRO NRC Examination QUESTION 9 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 RO Comprehension BANK
~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 515EPE038 Development References STMSGIO KA number EK1.02 Question Source 2005 NRC Q69 (Bank 473)
Student References Provided 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 c 2008 SRO NRC Examination QUESTION 9 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 RO Comprehension BANK
~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 515EPE038 Development References STMSGIO KA number EK1.02 Question Source 2005 NRC Q69 (Bank 473)
Student References Provided KA desc


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.
======l  
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)
~~~~:dJ;o;f~~~.~:'~~~~~~~~I.. ~::.~~~~~~~ns of the following concepts as they apply to the SGTR: (CFR 41.8/41.10/ 45.3)OLeak ~~
~    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
Wednesday, October 08, 2008 Page 18 of 200  
~~~~: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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 10 B
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 ., ....................
QuestionBank # IKA system IKA number I
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?
516 I
Auto Makeup                               Level Indication A.           Available                                   Available B.         Unavailable                                   Available C.           Available                                 Unavailable D.         Unavailable                                 Unavailable Wednesday, October 08, 2008                                                                                   Pa!!:e 19 of200
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%. 1 ERPA 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
QuestionBank # IKA system IKA number I
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%. 1 ERPA 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 10 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
~ Developed Development References Student References Provided 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 B 2008 SRO NRC Examination QUESTION 10 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
Answer A Discussion Incorrect for makeup but correct for indication Answer B Discussion
[CORRECT Answer C Discussion Incorrect for makeup and for indication.
[CORRECT Answer C Discussion Incorrect for makeup and for indication.
Answer D Discussion Correct for makeup but incorrect 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
Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
  ~ 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 ..................... .
~ Developed Development References Student References Provided API 1/ Al55001029 0
Wednesday, October 08, 2008                                                                                 Page 20 of 200
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 ............................ .
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 11 c
2008 SRO NRC Examination QuestionBank # IKA_system IKA_number I
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:
1 ERPD has been de-energized due to a blown fuse on inverter 1 EID.
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 1 ERPD 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 1 EID 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 QUESTION 11 c
2008 SRO NRC Examination QuestionBank # IKA_system IKA_number I
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:
Given the following:
* 1ERPD has been de-energized due to a blown fuse on inverter 1EID.
1 ERPD has been de-energized due to a blown fuse on inverter 1 EID.
* The crew has implemented AP/1/A/55001029 (Loss of Vital or Aux Control Power).
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.
The fuse has been replaced and the CRS wishes to re-energize 1 ERPD 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?
Which one of the following correctly states the minimum acceptable wait time prior to inverter restart and the sequence for operation of inverter 1 EID DC input breaker and AC output breaker?
A.           1. 5 seconds
A.
: 2. Close the DC input breaker and then close the AC output breaker B.         1. 5 seconds
: 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 B.
: 2. Close the DC input breaker and then close the AC output breaker D.         1. 60 seconds
: 1. 5 seconds
: 2. Close the AC output breaker and then close the DC input breaker Wednesday, October 08, 2008                                                                                 Page 21 of 200
: 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.
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 A Discussion ITime is incorrect.
Answer B Discussion
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
~ Developed Development References Student References Provided EPL 0
OPT Approved API 1/ Al55001029 0
OPS Approved OPIlI Al63501008 0
NRC Approved QuestionBank #[KA system IKA number I
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 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.
!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
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  
~ Developed EPL 0   OPT Approved                       API 1/Al55001029 OPIlIAl6350100S Al63501008 0   OPS Approved 0   NRC Approved QuestionBank #    #[KA
~ Developed Development References Student References Provided EPL 0
[KA system       IKA
OPT Approved API 1/ Al55001029 0
[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 ............................ .
OPS Approved OPIlI Al6350100S 0
Wednesday, October 08, 2008                                                                                     Pal!e 22 of 200
NRC Approved QuestionBank # [KA system
[KA number I
5171APE05SjAA1.02 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 12 A
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 ....
QuestionBank # IKA system IKA number I
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:
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
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 1 RN-48B (RN Supply X-Over Isol) could not be re-opened.
* 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?
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
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
QuestionBank # IKA system IKA number I
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 1 RN-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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 12 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
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 RO  
                                                                                                                                              =
~ Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References AP120 RN lesson QuestionBank # IKA system IKA number I
Job Level           Cognitive Level           QuestionType                                     Question Source RO                 Comprehension                NEW
5181APE062 IAK3.03 I
  ~   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 ....
KA desc
Wednesday, October 08, 2008                                                                                   Page 24 of 200
=
Question Source Student References Provided 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 A 2008 SRO NRC Examination QUESTION 12 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 RO
~ Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References AP120 RN lesson QuestionBank # IKA system IKA_number J
5181APE062 IAK3.03 I
KA desc  
=
Question Source Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 13 B
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 .....................................
QuestionBank # IKA system IKA number I
519 I APE065 I
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
QuestionBank # IKA_system IKA number I
519 I
APE065 1 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:
Given the following:
* One RL turnaround valve is manually pinned in place for mantenance
One RL turnaround valve is manually pinned in place for mantenance The crew has entered AP/O/A/55001022 (Loss of Instrument Air)
* 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.
* 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.
* 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.
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.
A.
B.         The unpinned RL turnaround valves will fail closed resulting in more flow to the components supplied by RL.
The unpinned RL turnaround valves will fail open 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.
B.
D.         The unpinned RL turnaround valves will fail closed resulting in less flow to the components supplied by RL.
The unpinned RL turnaround valves will fail closed resulting in more flow to the components supplied by RL.
Wednesday, October 08, 2008                                                                                         Page 25 of 200
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.
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 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 RO Comprehension NEW
~ Developed Development References D OPT Approved D OPS Approved D NRC Approved RL QuestionBank # IKA system IKA number I
519iAPE065
.iAK3.03 i
KA desc Question Source Student References Provided 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 J
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 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 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
Answer B Discussion iCORRECT Answer C Discussion iTrue ifthe valves DID fail open Answer D Discussion fail in right direction but the effect is reversed.
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 RO Comprehension NEW  
Job Level             Cognitive Level               QuestionType                                             Question Source RO               Comprehension                   NEW
~ Developed Development References D OPT Approved D OPS Approved D NRC Approved RL QuestionBank # IKA system IKA number I
  ~   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
5191APE065 IAK3.03 I
                                      .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
KA desc Question Source Student References Provided 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 J
__ ~~~
effects on plant operation of isolating certain equipment from instrument air.....................................  
of isolating
__  ~~~
certain
__equipment from instrument
___ air ....................................
~~~~~~~--~~~---=~~--~~~~~~~~~--.~~-------------------------------------------.---
~~~~~~~--~~~---=~~--~~~~~~~~~--.~~-------------------------------------------.---
L-~~~~~~                                            ~~~_~~~~~              ~~    ________________                    . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _
Wednesday, October 08, 2008 Page 26 of 200  
Wednesday, October 08, 2008                                                                                                         Page 26 of 200


FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 14 D
[KA system     [KA number IKA_number                        I
QuestionBank # IKA_system IKA_number I
520 I
APE077 I
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
QuestionBank # [KA system
[KA number
[
[
QUESTION 14                D 520 II  APE077 II      AAl.OI I
520 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 .........................................................
APE077 I
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:
Given the following:
* Unit 1 is at 100% power with power factor at 0.99 lagging.
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.
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.
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?
: 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?
: 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
Reference provided A.
: 2. The generator armature core end B.         1. The "RAISE" button
: 1. The "LOWER" button
: 2. The generator armature core end C.         1. The "LOWER" button
: 2. The generator armature core end B.
: 2. The generator field D.         1. The "RAISE" button
: 1. The "RAISE" button
: 2. The generator field Wednesday, October 08, 2008                                                                                     Page 27 of 200
: 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 14 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 A Discussion I.Both parts wrong, psychometric balance.
Answer B Discussion Wwrong gneerator component. This would be ifPF was severely LEADING.
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
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 RO  
  ~   Developed                           Development References                                           Student References Provided Generator Capability Curve (DataBook Curve 43)                   Databook Figure 43 (Generator Capability D   OPT Approved                         RL                                                                Curve)
~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension NEW Development References Generator Capability Curve (DataBook Curve 43)
D   OPS Approved D   NRC Approved QuestionBank #       \KA   system     \KA number                     \
RL 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
520IAPE077 IAAl.OI I
KA desc Question Source Student References Provided Databook Figure 43 (Generator Capability Curve)
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 D 2008 SRO NRC Examination QUESTION 14 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 RO
~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension NEW Development References Generator Capability Curve (DataBook Curve 43)
RL QuestionBank # \\KA system \\KA number  
\\
520IAPE077 IAAl.OI I
KA desc Question Source Student References Provided Databook Figure 43 (Generator Capability Curve)
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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 15 D
QuestionBank # IKA system IKA number I
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.
(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:
Unit 1 was operating at 100%. Given the following events and conditions:
* 0200 - reactor tripped due to a LOCA outside containment
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:
* 0210 - crew enters ECA-1.2, (LOCA Outside Containment)
o NCS pressure is 1100 psig o
* 0220 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc)
1 B NC pump running o
* 0240 - The crew is at the step in ECA-1.1 to determine NC subcooling
1A, 1 C, and 1 D NC pumps secured o
* Current conditions:
Reactor Vessel DIP is 20%
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
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?
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.
Reference provided A.
B.       210 gpm, stop the running NI pump.
210 gpm, stop the running NV pump.
C.       410 gpm, stop the running NI pump.
B.
D.       410 gpm, neither pump may be secured at this time.
210 gpm, stop the running NI pump.
Wednesday, October 08, 2008                                                                               Page 29 of 200
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
QuestionBank # IKA system IKA number I
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
1 B NC pump running o
1A, 1 C, and 1 D 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 D OPT Approved D OPS Approved D NRC Approved Lesson Plan Objective: EP-EP2 SEQ 29


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.
==References:==
: 1. ECA-l.l step 19 and Encl 5 - PROVIDED QuestionBank # IKA system IKA number J
5211WE04
!EK2.2 I
KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the foIJowing:
EP/II Al50001ECA-l.l (Step 19)
EP/II Al5000IECA-I.1 (Enclosure 5)
(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 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 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)
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)
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)
~ Developed Development References Student References Provided D OPT Approved D OPS Approved D NRC Approved Lesson Plan Objective: EP-EP2 SEQ 29  
D    OPT Approved                     


==References:==
==References:==
EP/IIAl5000IECA-I.1 (Enclosure 5)
: 1. ECA-l.l step 19 and Encl 5 - PROVIDED QuestionBank # IKA system IKA number I
: 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:
5211WE04 IEK2.2 I
KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the foIJowing:
EP/II Al50001ECA-l.l (Step 19)
EP/II Al5000IECA-I.1 (Enclosure 5)
(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.
(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
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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 16 D
QuestionBank # IKA system IKA number I
522 I
WE05 I
EK3.1 I
KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)
(CFR: 41.5! 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 1 B wide range level - 20%
S/G 1C wide range level-23%
S/G 1 D 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
QuestionBank # IKA system IKA_number I
522 I
WE05 I
EK3.1 I
KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)
(CFR: 41.5! 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.
(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:
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 1A wide range level-31 %
* S/G   1B wide range level - 20%
S/G 1 B wide range level - 20%
* S/G   1C wide range level- 23%
S/G 1C wide range level-23%
* S/G   1D wide range level - 28%
S/G 1 D wide range level - 28%
* The   BOP has just secured all the NC pumps
The BOP has just secured all the NC pumps The OATC notes NC system pressure is increasing
* The   OATC notes NC system pressure is increasing
: 1. Why have NC pumps been secured?
: 1. Why have NC pumps been secured?
: 2. Why is NCS pressure increasing?
: 2. Why is NCS pressure increasing?
A.           1. To begin NCS bleed and feed
A.
: 2. Due to NC temperature increase B.         1. To minimize heat input
: 1. To begin NCS bleed and feed
: 2. Due to letdown being secured C.         1. To begin NCS bleed and feed
: 2. Due to NC temperature increase B.
: 2. Due to letdown being secured D.         1. To minimize heat input
: 1. To minimize heat input
: 2. Due to NC temperature increase Wednesday, October 08, 2008                                                                                     Pa!1e 31 of200
: 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.
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 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
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
[Correct Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
  ~ 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)
~ Developed Development References Student References Provided 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.
(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
Wednesday, October 08, 2008 Pa{!e 32 of 200 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
~ Developed Development References Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I
I QUESTION 17                                         c KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:
523 I
(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.
WE 11 I
EK2.1 I
KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:
QUESTION 17 c
(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 1 NI-184B (ND Pump 1 B Cont Sump Suct) and 1 NI-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 QuestionBank # IKA system IKA number I
523 I
WE 11 I
EK2.1 I
KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:
QUESTION 17 c
(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),
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:
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%
FWST level is 55%
* Subcooling is +rF.
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?
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.
A.
B.         Remove power from 1NI-184B (ND Pump 1B Cont Sump Suct) and 1NI-185A (ND Pump 1A Cont Sump Suct)
Terminate safety injection and establish normal charging from the VCT.
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
B.
Remove power from 1 NI-184B (ND Pump 1 B Cont Sump Suct) and 1 NI-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%).
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 RO Comprehension NEW
~ Developed Development References 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:
Question Source Student References Provided (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 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 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 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%.
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
Job Level Cognitive Level QuestionType RO Comprehension NEW  
  ~ 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:
~ Developed Development References ECA l.l 0
(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.
OPT Approved 0
Wednesday, October 08, 2008                                                                                   Pal!e 34 of 200
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:
Question Source Student References Provided (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
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 18 2008 SRO NRC Examination c
I WEl2 IKA_number IKA I
QuestionBank # IKA system IKA number I
number EK1.3 I
524 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)
WEl2 I
EK1.3 I
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 QUESTION 18 2008 SRO NRC Examination c
QuestionBank # IKA_system IKA_number I
524 I
WEl2 I
EK1.3 I
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).
(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:
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.
Attempts to close any MSIV using its individual valve control board pushbutton have failed.
* Safety Injection has not been reset.
Safety Injection has not been reset.
: 1. What additional action is taken per this procedure to attempt to close any MSIV?
: 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?
: 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.
A.
: 2. NC loop T-hots B.         1. Both trains of Main Steam Isolation are initiated.
: 1. Maintenance is dispatched to isolate air to the MSIVs.
: 2. NC loop T-hots C.         1. Maintenance is dispatched to isolate air to the MSIVs.
: 2. NC loop T-hots B.
: 2. S/G pressure D.         1. Both trains of Main Steam Isolation are initiated.
: 1. Both trains of Main Steam Isolation are initiated.
: 2. S/G pressure Wednesday, October 08, 2008                                                                                 Page 35 of 200
: 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 18 c
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
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.
  ~ 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)
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 EP/II A/SOOO/ECA-2.1 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
5241WEI2 iEK1.3 i
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 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
~ Developed Development References Student References Provided EP/II A/SOOO/ECA-2.1 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # jKA system KA number J
5241WEI2 EK1.3 I
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).
(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
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 .............................................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D
QuestionBank # IKA system IKA number I
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:
Given the following events and conditions on Unit 1:
* NC system is at full temperature and pressure.
NC system is at full temperature and pressure.  
          *      "A" Shutdown Bank control rods are fully withdrawn.
"A" Shutdown Bank control rods are fully withdrawn.
* CRD BANK SELECT switch is in the "SBB" position.
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 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.
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?
: 1. What is the current plant Mode of Operation?
: 2. Which of the following describes the first required procedural action(s) for this situation?
: 2. Which of the following describes the first required procedural action(s) for this situation?
A.             1. Mode 2
A.
: 1. Mode 2
: 2. Immediately trip the reactor.
: 2. Immediately trip the reactor.
B.             1. Mode 3
B.
: 1. Mode 3
: 2. Immediately trip the reactor.
: 2. Immediately trip the reactor.
C.             1. Mode 2
C.
: 1. Mode 2
: 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor.
: 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor.
D.             1 Mode 3
D.
1 Mode 3
: 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor.
: 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
Wednesday, October 08, 2008 Pal!e 37 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D
QuestionBank # IKA system IKA number I
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D
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
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.
~ong action, right mode                                                                                                               ~
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 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
Answer B Discussion I ~-----------------------------------------------I  
  ~ Developed AP/15 D   OPT Approved                                     IRE D     OPS Approved D     NRC Approved QuestionBank # IKA system                           KA number         I 5251APEOOI                       AAl.06 I
~ong action, right mode  
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
Answer C Discussion Iright action, wrong mode Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
~ Developed Development References Student References Provided 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 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
~ Developed Development References Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 I
526 I
APE005 J 2.4.6 1
KA desc APE005 GENERICDKnowiedge ofEOP mitigation strategies. (CFR: 41.1 0/43.5/45.13)
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 B
I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 QuestionBank # [KA system
[KA number
[
[
QUESTION 20                B 526     I APE005     J I     2.4.6           1I KA desc                                                                                             I[
526 I
APE005 GENERICDKnowiedge ofEOP mitigation strategies. (CFR: 41.1 0/43.5/45.13)
APE005 I
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.
2.4.6 I
KA desc APE005 GENERICDKnowiedge ofEOP mitigation strategies. (CFR: 41.1 0/43.5/45.13)
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:
When conditions stabilized, the following indications were noted:
* Control Rod Bank 0 demand counters are indicating 190 steps.
Control Rod Bank 0 demand counters are indicating 190 steps.
* Control Rod Bank 0 rod 04 indicates 216 steps withdrawn on DRP!.
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!.
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?
: 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?
: 2. What are the modes of applicability for the corresponding Technical Specification?
A.       1. Verify only one rod - MISALIGNED.
A.
: 2. MODE 1, MODE 2 with keff ::: 1.0 B.       1. Verify only one rod - MISALIGNED.
: 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 B.
: 2. MODE 1, MODE 2 with keff ::: 1.0 D.       1. Ensure "CRD BANK SELECT" switch - IN MANUAL.
: 1. Verify only one rod - MISALIGNED.
: 2. MODE 1, MODE 2
: 2. MODE 1, MODE 2 C.
. Wednesday, October 08, 2008                                                     Pa!!:e 39 of 200
: 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 B
[
I


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 B
Answer A Discussion
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.
\wrong TS applicability Answer B Discussion
Answer A Discussion  
\CORRECT Answer C Discussion
\\wrong TS applicability Answer B Discussion  
\Both wrong (for psychometric balance.)
\\CORRECT Answer C Discussion  
Answer D Discussion
\\Both wrong (for psychometric balance.)
\Wrong action Job Level           Cognitive Level             QuestionType                               Question Source RO                     Memory                    NEW
Answer D Discussion  
~     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)
\\Wrong action Job Level Cognitive Level QuestionType RO  
Wednesday, October 08, 2008                                                                                 Page 40 of 200
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 526APE005 KA desc NEW Development References TS 3.1.6 AP/14 AP/15 TS3.1.4 KA number 2.4.6 APE005 GENERICDKnowledge ofEOP mitigation strategies. (CFR: 41.10/43.5/45.13)
Wednesday, October 08, 2008 Question Source Student References Provided Page 40 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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 526APE005 KA desc NEW Development References TS 3.1.6 AP/14 AP/15 TS3.1.4 KA number 2.4.6 APE005 GENERICDKnowledge ofEOP mitigation strategies. (CFR: 41.10/43.5/45.13)
Wednesday, October 08, 2008 Question Source Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 21 c
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 ....................
QuestionBank # IKA system IKA number I
527 I
APE024 I
AKl.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)OLow temperature limits for born concentration....................
Given the following:
Given the following:
* Unit 1 is in Mode 5
Unit 1 is in Mode 5 BAT temperature is 60&deg; F.
* BAT temperature is 60&deg; F.
FWST temperature is 70&deg; F.
* FWST temperature is 70&deg; 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?
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
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
QuestionBank # IKA system IKA number I
527 I
APE024 I
AKl.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)OLow temperature limits for born concentration....................
Given the following:
Unit 1 is in Mode 5 BAT temperature is 60&deg; F.
FWST temperature is 70&deg; 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE c 2008 SRO NRC Examination 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.
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
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Comprehension NEW  
  ~ 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 ................... .
~ Developed Development References TS 3.9.4 D OPT Approved SLC 16.9-7 D OPS Approved SLC 16.9-11 D NRC Approved QuestionBank # IKA system IKA number I
Wednesday, October 08, 2008                                                                               Pa!!e 42 of 200
527iAPE024 IAKl.04 I
KA desc QUESTION 21 Question Source Student References Provided 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 c 2008 SRO NRC Examination 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 RO Comprehension NEW
~ Developed Development References TS 3.9.4 D OPT Approved SLC 16.9-7 D OPS Approved SLC 16.9-11 D NRC Approved QuestionBank # IKA_system IK~number I
5271APE024 IAKl.04 I
KA desc QUESTION 21 Question Source Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 22 A
CFR 41.8/41.10/ 45.3)0 Effects of voltage changes on performance ...........................
QuestionBank # IKA system IKA number J
528 I
APE033 I
AK1.01 I
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:
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.
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 hours ago, the crew entered AP/1 IA/55001016 (Malfunction of Nuclear Instrumentation), Case III (Intermediate Range Malfunction).
N-36 failed 3 hours 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.
All actions required by AP/1/A/55001016 have been completed.
* A feedwater transient occurs resulting in a reactor trip.
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?
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.
A.
N-35 will indicate higher than the actual value.
The source ranges instruments will energize at a lower actual neutron flux.
The source ranges instruments will energize at a lower actual neutron flux.
B.         N-35 will indicate higher than the actual value.
B.
N-35 will indicate higher than the actual value.
The source ranges instruments will energize at the same actual neutron flux.
The source ranges instruments will energize at the same actual neutron flux.
C.         N-35 will indicate lower than the actual value.
C.
N-35 will indicate lower than the actual value.
The source ranges instruments will energize at the same actual neutron flux.
The source ranges instruments will energize at the same actual neutron flux.
D.         N-35 will indicate lower than the actual value.
D.
N-35 will indicate lower than the actual value.
The source ranges instruments will energize at a higher actual neutron flux.
The source ranges instruments will energize at a higher actual neutron flux.
Wednesday, October 08, 2008                                                                               Pave 43 of 200
Wednesday, October 08, 2008 Pave 43 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 22 A
QuestionBank # lKA system IKA number I
528 I
APE033 I
AK1.01 1
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 hours 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 22 A
Answer A Discussion Answer B Discussion
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.
!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
Answer A Discussion Answer B Discussion  
  ~ 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:
!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  
CFR 41.8 1 41.10 1 45.3)OEffects of voltage changes on performance .......................... .
~ Developed Development References Student References Provided API 1/ A/550010 16 0
Wednesday, October 08, 2008                                                                                     Pal!e 44 of 200
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 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
~ Developed Development References Student References Provided 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 ......................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 23 D
QuestionBank # IKA system IKA number I
529 I
APE037 I
AA2.03 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......................
Given the following:
Given the following:
* Unit 1 is operating with a known 0.6 GPO S/G tube leak
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)
* 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.
* 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?
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)
A.
B.         Comparing S/G feed flow to steam flow mismatch C.         Observing 1EMF-33 (Condenser Air Ejector Exhaust)
Observing 1 EMF-26, 27, 28 and 29 (Steamline 1A - 10)
O.         Observing 1EMF-71, 72, 73, 74 (S/G A-O leakage)
B.
Wednesday, October 08, 2008                                                                                   Pa2:e 45 of 200
Comparing S/G feed flow to steam flow mismatch C.
Observing 1 EMF-33 (Condenser Air Ejector Exhaust)
O.
Observing 1 EMF-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
QuestionBank # IKA_system IKA_number I
529 I
APE037 I
AA2.03 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......................
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 1 EMF-26, 27, 28 and 29 (Steamline 1A - 10)
B.
Comparing S/G feed flow to steam flow mismatch C.
Observing 1 EMF-33 (Condenser Air Ejector Exhaust)
O.
Observing 1 EMF-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).
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)
~ Developed Development References Student References Provided 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 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.
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.
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)
Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2003 NRC Q32 (Bank 232)  
Development References                                         Student References Provided
~ Developed Development References Student References Provided SM lesson 0
  ~ 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 .................... ..
OPT Approved NSD513 OPS Approved 0
Wednesday, October 08, 2008                                                                                       Page 46 of 200
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).
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 24 D
QuestionBank # IKA_system JKA_number I
530 I
EPE074 I
EA1.01 I
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
QuestionBank # lKA system IKA number I
530 I
EPE074 I
EA1.01 l
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?
: 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?
: 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%
A.
: 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 %
: 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 B.
: 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 %
: 1. Two NC Thots less than 328 deg F, RVLlS level greater than 41 %
: 2. Due to the NC system being depressurized Wednesday, October 08, 2008                                                                                 Page 47 of 200
: 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 %
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 24 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
~ Developed Development References Student References Provided F-O 0
OPT Approved FR-C.l and basis 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
530lEPE074 IEA1.01 I
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 D 2008 SRO NRC Examination QUESTION 24 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.
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
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
  ~ 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
~ Developed Development References Student References Provided F-O 0
OPT Approved FR-C.l and basis 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number 530lEPE074 iEA1.01 I
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 25 c
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 ..................
QuestionBank # IKA system IKA number I
531 I
APE036 I
AK3.03 I
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:
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.
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.
1VQ-10 (VQ Fans Disch to Unit Vent) is open to inspect the actuator for air leaks.
* Both trains of SSPS are in "TEST".
Both trains of SSPS are in "TEST".
* The refueling crew dropped a fuel assembly into the refueling cavity.
The refueling crew dropped a fuel assembly into the refueling cavity.
* 1RAD-1 Al2 "1 EMF-39 CONTAINMENT GAS HI RAD" - LIT
1 RAD-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).
* 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?
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
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
QuestionBank # IKA system IKA number I
531 I
APE036 I
AK3.03 I
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.
1 RAD-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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 25 c
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)
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.
Development References                                 Student References Provided
Answer A Discussion IVp is shutdown, partially correct 1 VQ lOis open Answer B Discussion Iboth parts wrong Psychometric balance Answer C Discussion ICORRECT l
~ 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 ................ ..
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)  
Wednesday, October 08, 2008                                                                                 Page 50 of 200
~ Developed Development References Student References Provided AP/25 D OPT Approved VQ D OPS Approved CNT 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 45.6 145.13)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 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 1 VQ 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)
~ Developed Development References Student References Provided AP/25 D OPT Approved VQ D OPS Approved CNT 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 45.6 145.13)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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 26 A
[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:
QuestionBank #jKA system IKA number I
532 I
WED3 I
EK2.1 I
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.
(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:
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)
Cooldown and depressurization is in progress in ES-1.2 (Post Cooldown and Depressurization)
* NC system pressure has stabilized at 410 psig
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 1 ND-1 Band 1 ND-2A (NO Pump 1A Suct from Loop B) will not open Which one of the following statements correctly describes why 1 ND-1 Band 1 ND-2A will not open?
* FWST level is 70% and slowly decreasing
A.
* The operators attempt to place 1A NO train in the RHR mode
The NC system pressure is too high B.
* 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?
1NI-185A (NO pump 1A Suctfrom CNMT Sump) is closed C.
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
ECCS has not been reset D.
1 NI-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
QuestionBank # [KA system IKA_number J
532 I
WED3 I
EK2.1 I
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 1 ND-1 Band 1 ND-2A (NO Pump 1A Suct from Loop B) will not open Which one of the following statements correctly describes why 1 ND-1 Band 1 ND-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.
1 NI-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.
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.
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.
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)
Job Level Cognitive Level QuestionType RO Comprehension BANK  
Development References                                 Student References Provided
~ Developed Development References PS-ND 9 D OPT Approved NSD3.1.30 D OPS Approved ND pages 8, 13 D NRC Approved QuestionBank # IKA system IKA_number I
  ~ 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!
5321WE03 IEK2.1 J
KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:
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.
Question Source 2004 NRC Q50 (Bank 350)
Wednesday, October 08, 2008                                                                                 Pa{!e 52 of 200
Student References Provided (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 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 RO Comprehension BANK
~ Developed Development References PS-ND 9 D OPT Approved NSD3.1.30 D OPS Approved ND pages 8, 13 D NRC Approved QuestionBank # IKA system IKA number I
5321WE03 IEK2.1 KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:
Question Source 2004 NRC Q50 (Bank 350)
Student References Provided (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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 27 D
I   WE09 J
QuestionBank # IKA system IKA number I
I        EK3.3 I
533 I
WE09 I
EK3.3 I
KA desc Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations)
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.
(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:
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.
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 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 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.
The crew has transitioned to ES-0.3 and is preparing to depressurize the NC system.
Which one of the following describes:
Which one of the following describes:
: 1. A condition that would stop the depressurization of the NC system during this cooldown?
: 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?
: 2. How S/G PORVs are being operated to support NC temperature control?
A.         1. PZR Level greater than 70%
A.
: 2. Manually by NLOs stationed in the doghouses B.       1. RVLlS level less than 73%
: 1. PZR Level greater than 70%
: 2. Manually by NLOs stationed in the doghouses C.         1. PZR Level greater than 70%
: 2. Manually by NLOs stationed in the doghouses B.
: 2. In manual from the control room D.       1. RVLlS level less than 73%
: 1. RVLlS level less than 73%
: 2. In manual from the control room Wednesday, October 08, 2008                                                                                   Pa2e 53 of 200
: 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
QuestionBank # [KA_system IKA_number I
533 I
WE09 J
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.
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)
~ Developed Development References Student References Provided ES-0.3 0
OPT Approved SM 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
5331WE09 IEK3.3 J
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 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%.
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 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 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)
Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2006R NRC Q65 (Bank 142)  
Development References                                       Student References Provided
~ Developed Development References Student References Provided ES-0.3 0
~ 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)
OPT Approved SM 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA_number I
5331WE09 IEK3.3 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)OManipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
(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
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 28 c
IKA number I        A2.02 JI I
QuestionBank # IKA system IKA number J
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 ...................
534 I
SYSOO3 I
A2.02 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: 41.5/43.5/45.31 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:
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
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 1 C NC Pump vibration level on the frame is at 6.5 mils using the NC Pump vibration monitor panel.
* 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?
Which one of the following selections is the list of the correct actions based on this situation?
A.         Reinsert Control Bank "A" rods.
A.
Trip 1C NC Pump.
Reinsert Control Bank "A" rods.
Trip 1 C NC Pump.
Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).
Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).
B.         Trip 1C NC Pump.
B.
Trip 1 C NC Pump.
Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).
Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).
C.         Trip the reactor.
C.
Trip 1C NC Pump.
Trip the reactor.
Trip 1 C NC Pump.
Go to EP/1/A15000/E-O (Reactor Trip or Safety Injection).
Go to EP/1/A15000/E-O (Reactor Trip or Safety Injection).
D.         Pump trip criteria is not yet met.
D.
Pump trip criteria is not yet met.
Go To AP/1/A155001008 (Reactor Coolant Pump Malfunction).
Go To AP/1/A155001008 (Reactor Coolant Pump Malfunction).
Wednesday, October 08, 2008                                                                                   Paj!e 55 of 200
Wednesday, October 08, 2008 Paj!e 55 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 28 c
QuestionBank # IKA system IKA number I
534 I
SYSOO3 I
A2.02 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: 41.5/43.5/45.31 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 1 C 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 1 C NC Pump.
Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).
B.
Trip 1 C NC Pump.
Go to AP/1/A155001004 (Loss of Reactor Coolant Pump).
C.
Trip the reactor.
Trip 1 C 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.
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
~ Developed Development References Student References Provided PS-NCP 12 0
OPT Approved OPIl/B/6100101G lAD-6 B/5 OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
5341SYS003 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 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 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 B Discussion Incorrect: With the plant in mode 2, E-O is the correct procedure.
Line 686: Line 1,797:
Answer D Discussion Incorrect: The pump trip criteria is > 5 mils on the frame.
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.
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
Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2004 NRC Q64 (Bank 364) Bank Question: 1183  
  ~ 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 .................. .
~ Developed Development References Student References Provided PS-NCP 12 0
Wednesday, October 08, 2008                                                                                     Pa!!e 56 of 200
OPT Approved OPIl/B/6100101G lAD-6 B/5 OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
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 ...................................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 D
QuestionBank # IKA system IKA number I
535 I
SYSOO4 I
Al.OI I
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:
Unit 1 is operating at 75% with some confirmed failed fuel. Given the following conditions and sequence of events:
* Letdown flow is 75 gpm.
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.
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
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.
* 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?
: 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)?
: 2. What is the applicability of Tech Spec 3.4.16 (RCS Specific Activity)?
A.           1. The demineralizers have been automatically bypassed.
A.
: 2. Modes 1,2, and 3 B.         1. The demineralizers have been automatically bypassed.
: 1. The demineralizers have been automatically bypassed.
: 2. Modes 1 and 2, Mode 3 with Tavg .::: 500&deg;F.
: 2. Modes 1,2, and 3 B.
C.         1. The demineralizers are still in service.
: 1. The demineralizers have been automatically bypassed.
: 2. Modes 1,2, and 3 D.         1. The demineralizers are still in service.
: 2. Modes 1 and 2, Mode 3 with Tavg.::: 500&deg;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&deg;F.
: 2. Modes 1 and 2, Mode 3 with Tavg.::: 500&deg;F.
Wednesday, October 08, 2008                                                                                   Pa!!e 57 of 200
Wednesday, October 08, 2008 Pa!!e 57 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 D
QuestionBank # IKA system IKA number I
535 I SYSOO4 I Al.OI I
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&deg;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&deg;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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 D
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
General Discussion INVI73 diverst to VCT (bypasses Demins) at 136 degrees. The alarm comes in at 128 degrees.
!first part correct, wrong appl Answer D Discussion Job Level             Cognitive Level         QuestionType                                       Question Source RO               Comprehension               NEW Development References                                       Student References Provided
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  
~ 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 .................................. .
!first part correct, wrong appl Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
Wednesday, October 08, 2008                                                                                   Page 58 of 200
~ Developed Development References Student References Provided OPIl/B/61 0010 I OH D OPT Approved NV lesson D OPS Approved TS3.4.I6 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 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
~ Developed Development References Student References Provided OPIl/B/61 0010 I OH D OPT Approved NV lesson D OPS Approved TS3.4.I6 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 30 c
I         K1.34 I
QuestionBank # IKA system IKA number 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 /
536 I
45.7 to 45.8)DInterface between evcs and reactor coolant drain tank; and PZR PCS ....
SYSOO4 I
K1.34 I
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.
1 NC-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 1 NC-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
QuestionBank # IKA system IKA number I
536 I
SYSOO4 I
K1.34 I
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:
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.
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.
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.
1 NC-36B does not re-close and the BOP closed its isolation valve.
* Minimum NC pressure reached during the event was 1820 psig.
Minimum NC pressure reached during the event was 1820 psig.
* Current NC pressure is 2145 psig and increasing.
Current NC pressure is 2145 psig and increasing.
Assuming no operator actions other than isolating 1NC-36B:
Assuming no operator actions other than isolating 1 NC-36B:
: 1. What tank other than the VCT can excess letdown be directed to by 1 NV-125B (Excess Letdn Hx Otlt Ctrl)?
: 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?
: 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
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 30 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
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
~ Developed Development References Student References Provided 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 c 2008 SRO NRC Examination QUESTION 30 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.
!Wrong tank, correct status.
Answer B Discussion
Answer B Discussion  
!Wrong tank, and status (balance)
!Wrong tank, and status (balance)
Answer C Discussion
Answer C Discussion  
!Correct Answer D Discussion
!Correct Answer D Discussion  
!Correct tank, wrong status Job Level           Cognitive Level             QuestionType                                     Question Source RO               Comprehension                     NEW Development References                                       Student References Provided
!Correct tank, wrong status Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
  ~ Developed APIIO D   OPT Approved                         NV D   OPS Approved D   NRC Approved QuestionBank #       IKA   system     IKA   number                 I 536!SYS004           !K1.34                       !
~ Developed Development References Student References Provided APIIO D OPT Approved NV D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I
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 /
536!SYS004  
45.7 to 45.8)OInterface between CVCS and reactor coolant drain tank; and PZR PCS ....
!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 /
Wednesday, October 08, 2008                                                                                         Pa!!e 60 of 200
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) ..........
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 31 D
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.
QuestionBank # IKA system IKA number I
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)..........
1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37A (NO Pump 1 B 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
QuestionBank # IKA system lKA number I
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)..........
1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37A (NO Pump 1 B 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?
: 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?
: 2. How are these valves positioned electrically in the current alignment?
A.         1. Interlocks operate normally
A.
: 2. From the main control boards B.         1. Interlocks operate normally
: 1. Interlocks operate normally
: 2. From the face of alternate MGG breaker G.         1. Interlocks are removed
: 2. From the main control boards B.
: 2. From the main control boards O.         1. Interlocks are removed
: 1. Interlocks operate normally
: 2. From the face of alternate MGG breaker Wednesday, October 08, 2008                                                                           Paffe lil of 200
: 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 31 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  
~ 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) ......... .
~ Developed Development References Student References Provided ND lesson 0
Wednesday, October 08, 2008                                                                                   Page 62 of 200
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 D 2008 SRO NRC Examination QUESTION 31 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
~ Developed Development References Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 32 c
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 ................................................
QuestionBank # IKA system IKA number I
538 I
SYSOO6 I
Al.05 I
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:
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?
NC system pressure (psig)
A.           1206 B.         1212 C.         1218 D.         1224 Wednesday, October 08, 2008                                                                                   PaIJe tl~ of 200
Containment pressure (psig)
FWST level (%)
Time 1200 2130 0.5 98 1206 1950 1.3 97 1212 5
2.8 80 1218 5
4.2 60 1224 5
2.5 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
QuestionBank # IKA system IKA number I
538 I
SYSOO6 I
Al.05 I
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:
NC system pressure (psig)
Containment pressure (psig)
FWST level (%)
Time 1200 2130 0.5 98 1206 1950 1.3 97 1212 5
2.8 80 1218 5
4.2 60 1224 5
2.5 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%)
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 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.
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
Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
~ 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 ............................................... .
~ Developed Development References Student References Provided KC lesson D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I
Wednesday, October 08, 2008                                                                                   Pal!e 64 of 200
5381SYSOO6 IAl.05 I
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 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
~ Developed Development References Student References Provided KC lesson D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I
538iSYSOO6 iAl.05 I
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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 QuestionBank # IKA system IKA number I
539 I
SYS007 I
2.4.6 I
KA desc SYS007 GENERICOKnowledge ofEOP mitigation strategies. (CFR: 4l.10 / 43.5/45.13)
Given the following sequence of events:
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).
1600 A reactor trip occurs 1605 The crew entered EP/1/A/5000/FR-H.1 (Loss of Heat Sink).
Line 773: Line 2,051:
: 1. What minimum SII pump configuration is required to ensure adequate feed?
: 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?
: 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
A.
: 2. One NC PORV B.     1. One NV pump and one NI pump are running
: 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 B.
: 2. One NC PORV D.     1. One NV pump is running
: 1. One NV pump and one NI pump are running
: 2. Two NC PORV Wednesday, October 08, 2008                                                       Pal!e 65 of 200
: 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 D
I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 QuestionBank # IKA system IKA number I
539 I
SYS007 I
2.4.6 I
KA desc 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 D
I


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 D
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level           Cognitive Level           QuestionType                                 Question Source RO             Comprehension                   NEW
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.
~   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)
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Comprehension NEW  
Wednesday, October 08, 2008                                                                                 Pa!1e 66 of 200
~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 539SYS007 KA desc Development References FR-H.l FR-H.l background KA number 2.4.6 SYS007 GENERICOKnowledge ofEOP mitigation strategies. (CFR: 41.10/43.5/45.13)
Wednesday, October 08, 2008 Question Source Student References Provided Pa!1e 66 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 RO Comprehension NEW
~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 539SYS007 KA desc Development References FR-H.l FR-H.l background KA number 2.4.6 SYS007 GENERICOKnowledge ofEOP mitigation strategies. (CFR: 41.10/43.5/45.13)
Wednesday, October 08, 2008 Question Source Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 34 B
* 1AD-6 E/3 "NCP THERMAL BARRIER KC OUTLET HIILO FLOW" - LIT
QuestionBank # IKA system IKA_number I
* OAC indicates KC flow to NCP 1C Thermal Barrier HX is 75 gpm.
540 I SYS008 1 K3.03 I
What effects will this have on NCP 1C and what action should be taken to address the alarm?
KA desc I
A.         NCP 1C seal cooling is being maintained. Verify 1KC-345A (NC Pump 1C Therm Bar Otlt) closes immediately.
Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:ORCP...........................................................
B.         NCP 1C seal cooling is being maintained. Verify 1KC-345A (NC Pump 1C Therm Bar Otlt) closes after a 30 second time delay.
I Unit 1 is in Mode 3 with all shutdown banks withdrawn in preparation for startup when the following occur:
C.         All seal cooling to NCP 1C is lost. Open the #1 seal bypass valve for the 1C NCP to restore cooling.
1AD-6 E/3 "NCP THERMAL BARRIER KC OUTLET HIILO FLOW" - LIT OAC indicates KC flow to NCP 1 C Thermal Barrier HX is 75 gpm.
D.         All seal cooling to NCP 1C is lost. Trip NCP 1C to prevent seal failure.
What effects will this have on NCP 1 C and what action should be taken to address the alarm?
Wednesday, October 08, 2008                                                                                   P<>(JP (\'7 nf '?OO
A.
NCP 1 C seal cooling is being maintained. Verify 1 KC-345A (NC Pump 1 C Therm Bar Otlt) closes immediately.
B.
NCP 1 C seal cooling is being maintained. Verify 1 KC-345A (NC Pump 1 C Therm Bar Otlt) closes after a 30 second time delay.
C.
All seal cooling to NCP 1 C is lost. Open the #1 seal bypass valve for the 1 C NCP to restore cooling.
D.
All seal cooling to NCP 1 C is lost. Trip NCP 1 C to prevent seal failure.
Wednesday, October 08, 2008 P<>(JP (\\'7 nf '?OO FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 34 B
2008 SRO NRC Examination QuestionBank #JKA system IKA number I
540 I
SYS008 I
K3.03 I
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 1 C Thermal Barrier HX is 75 gpm.
What effects will this have on NCP 1 C and what action should be taken to address the alarm?
A.
NCP 1 C seal cooling is being maintained. Verify 1 KC-345A (NC Pump 1 C Therm Bar Otlt) closes immediately.
B.
NCP 1 C seal cooling is being maintained. Verify 1 KC-345A (NC Pump 1 C Therm Bar Otlt) closes after a 30 second time delay.
C.
All seal cooling to NCP 1 C is lost. Open the #1 seal bypass valve for the 1 C NCP to restore cooling.
D.
All seal cooling to NCP 1 C is lost. Trip NCP 1 C 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 34 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.
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.
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.
Line 801: Line 2,134:
Answer D Discussion Incorrect: This would be correct if all seal cooling is lost in this mode.
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.
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
Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2004 NRC Q53 (Bank 353) Bank Question: 1170 B
~   Developed                           Development References                                   Student References Provided
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 540SYS008 KA desc


==References:==
==References:==
: 1. OP-CN-PSS-KC page 12
: 2. OP-CN-PS-NCP pages 15-19 KA number K3.03 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 QUESTION 34 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 B
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 540SYS008 KA desc


o  OPT Approved                        1. OP-CN-PSS-KC page 12
==References:==
: 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
: 1. OP-CN-PSS-KC page 12
: 2. OP-CN-PS-NCP pages 15-19 KA number K3.03 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 ............................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 35 A
QuestionBank # IKA system IKA_number I
541 I
SYSOO8 I
K4.09 J
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
QuestionBank # IKA_system lKA_number I
541 I
SYSOO8 I
K4.09 I
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:
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.
2A 1, 2B1, and 2B2 KC Pumps are in service.
* Both 2ETA and 2ETB are aligned to Unit 1 offsite power
Both 2ETA and 2ETB are aligned to Unit 1 offsite power An 86S relay actuates on 2ETB All systems respond appropriately in automatic.
* An 86S relay actuates on 2ETB
* All systems respond appropriately in automatic.
Assuming no operator actions, which Unit 2 KC pumps are in service?
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
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.
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 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 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)
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)
Job Level Cognitive Level RO
  ~    Developed                                Development References                                Student References Provided D   OPT Approved D     OPS Approved D   NRC Approved QuestionBank #          IKA
~ Developed D OPT Approved D OPS Approved D NRC Approved Memory QuestionType MODIFIED Development References QuestionBank # IKA system IKA number I
                    #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 ...................... " .. ..
54IISYS008 IK4.09 j
Wednesday, October 08, 2008                                                                                       Page 70 of 200
KA desc Question Source 2007 NRC Q36 (Bank 836)
Student References Provided 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 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 RO
~ Developed D OPT Approved D OPS Approved D NRC Approved Memory QuestionType MODIFIED Development References QuestionBank #JKA system IKA number I
54IISYS008 IK4.09 I
KA desc Question Source 2007 NRC Q36 (Bank 836)
Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 36 B
* A pressurizer PORV opens spuriously and will not close
2008 SRO NRC Examination QuestionBank # IKA system IKA_number I
* 5 minutes after the PORV opens, the block valve is closed.
542 I SYSOI0j 2.1.25 I
* NC pressure is 1500 psig
KA desc I
* NC temperature is 550 of
SYSOIO GENERICDAbiIity to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12)
* PRT pressure is 45 psig What is the approximate pressurizer PORV tailpipe temperature?
I Given the following sequence of events and conditions:
Reference provided A.     270 of B.     290 of C.     310 of D.     320 of Wednesday, October 08, 2008                                                                               Page 71 of 200
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 QUESTION 36 B
2008 SRO NRC Examination QuestionBank # IKA system IKA number I
542 I
SYSOI0 I
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)
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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 542SYSOlO KA desc ASME Steam Tables KA number 2.1.25 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 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 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)
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
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)
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 542SYSOlO KA desc ASME Steam Tables KA number 2.1.25 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
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 37 D
QuestionBank # IKA system IKA number I
543 I
SYS012 I
A2.02 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 /45.3 / 45.5)DLoss of instrument power Given the following conditions and sequence of events:
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.
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
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.
* IAE has not yet placed the required bistables in the trip condition per AP/1/A/5500/016.
A complete loss of 1 ERPD occurs What procedure takes priority for these conditions?
* A complete loss of 1ERPD occurs What procedure takes priority for these conditions?
A.
A.               Continue in AP/1/A/5500/016 B.               Enter AP/1/A/5500/029 (Loss of Vital or Aux Control Power)
Continue in AP/1/A/5500/016 B.
C.               Enter AP/1/A/5500/003 (Load Rejection)
Enter AP/1/A/5500/029 (Loss of Vital or Aux Control Power)
D.               Enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)
C.
Wednesday, October 08, 2008                                                                                   Page 73 of 200
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
QuestionBank # IKA system IKA number I
543 I
SYS012 I
A2.02 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 /45.3 / 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 1 ERPD 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~
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 37 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.                                                                                         ~
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 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 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 C Discussion There are 2/4 OTDT and if a reactor trip did not occur, a runback would.
Answer*D Discussion ICORRECT.
Answer*D Discussion ICORRECT.
Job Level             Cognitive Level           QuestionType                                   Question Source RO                 Comprehension                 NEW Development References                                   Student References Provided
Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
~ Developed ENB lesson 0   OPT Approved                         EPL lesson 0   OPS Approved 0   NRC Approved QuestionBank # IKA system             IKA   number             I 5431SYS012           IA2.02 I
~ Developed Development References Student References Provided ENB lesson 0
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
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 D 2008 SRO NRC Examination QUESTION 37 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
~ Developed Development References Student References Provided 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?
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 QuestionBank # IKA system IKA number I
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
544 I
SYS012 1 K5.01 I
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 D
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 QuestionBank # IKA system IKA_number I
544 J SYS012 I
K5.01 I
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 D


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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 D
Development References             Student References Provided
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)  
  ~ Developed TS 3.3.1 and bases D     OPT Approved                                         IPX D     OPS Approved D       NRC Approved QuestionBank # \KA_system     IKA    system            IKA  number
~ Developed Development References Student References Provided TS 3.3.1 and bases D OPT Approved IPX D OPS Approved D NRC Approved QuestionBank # \\KA_system  
                                                        \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
\\KA_number j
5441SYSOl2 IK5.01 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 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)
~ Developed Development References Student References Provided TS 3.3.1 and bases D OPT Approved IPX D OPS Approved D NRC Approved QuestionBank # IKA system IKA number 5441SYSOl2 iK5.01 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[
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 39 B
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:
QuestionBank # [KA system
* Unit 1 was performing a heatup following a refueling outage
[KA_number
* NC Temperature was 400 of
[
* NC pressure was 1600 psig
545 I
                  *      "A" and "B" shutdown banks were withdrawn
SYS013 I
* Containment Pressure Channel II failed high Current Conditions:
K6.01 I
* 1ERPD has lost power
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:
* Containment pressure channels read:
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:
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?
1 ERPD has lost power Containment pressure channels read:
A.               Only Train "A" safety injection actuates.
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.
Implement EP/1/A/5000/E-O, Reactor Trip or Safety Injection.
B.               Only Train "A" safety injection actuates.
B.
Only Train "A" safety injection actuates.
Implement AP/1/A/5500/005, Reactor Trip or Inadvertent S/I Below P-11.
Implement AP/1/A/5500/005, Reactor Trip or Inadvertent S/I Below P-11.
C.               Train "A" and "B" safety injection actuates.
C.
Train "A" and "B" safety injection actuates.
Implement EP/1/A/5000/E-O, Reactor Trip or Safety Injection.
Implement EP/1/A/5000/E-O, Reactor Trip or Safety Injection.
D.               Train "A" and "B" safety injection actuates.
D.
Train "A" and "B" safety injection actuates.
Implement AP/1IA/5500/005, Reactor Trip or Inadvertent S/I Below P-11.
Implement AP/1IA/5500/005, Reactor Trip or Inadvertent S/I Below P-11.
Wednesday, October 08, 2008                                                                             Page 77 of 200
Wednesday, October 08, 2008 Page 77 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 39 B
QuestionBank # IKA system IKA number I
545 I
SYS013 I
K6.01 I
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:
1 ERPD 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.
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 o OPT Approved OOPS Approved o NRC Approved Development References Lesson 0 OP-CN-ECCS-ISE Objectives02 & 3 REFERENCESOAP/1/A/5500/029 Enclosure 17 (lERPD load list) rev 013 QuestionBank # IKA system IKA number I
545ISYS013 JK6.01 I
KA desc Student References Provided 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 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.
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.
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.
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
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
~ Developed o OPT Approved OOPS Approved o NRC Approved Development References Lesson 0 OP-CN-ECCS-ISE Objectives02 & 3 REFERENCESOAP/1/A/5500/029 Enclosure 17 (lERPD load list) rev 013 QuestionBank # IKA system IKA number I
545ISYS013 IK6.01 J
KA desc Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 QuestionBank #IKA system IKA number J
                #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.
546 I
SYS022 I
K2.02 I
KA desc Knowledge of power supplies to the following: (CFR: 41.7)OChillers........................................................
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?
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
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 D
I I
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 QuestionBank # IKA system IKA number I
546 I
SYS022 I
K2.02 I
KA desc Knowledge of power supplies to the following: (CFR: 41.7)OChillers........................................................
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 D
I I


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 D
Answer D Discussion Job Level         Cognitive Level             QuestionType                                               Question Source RO                 Memory                       NEW
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.
~   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 ...................................................... ..
Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
Wednesday, October 08, 2008                                                                                                 Page 80 of 200
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 546SYS022 KA desc RN lesson KA number K2.02 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 546SYS022 KA desc RN lesson KA number K2.02 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 QuestionBank # IKA system IKA number I
547 I
SYS025 I
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:
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
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?
* 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.
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
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 A
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 QuestionBank # IKA system IKA number I
547 I
SYS025 1 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 A


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 A
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion 1'---__________________________-----'
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.
Job Level           Cognitive Level           QuestionType                               Question Source RO                   Memory                     NEW Development References                                 Student References Provided
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW
~ 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
~ Developed Development References Student References Provided NF lesson 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
547!SYS025 IA4.01 I
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 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  
~ Developed Development References Student References Provided NF lesson 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
547jSYS025 jA4.01 I
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 ...........................................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 42 c
QuestionBank # IKA system IKA_number I
548 I
SYS026 I
A1.03 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) 0 Containment sump level...........................................
Given the following:
Given the following:
* A large break LOCA has occurred.
A large break LOCA has occurred.
* Containment pressure is 3.2 psig and slowly decreasing.
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)
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?
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
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
QuestionBank # IKA system IKA number I
548 I
SYS026 I
A1.03 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) 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 42 c
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
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.
~ 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 .......................................... .
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
Wednesday, October 08, 2008                                                                                   Page 84 of 200
~ Developed Development References Student References Provided 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 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
~ Developed Development References Student References Provided 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 .......................................... ,...............
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 43 A
QuestionBank # IKA system IKA number J
549 I
SYS026 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 1 NI-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 1 A 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
QuestionBank # IKA system IKA_number I
549 I
SYS026 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:
Given the following sequence of events:
1200 Unit 1 reactor tripped from 100% power due to a large break LOCA 1236 BOP reports:
1200 Unit 1 reactor tripped from 100% power due to a large break LOCA 1236 BOP reports:
* FWST level is currently 36% and decreasing
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.
* 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.
1241 1A NO pump is secured.
1245 NLOs have been dispatched to manually open 1NI-185A.
1245 NLOs have been dispatched to manually open 1 NI-185A.
1300 NLOs report 1 NI-185A is fully open.
1300 NLOs report 1 NI-185A is fully open.
1301 1A NO pump is started.
1301 1A NO pump is started.
1305 BOP reports:
1305 BOP reports:
* FWST level is currently 16% and decreasing
FWST level is currently 16% and decreasing Containment pressure is 3.1 psig and decreasing Which one of the following states:
* Containment pressure is 3.1 psig and decreasing Which one of the following states:
: 1. What was the status of the 1 A NS pump at 1245?
: 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?
: 2. What was the earliest time that any NO Aux Spray could be aligned if needed?
A.       1. 1A NS pump was running
A.
: 2. 1250 B.       1. 1A NS pump was running
: 1. 1A NS pump was running
: 2. 1301 C.       1. 1A NS pump was off
: 2. 1250 B.
: 2. 1250 O.       1. 1A NS pump was off
: 1. 1A NS pump was running
: 2. 1301 Wednesday, October 08, 2008                                                                               Page 85 of 200
: 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.
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.
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.
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.
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
Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
  ~ 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 ........................................................ ..
~ Developed Development References Student References Provided NS lesson 0
Wednesday, October 08, 2008                                                                               Page 86 of 200
OPT Approved ES 1.3 0
OPS Approved ES 1.3 background 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 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
~ Developed Development References Student References Provided NS lesson 0
OPT Approved ES 1.3 0
OPS Approved ES 1.3 background 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 ........................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 44 D
QuestionBank # IKA system IKA number I
550 I
SYS039 I
K5.01 J
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:
Given the following conditions and sequence of events:
* Unit 1 is manually tripped due to a loss of normal feedwater
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 1 CA-58A (CA Pump A Disch To S/G 1 B Isol) have failed NLOs have been dispatched to manually isolate flow to 1 B S/G When CA flow is secured to 1 B S/G, level is noted to be 96% on NR level gauges Which of the following consequences have increased risk for 1 B S/G based on the current water level in that S/G?
* 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
: 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
: 2. Failure of S/G PORV and/or SM safety valves to reseat following an actuation
: 3. Water hammer upon initiation of steam flow
: 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
: 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
QuestionBank # IKA system IKA number I
550 I
SYS039 I
K5.01 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........................
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 1 CA-58A (CA Pump A Disch To S/G 1 B Isol) have failed NLOs have been dispatched to manually isolate flow to 1 B S/G When CA flow is secured to 1 B S/G, level is noted to be 96% on NR level gauges Which of the following consequences have increased risk for 1 B 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 44 D
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
General Discussion 2, 3 and 4 are all potential consequences of a SO overfill.
~ 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
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
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 ...................... ..
~ Developed Development References Student References Provided SM lesson 0
Wednesday, October 08, 2008                                                                               Page 88 of 200
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 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
~ Developed Development References Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 45 B
* The plant is currently stable.
QuestionBank # IKA system IKA number I
* The steam dumps have just closed at no-load Tave.
551 I
* Steam generator NR levels are 35% in unaffected steam generators and 80%
SYS059 I
A4.11 I
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
QuestionBank # IKA system IKA_number I
551 I
SYS059 I
A4.11 I
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.
in the affected steam generator.
What action must the operator take to reset CF isolation?
What action must the operator take to reset CF isolation?
A.               Cycle the reactor trip breakers only.
A.
B.               Cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.
Cycle the reactor trip breakers only.
C.               Lower the affected steam generator level and cycle the reactor trip breakers.
B.
D.               Lower the affected steam generator level, cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.
Cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.
Wednesday, October 08, 2008                                                                             Page 89 of 200
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 45 B
S/!.
General Discussion Answer A Discussion Incorrect: must also depress FWI push buttons Plausible: would be true ifP-41L0w Tave FWI had not occurred. Cycling Rx trip breakers does clear auto S/I block following an 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 B Discussion Correct: to clear the P-14, the trip breakers must be cycled. To clear the low tave/p-4 FWI, 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 C Discussion Incorrect: not need to reduce S/G level on Unit 1 - must reset FWI Plausible: partially correct - would be true on Unit 2 and Low Tave/P-4 FWI had not occurred.
Answer D Discussion Incorrect: no need to reduce S/G level Plausible: would be true on unit 2.
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
Job Level Cognitive Level QuestionType RO  
~   Developed                           Development References                                 Student References Provided Lesson Plan Objective: ISE Obj: 5 D    OPT Approved                       
~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension BANK Development References Lesson Plan Objective: ISE Obj: 5  


==References:==
==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
: 1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank # IKA system IKA number I
L_
5511SYS059 IA4.11 I
KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question: 970BH Student References Provided 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 QUESTION 45 B
General Discussion Answer A Discussion Incorrect: must also depress FWI push buttons Plausible: would be true ifP-4lLow Tave FWI had not occurred. Cycling Rx trip breakers does clear auto sir block following an SII.
Answer B Discussion Correct: to clear the P-14, the trip breakers must be cycled. To clear the low tave/p-4 FWr, it must be reset.
Answer C Discussion Incorrect: not need to reduce S/G level on Unit 1 - must reset FWr Plausible: partially correct - would be true on Unit 2 and Low Tave/P-4 Fwr 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 RO
~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension BANK Development References Lesson Plan Objective: ISE Obj: 5


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
==References:==
~ 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:
: 1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank # IKA_system IKA_number I
* Unit 2 was operating at 100% power.
L_
* 2A steamline ruptured inside containment resulting in containment pressure rapidly increasing to 3.7 psig.
5511SYS059 IA4.11 I
* Current containment pressure is 2.4 psig and slowly decreasing.
KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question: 970BH Student References Provided 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
* 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).
 
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 46 D
QuestionBank # IKA system IKA number I
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?
Within what operating band should the BOP be attempting to control S/G N/R levels?
A.         Between 11 % and 50%
A.
B.         Between 29% and 50%
Between 11 % and 50%
C.         Between 9% and 62%
B.
D.         Between 21% and 62%
Between 29% and 50%
Wednesday, October 08, 2008                                                                             Page 91 of 200
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
QuestionBank # IKA system IKA number I
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 46 D
Answer A Discussion
General Discussion ACC values should be used since containment pressure exceeded 3 psig even though it has been redced below 3 psig.
!Unit 1 non-ACC number Answer B Discussion
Answer A Discussion  
!Unit 1 ACC numbers Answer C Discussion
!Unit 1 non-ACC number Answer B Discussion  
!Unit 2 non-ACC numbers Answer D Discussion Job Level           Cognitive Level           QuestionType                                 Question Source RO                   Memory                   NEW
!Unit 1 ACC numbers Answer C Discussion  
~   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 ........................... .
!Unit 2 non-ACC numbers Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
Wednesday, October 08, 2008                                                                               Page 92 of 200
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 552 SYS061 KA desc E-O KA number A3.03 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 552 SYS061 KA desc E-O KA number A3.03 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 QuestionBank # IKA system IKA_number I
* 2B DIG automatically started due to the incoming breaker to 2ETB spuriously opening.
553 I
* While checking DIG operating parameters, the crew notes that DIG 2B "VOLTS" is 4300 V.
SYS062 I
* At the direction of the CRS, the BOP adjusts voltage to normal.
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?
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
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 B
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 QuestionBank # IKA system IKA number I
553 I
SYS062 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 B


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 B
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
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.
  ~ Developed DG31esson 0   OPT Approved 0   OPS Approved 0   NRC Approved QuestionBank # IKA system           IKA number               I 553[SYS062         [A3.0!                     [
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
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
~ Developed Development References Student References Provided 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 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
~ Developed Development References Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 QuestionBank # [KA_system
[KA_system QuestionBank # IKA 554        I system [KA_number SYS063
[KA_number
[KA number I         K2.01 I[
[
II QUESTION 48              c KA desc                                                                                               I[
554 I
Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads I
SYS063 I
Which of the following buses powers the Unit 1 Turbine Emergency Bearing Oil Pump (EBOP)?
K2.01 I
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
KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads Which of the following buses powers the Unit 1 Turbine Emergency Bearing Oil Pump (EBOP)?
A.
1 EDB - 125V Vital Instrumentation and Control Power B.
1 EMXF - 600V Unit Essential Power C.
1 DPD - 250V Auxilary Power D.
SMXD - 600V Shared Power Wednesday, October 08, 2008 Page 95 of 200 c
[
I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 QuestionBank # IKA system
[KA number I
554 I
SYS063 I
K2.01 I
KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads Which of the following buses powers the Unit 1 Turbine Emergency Bearing Oil Pump (EBOP)?
A.
1 EDB - 125V Vital Instrumentation and Control Power B.
1 EMXF - 600V Unit Essential Power C.
1 DPD - 250V Auxilary Power D.
SMXD - 600V Shared Power Wednesday, October 08, 2008 Page 95 of 200 c
I I


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.
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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 554SYS063 KA desc EPL KA number K2.01 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 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 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.
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
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 ................................................ .
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 554SYS063 KA desc EPL KA number K2.01 Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads.................................................
Wednesday, October 08, 2008                                                                                           Page 96 of 200
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 49 c
number K3.01 JI I
QuestionBank # IKA system lKA number J
QUESTION 49                                     c I
555 I
SYS063 I
K3.01 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 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 1 DGCA 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 1 A 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
QuestionBank # IKA system IKA_number I
555 I
SYS063 J K3.01 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 I 45.6) 0 ED/G Unit 1 was operating at 10% power preparing to roll the turbine. Given the following sequence of events:
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.
0200 - 1A DIG Battery Charger 1 DGCA fails.
0700 - DIG 1A Panel, E/5 "LOSS OF DC CONTROL POWER" - LIT 0900 - A tornado results in a complete loss of the switchyard.
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?
Assuming no actions have been taken to address the failed charger, which one of the following statements correctly describes the operating status of the 1 A DIG and the reason for this status?
A.               The 1A DIG starts because the auto-start function is not dependent on DC control power.
A.
B.               The 1A DIG starts because the loads of the failed charger are supplied from vital power through auctioneering diode 1VADA.
The 1A DIG starts because the auto-start function is not dependent on DC control power.
C.               The 1A DIG did not start because it has lost all control power.
B.
D.               The 1A DIG started but did not tie to the bus because the sequencer has lost all control power.
The 1A DIG starts because the loads of the failed charger are supplied from vital power through auctioneering diode 1VADA.
Wednesday, October 08, 2008                                                                                   Page 97 of 200
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 hours.
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 V ADA 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 o OPT Approved OOPS Approved o NRC Approved Development References Lesson Plan Objective: DG-DGI-14, 19


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.
==References:==
: 1. OP-CN-DG-DGI pages 17-19,26 QuestionBank # IKA system IKA number I
5551SYS063 IK3.01 I
KA desc Student References Provided 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 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 hours.
Plausible: If the candidate thinks that the battery will carry DC control power loads for> 2 hours.
Answer B Discussion Incorrect: DIG will not start.
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.
Plausible: if student thinks that control power to the DIG is available thru VADA. This is reversed, the DGCA supplies power thru V ADA to the sequencer.
Answer C Discussion ICorrect:
Answer C Discussion ICorrect:
Answer D Discussion Incorrect: DIG will not start.
Answer D Discussion Incorrect: DIG will not start.
Plausible: The sequencer has normal power available thru lEDA (from vital power)
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
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                       
~ Developed o OPT Approved OOPS Approved o NRC Approved Development References Lesson Plan Objective: DG-DGI-14, 19  


==References:==
==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
: 1. OP-CN-DG-DGI pages 17-19,26 QuestionBank # IKA system IKA number I
5551SYS063 IK3.01 I
KA desc Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 50 B
* Unit 2 was operating at 100% power when a LOCA occurred
QuestionBank # IKA_system IKA_number I
* Containment pressure peaked at 2.6 psig and is slowly decreasing
556 I
* 1A CA Pump failed to start
SYS064 1 A3.07 I
          *  "A" train ECCS and O/G load sequencer was reset
KA~
* 1A CA Pump was manually started
I Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/ 45.5)OLoad sequencing.................................................
* 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?
I Given the following conditions and sequence of events:
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
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
QuestionBank # IKA system IKA number I
556 I
SYS064 I
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 ...
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 50 B
Answer D Discussion This would occur if BOTH trains were reset Job Level           Cognitive Level             QuestionType                                 Question Source RO               Comprehension                   NEW
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...
  ~   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 ................................................ .
Answer D Discussion This would occur if BOTH trains were reset Job Level Cognitive Level QuestionType RO Comprehension NEW  
Wednesday, October 08, 2008                                                                                   Page 100 of 200
~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 556SYS064 KA desc Development References E-O and backgmd doc EQB KA number A3.07 Question Source Student References Provided 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 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 RO Comprehension NEW
~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 556SYS064 KA desc Development References E-O and backgmd doc EQB KA number A3.07 Question Source Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 51 QuestionBank # IKA system IKA number I
* DIG 1A Panel, B/8 "LOW VG AIR TANK PRESS" - LIT
557 I
* 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?
SYS064 I
A.               The DIG cannot be manually or automatically started until the VG receiver is repressurized.
K6.07 I
B.               The DIG can be manually started and is capable of one or two starts.
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:
C.               The DIG can be automatically started and is capable of one or two starts.
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?
D.               The DIG can be automatically started and is capable of five starts.
A.
Wednesday, October 08, 2008                                                                             Page 101 of200
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 B
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 51 QuestionBank # IKA system IKA number I
557 I
SYS064 I
K6.07 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 B


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.
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 RO Comprehension BANK
~ Developed Development References
: 1. DG 1 lesson D OPT Approved
: 2. Tech Spec Bases 3.8.3 El D OPS Approved D NRC Approved QuestionBank # JKA system jKA number j
557!SYS064 jK6.07 J
KA desc Question Source 2003 NRC Q64 (Bank 264)
Student References Provided 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 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.
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.
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.
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)
Plausible: This is the FSAR requirement for the number of starts on a DIG Job Level Cognitive Level QuestionType RO Comprehension BANK  
Development References                                 Student References Provided
~ Developed Development References
~ Developed
: 1. DG 1 lesson D OPT Approved
: 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
: 2. Tech Spec Bases 3.8.3 El D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I
                                      !K6.07                   J!
557!SYS064  
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
!K6.07 KA desc Question Source 2003 NRC Q64 (Bank 264)
Student References Provided 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   [
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 52 B
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 .................................................
QuestionBank # [KA system
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.
[KA number
[
558 I
SYS073 I
A2.02 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 1 EMF-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
QuestionBank # [KA system
[KA number
[
558 I
SYS073 I
A2.02 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 1 EMF-39 "CONTAINMENT GAS HI RAD" detector fails causing a Trip 2 alarm.
: 1. What is the status of the Unit 1 Containment Evacuation 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?
: 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.
A.
: 1. The Containment Evacuation alarm has actuated.
: 2. Bypass the failed EMF detector and then RESET the safety signal.
: 2. Bypass the failed EMF detector and then RESET the safety signal.
B.               1. The Containment Evacuation alarm has NOT actuated.
B.
: 1. The Containment Evacuation alarm has NOT actuated.
: 2. Bypass the failed EMF detector and then RESET the safety signal.
: 2. Bypass the failed EMF detector and then RESET the safety signal.
C.               1. The Containment Evacuation alarm has actuated.
C.
: 1. The Containment Evacuation alarm has actuated.
: 2. RESET the safety signal only.
: 2. RESET the safety signal only.
D.               1. The Containment Evacuation alarm has NOT actuated.
D.
: 1. The Containment Evacuation alarm has NOT actuated.
: 2. RESET the safety signal only.
: 2. RESET the safety signal only.
Wednesday, October 08, 2008                                                                                 Page 103 of 200
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).
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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension NEW Development References OP/1/B/61 00/0 I 0 X QuestionBank # IKA system IKA number I
55S[SYS073
[A2.02
[
KA desc Question Source Student References Provided 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 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.
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%
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)
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
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO  
~     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                     [
~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension NEW Development References OP/1/B/61 00/0 I 0 X QuestionBank # IKA system IKA number 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: 41.5 143.5 145.3 1 45. I 3) D Detector failure ............................................... ..
55S[SYS073
Wednesday, October 08, 2008                                                                                 Page 104 of 200
[A2.02
[
KA desc Question Source Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 53 A
              #/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 .................................................. ..
2008 SRO NRC Examination QuestionBank #/KA system IKA number J
559 I
SYS076 I
K2.01 I
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:
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
A.
4160V bus 1 ETA 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
QuestionBank # IKA system IKA_number I
559 J SYS076 I
K2.01 I
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 1 ETA 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.
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 A Discussion Answer B Discussion '
Answer C Discussion Answer D Discussion Job Level             Cognitive Level           QuestionType                                         Question Source RO                   Memory                       NEW
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 .................................................. ..
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 559 SYS076 KA desc RN lesson EPC lesson KA number K2.0l Knowledge of bus power supplies to the following: (CFR: 41.7)DService water....................................................
Wednesday, October 08, 2008                                                                                               Page 106 of 200
Wednesday, October 08, 2008 Page 106 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 559 SYS076 KA desc RN lesson EPC lesson KA number K2.0l 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 ........................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 54 B
QuestionBank # IKA system IKA number I
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.
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?
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
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
QuestionBank # IKA system IKA number I
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 54 General Discussion INV294 and INV309 fail open, letdown orifice vlaves fail closed on loss of air. Letdown isolation valves lNV-IA and INV-2A fail close on Loss of VI Answer A Discussion Ipartially correct.
Answer B Discussion Answer C Discussion Ireversed - psychometric balance Answer D 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
Job Level Cognitive Level QuestionType RO  
~   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 ....................... .
~ Developed D OPT Approved D OPS Approved D NRC Approved Memory NEW Development References NV lesson QuestionBank # IKA system IKA number I
Wednesday, October 08, 2008                                                                                   Page 108 of 200
560lSYS078 IK3.02 I
KA desc Question Source Student References Provided 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 B 2008 SRO NRC Examination QUESTION 54 General Discussion INY294 and INY309 fail open, letdown orifice vlaves fail closed on loss of air. Letdown isolation valves lNY-IA and INY-2A fail close on Loss ofYI Answer A Discussion Ipartially correct.
Answer B Discussion Answer C Discussion Ireversed - psychometric balance Answer D Discussion Ipartially correct.
Job Level Cognitive Level QuestionType RO
~ Developed D OPT Approved D OPS Approved D NRC Approved Memory NEW Development References INY lesson QuestionBank # IKA system IKA number I
560lSYS078 IK3.02 I
KA desc Question Source Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 55 A
41.2 to 41.9 / 45.7 to 45. 8)0 Containment vacuum system .......................................
QuestionBank # IKA system IKA_number I
561 I
SYSI03 L
K1.07 1
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).
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?
: 1. What is a potential negative consequence of 1 VQ-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?
: 2. What EMFs in Trip 2 alarm send a closed signal to 1VQ-10?
A.         1. Non-compliance with technical specification on containment pressure
A.
: 1. Non-compliance with technical specification on containment pressure
: 2. Unit Vent EMFs (35L, 36L)
: 2. Unit Vent EMFs (35L, 36L)
B.         1. Unexpected opening of ice condenser inlet doors
B.
: 1. Unexpected opening of ice condenser inlet doors
: 2. Unit Vent EMFs (35L, 36L)
: 2. Unit Vent EMFs (35L, 36L)
C.         1. Non-compliance with technical specification on containment pressure
C.
: 1. Non-compliance with technical specification on containment pressure
: 2. Containment EMFs (38L, 39L)
: 2. Containment EMFs (38L, 39L)
D.         1. Unexpected opening of ice condenser inlet doors
D.
: 1. Unexpected opening of ice condenser inlet doors
: 2. Containment EMFs (38L, 39L)
: 2. Containment EMFs (38L, 39L)
Wednesday, October 08, 2008                                                                               Page 109 of 200
Wednesday, October 08, 2008 Page 109 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 55 A
QuestionBank # IKA system IKA number J
561 I
SYSI03 I
K1.07 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)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 1 VQ-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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 55 A
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
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 1 VQ-l O.
  ~ 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
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 VQ lesson 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA_system IKA_number 5611SYS103 IK1.07 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 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 1 VQ-l O.
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 VQ lesson 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA system 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:
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 ......................................
41.2 to 41.9 / 45.7 to 45.8)DContainment vacuum system.......................................
Wednesday, October 08, 2008                                                                                   Page 110 of200
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 56 QuestionBank # IKA system IKA number I
562 I
SYSOOI I
K2.02 I
KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)DOne-line diagram of power supply to trip breakers.....................
Unit 2 is operating at 100% power with Reactor Trip breaker RTA is out of service for PMs.
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?
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
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 A
I I
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 56 A
QuestionBank # IKA system IKA number I
562 I
SYSOOI i K2.02 I
KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)DOne-line diagram of power supply to trip breakers.....................
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.
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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 562SYSOOI KA desc IPX KA number K2.02 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 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 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.
Answer D Discussion IIF student thinks the breaker will stay closed.
Job Level             Cognitive Level             QuestionType                                 Question Source RO                   Memory                       NEW
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 .................... .
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 562SYSOOI KA desc IPX KA number K2.02 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
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 ........................................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 57 D
QuestionBank # IKA system IKA number I
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
QuestionBank # IKA system IKA number I
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:
Initial conditions at 1300:
* Unit 2 was at 50% power
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):
* Pressurizer level was at program level
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)?
* 2NV-312A (Chrg Line Cont Isol) spuriously closed and could not be reopened
Reference provided A.
* Operators have taken the following actions per AP/21N55001012 (Loss of Charging or Letdown), Case I (Loss of Charging):
1434 B.
o Secured letdown o Total charging flow has been reduced to 32 gpm
1608 C.
* Excess letdown can not be established At approximately what time will the pressurizer become inoperable per Tech Spec 3.4.9 (Pressurizer)?
1651 D.
Reference provided A.         1434 B.         1608 C.         1651 D.         1825 Wednesday, October 08, 2008                                                                                   Page 113 of 200
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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 57 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).
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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension MODIFIED Development References LessonDOP-CN-PS-ILE rev 23 REFERENCESDTS 3.4.9 PZR level to gallons graph (REF PROVIDED)
QuestionBank # IKA system IKA number I
5631SYSOIl lAl.02 I
KA desc Question Source 2005 SRO Q77 (Bank 481)
Student References Provided Pressurizer volume (gal) to level (%) graph 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 D 2008 SRO NRC Examination QUESTION 57 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).
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%.
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)
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 RO  
  ~   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)
~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension MODIFIED Development References LessonDOP-CN-PS-ILE rev 23 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 ...................................... ..
QuestionBank # IKA system IKA number I
Wednesday, October 08, 2008                                                                                     Page 114 of 200
5631SYSOIl lAl.02 I
KA desc Question Source 2005 SRO Q77 (Bank 481)
Student References Provided Pressurizer volume (gal) to level (%) graph 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 /
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 58 B
45.7 to 45.8)OS/G ............................................................
QuestionBank # IKA_system IKA_number I
564 I
SYS016 I
K1.l2 I
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)
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.
Level output to the Digital Feedwater Control System (DFCS) fails low.
How will the DFCS respond to this event?
How will the DFCS respond to this event?
A.       DFCS will reduce S/G 1 C WR level to 50%.
A.
B.       DFCS will generate a "DFCS TROUBLE" alarm only.
DFCS will reduce S/G 1 C WR level to 50%.
C.       DFCS will substitute another S/G's WR level input into                       "c" loop.
B.
D.       DFCS will switch 1C S/G CF reg valve and CF bypass reg valve to MANUAL.
DFCS will generate a "DFCS TROUBLE" alarm only.
Wednesday, October 08, 2008                                                                               Pae:e 115 of 200
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
QuestionBank # IKA system IKA number I
564 I
SYS016 I
K1.l2 I
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%
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
Answer B Discussion
[CORRECT Answer C Discussion This would be true for CF temperature which substitutes another S/Gs value.
[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.
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
Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK TASKMASTER IFE-002-A  
  ~ 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                              [
~ Developed Development References Student References Provided IFE lesson D OPT Approved ARP D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I
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 /
564ISYSOI6 IK1.l2
45.7 to 45.8)OS/G ........................................................... .
[
Wednesday, October 08, 2008                                                                                     Page 116 of 200
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............................................................
Wednesday, October 08, 2008 Page 116 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
~ Developed Development References Student References Provided IFE lesson D OPT Approved ARP D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I
564[SYS016
[K1.l2
[
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............................................................
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 .....................................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 B
QuestionBank # IKA system IKA number I
565 I
SYSOl7 I
K3.01 I
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
QuestionBank # IKA system IKA number I
565 I
SYSOl7 I
K3.01 I
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.
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?
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%.
A.
B.           S/G pressures are decreasing and Tcold is at S/G saturation temperature.
S/G saturation temperatures are decreasing and REACTOR VESSEL UR LEVEL indication is greater than 100%.
C.           S/G pressures are decreasing and REACTOR VESSEL DIP indication is greater than 100%.
B.
D.           S/G pressure is at saturation pressure for Tcold and REACTOR VESSEL DIP indication is greater than 100%.
S/G pressures are decreasing and Tcold is at S/G saturation temperature.
Wednesday, October 08, 2008                                                                               Page 117 of200
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.
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 B Discussion ICorrect:
Answer C Discussion Incorrect: Reactor Vessel DIP is unavailable during natural circulation.
Answer C Discussion Incorrect: Reactor Vessel DIP is unavailable during natural circulation.
Line 1,244: Line 3,450:
Answer D Discussion Incorrect:Reactor Vessel DIP is unavailable during natural circulation.
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.
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)
Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 RO Q48 (Bank 248)  
Development References                     Student References Provided
~ Developed Development References Student References Provided HT D OPT Approved
  ~ Developed HT D   OPT Approved                                       1. ES-O.l page 15
: 1. ES-O.l page 15 D OPS Approved
: 2. ES-O.I Enclosure 3 page I D   OPS Approved D  NRC Approved QuestionBank #         IKA     system             IKA IKA  number             I 5651SYSOl7                       IK3.01
: 2. ES-O.I Enclosure 3 page I D NRC Approved QuestionBank # IKA system IKA number I
                                                  -'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 .. ,................................. .
5651SYSOl7  
Wednesday, October 08, 2008                                                                                   Page 118 of 200
-'K3.01 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 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)
~ Developed Development References Student References Provided HT D OPT Approved
: 1. ES-O.l page 15 D OPS Approved
: 2. ES-O.I Enclosure 3 page I D NRC Approved QuestionBank # IKA system IKA number I
5651SYSOl7 IK3.01 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 60 B
QuestionBank # IKA system IKA_number I
566 I
SYS027 l K5.01 1
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?
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
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
QuestionBank # IKA_system lKA_number J
566 I
SYS027 I
K5.01 I
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE B 2008 SRO NRC Examination General Discussion tBank Question: 834 Answer A Discussion Incorrect: HEP A filters do not remove radioactive Iodine Plausible: HEP A 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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionType BANK Development References
: 1. OP-CN-CNT-VE pages 5-6 QuestionBank # IKA system IKA_number I
566)SYS027 IK5.01 I
KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241)
Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CrRS: (CFR: 41.7 I 45.7)OPurpose of charcoal filters Wednesday, October 08, 2008 Page 120 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE B 2008 SRO NRC Examination General Discussion tBank Question: 834 Answer A Discussion Incorrect: HEP A filters do not remove radioactive Iodine Plausible: HEP A filter remove small particulates Answer B Discussion  
)Correct:
)Correct:
Answer C Discussion Incorrect: Prefilter/demister do not remove Iodine.
Answer C Discussion Incorrect: Prefilter/demister do not remove Iodine.
Line 1,261: Line 3,511:
Answer D Discussion Incorrect: Heaters are supposed to be energized.
Answer D Discussion Incorrect: Heaters are supposed to be energized.
Plausible: If the candidate does not know the heater function.
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)
Job Level Cognitive Level RO  
~   Developed                           Development References                                 Student References Provided
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionType BANK Development References
: 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
: 1. OP-CN-CNT-VE pages 5-6 QuestionBank # IKA system IKA number I
566)SYS027  
)KS.01 J
KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241)
Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 I 4S.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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 QuestionBank # /KA system  
                /KA system IKA_number
/KA number  
                              /KA number               I
/
                                                      /
567 I
QUESTION 61                            A 567       I SYS035 I             2.2.40         I I
SYS035 I
2.2.40 I
KA desc SYS035 GENERICDAbility to apply Technical Specifications for a system. (CFR: 4l.I0 143.2/43.5/45.3)
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.
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:
The following conditions existed during the filling operation and have been verified to be the current conditions:
Primary conditions:
Primary conditions:
* 1A NO Hx inlet temperature 185 OF            of
1A NO Hx inlet temperature 185 of 1 B NO Hx inlet temperature 185 of NC pressure 218 psig Secondary conditions:
* 1B NO Hx inlet temperature 185 of
S/G 1A CF inlet temperature 71&deg;F S/G 1 B CF inlet temperature 72 of S/G 1 C CF inlet temperature 68 of S/G 10 CF inlet temperature 71&deg;F All S/Gs pressures are 0 psig.
* NC pressure 218 psig Secondary conditions:
* S/G 1A CF inlet temperature 71&deg;F
* S/G 1B CF inlet temperature 72 of
* S/G 1C CF inlet temperature 68 of
* S/G 10 CF inlet temperature 71&deg;F
* All S/Gs pressures are 0 psig.
Based on the reported conditions, what is the action required by Selected License Commitments?
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.
A.
B.       Reduce NC pressure to less than or equal to 200 psig within 1 hour.
Reduce NC pressure to less than or equal to 200 psig within 30 minutes.
C.       Increase 1C S/G secondary temperature to greater than 70 of within 30 minutes.
B.
O.       Increase 1C S/G secondary temperature to greater than 70 of within 1 hour.
Reduce NC pressure to less than or equal to 200 psig within 1 hour.
Wednesday, October 08, 2008                                                                       Page 121 of 200
C.
Increase 1 C S/G secondary temperature to greater than 70 of within 30 minutes.
O.
Increase 1 C S/G secondary temperature to greater than 70 of within 1 hour.
Wednesday, October 08, 2008 Page 121 of 200 A
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 QuestionBank # IKA_system IKA_number I
567 I
SYS035 I
2.2.40 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 1 B NO Hx inlet temperature 185 of NC pressure 218 psig Secondary conditions:
S/G 1A CF inlet temperature 71&deg;F S/G 1 B CF inlet temperature 72 of S/G 1 C CF inlet temperature 68 of S/G 10 CF inlet temperature 71&deg;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 hour.
C.
Increase 1 C S/G secondary temperature to greater than 70 of within 30 minutes.
O.
Increase 1 C S/G secondary temperature to greater than 70 of within 1 hour.
Wednesday, October 08, 2008 Page 121 of 200 A


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.
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.
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 hour will not meet the action.
THIS ONE NEEDS WORK Answer A Discussion Answer B Discussion Incorrect: 1 hour 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.
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)
Job Level Cognitive Level QuestionType RO  
  ~   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)
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 567 SYS035 KA desc BANK Development References Lesson 0 OP-CN-CF-SG ObjectivesD25 REFERENCESDSLC 16.5-7 KA number 2.2.40 Question Source 2005 NRC Q86 (Bank 490)
Wednesday, October 08, 2008                                                                       Page 122 of 200
Student References Provided 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 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 hour 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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 567 SYS035 KA desc BANK Development References Lesson 0 OP-CN-CF-SG ObjectivesD25 REFERENCESDSLC 16.5-7 KA number 2.2.40 Question Source 2005 NRC Q86 (Bank 490)
Student References Provided 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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 QuestionBank # IKA_system.IKA_number I
* 1AD-01, Fig "EHC Emergency Manual Mode" - LIT
568 I
* 1B CFPT trips
SYS045 I
A3.05 I
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 1 B 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 B
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 QuestionBank # IKA system IKA number I
568 I
SYS045 I
A3.05 I
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 1 B CFPT trips
: 1. How was the EHC Emergency Manual Mode selected?
: 1. How was the EHC Emergency Manual Mode selected?
: 2. How do the control valves respond to a manual runback under the above conditions?
: 2. How do the control valves respond to a manual runback under the above conditions?
A.               1. automatically
A.
: 2. the control valves will operate per the valve curves B.               1. automatically
: 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 B.
: 2. the control valves will operate per the valve curves D.               1. manually
: 1. automatically
: 2. the control valves will NOT operate per the valve curves Wednesday, October 08, 2008                                                                             Page 123 of 200
: 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 B


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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 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.
!first part true second part false.
Answer B Discussion Answer C Discussion
Answer B Discussion Answer C Discussion  
!both Iboth parts false - psychometric balance Answer D Discussion lfirst part is wrong, second part is true
!both parts false - psychometric balance Answer D Discussion  
!first Job Level                       Cognitive Level             QuestionType               Question Source RO                               Memory                     NEW Development References                 Student References Provided
!first part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B
  ~ 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
~ Developed Development References Student References Provided OPIIIB16 I 0010 lOB 0
OPT Approved EHC lesson 0
OPS Approved 0
NRC Approved QuestionBank # IKA system KA number J
5681SYS045 A3.05 I
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 QUESTION 62 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 lfirst part true second part false.
Answer B Discussion Answer C Discussion Iboth parts false - psychometric balance Answer D Discussion lfirst part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B
~ Developed Development References Student References Provided OPIIIB16 I 0010 lOB 0
OPT Approved EHC lesson 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
5681SYS045 iA3.05 I
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 .......................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 63 A
QuestionBank # IKA system IKA number I
569 I
SYS071 I
K4.01 I
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?
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
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
QuestionBank # IKA system IKA number I
569 I
SYS071 I
K4.01 I
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 63 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 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
~ Developed Development References Student References Provided D OPT Approved WG lesson plan page 6 OP/0IAl65001003 BLIP D OPS Approved OP/0IAl65001003 A LIP 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 A 2008 SRO NRC Examination QUESTION 63 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.
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
Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
  ~ 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
~ Developed Development References Student References Provided D OPT Approved WG lesson plan page 6 OP/0IAl65001003 BLIP D OPS Approved OP/0IAl65001003 A LIP D NRC Approved QuestionBank # IKA system KA number 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 .......................
5691SYS07l K4.01 I
Wednesday, October 08, 2008                                                                                 Page 126 of 200
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 64 QuestionBank # IKA system IKA number 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.
570 I SYS079 I
A4.01 I
KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) D Cross-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 c
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 64 QuestionBank # IKA system IKA number I
570 I SYS079 I
A4.01 I
KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) D Cross-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?
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
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 c


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination 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)
Job Level Cognitive Level RO Memory QuestionType BANK QUESTION 64 Question Source 2003 NRC Q7 (Bank 207) c
  ~   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
~ Developed OPT Approved OOPS Approved o NRC Approved Development References Student References Provided OP-CN-SS-VI page 21 Lesson Plan Objective: VI Obj: 5, 8, 28, 30 AP-22 QuestionBank # IKA system IKA number I
                    /KA_system             number            I 570lSYS079           IA4.01                   I KA desc
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 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 RO Memory QuestionType BANK QUESTION 64 Question Source 2003 NRC Q7 (Bank 207) c
~ Developed OPT Approved OOPS Approved o NRC Approved Development References Student References Provided OP-CN-SS-VI page 21 Lesson Plan Objective: VI Obj: 5, 8, 28, 30 AP-22 QuestionBank # /KA_system JKA_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
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 .....................................
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 65 A
QuestionBank # IKA system IKA number I
571 I
SYS086 I
K6.04 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.....................................
Given the following conditions and sequence of events:
Given the following conditions and sequence of events:
* 2A DIG auto-started due to a blackout on 2ETA
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:
* 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?
: 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?
: 2. What is the status of the 2A DIG emergency ventilation after the Cardox system discharges?
A.         1. 6.5 minutes
A.
: 2. Running due to sequencer actuation B.         1. 6.5 minutes
: 1. 6.5 minutes
: 2. Secured due to Cardox actuation C.         1. 1.5 minutes
: 2. Running due to sequencer actuation B.
: 2. Running due to sequencer actuation D.         1. 1.5 minutes
: 1. 6.5 minutes
: 2. Secured due to Cardox actuation Wednesday, October 08, 2008                                                                                 Page 129 of 200
: 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
QuestionBank # IKA_system JKA_number I
571 I
SYS086 I
K6.04 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.....................................
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 65 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
Answer A Discussion Answer B Discussion
[correct time, but fans run Answer C 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
[incorrect time, fan status is correct Answer D Discussion IBoth incorrect pyschometric balance Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
  ~ Developed RFY lesson 0   OPT Approved                                     DG 1 lesson VD 0   OPS Approved 0   NRC Approved IKA QuestionBank # \KA system                       IKA
~ Developed Development References Student References Provided RFY lesson 0
                                                \KA     number         I
OPT Approved DG 1 lesson VD 0
                                                                        \
OPS Approved 0
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 ....................................
NRC Approved QuestionBank # \\KA system \\KA number
Wednesday, October 08,2008                                                                                     Page 130 of 200
\\
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 A 2008 SRO NRC Examination QUESTION 65 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
~ Developed Development References Student References Provided RFY lesson 0
OPT Approved DG 1 lesson VD 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA 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/
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 66 D
QuestionBank # IKA system IKA number I
572 I
GEN2.1 I
2.1.45 I
KA desc Conduct of Operations D Ability 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
QuestionBank # IKA system IKA_number I
572 I
GEN2.1 I
2.1.45 I
KA desc Conduct of Operations D Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7/43.5/
45.4)
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.
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?
Which set of the following indications could be used to confirm their suspicions?
: 1. % Steam flow
: 1. % Steam flow
: 2. Steam pressure
: 2. Steam pressure
: 3. Containment 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
: 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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 66 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
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW  
  ~ 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
~ Developed Development References Student References Provided AP/28 0
KA desc Conduct of OperationsO Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7/43.5/
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number J
572IGEN2.1 12.1.45 I
KA desc Conduct of Operation sO 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 D 2008 SRO NRC Examination QUESTION 66 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
~ Developed Development References Student References Provided AP/28 0
OPT Approved 0
OPS Approved 0
NRC Approved QuestionBank # IKA system IKA number I
572IGEN2.1 12.1.45 I
KA desc Conduct of Operation sO Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7/43.5/
45.4)
45.4)
Wednesday, October 08, 2008                                                                                   Page 132 of 200
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 67 QuestionBank # IKA_system IKA_number I
What instructions are provided to the NLO dispatched to the 1ETA switchgear room and which procedure provides that guidance?
573 I
A.         Perform a partial transfer to the SSF per AP/1/AJ55001017 (Loss of Control Room)
GEN2.1 I
B.         Transfer control to the SSF per AP/1 IA/55001017 (Loss of Control Room)
2.1.8 I
C.         Perform a partial transfer to the SSF per AP/OIAJ55001045 (Plant Fire)
KA desc Conduct of OperationsDAbility to coordinate personnel activities outside the control room. (CFR: 41.10/45.5 /45.12/45.13)
D.         Transfer control to the SSF per AP/O/A/55001045 (Plant Fire)
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.
Wednesday, October 08, 2008                                                                               Page 133 of 200
What instructions are provided to the NLO dispatched to the 1 ETA 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 B
I I
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 67 QuestionBank # IKA systemlKA number I
573 I
GEN2.1 I
2.1.8 I
KA desc Conduct of OperationsDAbility to coordinate personnel activities outside the control room. (CFR: 41.10/45.5 /45.12/45.13)
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 1 ETA 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 B
I I


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.
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 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.
Answer D Discussion Full control is not transferred to the SSF in AP/45.
Job Level           Cognitive Level             QuestionType                                       Question Source RO                     Memory                      NEW
Job Level Cognitive Level QuestionType RO  
~   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)
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 573 GEN2.1 KA desc NEW Development References AP/17 ENCL 11 AP/45 API17 Symptoms API17 step Sc KA number 2.1.S Question Source Student References Provided 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
Wednesday, October 08, 2008 Page 134 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 RO
~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 573 GEN2.1 KA desc NEW Development References AP/17 ENCL 11 AP/45 API17 Symptoms API17 step Sc KA number 2.1.S Question Source Student References Provided 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)
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 68 D
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 _ _ __
QuestionBank # IKA system IKA number I
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
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
QuestionBank # IKA system IKA number I
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%
FOR REVIEW ONLY - DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 68 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
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  
  ~ 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)
~ Developed Development References Student References Provided 0
Wednesday, October 08, 2008                                                                                 Page 136 of 200
OPT Approved CM Lesson plan 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 D 2008 SRO NRC Examination QUESTION 68 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
~ Developed Development References Student References Provided 0
OPT Approved CM Lesson plan 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 69 A
                                                          -'I QUESTION 69                                        A 575       I GEN2.2 I         2.2.39 I
QuestionBank # IKA system IKA number 575 I GEN2.2 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 !
2.2.39 I
KA desc Equipment Control o Knowledge 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)
43.2! 45.13)
Unit 1 is at 4% power, conducting a plant startup. Given the following events and conditions:
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
One control bank "A" rod drops fully into the core NCS temperature decreases to 550&deg;F Which one of the following statements correctly describes an action that is required within 30 minutes by Technical Specifications?
* NCS temperature decreases to 550&deg;F Which one of the following statements correctly describes an action that is required within 30 minutes by Technical Specifications?
A.
A.       Be in mode 2 with Keff less than 1.0.
Be in mode 2 with Keff less than 1.0.
B.       Restore rod group within alignment limits.
B.
C.       Verify shutdown margins within the limits specified in the COLR.
Restore rod group within alignment limits.
D.       Adjust power range Nils to increase reactor power so that reactor power and thermal power best estimate are equal.
C.
Wednesday, October 08, 2008                                                                               Page 137 of 200
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
QuestionBank # IKA system IKA number I
575 I
GEN2.2 I
2.2.39 I
KA desc Equipment Control o Knowledge 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&deg;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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 69 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
Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2003 NRC Q30 (Bank 230) Bank Question: 600  
~ Developed Lesson Plan Objective: NC SEQ 10 OPT Approved                     
~ Developed Development References Student References Provided OPT Approved Lesson Plan Objective: NC SEQ 10
 
==References:==
D OPS Approved
: 1. OP-CN-PS-NC page 33
: 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 A 2008 SRO NRC Examination QUESTION 69 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
~ Developed Development References Student References Provided OPT Approved Lesson Plan Objective: NC SEQ 10  


==References:==
==References:==
: 1. OP-CN-PS-NC page 33 D    OPS Approved
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/
: 1. OP-CN-PS-NC page 33
: 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)
43.2/45.13)
Wednesday, October 08, 2008                                                                               Page 138 of 200
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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 QuestionBank # IKA system IKA number I
JI QUESTION 70              c KA desc                                                                                                 I Radiation ControlOAbility to control radiation releases. (CPR: 41.11/43.4/45.10)
576 I
I A Unit 1 containment purge is in progress using OP/1/N64501015. Given the following events and conditions:
GEN2.31 2.3.11 J
* 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?
Radiation ControlOAbility to control radiation releases. (CPR: 41.11/43.4/45.10)
A.         The VP release may not be reinitiated until RP draws a new containment air activity sample.
A Unit 1 containment purge is in progress using OP/1/N64501015. Given the following events and conditions:
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.
1 EMF-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?
C.         The VP release may be reinitiated after the spike clears. If 1EMF-39 spikes a second time, the release may also be reinitiated.
A.
D.         The VP release may be reinitiated if grab samples are taken of Unit Vent activity during subsequent reinitiation.
The VP release may not be reinitiated until RP draws a new containment air activity sample.
Wednesday, October 08, 2008                                                             Page 139 of 200
B.
The VP release may be reinitiated after the spike clears. If 1 EMF-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 1 EMF-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 c
I I
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 QuestionBank # IKA system IKA number I
576 I
GEN2.3 I
2.3.11 I
KA desc Radiation ControlOAbility to control radiation releases. (CPR: 41.11/43.4/45.10)
A Unit 1 containment purge is in progress using OP/1/N64501015. Given the following events and conditions:
1 EMF-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 1 EMF-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 1 EMF-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 c
I I


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 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.
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.
Answer B Discussion Incorrect: the OP allows the VP release to be reset twice if due to EMF spike.
Line 1,442: Line 4,016:
Answer D Discussion Incorrect: 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.
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
Job Level Cognitive Level QuestionType Question Source c
~   Developed                           Development References                               Student References Provided Lesson Plan Objective: VP Obj: 8,9 D  OPT Approved                     
RO Memory BANK 2003 NRC Q54 (Bank 254) Bank Question: 968.3  
~ Developed D OPT Approved OPS Approved D NRC Approved QuestionBank # KA system 576GEN2.3 KA desc Development References Lesson Plan Objective: VP Obj: 8,9  


==References:==
==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)
: 1. OP/l/N6450/015, limits and precautions page 2 rev44
Wednesday, October 08, 2008                                                                             Page 140 of200
: 2. OP-CN-CNT-VP page 15 KA number 2.3.11 Radiation ControlDAbility to control radiation releases. (CFR: 41.11 /43.4/45.10)
Wednesday, October 08, 2008 Student References Provided Page 140 of200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 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 c
RO Memory BANK 2003 NRC Q54 (Bank 254) Bank Question: 968.3
~ Developed D OPT Approved OPS Approved D NRC Approved QuestionBank # KA system 576GEN2.3 KA desc Development References Lesson Plan Objective: VP Obj: 8,9


FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system JKA_number 577       I GEN2.3 I               2.3.4 I
==References:==
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)
: 1. OP/l/N6450/015, limits and precautions page 2 rev44
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.
: 2. OP-CN-CNT-VP page 15 KA number 2.3.11 Radiation ControlDAbility to control radiation releases. (CFR: 41.11 /43.4/45.10)
Wednesday, October 08, 2008 Student References Provided Page 140 of200
 
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 QuestionBank # IKA_system JKA_number I
577 I
GEN2.3 I
2.3.4 I
KA desc Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10)
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?
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.
A.
B.         17 Rem internal dose equivalent to the lens of the eye.
55 Rem external dose to the lens of the eye.
C.         55 Rem external dose to the leg below the knee.
B.
D.         17 Rem internal dose to the right forearm.
17 Rem internal dose equivalent to the lens of the eye.
Wednesday, October 08, 2008                                                                           Page 141 of200
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 c
I I
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 QuestionBank # IKA_system JKA_number I
577 I
GEN2.3 I
2.3.4 I
KA desc Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10)
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 c
I I


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).
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination 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 C Discussion QUESTION 71 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)
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 Q 16 (Bank 316) c  
  ~   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)
~ Developed Development References Student References Provided D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 577GEN2.3 KA desc HP lesson KA number 2.3.4 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
Wednesday, October 08, 2008 Page 142 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination 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 QUESTION 71 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 Q 16 (Bank 316) c
~ Developed Development References Student References Provided D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 577GEN2.3 KA desc HP lesson 2.3.4 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~
FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 72 A
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:
2008 SRO NRC Examination QuestionBank # IKA system IKA number I
* The worker's present exposure is 1938 mrem for the year
578 I
* The RWP states:
GEN2.3 I
o General area dose rate = 30 mrem/hr o Airborne contamination concentration =10.0 DAC The job will take 2 hours if the worker wears a full-face respirator. It will only take 1 hour if the worker does not wear the respirator.
2.3.7 I
KA~
i Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10)
I 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 hours if the worker wears a full-face respirator. It will only take 1 hour 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 QUESTION 72 A
2008 SRO NRC Examination QuestionBank # IKA system IKA number I
578 I
GEN2.3 I
2.3.7 I
KA desc I
Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10)
I 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 hours if the worker wears a full-face respirator. It will only take 1 hour 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?
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.
A.
The worker should not wear the respirator.
The calculated TEDE dose received will be less than if he does wear one.
The calculated TEDE dose received will be less than if he does wear one.
B.         The worker should not wear the respirator.
B.
The worker should not wear the respirator.
The dose received wearing a respirator will exceed site annual personnel dose limits.
The dose received wearing a respirator will exceed site annual personnel dose limits.
C.         The worker should wear the respirator.
C.
The worker should wear the respirator.
The calculated TEDE dose received will be less than if he does not wear one.
The calculated TEDE dose received will be less than if he does not wear one.
D.         The worker should wear the respirator.
D.
The worker should wear the respirator.
He could exceed DAC limits.
He could exceed DAC limits.
Wednesday, October 08, 2008                                                                             Page 143 of200
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:
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion Radiation exposure comparison:
Without respirator DDE = 30 mremlhr x 1 hr = 30 mrem From airborne contamination:
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)
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.
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 miscalculates the dose Answer C Discussion QUESTION 72 A
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.
Plausible: If the candidate does not understand the concept of derived airborne concentrations.
Job Level           Cognitive Level             QuestionType                                     Question Source
Job Level Cognitive Level QuestionType Question Source  
                .4-----~~----------~----------~--~--------------------------------------------------~
.4-----~~----------~----------~--~--------------------------------------------------~
RO                 Comprehension                 BANK                       2003 NRC Qll (Bank 211) Bank Question: 353.3
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)
~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 578GEN2.3 KA desc Development References Lesson Plan Objective: HP Obj: 2, 4 I. OP-CN-RAO-HP pages 14-15 KA number 2.3.7 Student References Provided 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
Wednesday, October 08, 2008 Page 144 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE A 2008 SRO NRC Examination 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 QUESTION 72 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 RO Cognitive Level QuestionType Comprehension BANK
~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 578GEN2.3 KA desc Development References Lesson Plan Objective: HP Obj: 2, 4 I. OP-CN-RAO-HP pages 14-15 KA number 2.3.7 Question Source 2003 NRC Qll (Bank 211) Bank Question: 353.3 Student References Provided 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 QuestionBank # IKA system IKA number 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?
579 I
A.       The OSM has responsibility, but he can delegate the task if necessary.
GEN2.4 I
B.       The OSM has responsibility and he can not delegate this task.
2.4.13 I
C.       The STA has responsibility, but the OSM can reassign the task if necessary.
KA desc Emergency Procedures / PlanDKnowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12)
D.       The STA has responsibility and this task can not be reassigned.
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?
Wednesday, October 08, 2008                                                                           Page 145 of200
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 c
J I
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 QuestionBank # IKA system IKA number I
579 I
GEN2.4 I
2.4.13 I
KA desc Emergency Procedures / PlanDKnowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12)
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 c
J I


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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 c
~   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)
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  
Wednesday, October 08, 2008                                                                           Page 146 of 200
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 579GEN2.4 KA desc OMP 1-7 OMP 1-8 KA number 2.4.13 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 579GEN2.4 KA desc OMP 1-7 OMP 1-8 KA number 2.4.13 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B
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)
QuestionBank # IKA system IKA number I
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):
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
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?
* forms the bases for protection of the fuel and fuel cladding?
A.
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
: 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
QuestionBank # IKA system IKA number I
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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B
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
General Discussion Answer A Discussion IIncorrect: Wrong order, wrong functions.
~   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/
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 o OPT Approved OOPS Approved o NRC Approved LessonOOP-CN-EP-CSF Objectives02 REFERENCES 0 Lesson plan information page 10 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)
41.10/43.5/45.12)
Wednesday, October 08, 2008                                                                               Page 148 of200
Wednesday, October 08, 2008 Page 148 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 o OPT Approved OOPS Approved o NRC Approved LessonOOP-CN-EP-CSF Objectives02 REFERENCES 0 Lesson plan information page 10 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             )
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 QuestionBank # )KA system  
QUESTION 75                     A 581       I GEN2.4       I       2.4.42         I KA desc                                                                                                       )
)KA number  
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.
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)
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 A
)
I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 QuestionBank # )KA system
)KA number
)
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)
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:
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?
: 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?
: 2. What is the lowest classification level that requires this facility's activation?
A.         1. Technical Support Center (TSC)
A.
: 2. Alert B.         1. Technical Support Center (TSC)
: 1. Technical Support Center (TSC)
: 2. Unusual Event C.         1. Operations Support Center (OSC)
: 2. Alert B.
: 2. Alert D.         1. Operations Support Center (OSC)
: 1. Technical Support Center (TSC)
: 2. Unusual Event Wednesday, October 08, 2008                                                                 Page 149 of 200
: 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 A
)
I


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.
FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 A
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.
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.
  .Job Level         Cognitive Level             QuestionType                                     Question Source RO                   Memory                     NEW
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.  
~   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)
.Job Level Cognitive Level QuestionType Question Source RO Memory NEW  
Wednesday, October 08, 2008                                                                                 Page 150 of 200}}
~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 581 GEN2.4 KA_desc SEP lesson KA number 2.4.42 Emergency Procedures / Plan 0 Knowledge of emergency response facilities. (CFR: 41.10/45.11)
Wednesday, October 08, 2008 Page 150 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 581 GEN2.4 KA desc SEP lesson KA number 2.4.42 Emergency Procedures / Plan 0 Knowledge of emergency response facilities. (CFR: 41.10/45.11)
Wednesday, October 08, 2008 Page 150 of 200}}

Latest revision as of 08:48, 14 January 2025

Initial Exam 2008-301 Draft RO Written Exam
ML092940704
Person / Time
Site: Catawba  Duke Energy icon.png
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)
v • d • e


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U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date:

Facility/Unit: CATAWBA Region: I C0 III IV Reactor Type: (ij) 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 f~:*lJ. r:\\ F""7" l])j

. £~ t;F.~

u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date:

Facility/Unit: CATAWBA Region: I (i) III IV Reactor Type: (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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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*--~

-~-..

507 EPE007 EK2.03 D

rQ. ~:LION 1

~\\{A IF' Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7/45. 7) 0 Reactor trip status panel 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:

1 EDC 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 D

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination Questlo-n-S-an-k-#-'-K-A-_-sy-s--te-m----,-K-A-_-nu-m-b~er--~

-~--.

507 EPE007 EK2.03 D

rQ.

~Y~:LION 1

~V{Ar,

D

~;:l::;e-o;the interrelations between a reactor trip and the following: (CFR 41.7/ 45. 7)D-R-ea-ct-or-tr-iP-st-at-us-p-an-el~~-~

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:

1 EDC 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

~~I

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

~RRECT Job Level Cognitive Level QuestionType Question Source J

R_O ____ ~ _____ C

__ o_m_p_r_eh_e_ns_i_on ____ _L ___

M_O_D __

IF_IE_D __ ~

_________________ 2_0_0_6_N_R_C_Q __

l_(_B_an_k_6_0_7_) ______ ~~_

~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA_system 507 EPE007 Development References EPINTR013 OMP 1-7 TS 3.3.1 EK2.03 Student References Provided

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

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 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

~RRECT--~~--~~~~~~-~~~~~~~~~~~~-

Job Level Cognitive Level QuestionType Question Source J

R_O ____ ~ _____ C __ o_m_p_re_h_en_s_io_n ____ _L ___

M_O_D_I_F_IE_D __ ~

________________ 2_0_06 __

N_R_C_Q __

l_(_B_an_k_6_0_7_)________

~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA_system 507 EPE007 Development References EPINTR013 OMP 1-7 TS 3.3.1 Student References Provided 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 QUESTION 2 QuestionBank # IKA system IKA number I

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:

1 RAD-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 D

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 QuestionBank # IKA system IKA number J

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:

1 RAD-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 D

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 1 9 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 RO Comprehension NEW

~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # JKA system 50SiEPE009 Development References OPIlIB161 0010 lOX AP/lIAl55001027 EP/lIAl50001E-l EP/lI Al5000IECA-1.2 KA number I

EA2.10 I

Question Source Student References Provided

~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 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 1 9 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 RO Comprehension NEW

~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # JKA system 50SiEPE009 Development References OPIlIB161 0010 lOX AP/lIAl55001027 EP/lIAl50001E-l EP/lI Al5000IECA-1.2 KA number I

EA2.10 I

Question Source Student References Provided

~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 QUESTION 3 A

QuestionBank # IKA system IKA number I

509 I

EPEOll I

2.4.30 I

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

QuestionBank # IKA system IKA_number I

509 I

EPEOll J 2.4.30 i

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)

~ Developed Development References Student References Provided 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 I

KA desc

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

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 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)

~ Developed Development References Student References Provided 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 1

KA desc BPEOll 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 QUESTION 4 A

2008 SRO NRC Examination QuestionBank # [KA system

[KA number

[

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:

  • 1 NV-294 (NV Pmps A&B Disch Flow Ctrl) in MANUAL
  • 1 NV-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 QUESTION 4 A

2008 SRO NRC Examination QuestionBank # [KA system

[KA number

[

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:

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

line flow and total seal flow will decrease while charging line discharge pressure increases.

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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension BANK Development References THFFF 12 thru THFFF 15 QuestionBank # IKA system IKA number I

510lAPE022 IAK 1. 02 J

KA desc Question Source 2005 NRC Q6 (Bank 410)

Student References Provided 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 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,,-p_re_s_su_r_e_in_c-,roceas 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]

line flow and total seal flow will decrease while charging line discharge pressure increases.

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 RO

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

~_

510lAPE022 IAK 1. 02 I

KA desc Question Source 2005 NRC Q6 (Bank 410)

Student References Provided 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 QUESTION 5 c

QuestionBank # IKA system IKA number I

511 I

APE025 I

2.4.30 I

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

QuestionBank # IKA system IKA number I

511 I APE025 I

2.4.30 I

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.

procedure, 2 are required.

OMP 1-7 says for situations not covered by Answer A Discussion I

________ ~

Answer B Discussion

~I ______________ ~~

I Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 511 APE025 NEW Development References OMP 1-7 KA number 2.4.30

__ I Question Source Student References Provided KA desc

_I' APE025 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.) 0/43.5/45.) 1)

Wednesday, October 08, 2008 Page 10 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.

procedure, 2 are required.

OMP 1-7 says for situations not covered by Answer A Discussion 1

________ ~

Answer B Discussion

~I -------------------------------------------------_1 Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 511 APE025 NEW Development References OMP 1-7 KA number 2.4.30

__ I Question Source Student References Provided KA desc

_I' APE025 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.) 0/43.5/45.) 1)

Wednesday, October 08, 2008 Page 10 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 6 A

QuestionBank # IKA system IKA number I

512 I

APE026 I

AA2.03 I

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 1 ETB 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

QuestionBank # IKA system IKA number J

512 I

APE026 I

AA2.03 I

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 1 ETB 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

~ Developed Development References Student References Provided API 1/ Al55001021 0

OPT Approved PSSKC 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

512IAPE026 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 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

~ Developed Development References API 1/ Al55001021 0

OPT Approved PSSKC 0

OPS Approved

==!

Student References Provided 0

NRC Approved L-__________________________ ~

~_____________________j QuestionBank # IKA system IKA number I

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 QUESTION 7 QuestionBank # IKA_system I~number I

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 B

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 7 QuestionBank # IKA_system I~number I

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 B

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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA_system SI3APE027 NEW Development References OP/O/B/610010 13 PSILE AAI.04 Question Source Student References Provided 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 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA_system SI3APE027 NEW Development References OP/O/B/610010 13 PSILE AAI.04 Question Source Student References Provided 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 QUESTION 8 D

QuestionBank # IKA system IKA_number I

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 BY A 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

QuestionBank # IKA system IKA number I

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 BY A 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 D 2008 SRO NRC Examination QUESTION 8 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!1I A/SOOIFR-S.l requires opening all the breakers.

needs to be open to trip the reactor.

Answer B Discussion Plausible: Students knows only one breaker

]

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

~ Developed Development References Student References Provided 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 D 2008 SRO NRC Examination QUESTION 8 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!1I A/SOOIFR-S.l requires opening all the breakers.

needs to be open to trip the reactor.

Answer B Discussion Plausible: Students knows only one breaker

]

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

~ Developed Development References Student References Provided 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 QUESTION 9 c

2008 SRO NRC Examination QuestionBank # IKA system IKA number I

515 I

EPE038 I

EK1.02 I

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 QUESTION 9 c

2008 SRO NRC Examination QuestionBank # IKA system IKA number I

515 I

EPE038 I

EK1.02 I

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 c 2008 SRO NRC Examination QUESTION 9 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 RO Comprehension BANK

~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 515EPE038 Development References STMSGIO KA number EK1.02 Question Source 2005 NRC Q69 (Bank 473)

Student References Provided 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 c 2008 SRO NRC Examination QUESTION 9 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 RO Comprehension BANK

~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 515EPE038 Development References STMSGIO KA number EK1.02 Question Source 2005 NRC Q69 (Bank 473)

Student References Provided 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 QUESTION 10 B

QuestionBank # IKA system IKA number I

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%. 1 ERPA 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

QuestionBank # IKA system IKA number I

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%. 1 ERPA 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 B 2008 SRO NRC Examination QUESTION 10 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

~ Developed Development References Student References Provided 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 B 2008 SRO NRC Examination QUESTION 10 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

~ Developed Development References Student References Provided 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 QUESTION 11 c

2008 SRO NRC Examination QuestionBank # IKA_system IKA_number I

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:

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

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 1 ERPD 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 1 EID 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 QUESTION 11 c

2008 SRO NRC Examination QuestionBank # IKA_system IKA_number I

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:

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

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 1 ERPD 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 1 EID 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

~ Developed Development References Student References Provided EPL 0

OPT Approved API 1/ Al55001029 0

OPS Approved OPIlI Al63501008 0

NRC Approved QuestionBank #[KA system IKA number I

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 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

~ Developed Development References Student References Provided EPL 0

OPT Approved API 1/ Al55001029 0

OPS Approved OPIlI Al6350100S 0

NRC Approved QuestionBank # [KA system

[KA number I

5171APE05SjAA1.02 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 QUESTION 12 A

QuestionBank # IKA system IKA number I

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 1 RN-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

QuestionBank # IKA system IKA number I

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 1 RN-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 A 2008 SRO NRC Examination QUESTION 12 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 RO

~ Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References AP120 RN lesson QuestionBank # IKA system IKA number I

5181APE062 IAK3.03 I

KA desc

=

Question Source Student References Provided 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 A 2008 SRO NRC Examination QUESTION 12 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 RO

~ Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References AP120 RN lesson QuestionBank # IKA system IKA_number J

5181APE062 IAK3.03 I

KA desc

=

Question Source Student References Provided 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 QUESTION 13 B

QuestionBank # IKA system IKA number I

519 I APE065 I

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

QuestionBank # IKA_system IKA number I

519 I

APE065 1 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 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 RO Comprehension NEW

~ Developed Development References D OPT Approved D OPS Approved D NRC Approved RL QuestionBank # IKA system IKA number I

519iAPE065

.iAK3.03 i

KA desc Question Source Student References Provided 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 J

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 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 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 RO Comprehension NEW

~ Developed Development References D OPT Approved D OPS Approved D NRC Approved RL QuestionBank # IKA system IKA number I

5191APE065 IAK3.03 I

KA desc Question Source Student References Provided 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 J

effects on plant operation of isolating certain equipment from instrument air.....................................

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

Wednesday, October 08, 2008 Page 26 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 14 D

QuestionBank # IKA_system IKA_number I

520 I

APE077 I

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

QuestionBank # [KA system

[KA number

[

520 I

APE077 I

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 D 2008 SRO NRC Examination QUESTION 14 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 RO

~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension NEW Development References Generator Capability Curve (DataBook Curve 43)

RL QuestionBank # \\KA system \\KA number

\\

520IAPE077 IAAl.OI I

KA desc Question Source Student References Provided Databook Figure 43 (Generator Capability Curve)

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 D 2008 SRO NRC Examination QUESTION 14 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 RO

~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension NEW Development References Generator Capability Curve (DataBook Curve 43)

RL QuestionBank # \\KA system \\KA number

\\

520IAPE077 IAAl.OI I

KA desc Question Source Student References Provided Databook Figure 43 (Generator Capability Curve)

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 QUESTION 15 D

QuestionBank # IKA system IKA number I

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

1 B NC pump running o

1A, 1 C, and 1 D 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

QuestionBank # IKA system IKA number I

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

1 B NC pump running o

1A, 1 C, and 1 D 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 D OPT Approved D OPS Approved D NRC Approved Lesson Plan Objective: EP-EP2 SEQ 29

References:

1. ECA-l.l step 19 and Encl 5 - PROVIDED QuestionBank # IKA system IKA number J

5211WE04

!EK2.2 I

KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the foIJowing:

EP/II Al50001ECA-l.l (Step 19)

EP/II Al5000IECA-I.1 (Enclosure 5)

(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 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 D OPT Approved D OPS Approved D NRC Approved Lesson Plan Objective: EP-EP2 SEQ 29

References:

1. ECA-l.l step 19 and Encl 5 - PROVIDED QuestionBank # IKA system IKA number I

5211WE04 IEK2.2 I

KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the foIJowing:

EP/II Al50001ECA-l.l (Step 19)

EP/II Al5000IECA-I.1 (Enclosure 5)

(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 QUESTION 16 D

QuestionBank # IKA system IKA number I

522 I

WE05 I

EK3.1 I

KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)

(CFR: 41.5! 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 1 B wide range level - 20%

S/G 1C wide range level-23%

S/G 1 D 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

QuestionBank # IKA system IKA_number I

522 I

WE05 I

EK3.1 I

KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink)

(CFR: 41.5! 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 1 B wide range level - 20%

S/G 1C wide range level-23%

S/G 1 D 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

~ Developed Development References Student References Provided 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 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

~ Developed Development References Student References Provided 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 IKA number I

523 I

WE 11 I

EK2.1 I

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

QUESTION 17 c

(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 1 NI-184B (ND Pump 1 B Cont Sump Suct) and 1 NI-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 QuestionBank # IKA system IKA number I

523 I

WE 11 I

EK2.1 I

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

QUESTION 17 c

(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 1 NI-184B (ND Pump 1 B Cont Sump Suct) and 1 NI-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 RO Comprehension NEW

~ Developed Development References 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:

Question Source Student References Provided (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 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 RO Comprehension NEW

~ Developed Development References 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:

Question Source Student References Provided (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 QUESTION 18 2008 SRO NRC Examination c

QuestionBank # IKA system IKA number I

524 I

WEl2 I

EK1.3 I

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 QUESTION 18 2008 SRO NRC Examination c

QuestionBank # IKA_system IKA_number I

524 I

WEl2 I

EK1.3 I

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

~ Developed Development References Student References Provided EP/II A/SOOO/ECA-2.1 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

5241WEI2 iEK1.3 i

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 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

~ Developed Development References Student References Provided EP/II A/SOOO/ECA-2.1 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # jKA system KA number J

5241WEI2 EK1.3 I

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 QUESTION 19 D

QuestionBank # IKA system IKA number I

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

QuestionBank # IKA system IKA number I

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

~ Developed Development References Student References Provided 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 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

~ Developed Development References Student References Provided 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 QUESTION 20 I

526 I

APE005 J 2.4.6 1

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

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 B

I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 QuestionBank # [KA system

[KA number

[

526 I

APE005 I

2.4.6 I

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

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 B

[

I

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 RO

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

Wednesday, October 08, 2008 Question Source Student References Provided Page 40 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 RO

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

Wednesday, October 08, 2008 Question Source Student References Provided Page 40 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 21 c

QuestionBank # IKA system IKA number I

527 I

APE024 I

AKl.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)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

QuestionBank # IKA system IKA number I

527 I

APE024 I

AKl.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)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 c 2008 SRO NRC Examination 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 RO Comprehension NEW

~ Developed Development References TS 3.9.4 D OPT Approved SLC 16.9-7 D OPS Approved SLC 16.9-11 D NRC Approved QuestionBank # IKA system IKA number I

527iAPE024 IAKl.04 I

KA desc QUESTION 21 Question Source Student References Provided 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 c 2008 SRO NRC Examination 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 RO Comprehension NEW

~ Developed Development References TS 3.9.4 D OPT Approved SLC 16.9-7 D OPS Approved SLC 16.9-11 D NRC Approved QuestionBank # IKA_system IK~number I

5271APE024 IAKl.04 I

KA desc QUESTION 21 Question Source Student References Provided 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 QUESTION 22 A

QuestionBank # IKA system IKA number J

528 I

APE033 I

AK1.01 I

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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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

QuestionBank # lKA system IKA number I

528 I

APE033 I

AK1.01 1

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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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

~ Developed Development References Student References Provided 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 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

~ Developed Development References Student References Provided 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 QUESTION 23 D

QuestionBank # IKA system IKA number I

529 I

APE037 I

AA2.03 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......................

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

B.

Comparing S/G feed flow to steam flow mismatch C.

Observing 1 EMF-33 (Condenser Air Ejector Exhaust)

O.

Observing 1 EMF-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

QuestionBank # IKA_system IKA_number I

529 I

APE037 I

AA2.03 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......................

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

B.

Comparing S/G feed flow to steam flow mismatch C.

Observing 1 EMF-33 (Condenser Air Ejector Exhaust)

O.

Observing 1 EMF-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)

~ Developed Development References Student References Provided 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 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)

~ Developed Development References Student References Provided 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 QUESTION 24 D

QuestionBank # IKA_system JKA_number I

530 I

EPE074 I

EA1.01 I

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

QuestionBank # lKA system IKA number I

530 I

EPE074 I

EA1.01 l

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 D 2008 SRO NRC Examination QUESTION 24 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

~ Developed Development References Student References Provided F-O 0

OPT Approved FR-C.l and basis 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

530lEPE074 IEA1.01 I

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 D 2008 SRO NRC Examination QUESTION 24 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

~ Developed Development References Student References Provided F-O 0

OPT Approved FR-C.l and basis 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number 530lEPE074 iEA1.01 I

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 QUESTION 25 c

QuestionBank # IKA system IKA number I

531 I

APE036 I

AK3.03 I

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.

1 RAD-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

QuestionBank # IKA system IKA number I

531 I

APE036 I

AK3.03 I

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.

1 RAD-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 1 VQ 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)

~ Developed Development References Student References Provided AP/25 D OPT Approved VQ D OPS Approved CNT 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 45.6 145.13)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 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 1 VQ 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)

~ Developed Development References Student References Provided AP/25 D OPT Approved VQ D OPS Approved CNT 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 45.6 145.13)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 QUESTION 26 A

QuestionBank #jKA system IKA number I

532 I

WED3 I

EK2.1 I

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

1 NI-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

QuestionBank # [KA system IKA_number J

532 I

WED3 I

EK2.1 I

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

1 NI-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 RO Comprehension BANK

~ Developed Development References PS-ND 9 D OPT Approved NSD3.1.30 D OPS Approved ND pages 8, 13 D NRC Approved QuestionBank # IKA system IKA_number I

5321WE03 IEK2.1 J

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

Question Source 2004 NRC Q50 (Bank 350)

Student References Provided (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 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 RO Comprehension BANK

~ Developed Development References PS-ND 9 D OPT Approved NSD3.1.30 D OPS Approved ND pages 8, 13 D NRC Approved QuestionBank # IKA system IKA number I

5321WE03 IEK2.1 KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:

Question Source 2004 NRC Q50 (Bank 350)

Student References Provided (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 QUESTION 27 D

QuestionBank # IKA system IKA number I

533 I

WE09 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

QuestionBank # [KA_system IKA_number I

533 I

WE09 J

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)

~ Developed Development References Student References Provided ES-0.3 0

OPT Approved SM 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

5331WE09 IEK3.3 J

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 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)

~ Developed Development References Student References Provided ES-0.3 0

OPT Approved SM 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA_number I

5331WE09 IEK3.3 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)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 QUESTION 28 c

QuestionBank # IKA system IKA number J

534 I

SYSOO3 I

A2.02 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: 41.5/43.5/45.31 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 1 C 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 1 C NC Pump.

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

B.

Trip 1 C NC Pump.

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

C.

Trip the reactor.

Trip 1 C 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

QuestionBank # IKA system IKA number I

534 I

SYSOO3 I

A2.02 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: 41.5/43.5/45.31 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 1 C 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 1 C NC Pump.

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

B.

Trip 1 C NC Pump.

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

C.

Trip the reactor.

Trip 1 C 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

~ Developed Development References Student References Provided PS-NCP 12 0

OPT Approved OPIl/B/6100101G lAD-6 B/5 OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

5341SYS003 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 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

~ Developed Development References Student References Provided PS-NCP 12 0

OPT Approved OPIl/B/6100101G lAD-6 B/5 OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

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 QUESTION 29 D

QuestionBank # IKA system IKA number I

535 I

SYSOO4 I

Al.OI I

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

QuestionBank # IKA system IKA number I

535 I SYSOO4 I Al.OI I

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

~ Developed Development References Student References Provided OPIl/B/61 0010 I OH D OPT Approved NV lesson D OPS Approved TS3.4.I6 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 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

~ Developed Development References Student References Provided OPIl/B/61 0010 I OH D OPT Approved NV lesson D OPS Approved TS3.4.I6 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 QUESTION 30 c

QuestionBank # IKA system IKA number I

536 I

SYSOO4 I

K1.34 I

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.

1 NC-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 1 NC-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

QuestionBank # IKA system IKA number I

536 I

SYSOO4 I

K1.34 I

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.

1 NC-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 1 NC-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 c 2008 SRO NRC Examination QUESTION 30 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

~ Developed Development References Student References Provided 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 c 2008 SRO NRC Examination QUESTION 30 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

~ Developed Development References Student References Provided 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 QUESTION 31 D

QuestionBank # IKA system IKA number I

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)..........

1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37A (NO Pump 1 B 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

QuestionBank # IKA system lKA number I

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)..........

1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37A (NO Pump 1 B 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 D 2008 SRO NRC Examination QUESTION 31 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

~ Developed Development References Student References Provided 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 D 2008 SRO NRC Examination QUESTION 31 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

~ Developed Development References Student References Provided 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 QUESTION 32 c

QuestionBank # IKA system IKA number I

538 I

SYSOO6 I

Al.05 I

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:

NC system pressure (psig)

Containment pressure (psig)

FWST level (%)

Time 1200 2130 0.5 98 1206 1950 1.3 97 1212 5

2.8 80 1218 5

4.2 60 1224 5

2.5 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

QuestionBank # IKA system IKA number I

538 I

SYSOO6 I

Al.05 I

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:

NC system pressure (psig)

Containment pressure (psig)

FWST level (%)

Time 1200 2130 0.5 98 1206 1950 1.3 97 1212 5

2.8 80 1218 5

4.2 60 1224 5

2.5 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

~ Developed Development References Student References Provided KC lesson D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I

5381SYSOO6 IAl.05 I

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 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

~ Developed Development References Student References Provided KC lesson D OPT Approved D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I

538iSYSOO6 iAl.05 I

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 QUESTION 33 QuestionBank # IKA system IKA number I

539 I

SYS007 I

2.4.6 I

KA desc 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 D

I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 QuestionBank # IKA system IKA number I

539 I

SYS007 I

2.4.6 I

KA desc 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 D

I

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 RO Comprehension NEW

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

Wednesday, October 08, 2008 Question Source Student References Provided Pa!1e 66 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 RO Comprehension NEW

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

Wednesday, October 08, 2008 Question Source Student References Provided Pa!1e 66 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 34 B

QuestionBank # IKA system IKA_number I

540 I SYS008 1 K3.03 I

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 1 C Thermal Barrier HX is 75 gpm.

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

A.

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

B.

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

C.

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

D.

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

Wednesday, October 08, 2008 P<>(JP (\\'7 nf '?OO FOR REVIEW ONLY - DO NOT DISTRIBUTE QUESTION 34 B

2008 SRO NRC Examination QuestionBank #JKA system IKA number I

540 I

SYS008 I

K3.03 I

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 1 C Thermal Barrier HX is 75 gpm.

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

A.

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

B.

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

C.

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

D.

All seal cooling to NCP 1 C is lost. Trip NCP 1 C 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 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 B

~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 540SYS008 KA desc

References:

1. OP-CN-PSS-KC page 12
2. OP-CN-PS-NCP pages 15-19 KA number K3.03 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 QUESTION 34 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 B

~ Developed Development References Student References Provided o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 540SYS008 KA desc

References:

1. OP-CN-PSS-KC page 12
2. OP-CN-PS-NCP pages 15-19 KA number K3.03 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 QUESTION 35 A

QuestionBank # IKA system IKA_number I

541 I

SYSOO8 I

K4.09 J

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

QuestionBank # IKA_system lKA_number I

541 I

SYSOO8 I

K4.09 I

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 RO

~ Developed D OPT Approved D OPS Approved D NRC Approved Memory QuestionType MODIFIED Development References QuestionBank # IKA system IKA number I

54IISYS008 IK4.09 j

KA desc Question Source 2007 NRC Q36 (Bank 836)

Student References Provided 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 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 RO

~ Developed D OPT Approved D OPS Approved D NRC Approved Memory QuestionType MODIFIED Development References QuestionBank #JKA system IKA number I

54IISYS008 IK4.09 I

KA desc Question Source 2007 NRC Q36 (Bank 836)

Student References Provided 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 QUESTION 36 B

2008 SRO NRC Examination QuestionBank # IKA system IKA_number I

542 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 QUESTION 36 B

2008 SRO NRC Examination QuestionBank # IKA system IKA number I

542 I

SYSOI0 I

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 542SYSOlO KA desc ASME Steam Tables KA number 2.1.25 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 542SYSOlO KA desc ASME Steam Tables KA number 2.1.25 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 QUESTION 37 D

QuestionBank # IKA system IKA number I

543 I

SYS012 I

A2.02 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 /45.3 / 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 1 ERPD 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

QuestionBank # IKA system IKA number I

543 I

SYS012 I

A2.02 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 /45.3 / 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 1 ERPD 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 D 2008 SRO NRC Examination QUESTION 37 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

~ Developed Development References Student References Provided 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 D 2008 SRO NRC Examination QUESTION 37 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

~ Developed Development References Student References Provided 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 QUESTION 38 QuestionBank # IKA system IKA number I

544 I

SYS012 1 K5.01 I

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 D

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 QuestionBank # IKA system IKA_number I

544 J SYS012 I

K5.01 I

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 D

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)

~ Developed Development References Student References Provided TS 3.3.1 and bases D OPT Approved IPX D OPS Approved D NRC Approved QuestionBank # \\KA_system

\\KA_number j

5441SYSOl2 IK5.01 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 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)

~ Developed Development References Student References Provided TS 3.3.1 and bases D OPT Approved IPX D OPS Approved D NRC Approved QuestionBank # IKA system IKA number 5441SYSOl2 iK5.01 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 QUESTION 39 B

QuestionBank # [KA system

[KA_number

[

545 I

SYS013 I

K6.01 I

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:

1 ERPD 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

QuestionBank # IKA system IKA number I

545 I

SYS013 I

K6.01 I

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:

1 ERPD 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 o OPT Approved OOPS Approved o NRC Approved Development References Lesson 0 OP-CN-ECCS-ISE Objectives02 & 3 REFERENCESOAP/1/A/5500/029 Enclosure 17 (lERPD load list) rev 013 QuestionBank # IKA system IKA number I

545ISYS013 JK6.01 I

KA desc Student References Provided 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 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 o OPT Approved OOPS Approved o NRC Approved Development References Lesson 0 OP-CN-ECCS-ISE Objectives02 & 3 REFERENCESOAP/1/A/5500/029 Enclosure 17 (lERPD load list) rev 013 QuestionBank # IKA system IKA number I

545ISYS013 IK6.01 J

KA desc Student References Provided 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 QUESTION 40 QuestionBank #IKA system IKA number J

546 I

SYS022 I

K2.02 I

KA desc Knowledge of power supplies to the following: (CFR: 41.7)OChillers........................................................

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 D

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 QuestionBank # IKA system IKA number I

546 I

SYS022 I

K2.02 I

KA desc Knowledge of power supplies to the following: (CFR: 41.7)OChillers........................................................

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 D

I I

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 546SYS022 KA desc RN lesson KA number K2.02 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 546SYS022 KA desc RN lesson KA number K2.02 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 QUESTION 41 QuestionBank # IKA system IKA number I

547 I

SYS025 I

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 A

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 QuestionBank # IKA system IKA number I

547 I

SYS025 1 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 A

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 Job Level Cognitive Level QuestionType Question Source RO Memory NEW

~ Developed Development References Student References Provided NF lesson 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

547!SYS025 IA4.01 I

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 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

~ Developed Development References Student References Provided NF lesson 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

547jSYS025 jA4.01 I

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 QUESTION 42 c

QuestionBank # IKA system IKA_number I

548 I

SYS026 I

A1.03 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) 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

QuestionBank # IKA system IKA number I

548 I

SYS026 I

A1.03 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) 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

~ Developed Development References Student References Provided 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 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

~ Developed Development References Student References Provided 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 QUESTION 43 A

QuestionBank # IKA system IKA number J

549 I

SYS026 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 1 NI-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 1 A 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

QuestionBank # IKA system IKA_number I

549 I

SYS026 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 1 NI-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 1 A 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

~ Developed Development References Student References Provided NS lesson 0

OPT Approved ES 1.3 0

OPS Approved ES 1.3 background 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 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

~ Developed Development References Student References Provided NS lesson 0

OPT Approved ES 1.3 0

OPS Approved ES 1.3 background 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 QUESTION 44 D

QuestionBank # IKA system IKA number I

550 I

SYS039 I

K5.01 J

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 1 CA-58A (CA Pump A Disch To S/G 1 B Isol) have failed NLOs have been dispatched to manually isolate flow to 1 B S/G When CA flow is secured to 1 B S/G, level is noted to be 96% on NR level gauges Which of the following consequences have increased risk for 1 B 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

QuestionBank # IKA system IKA number I

550 I

SYS039 I

K5.01 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........................

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 1 CA-58A (CA Pump A Disch To S/G 1 B Isol) have failed NLOs have been dispatched to manually isolate flow to 1 B S/G When CA flow is secured to 1 B S/G, level is noted to be 96% on NR level gauges Which of the following consequences have increased risk for 1 B 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

~ Developed Development References Student References Provided 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 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

~ Developed Development References Student References Provided 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 QUESTION 45 B

QuestionBank # IKA system IKA number I

551 I

SYS059 I

A4.11 I

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

QuestionBank # IKA system IKA_number I

551 I

SYS059 I

A4.11 I

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 Plausible: would be true ifP-41L0w Tave FWI had not occurred. Cycling Rx trip breakers does clear auto S/I block following an S/!.

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

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

~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension BANK Development References Lesson Plan Objective: ISE Obj: 5

References:

1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank # IKA system IKA number I

L_

5511SYS059 IA4.11 I

KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question: 970BH Student References Provided 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 QUESTION 45 B

General Discussion Answer A Discussion Incorrect: must also depress FWI push buttons Plausible: would be true ifP-4lLow Tave FWI had not occurred. Cycling Rx trip breakers does clear auto sir block following an SII.

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

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

~ Developed D OPT Approved D OPS Approved D NRC Approved Comprehension BANK Development References Lesson Plan Objective: ISE Obj: 5

References:

1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank # IKA_system IKA_number I

L_

5511SYS059 IA4.11 I

KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question: 970BH Student References Provided 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 QUESTION 46 D

QuestionBank # IKA system IKA number I

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

QuestionBank # IKA system IKA number I

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 552 SYS061 KA desc E-O KA number A3.03 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 552 SYS061 KA desc E-O KA number A3.03 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 QUESTION 47 QuestionBank # IKA system IKA_number I

553 I

SYS062 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 B

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 QuestionBank # IKA system IKA number I

553 I

SYS062 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 B

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

~ Developed Development References Student References Provided 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 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

~ Developed Development References Student References Provided 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 QUESTION 48 QuestionBank # [KA_system

[KA_number

[

554 I

SYS063 I

K2.01 I

KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads Which of the following buses powers the Unit 1 Turbine Emergency Bearing Oil Pump (EBOP)?

A.

1 EDB - 125V Vital Instrumentation and Control Power B.

1 EMXF - 600V Unit Essential Power C.

1 DPD - 250V Auxilary Power D.

SMXD - 600V Shared Power Wednesday, October 08, 2008 Page 95 of 200 c

[

I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 QuestionBank # IKA system

[KA number I

554 I

SYS063 I

K2.01 I

KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads Which of the following buses powers the Unit 1 Turbine Emergency Bearing Oil Pump (EBOP)?

A.

1 EDB - 125V Vital Instrumentation and Control Power B.

1 EMXF - 600V Unit Essential Power C.

1 DPD - 250V Auxilary Power D.

SMXD - 600V Shared Power Wednesday, October 08, 2008 Page 95 of 200 c

I I

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 554SYS063 KA desc EPL KA number K2.01 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 554SYS063 KA desc EPL KA number K2.01 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 QUESTION 49 c

QuestionBank # IKA system lKA number J

555 I

SYS063 I

K3.01 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 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 1 DGCA 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 1 A 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

QuestionBank # IKA system IKA_number I

555 I

SYS063 J K3.01 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 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 1 DGCA 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 1 A 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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 V ADA 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 o OPT Approved OOPS Approved o NRC Approved Development References Lesson Plan Objective: DG-DGI-14, 19

References:

1. OP-CN-DG-DGI pages 17-19,26 QuestionBank # IKA system IKA number I

5551SYS063 IK3.01 I

KA desc Student References Provided 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 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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 V ADA 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 o OPT Approved OOPS Approved o NRC Approved Development References Lesson Plan Objective: DG-DGI-14, 19

References:

1. OP-CN-DG-DGI pages 17-19,26 QuestionBank # IKA system IKA number I

5551SYS063 IK3.01 I

KA desc Student References Provided 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 QUESTION 50 B

QuestionBank # IKA_system IKA_number I

556 I

SYS064 1 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

QuestionBank # IKA system IKA number I

556 I

SYS064 I

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 RO Comprehension NEW

~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 556SYS064 KA desc Development References E-O and backgmd doc EQB KA number A3.07 Question Source Student References Provided 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 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 RO Comprehension NEW

~ Developed o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 556SYS064 KA desc Development References E-O and backgmd doc EQB KA number A3.07 Question Source Student References Provided 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 QUESTION 51 QuestionBank # IKA system IKA number I

557 I

SYS064 I

K6.07 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 B

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 51 QuestionBank # IKA system IKA number I

557 I

SYS064 I

K6.07 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 B

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 RO Comprehension BANK

~ Developed Development References

1. DG 1 lesson D OPT Approved
2. Tech Spec Bases 3.8.3 El D OPS Approved D NRC Approved QuestionBank # JKA system jKA number j

557!SYS064 jK6.07 J

KA desc Question Source 2003 NRC Q64 (Bank 264)

Student References Provided 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 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 RO Comprehension BANK

~ Developed Development References

1. DG 1 lesson D OPT Approved
2. Tech Spec Bases 3.8.3 El D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I

557!SYS064

!K6.07 KA desc Question Source 2003 NRC Q64 (Bank 264)

Student References Provided 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 QUESTION 52 B

QuestionBank # [KA system

[KA number

[

558 I

SYS073 I

A2.02 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 1 EMF-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

QuestionBank # [KA system

[KA number

[

558 I

SYS073 I

A2.02 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 1 EMF-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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension NEW Development References OP/1/B/61 00/0 I 0 X QuestionBank # IKA system IKA number I

55S[SYS073

[A2.02

[

KA desc Question Source Student References Provided 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 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension NEW Development References OP/1/B/61 00/0 I 0 X QuestionBank # IKA system IKA number I

55S[SYS073

[A2.02

[

KA desc Question Source Student References Provided 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 QUESTION 53 A

2008 SRO NRC Examination QuestionBank #/KA system IKA number J

559 I

SYS076 I

K2.01 I

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 1 ETA 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

QuestionBank # IKA system IKA_number I

559 J SYS076 I

K2.01 I

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 1 ETA 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 559 SYS076 KA desc RN lesson EPC lesson KA number K2.0l 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 559 SYS076 KA desc RN lesson EPC lesson KA number K2.0l 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 QUESTION 54 B

QuestionBank # IKA system IKA number I

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

QuestionBank # IKA system IKA number I

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 B 2008 SRO NRC Examination QUESTION 54 General Discussion INV294 and INV309 fail open, letdown orifice vlaves fail closed on loss of air. Letdown isolation valves lNV-IA and INV-2A fail close on Loss 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 RO

~ Developed D OPT Approved D OPS Approved D NRC Approved Memory NEW Development References NV lesson QuestionBank # IKA system IKA number I

560lSYS078 IK3.02 I

KA desc Question Source Student References Provided 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 B 2008 SRO NRC Examination QUESTION 54 General Discussion INY294 and INY309 fail open, letdown orifice vlaves fail closed on loss of air. Letdown isolation valves lNY-IA and INY-2A fail close on Loss ofYI Answer A Discussion Ipartially correct.

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

Job Level Cognitive Level QuestionType RO

~ Developed D OPT Approved D OPS Approved D NRC Approved Memory NEW Development References INY lesson QuestionBank # IKA system IKA number I

560lSYS078 IK3.02 I

KA desc Question Source Student References Provided 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 QUESTION 55 A

QuestionBank # IKA system IKA_number I

561 I

SYSI03 L

K1.07 1

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 1 VQ-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

QuestionBank # IKA system IKA number J

561 I

SYSI03 I

K1.07 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)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 1 VQ-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 1 VQ-l O.

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 VQ lesson 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA_system IKA_number 5611SYS103 IK1.07 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 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 1 VQ-l O.

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 VQ lesson 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA system 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 QUESTION 56 QuestionBank # IKA system IKA number I

562 I

SYSOOI I

K2.02 I

KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)DOne-line diagram of power supply to trip breakers.....................

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 A

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 56 A

QuestionBank # IKA system IKA number I

562 I

SYSOOI i K2.02 I

KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)DOne-line diagram of power supply to trip breakers.....................

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 562SYSOOI KA desc IPX KA number K2.02 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 562SYSOOI KA desc IPX KA number K2.02 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 QUESTION 57 D

QuestionBank # IKA system IKA number I

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

QuestionBank # IKA system IKA number I

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 D 2008 SRO NRC Examination QUESTION 57 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension MODIFIED Development References LessonDOP-CN-PS-ILE rev 23 REFERENCESDTS 3.4.9 PZR level to gallons graph (REF PROVIDED)

QuestionBank # IKA system IKA number I

5631SYSOIl lAl.02 I

KA desc Question Source 2005 SRO Q77 (Bank 481)

Student References Provided Pressurizer volume (gal) to level (%) graph 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 D 2008 SRO NRC Examination QUESTION 57 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Comprehension MODIFIED Development References LessonDOP-CN-PS-ILE rev 23 REFERENCESDTS 3.4.9 PZR level to gallons graph (REF PROVIDED)

QuestionBank # IKA system IKA number I

5631SYSOIl lAl.02 I

KA desc Question Source 2005 SRO Q77 (Bank 481)

Student References Provided Pressurizer volume (gal) to level (%) graph 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 QUESTION 58 B

QuestionBank # IKA_system IKA_number I

564 I

SYS016 I

K1.l2 I

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

QuestionBank # IKA system IKA number I

564 I

SYS016 I

K1.l2 I

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

~ Developed Development References Student References Provided IFE lesson D OPT Approved ARP D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I

564ISYSOI6 IK1.l2

[

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............................................................

Wednesday, October 08, 2008 Page 116 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

~ Developed Development References Student References Provided IFE lesson D OPT Approved ARP D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I

564[SYS016

[K1.l2

[

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............................................................

Wednesday, October 08, 2008 Page 116 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 B

QuestionBank # IKA system IKA number I

565 I

SYSOl7 I

K3.01 I

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

QuestionBank # IKA system IKA number I

565 I

SYSOl7 I

K3.01 I

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)

~ Developed Development References Student References Provided HT D OPT Approved

1. ES-O.l page 15 D OPS Approved
2. ES-O.I Enclosure 3 page I D NRC Approved QuestionBank # IKA system IKA number I

5651SYSOl7

-'K3.01 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 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)

~ Developed Development References Student References Provided HT D OPT Approved

1. ES-O.l page 15 D OPS Approved
2. ES-O.I Enclosure 3 page I D NRC Approved QuestionBank # IKA system IKA number I

5651SYSOl7 IK3.01 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 QUESTION 60 B

QuestionBank # IKA system IKA_number I

566 I

SYS027 l K5.01 1

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

QuestionBank # IKA_system lKA_number J

566 I

SYS027 I

K5.01 I

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 B 2008 SRO NRC Examination General Discussion tBank Question: 834 Answer A Discussion Incorrect: HEP A filters do not remove radioactive Iodine Plausible: HEP A 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionType BANK Development References

1. OP-CN-CNT-VE pages 5-6 QuestionBank # IKA system IKA_number I

566)SYS027 IK5.01 I

KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241)

Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CrRS: (CFR: 41.7 I 45.7)OPurpose of charcoal filters Wednesday, October 08, 2008 Page 120 of 200 FOR REVIEW ONLY - DO NOT DISTRIBUTE B 2008 SRO NRC Examination General Discussion tBank Question: 834 Answer A Discussion Incorrect: HEP A filters do not remove radioactive Iodine Plausible: HEP A 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionType BANK Development References

1. OP-CN-CNT-VE pages 5-6 QuestionBank # IKA system IKA number I

566)SYS027

)KS.01 J

KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241)

Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 I 4S.7)OPurpose of charcoal filters Wednesday, October 08, 2008 Page 120 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 QuestionBank # /KA system

/KA number

/

567 I

SYS035 I

2.2.40 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 1 B NO Hx inlet temperature 185 of NC pressure 218 psig Secondary conditions:

S/G 1A CF inlet temperature 71°F S/G 1 B CF inlet temperature 72 of S/G 1 C 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

C.

Increase 1 C S/G secondary temperature to greater than 70 of within 30 minutes.

O.

Increase 1 C S/G secondary temperature to greater than 70 of within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Wednesday, October 08, 2008 Page 121 of 200 A

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 QuestionBank # IKA_system IKA_number I

567 I

SYS035 I

2.2.40 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 1 B NO Hx inlet temperature 185 of NC pressure 218 psig Secondary conditions:

S/G 1A CF inlet temperature 71°F S/G 1 B CF inlet temperature 72 of S/G 1 C 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

C.

Increase 1 C S/G secondary temperature to greater than 70 of within 30 minutes.

O.

Increase 1 C S/G secondary temperature to greater than 70 of within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Wednesday, October 08, 2008 Page 121 of 200 A

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 567 SYS035 KA desc BANK Development References Lesson 0 OP-CN-CF-SG ObjectivesD25 REFERENCESDSLC 16.5-7 KA number 2.2.40 Question Source 2005 NRC Q86 (Bank 490)

Student References Provided 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 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 567 SYS035 KA desc BANK Development References Lesson 0 OP-CN-CF-SG ObjectivesD25 REFERENCESDSLC 16.5-7 KA number 2.2.40 Question Source 2005 NRC Q86 (Bank 490)

Student References Provided 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 QUESTION 62 QuestionBank # IKA_system.IKA_number I

568 I

SYS045 I

A3.05 I

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 1 B 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 B

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 QuestionBank # IKA system IKA number I

568 I

SYS045 I

A3.05 I

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 1 B 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 B

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 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 part true second part false.

Answer B Discussion Answer C Discussion

!both parts false - psychometric balance Answer D Discussion

!first part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B

~ Developed Development References Student References Provided OPIIIB16 I 0010 lOB 0

OPT Approved EHC lesson 0

OPS Approved 0

NRC Approved QuestionBank # IKA system KA number J

5681SYS045 A3.05 I

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 QUESTION 62 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 lfirst part true second part false.

Answer B Discussion Answer C Discussion Iboth parts false - psychometric balance Answer D Discussion lfirst part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B

~ Developed Development References Student References Provided OPIIIB16 I 0010 lOB 0

OPT Approved EHC lesson 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

5681SYS045 iA3.05 I

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 QUESTION 63 A

QuestionBank # IKA system IKA number I

569 I

SYS071 I

K4.01 I

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

QuestionBank # IKA system IKA number I

569 I

SYS071 I

K4.01 I

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 A 2008 SRO NRC Examination QUESTION 63 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

~ Developed Development References Student References Provided D OPT Approved WG lesson plan page 6 OP/0IAl65001003 BLIP D OPS Approved OP/0IAl65001003 A LIP 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 A 2008 SRO NRC Examination QUESTION 63 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

~ Developed Development References Student References Provided D OPT Approved WG lesson plan page 6 OP/0IAl65001003 BLIP D OPS Approved OP/0IAl65001003 A LIP 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 QUESTION 64 QuestionBank # IKA system IKA number I

570 I SYS079 I

A4.01 I

KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) D Cross-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 c

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 64 QuestionBank # IKA system IKA number I

570 I SYS079 I

A4.01 I

KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) D Cross-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 c

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination 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 RO Memory QuestionType BANK QUESTION 64 Question Source 2003 NRC Q7 (Bank 207) c

~ Developed OPT Approved OOPS Approved o NRC Approved Development References Student References Provided OP-CN-SS-VI page 21 Lesson Plan Objective: VI Obj: 5, 8, 28, 30 AP-22 QuestionBank # IKA system IKA 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 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 RO Memory QuestionType BANK QUESTION 64 Question Source 2003 NRC Q7 (Bank 207) c

~ Developed OPT Approved OOPS Approved o NRC Approved Development References Student References Provided OP-CN-SS-VI page 21 Lesson Plan Objective: VI Obj: 5, 8, 28, 30 AP-22 QuestionBank # /KA_system JKA_number I

570lSYS079 IA4.01 I

KA desc

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

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 QUESTION 65 A

QuestionBank # IKA system IKA number I

571 I

SYS086 I

K6.04 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.....................................

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

QuestionBank # IKA_system JKA_number I

571 I

SYS086 I

K6.04 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.....................................

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 A 2008 SRO NRC Examination QUESTION 65 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

~ Developed Development References Student References Provided RFY lesson 0

OPT Approved DG 1 lesson VD 0

OPS Approved 0

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

\\

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 A 2008 SRO NRC Examination QUESTION 65 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

~ Developed Development References Student References Provided RFY lesson 0

OPT Approved DG 1 lesson VD 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA 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 QUESTION 66 D

QuestionBank # IKA system IKA number I

572 I

GEN2.1 I

2.1.45 I

KA desc Conduct of Operations D Ability 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

QuestionBank # IKA system IKA_number I

572 I

GEN2.1 I

2.1.45 I

KA desc Conduct of Operations D Ability 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 D 2008 SRO NRC Examination QUESTION 66 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

~ Developed Development References Student References Provided AP/28 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number J

572IGEN2.1 12.1.45 I

KA desc Conduct of Operation sO 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 D 2008 SRO NRC Examination QUESTION 66 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

~ Developed Development References Student References Provided AP/28 0

OPT Approved 0

OPS Approved 0

NRC Approved QuestionBank # IKA system IKA number I

572IGEN2.1 12.1.45 I

KA desc Conduct of Operation sO 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 QUESTION 67 QuestionBank # IKA_system IKA_number I

573 I

GEN2.1 I

2.1.8 I

KA desc Conduct of OperationsDAbility to coordinate personnel activities outside the control room. (CFR: 41.10/45.5 /45.12/45.13)

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 1 ETA 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 B

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 67 QuestionBank # IKA systemlKA number I

573 I

GEN2.1 I

2.1.8 I

KA desc Conduct of OperationsDAbility to coordinate personnel activities outside the control room. (CFR: 41.10/45.5 /45.12/45.13)

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 1 ETA 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 B

I I

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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 573 GEN2.1 KA desc NEW Development References AP/17 ENCL 11 AP/45 API17 Symptoms API17 step Sc KA number 2.1.S Question Source Student References Provided 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 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 RO

~ Developed o OPT Approved OOPS Approved o NRC Approved Memory QuestionBank # KA system 573 GEN2.1 KA desc NEW Development References AP/17 ENCL 11 AP/45 API17 Symptoms API17 step Sc KA number 2.1.S Question Source Student References Provided 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 QUESTION 68 D

QuestionBank # IKA system IKA number I

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

QuestionBank # IKA system IKA number I

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 D 2008 SRO NRC Examination QUESTION 68 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

~ Developed Development References Student References Provided 0

OPT Approved CM Lesson plan 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 D 2008 SRO NRC Examination QUESTION 68 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

~ Developed Development References Student References Provided 0

OPT Approved CM Lesson plan 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 QUESTION 69 A

QuestionBank # IKA system IKA number 575 I GEN2.2 I

2.2.39 I

KA desc Equipment Control o Knowledge 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

QuestionBank # IKA system IKA number I

575 I

GEN2.2 I

2.2.39 I

KA desc Equipment Control o Knowledge 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 A 2008 SRO NRC Examination QUESTION 69 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

~ Developed Development References Student References Provided OPT Approved Lesson Plan Objective: NC SEQ 10

References:

D OPS Approved

1. OP-CN-PS-NC page 33
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 A 2008 SRO NRC Examination QUESTION 69 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

~ Developed Development References Student References Provided OPT Approved Lesson Plan Objective: NC SEQ 10

References:

D OPS Approved

1. OP-CN-PS-NC page 33
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 QUESTION 70 QuestionBank # IKA system IKA number I

576 I

GEN2.31 2.3.11 J

Radiation ControlOAbility to control radiation releases. (CPR: 41.11/43.4/45.10)

A Unit 1 containment purge is in progress using OP/1/N64501015. Given the following events and conditions:

1 EMF-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 1 EMF-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 1 EMF-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 c

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 QuestionBank # IKA system IKA number I

576 I

GEN2.3 I

2.3.11 I

KA desc Radiation ControlOAbility to control radiation releases. (CPR: 41.11/43.4/45.10)

A Unit 1 containment purge is in progress using OP/1/N64501015. Given the following events and conditions:

1 EMF-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 1 EMF-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 1 EMF-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 c

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 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 c

RO Memory BANK 2003 NRC Q54 (Bank 254) Bank Question: 968.3

~ Developed D OPT Approved OPS Approved D NRC Approved QuestionBank # KA system 576GEN2.3 KA desc Development References Lesson Plan Objective: VP Obj: 8,9

References:

1. OP/l/N6450/015, limits and precautions page 2 rev44
2. OP-CN-CNT-VP page 15 KA number 2.3.11 Radiation ControlDAbility to control radiation releases. (CFR: 41.11 /43.4/45.10)

Wednesday, October 08, 2008 Student References Provided Page 140 of200 FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 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 c

RO Memory BANK 2003 NRC Q54 (Bank 254) Bank Question: 968.3

~ Developed D OPT Approved OPS Approved D NRC Approved QuestionBank # KA system 576GEN2.3 KA desc Development References Lesson Plan Objective: VP Obj: 8,9

References:

1. OP/l/N6450/015, limits and precautions page 2 rev44
2. OP-CN-CNT-VP page 15 KA number 2.3.11 Radiation ControlDAbility to control radiation releases. (CFR: 41.11 /43.4/45.10)

Wednesday, October 08, 2008 Student References Provided Page 140 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 QuestionBank # IKA_system JKA_number I

577 I

GEN2.3 I

2.3.4 I

KA desc Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10)

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 c

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 QuestionBank # IKA_system JKA_number I

577 I

GEN2.3 I

2.3.4 I

KA desc Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10)

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 c

I I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination 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 QUESTION 71 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 Q 16 (Bank 316) c

~ Developed Development References Student References Provided D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 577GEN2.3 KA desc HP lesson KA number 2.3.4 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 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 QUESTION 71 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 Q 16 (Bank 316) c

~ Developed Development References Student References Provided D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 577GEN2.3 KA desc HP lesson 2.3.4 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 QUESTION 72 A

2008 SRO NRC Examination QuestionBank # IKA system IKA number I

578 I

GEN2.3 I

2.3.7 I

KA~

i Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10)

I 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the worker wears a full-face respirator. It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 QUESTION 72 A

2008 SRO NRC Examination QuestionBank # IKA system IKA number I

578 I

GEN2.3 I

2.3.7 I

KA desc I

Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10)

I 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the worker wears a full-face respirator. It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 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 QUESTION 72 A

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 D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 578GEN2.3 KA desc Development References Lesson Plan Objective: HP Obj: 2, 4 I. OP-CN-RAO-HP pages 14-15 KA number 2.3.7 Student References Provided 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 A 2008 SRO NRC Examination 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 QUESTION 72 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 RO Cognitive Level QuestionType Comprehension BANK

~ Developed D OPT Approved D OPS Approved D NRC Approved QuestionBank # KA system 578GEN2.3 KA desc Development References Lesson Plan Objective: HP Obj: 2, 4 I. OP-CN-RAO-HP pages 14-15 KA number 2.3.7 Question Source 2003 NRC Qll (Bank 211) Bank Question: 353.3 Student References Provided 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 QUESTION 73 QuestionBank # IKA system IKA number I

579 I

GEN2.4 I

2.4.13 I

KA desc Emergency Procedures / PlanDKnowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12)

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 c

J I

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 QuestionBank # IKA system IKA number I

579 I

GEN2.4 I

2.4.13 I

KA desc Emergency Procedures / PlanDKnowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12)

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 c

J I

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 579GEN2.4 KA desc OMP 1-7 OMP 1-8 KA number 2.4.13 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 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 579GEN2.4 KA desc OMP 1-7 OMP 1-8 KA number 2.4.13 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 QUESTION 74 B

QuestionBank # IKA system IKA number I

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

QuestionBank # IKA system IKA number I

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 o OPT Approved OOPS Approved o NRC Approved LessonOOP-CN-EP-CSF Objectives02 REFERENCES 0 Lesson plan information page 10 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 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 o OPT Approved OOPS Approved o NRC Approved LessonOOP-CN-EP-CSF Objectives02 REFERENCES 0 Lesson plan information page 10 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 QUESTION 75 QuestionBank # )KA system

)KA number

)

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)

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 A

)

I FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 QuestionBank # )KA system

)KA number

)

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)

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 A

)

I

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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 581 GEN2.4 KA_desc SEP lesson KA number 2.4.42 Emergency Procedures / Plan 0 Knowledge of emergency response facilities. (CFR: 41.10/45.11)

Wednesday, October 08, 2008 Page 150 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 o OPT Approved OOPS Approved o NRC Approved QuestionBank # KA system 581 GEN2.4 KA desc SEP lesson KA number 2.4.42 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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