ML092940712

Initial Exam 2008-301 Draft SRO Written Exam

ML092940712
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/08-301, 50-414/08-301
Download: ML092940712 (51)

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'$111 Ilt U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: Facility/Unit: CATAWBA Region: I CI~ III IV Reactor Type: (W) 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO port Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results RO/SRO-Only/Total Examination Values / / Points I

Applicant's Score / / Points Applicant's Grade / / Percent

~.

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system 582 I EPE009 IKA number I *-2-.2-.2-5~-.

• -2-.2-.2-5--,

j DR9JiPrION 76 c KA desc EPE009 GENERICOKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 /

41.7 /43.2)

Per technical specification 3.5.2 (EGGS-Operating), during all phases of a larger small break LOGA:

1. Which EGGS pumps are credited for this event?

2. What acceptance criteria for maximum fuel clad temperature does the LGO ensure?

A. 1. NV and NI pumps only

2. 2200° F.

B. 1. NV, NI and NO pumps

2. 4700° F.

C. 1. NV, NI and NO pumps

2. 2200° F.

O. 1. NV and NI pumps only

2. 4700° F.

DRAFT Wednesday, October 08, 2008 Page 151 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 76 c General Discussion 4700 degrees is the safety limit for the fuel. ECCS criteria is 2200 degrees. NV and NI pumps are what an operator might think of for small break locas since pressure is likely above the shutoff head of the ND pumps, however, for "larger" small break locas, ND is required when swapping to the sump. (see basis)

Answer A Discussion isecond part correct Answer B Discussion ifirst part correct Answer C Discussion iCORRECT Answer D Discussion iBoth wrong Job Level Cognitive Level QuestionType Question Source SRO Memory NEW

~ Developed Development References Student References Provided TS 3.5.2 Bases D OPT Approved AM lesson D OPS Approved D NRC Approved QuestionBank # jKA jKA system jKA number JI 5821EPE009 12.2.25 i KA desc EPE009 GENERICDKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CPR: 41.51 41.7/43.2)

Wednesday, October 08, 2008 Page 152 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 583 I EPEOII lI 2.2.36 I

lI QUESTION 77 c KA desc EPEOII GENERIC oAbility to analyze the effect of maintenance activities, such as degraded power sources, on the status ofiimiting conditions for operations. (CFR: 41.10/43.2/45.13)

Unit 2 is at 3% power. Given the following sequence of events:

12/01/08 1100 2A NI pump tagged to replace the motor cooler.

12/03/08 0500 2B DIG tripped on high vibration during performance of PT/2/A/43501002B (Diesel Generator 2B Operability Test).

12/03/08 0700 You complete turnover and take the position of GRS.

1. What is the latest time that entry into Mode 3 is required per Technical Specifications assuming work on both components is delayed?

2. When you take shift duty at 0700, can the EGGS design criteria for a large break LOGA be assumed to be met?

Reference provided A. 1. 12/03/08 1200

2. Yes B. 1. 12/03/08 1200

2. No G. 1. 12/03/08 1600

2. Yes D. 1. 12/03/08 1600

2. No Wednesday, October 08, 2008 Page 153 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 77 c General Discussion This tests knowledge of the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> additional time before redundant equipment is declared inoperable after the DIG is declared inoperable.

Until that time 3.0.3 does not apply to this situation after that, 3.0.3 is entered.

Answer A Discussion this is the time for 3.0.3 without the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; second part correct Answer B Discussion this is the time for 3.0.3 without the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; still within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> window, therefore 2B NI is assumed to be operable.

Answer C Discussion icorrect Answer D Discussion correct time, still within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> window, therefore 2B NI is assumed to be operable.

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

~ Developed T.S. 3.5.2 and basis Technical Specification 3.5.2 D OPT Approved T.S. 3.8.1 and basis Technical Specification 3.8.1 D OPS Approved D NRC Approved IKA QuestionBank # IKA system IKA IKA number .1I 583iEPEOll 12 .2 .36 J I KA desc EPEOll GENERIC 0 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status oflimiting conditions EPE011 for operations. (CFR: 41.1 0 I 43.2 I 45.13)

Wednesday, October 08, 2008 Page 154 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 78 B AA2.05 584 I APE026 I I KA desc Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 /45. I 3)OThe normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS ........................

Unit 2 is at 100% power when an NLO reports the breaker for 2KG-56A (KG To NO Hx 1A Sup Isol) looks damaged. Upon investigation, the SPOG crew determines that 2KG-56A (KG To NO Hx 1A Sup Isol) will not open.

What is the minimum flow required through this valve when aligned for cold leg recirculation and for the situation above, what is declared inoperable?

A. 5000 gpm / 2A Train of KG B. 5000 gpm / 2A Train of NO G. 5700 gpm / 2A Train of NO O. 5700 gpm / 2A Train of KG Wednesday, October 08, 2008 Page 155 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 78 B General Discussion KC SR is modified by a Note indicating that the isolation of the CCW flow to individual components may render those components inoperable but does not affect the OPERABILITY of the CCW System. Per EPIES- 1.3, 5000 per train is required. 5700 gpm is the miniflow given in ARP.

Answer A Discussion ICorrect flow with incorrect TS.

Answer B Discussion Answer C Discussion lIn correct flow but correct TS Answer D Discussion IIncorrect flow and TS Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided

~ Developed TSB 3.7.7 0 OPT Approved ESl.3 OP/I/A/61 0010 IOJ 0 OPS Approved KC56ADBD 0 NRC Approved IKA QuestionBank # IKA system IKA number IKA II 5841APE026 IAA2.05 II 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 normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS ....................... .

Wednesday, October 08, 2008 Page 156 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 79 D 2.4.21 585 I APE057 I I KA desc APE057 GENERlCDKnowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CPR: 41.7/43.5 145.12)

Unit 1 is at 100% when loss of vital bus ERPA occurred. Assuming no actions have been taken:

1. What is the status of the associated channel Cont Hi-Hi Press bistable light?

2. What is the basis of this status per Technical Specification 3.3.2 (Engineered Safety Feature Actuation System (ESFAS) Instrumentation)?

A. 1. The bistable is LIT

2. To prevent an inadvertent main steam isolation B. 1. The bistable is DARK

2. To prevent an inadvertent main steam isolation C. 1. The bistable is LIT

2. To prevent an inadvertent NS actuation D. 1. The bistable is DARK

2. To prevent an inadvertent NS actuation Wednesday, October 08, 2008 Page 157 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 79 D General Discussion bistable is different than all others save 1 in that it is energized to actuate not deenergized to actuate. Basis is from TS 3.3.2.

Answer A Discussion lIn correct status and incorrect basis Answer B Discussion ICorrect status with incorrect basis Answer C Discussion lIn correct status with correct basis Answer D Discussion Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided

~ Developed TS 3.3.2 basis 0 OPT Approved AP29 0 OPS Approved 0 NRC Approved QuestionBank # IKA \KA system IKA

\KA number I 5851APE057 12 .4.21

[2.4.21 [1 KA desc APE057 GENERIC 0 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12)

Wednesday, October 08, 2008 Page 158 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 80 D APE058 586 I I AA2.03 I KA desc Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 / 45.13)DDC loads lost; impact on ability to operate and monitor plant systems ....

Given the following:

• Unit 2 was operating at 100%.

• At 1000, charger 2ECA output breaker opened due to an overvoltage condition.

• The 2EDA tie breaker to 2EDC can not be closed.

• At 1130, battery 2EBA voltage dropped below the voltage required per Technical Specifications.

Which one of the following describes the latest time that 2EDA can be restored to prevent entering a shutdown action and which procedure will be entered initially to respond to this failure?

Reference Provided A. 1200; EP/2/A/5500/E-0 (Reactor Trip or Safety Injection)

B. 1200; AP/2/A/55001029 (Loss of Vital or Aux Control Power)

C. 1330; EP/2/A/5500/E-0 (Reactor Trip or Safety Injection)

D. 1330; AP/2/A/55001029 (Loss of Vital or Aux Control Power)

Wednesday, October 08, 2008 Page 159 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 80 D General Discussion Loss of EPA causes Reactor Trip. EP/E-O will take precedence over AP/29. AP129 would be used after crew exits E-O and enters ES-Ol.

Correct action is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for DC. EDA does not become inoperable until the battery voltage drops below TS limits per the basis ofTS 3.8.9 Answer A Discussion Answer B Discussion J

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

~ Developed TS 3.8.9 Technical Specification 3.8.9 D OPT Approved EPL lesson D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 5861APE058 1AA2

• 03 I KA desc Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 I 45.I3)ODC loads lost; impact on ability to operate and monitor plant systems ....

Wednesday, October 08, 2008 Page 160 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA system IKA QuestionBank # IKA_system number lKA_number II QUESTION 81 B 587 I I APE077 I AA2.09 II KA desc Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 4l.5 and 43.5 /45.5, 45.7, and 45.8)DOperational status of emergency diesel generators ........................

Given the following conditions and sequence of events:

0300 Unit 1 CAPT is tagged out for a scheduled 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> PM.

0530 1AD-11, G/6 "SWGR 1ETA DEGRADED BUS VOLTAGE" is LIT 1AD-11, H/6 "SWGR 1 ETB DEGRADED BUS VOLTAGE" is LIT 1AD-11, K/6 "230KV SWITCHYARD VOLTAGE LO" is LIT 0536 1AD-11, G/6 "SWGR 1 ETA DEGRADED BUS VOLTAGE" is DARK 1AD-11, H/6 "SWGR 1 ETA DEGRADED BUS VOLTAGE" is DARK 0537 1AD-11, K/6 "230KV SWITCHYARD VOLTAGE LO" is DARK 0540 The STA notes by OAC trends that 1ETA and 1 ETB minimum voltages were 3620V and 3637V respectively before recovering.

1. At 0535, the RN system, the VCIYC system, and the system are in Technical Specification 3.0.3.

2. What is the current status of DIG 1A and DIG 1B?

A. VA; both running B. VA; both secured C. CA; both running D. CA; both secured Wednesday, October 08, 2008 Page 161 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 81 B General Discussion At 90% voltage a 10 min timer starts to intiate a BO of the essential busses. This time is 5 seconds if a LOCA has occurred (in this case the DIGs would start and load). Also, if voltage decreases to approximately 84% the DIG would start and load. Neither of these situations occurred so the DIGs are not started. The annunciators imply a grid disturbance. With degraded bus voltage shared systems VA, RN and VCYC are in 3.0.3. Since the CAPT is tagged out already, the student may think that all three CA pumps out is 3.0.3 which is wrong. Also, the RN procedure refers to RN, VCYC and CA when various protions ofRN are inoperable therby making CA a valid distractor.

Answer A Discussion

( Wrong DIG status Answer B Discussion ICORRECT Answer C Discussion (Both parts wrong - psychometric balance Answer D Discussion (Wrong system Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW

~ Developed Development References Student References Provided EQB lesson o OPT Approved EPA lesson OPIl/B/6100101OL lAD-ll Annun resp OOPS Approved o NRC Approved QuestionBank # IKA system IKA number I 587~E077 iIAA2.09 AA2 .09 iI KA desc Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CPR: 41.5 and 43.5 145.5, 45.7, and 45.8)OOperational status of emergency diesel generators ...................... ..

Wednesday, October 08, 2008 Page 162 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA system lKA_number QuestionBank # IKA IKA number I QUESTION 82 D 588 I APE024 I L

2.2.39 I L

KA KA desc APE024 GENERICDKnowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/

43.2/45.13)

Which one of the following FWST Technical Specification 3.5.4 parameters has the most limiting required action time and what is the basis for maintaining that parameter within limits?

A. FWST boron concentration To prevent excessive boron precipitation in the core B. FWST boron concentration To prevent a reduction in shutdown margin

c. FWST level To maximize the total energy release to containment D. FWST level To ensure sufficient volume to support containment sump recirculation Wednesday, October 08, 2008 Page 163 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 82 D General Discussion Answer A Discussion Reason is correct, paraemeter is not the first one (its 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)

Answer B Discussion Reason is correct, paraemeter is not the first one (its 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)

Answer C Discussion Correct parameter but wrong reason (this is why temperature is limited)

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

~ Developed TS 3.5.4 and basis 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # )KA system

1. )KA IKA

)KA_number number I) 5881APE024 12.2.39 I[

KA desc APE024 GENERICDKnowledge of less 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 164 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number 589 I APE068 I 2.4.21 I

I QUESTION 83 c KA desc APE068 GENERICOKnowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 4l. 7/43.5 /45.12)

Unit 1 is operating at 100% power. Unit 2 is in No Mode. The control room has become uninhabitable due to chlorine gas intrusion and the OSM has directed manning of the Auxiliary Shutdown Complex per AP/1/N55001017 (Loss of Control Room).

1. Once control is shifted to the Auxiliary Shutdown Complex, how is adequate primary side inventory assured?

2. Does the design basis of the Auxiliary Shutdown Complex include provisions for a concurrent Design Basis Accident?

A. 1. Automatic swap of NV pump suctions to the FWST

2. Yes B. 1. Automatic swap of NV pump suctions to the FWST

2. No C. 1. Manual swap of NV pump suctions to the FWST

2. No D. 1. Manual swap of NV pump suctions to the FWST

2. Yes Wednesday, October 08, 2008 Page 165 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 83 c General Discussion The design basis for the ASP does not allow for a DBA concurrent with its operation. When swapped to the ASP the interlock for automatic swap ofNV pump suctions is defeated and manually is perfromed by procedure at 23% VCT level. 4% is the correct swap setpoint for autoswap.

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

~ Developed API I 7 and basis 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # IKA system IKA number 5891APE068 12.4.21 1 KA desc APE068 GENERICDKnowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41. 7 I 43.5 145.12)

Wednesday, October 08, 2008 Page 166 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 84 B 590 J APE069 I AA2.01 l

KA_desc Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5 ! 45.13)DLoss of containment integrity ......................................

Given the following events and conditions:

• A large break LOCA occurred on Unit 1.

• 1ETA has lost all power

• 1B NS pump did not start in auto and efforts to start it manually have failed.

• Containment pressure is 8.6 psig

• The crew is reading step 5.i of EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) which reads:

"i. Verify proper recirc flow as follows:

• "NV S/I FLOW" - INDICA TlNG FLOW pump(s).

• NI pumps - INDICA TlNG FLOW

• NO pumps - INDICA TlNG FLOW II What is the current status of the Loss of Containment Integrity CSF block?

When is the CSF procedure implemented?

A. ORANGE; immediately B. ORANGE; when directed by EP/1/A/5000/ES-1.3 C. RED; immediately O. RED; when directed by EP/1/A/5000/ES-1.3 Wednesday, October 08, 2008 Page 167 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 84 B General Discussion During ES I.3 CSFs are not implemeneted until step IO is reached which says they may be re-implemented. The path is orange even though no NS pumps are running. Red is I5 psig.

Answer A Discussion IRight CSF color, wrong timing.

Answer B Discussion ICORRECT Answer C Discussion Wrong CSF color, wrong timing - psychometric balance.

Answer D Discussion IWrong CSF color, correct timing,.

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

~ Developed ESI-.3 0 OPT Approved F-O 0 OPS Approved 0 NRC Approved QuestionBank # IKA system )KA_number j 59~APE069 IAA2.0I I KA desc*

lAbility to determine and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5 / 45. I3)OLoss of containment integrity ..................................... .

Wednesday, October 08, 2008 Page 168 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank #IKA system IKA number J QUESTION 85 A 591 I WEI6 I EA2.1 I KA desc Ability to detennine and interpret the following as they apply to the (High Containment Radiation)

(CFR: 43.5/45. I3)OFacility conditions and selection of appropriate procedures during abnonnal and emergency operations.

Regarding the use of EP/1/A/5000/FR-Z.3 (Response To High Containment Radiation):

1. At what minimum reading on 1EMF 53A (Containment High Range) is the YELLOW path for Containment High Radiation valid?

2. What is the basis for placing the containment auxiliary charcoal filters in service when using this procedure?

A. 1. 35 Rlhr

2. To reduce activity in the containment atmosphere.

B. 1. 117 R/hr

2. To reduce activity in the containment atmosphere.

C. 1. 35 Rlhr

2. To reduce hydrogen concentration to prevent VE filter saturation if the Hydrogen Purge System is utilized.

D. 1. 117 R/hr

2. To reduce hydrogen concentration to prevent VE filter saturation if the Hydrogen Purge System is utilized.

Wednesday, October 08, 2008 Page 169 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 85 A General Discussion 117 is the value for EAL upgrade from RP/OI. H2 removal is plausible because the VE filters will get saturated with H2 ifH2 Purge is used.

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

~ Developed VV lesson 0 OPT Approved F-O RP-O.l 0 OPS Approved 0 NRC Approved IKA system QuestionBank # IKA_system IKA KA number I 5911WEl6 EA2.1 IEA2.1 jI KA desc Ability to determine and interpret the following as they apply to the (High Containment Radiation)

(CFR: 43.5 I 45.13)DFacility conditions and selection of appropriate procedures during abnormal and emergency operations.

Wednesday, October 08, 2008 Page 170 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA system IKA number I QUESTION 86 B 592 II SYSOO3 I A2.01 I

KA 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)DProblems with RCP seals, especially rates of seal leak-off ..............

Unit 2 is in preparations for startup with the shutdown banks withdrawn and the control banks inserted. Given the following:

• 2AO-7 C/1 NCP #1 "SEAL LEAKOFF HI FLOW' is LIT

• 2B NCP sealleakoff is 6.5 gpm

• 2B NCP Seal Outlet temperature is slowly increasing

• The crew enters AP/2IN55001008 (Malfunction of Reactor Coolant Pump)

What is the maximum time 2B NCP can remain in service and what procedure does AP/2/A/55001008 direct the crew to enter once the pump is tripped?

A. 5 minutes; EP/2IN5000/E-0 (Reactor Trip or Safety Injection)

B. 5 minutes; AP/2IN55001004 (Loss of Reactor Coolant Pump)

C. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; OP/21N61 001003 (Controlling Procedure For Unit Operation)

O. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; AP/2IN55001004 (Loss of Reactor Coolant Pump)

Wednesday, October 08, 2008 Page 171 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 86 B General Discussion A "normal" value requiring a 5 minute SID is greater than or equal to 7.5. The 6.5 would normally cause an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> SID however, in this case the temperature is slowly increasing. Since the plant is in MODE 3 tripping the reactor is not required and API04 will be entered not E-O Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided

~ Developed OPIl/B/6100IOIOH IAD07 0 OPT Approved API 1/Al55001004 AP/l/Al55001008 0 OPS Approved 0 NRC Approved QuestionBank # [KA system [KA number [

5921SYS003 IA2.01 JI 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 45/13)DProblems with RCP seals, especially rates of seal leak-off ............. .

Wednesday, October 08, 2008 Page 172 of 200

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

593 IKA system IKA_number

1. JKA I SYS026 jKA number I 2.4.47 II JI QUESTION 87 c KA KA desc SYS026 GENERIC 0 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/45.12)

The night shift surveillance readings for Lake Wylie temperature over the past several days are as follows:

• 8/01/08 - 87.50° F.

• 8/02/08 - 88.25° F.

• 8/03/08 - 89.00° F.

• 8/04/08 - 89.75° F.

• 8/05/08 - 90.50° F.

1. Assuming lake temperature continues to increase at a constant rate, on what date will Lake Wylie temperature first exceed the requirements of SLC 16.9-14 (Lake Wylie Water Temperature)?

2. What affect, if any, will this higher lake temperature have on the ability of the NS system to affect containment pressure following a large break LOCA?

A. 1. 8/09/08

2. Minimal impact prior to ice melt, but significant impact later in the accident sequence when the ice has been depleted.

B. 1. 8/09/08

2. Minimal impact during the entire accident sequence since lake temperature is still below the design basis accident assumptions.

C. 1. 8/12/08

2. Minimal affect prior to ice melt, but significant affect later in the accident sequence when the ice has been depleted.

D. 1. 8/12/08

2. Minimal impact during the entire accident sequence since lake temperature is still below the design basis accident assumptions.

~ Wednesday, October 08, 2008 Page 173 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 87 c General Discussion SLC requirement is 95.5 degrees which would be exceeded on 8112/08. 08109/08 is the time which would require one train ofRN to be aligned to the pond during ES 1.3. and is the same action as the sic.

Answer A Discussion IWrong date; 2 is incorrect Answer B Discussion Iwrong date Answer C Discussion ICORRECT Answer D Discussion 12 is incorrect Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW

~ Developed Development References Student References Provided SLC 16.9-14 D OPT Approved ESI.3 TSB3.7.9 D OPS Approved D NRC Approved QuestionBank # IKA system IKA number I 5931SYS026 12.4.47 I1 KA KA desc SYS026 GENERlCOAbility to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10 I 43.5 145.12)

Wednesday, October 08, 2008 Page 174 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 88 c 594 I SYS039 I A2.02 I

KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 I 45. 13)0 Decrease in turbine load as it relates to steam escaping from relief valves.

Given the following:

• Rod control is in MANUAL.

• Turbine power has decreased from 1227 MW to 1219 MW and stabilized.

• The crew has just entered AP/1/A/55001028 (Secondary Steam Leak).

What single steam relief valve passing 25% of full flow would produce the conditions noted and what actions will be directed per AP/1/A/55001028 based on the leak size?

A. A steam line safety; trip the reactor and go to EP/1/A/5000/E-0 (Reactor Trip or Safety Injection.

B. A S/G PORV; trip the reactor and go to EP/1/A/5000/E-0 (Reactor Trip or Safety Injection.

C. A S/G PORV; initiate a unit shutdown per AP/1 lA/55 001009 (Rapid Downpower)

D. A steam line safety; initiate a unit shutdown per AP/1/A/55001009 (Rapid Downpower)

Wednesday, October 08, 2008 Page 175 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 88 c General Discussion A PORV is about 2.5% steam flow and a safety is about 5%. This turbine MW represents a -2.5% load reduction. Therefore it is a PORV.

AP/28 directs tripping the reactor and entering E-O if steam leak is >5%. Otherwise a load reduction is performed per AP/09 (or the OP which is not an answer choice)

Answer A Discussion Answer B Discussion lesson plan provided TOTAL PORV capacity at 10% which could lead student to erroneously think this is correct if they misread.

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

~ Developed AP/28 D OPT Approved SM D OPS Approved D NRC Approved QuestionBank # #JKA IKA system IKA number II 594!SYS039 iA2 *02 Ji KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 I 45. 13)0 Decrease in turbine load as it relates to steam escaping from relief valves.

Wednesday, October 08, 2008 Page 176 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination Q~o~~n~# KA_sy~tem 0L KA nUmber----- .l- QUESTION 89 A 595 SYS062 2.1.20

==<1----->=-==== ~~ - - ~~-_

KA_desc ISYS062 G-E-N-ERI-C-O-A-bi-lity-to interpre_t and execute procedure steps. (CFR: 41-.10 / 43.5 / 45.12) ~I Unit 1 is operating at 100% power. Given the following:

• 1A DIG was manually started by NLOs for monthly surveillance testing

• A grid instability and relay failures cause all Unit 1 Switchyard PCBs to open

• The ensuing transient results in a 1B S/G tube rupture

• Annunciator DIG 1A Panel, A/4 'TRIP LOW PRESS LUBE OIL" - LIT

• 1B DIG failed to start Which procedure will isolate the ruptured S/G and what is the continuing guidance regarding ruptured S/G level?

A. EP/1/A/5000/E-3 (Steam Generator Tube Rupture); maintain ruptured S/G greater than 11 % NR using CA as required.

B. EP/1/A/5000/E-3 (Steam Generator Tube Rupture); maintain ruptured S/G isolated.

C. EP/1/N5000/ECA-0.0 (Loss of All AC Power); maintain ruptured S/G greater than 11 % NR using CA as required.

D. EP/1/A/5000/ECA-0.0 (Loss of All AC Power); maintain ruptured S/G isolated.

Wednesday, October 08, 2008 Page 177 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 89 A General Discussion Setup is that the only source of power may (or may not) be IA DIG. The 10 lube oil setpoint will trip the DIG for manual starts, however, the loca seq will cause the non-emergency trips to be blocked, hence IA DIG will be available so entry into ECA 0.0 is not required. E3 guidance is to maintian > 11% NR level Answer A Discussion Answer B Discussion Iright procedure wrong guidance Answer C Discussion I wrong guidance (CAPT only in ECA 0.0)

Answer D Discussion Iboth parts wrong _ psychometric balance Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW

~ Developed Development References Student References Provided DIG IA Annun RESP o OPT Approved ECAO.O E-3 OOPS Approved DG3 o NRC Approved QuestionBank # KA system KA number 595 SYS062 2.1.20 KA desc SYS062 GENERlCDAbility to interpret and execute procedure steps. (CFR: 41.10 I 43.5 145.12)

Wednesday, October 08, 2008 Page 178 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA IKA_system IKA_number number II QUESTION 90 D 596 SYS076 A2.02 I I I KA KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; 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/ 45113)0 Service water header pressure ......................................

Both units were operating at 100% power with 1A RN pump in service.

1A DIG was operating in parallel for surveillance testing when the following conditions and sequence of events occurred:

• 1AD-12, Al2 URN ESSENTIAL HDR A PRESSURE - LO" - LIT

• 2AD-12, Al2 "RN ESSENTIAL HDR A PRESSURE - LO" - LIT

• 1AD-12, Al5 URN ESSENTIAL HDR B PRESSURE - LO" - LIT

• 2AD-12, Al5 "RN ESSENTIAL HDR B PRESSURE - LO" - LIT

• NLO reported that he evacuated the DIG room due to flooding.

• 1A DIG was immediately secured by the control room crew.

• All annunciators listed above continue to remain LIT.

• The crew entered and took all actions per AP/OIAl55001030 (Plant Flooding) necessary to stop the flooding.

1. At what RN header pressure do the annuciators first come into alarm?

2. What is the current overall status related to Tech Spec 3.7.8 (Nuclear Service Water System (NSWS))?

A. 1. 40 psig decreasing

2. Unit 1 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action, Unit 2 operable B. 1. 40 psig decreasing

2. Both units in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action C. 1. 46 psig decreasing

2. Unit 1 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action, Unit 2 operable D. 1. 46 psig decreasing

2. Both units in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action Wednesday, October 08, 2008 Page 179 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 90 D General Discussion Rn low header pressure comes in at 46 pisg decreaing. With the lA DIG secured, RN232A would close. Since the conditions persist following shutdown, the leak must be between the DIG building wall and RN232A. The only way that this leak can be secured is to separate RN trains and secure all of A train RN which is what AP30 does. This makes both units enter a 72 action for RN. The 40 psig value is the RNIYV opearble light pressure setpoint.

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

~ Developed AP30 D OPT Approved RN lesson TS 3.7.8 D OPS Approved D NRC Approved QuestionBank # IKA system IKA number JI 596\SYS076 596iSYS076 A2 02 i\A2.02

• JI KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; 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 I 45/3 145/13)0 Service water header pressure ..................................... .

Wednesday, October 08, 2008 Page 180 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number II QUESTION 91 A 597 I I SYS033 I 2.2.22 I KA desc I SYS033 GENERlC 0 Knowledge of limiting conditions for operations and safety limits. (CPR: 41.5/43.2/45.2) I Unit 2 is in Mode 6 performing core unloading when Spent Fuel Pool level is noted at 22 feet above the fuel assemblies.

1. Which one of the following is a required action for the above condition?

2. What is the basis for that action?

A. 1. Immediately suspend movement of irradiated fuel assemblies

2. Shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident B. 1. Immediately suspend movement of irradiated fuel assemblies

2. Ensures that an adequate water volume is available to supply the Standby Makeup Pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. 1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate action to restore spent fuel pool level to within limits.

2. Shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident D. 1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate action to restore spent fuel pool level to within limits.

2. Ensures that an adequate water volume is available to supply the Standby Makeup Pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Wednesday, October 08, 2008 Page 181 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 A General Discussion SFP Boron should be >2700 and level should be >23 feet. Both specs are not met.

Action for boron out is to stop moving all fuel assemblies in the spent fuel pool and initiate action to get It back.

Action for level out is to stop moving irradiated fuel.

Correct answer states stop moving fuel assemblies. This encompasses both irradiated and none irradiated.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> basis is from the SSF and the SFP level requirements Basis for boron: Calculations show that the soluble boron concentrations needed to maintain the spent fuel pool keffbelow 0.95 for the postulated accidents related to fuel assembly movement are far less than the minimum amount available in the spent fuel pools (per the LCO for TS 3 .. 7.15).

Level basis is: The specified water level shields and minimizes the general area dose when the storage racks are filled to their maximum capacity.

Answer A Discussion Answer B Discussion ICorrect action with correct basis Answer C Discussion IIncorrect action with correct basis Answer D Discussion lIn correct action with incorrect basis Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW

~ Developed Development References Student References Provided COLR o OPT Approved TS3.7.14 and basis TS3.7.15 and basis OOPS Approved SLC16.7-9 o NRC Approved QuestionBank # KA system KA number 597 SYS033 2.2.22 KA desc SYS033 GENERICOKnowledge ofiimiting conditions for operations and safety limits. (CFR: 41.5/43.2/45.2)

Wednesday, October 08, 2008 Page 182 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA 598 I syson system IKA JKA_system SYSOn I number JKA_number A2.02 IJ I

QUESTION 92 c KA KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 4\.5/43.5/43.3/ 45. 13) 0 Detector failure .................................................

Given the following:

• Unit 2 has experienced a Safety Injection.

• The crew has entered EP/21A150001E-3 (Steam Generator Tube Rupture) due to 2EMF-1 0 (Steamline A) Trip 1 light being LIT.

• The OSM believes the EMF indication to be false.

1. What method can the crew use to determine the indication is false?

2. Once the indication is determined to be false, how will the correct procedure be implemented?

A. 1. Verify Trip 1 alarm on adjacent steamline EMF (2EMF-13 (Steamline D))

is DARK

2. Immediately enter EP/21A15000/ES-O.O (Rediagnosis)

B. 1. Verify Trip 1 alarm on adjacent steamline EMF (2EMF-13 (Steamline D))

is DARK

2. Transition to EP/2IAl5000/E-1 (Loss of Reactor or Secondary Coolant) per Enclosure 1 of EP/21A150001E-3 (Steam Generator Tube Rupture)

C. 1. Request that RP frisk cation columns

2. Immediately enter EP/21A15000IES-O.O (Rediagnosis)

D. 1. Request that RP frisk cation columns

2. Transition to EP/21A15000/E-1 (Loss of Reactor or Secondary Coolant) per Enclosure 1 of EP/21A15000/E-3 (Steam Generator Tube Rupture)

Wednesday, October 08, 2008 Page 183 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 92 c General Discussion Entry into ES-O.O may be made at anytime. Adjacent steam line EMFs can be used to diagnose a SGTR if the actual S/G EMF is broken.

However those are the N16 monitors and these are not (plausible).

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

~ Developed E-1 D OPT Approved E-3 D OPS Approved D NRC Approved QuestionBank # IKA KA system IKA IKA number JI 5981syson 598 SYSOn IA2.02 IA2.02 II KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system- 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 /43.3 /45.13)ODetector failure ...............................................

Wednesday, October 08, 2008 Page 184 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA system IKA number I QUESTION 93 D 599 I SYS086 I A2.01 I!

KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; 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 I 45.3 1 45.13)OManual shutdown of the FPS .......................................

Given the following:

• Unit 1 is at 100% power.

• Unit 2 is in No Mode.

• "c" Main Fire Pump is tagged out for PMs.

• NLOs were running the SSF DIG per PT/O/A/42001017 (Standby Shutdown Facility Diesel Test) when a fuel oil leak resulted in a fire.

• The control room has implemented AP/O/A/55001045 (Plant Fire).

• The Plant Fire Brigade extinguished the fire 20 minutes later and it was noted that some damage was evident on the SSF DIG.

1. What is the current emergency classification for this situation?

2. Once the fire has been extinguished, what is the minimum fire header pressure that will allow all currently available fire pumps to be manually secured?

Reference provided A. 1. Unusual Event

2. greater than 90 psig B. 1. Unusual Event

2. greater than 95 psig C. 1. Alert

2. greater than 90 psig D. 1. Alert

2. greater than 95 psig Wednesday, October 08, 2008 Page 185 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 93 D General Discussion Unusual event is fire extinguished after 15 min or greater. Alert is visible damage to certain equipment (of which the SSF is one) regardless of length of fire. The available fire pumps are A and B. They autostart at 95 psig and 90 psig respectively. C starts at 85 but is not available due to tagout. Therefore, anything >95 psig will allow all available pumps to be stopped.

Answer A Discussion IWrong classification, wrong pressure Answer B Discussion Iworng classification,. Right pressure Answer C Discussion Iright classification, wrong pressure Answer D Discussion Iwrong and right Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided

~ Developed RP/OI RP/OIA/50001001 Classification of 0 OPT Approved RFY Emergency 0 OPS Approved 0 NRC Approved QuestionBank #IKA system IKA number J 599/SYS086 /A2.01 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 145.13)DManual shutdown of the FPS ...................................... .

Wednesday, October 08, 2008 Page 186 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA_system IKA number IKA system .IKA_number II QUESTION 94 A 600 II GEN2.1 I I 2.l.l4 I KA desc Conduct of Operations 0 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10/43.5/45.12)

Unit 1 is at 100% with 1A CA pump tagged for preventative maintenance. Given the following conditions and sequence of events:

• The main turbine trips due to faulty MSR high level signal

• NLOs were dispatched and opened the reactor trip breakers locally

• CAPT tripped on overs peed

• 1B CA Pump is found to have no indicating lights and no discharge pressure or flow indicated

• NLO reports 1B CA Pump control power is unavailable

• CAPT was successfully reset and restarted

• Current S/G parameters are:

1A 1B 1C 10 I N/R level 10% 7% 9% 10%

I CA flow 105 gpm 105 gpm 115 gpm 110 gpm Which one of the following is the correct Emergency Action Level and the first required notification to plant personnel for this current conditions?

Reference provided A. Enter a General Emergency and notify plant personnel to perform a site assembly B. Enter a General Emergency and notify plant personnel to perform a site evacuation C. Enter a Site Area Emergency and notify plant personnel to perform a site assembly

o. Enter a Site Area Emergency and notify plant personnel to perform a site evacuation Wednesday, October 08, 2008 Page 187 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 94 A General Discussion Turbine trip should have resulted in a reactor trip but didn't and rx had to be tripped locally. Based on S/G conditions, Heat Sink is in RED due to S/G levels <11% with total feed flow <450gpm. This loss of heat sink will cause entry into the fission product barrier matrix ofRP/OI as Site Area Emergency, however it is a general emergency based on ATWS requiring local trip AND HEAT SINK in red. A site evacuation is always precluded by a site assembly, and never done directly.

Answer A Discussion

!L--____________________________

I'---__________________________ - - --.-..J J

Answer B Discussion ICorrect classification wrong action Answer C Discussion Wrong classification and action (but a correct action if the classification was true).

Answer D Discussion lIn correct classification and action Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED 2006 NRC Q90 (Bank 696)

Development References Student References Provided

~ Developed

References:

RP/OIA/50001001 Classification of 0 OPT Approved l. RP/OI Emergency

2. TS 3.7.5 0 OPS Approved OP-CN-EP-SEPI4 0 NRC Approved QuestionBank # IKA system IKA number I 6001GEN2.1 600!GEN2.1 12 .1.14

\2.1.14 1

KA desc Conduct of OperationsOKnowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10 143.5 145.12)

Wednesday, October 08, 2008 Page 188 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA 601

[KA system I GEN2.1 IKA number I 2.1.36 I[

I QUESTION 95 c KA desc I Conduct of OperationsDKnowledge of procedures and limitations involved in core alterations. (CFR: 41.10/43.6/45.7)

I Given the following:

• Core reload is in progress with 1A NO train in service.

• 1B NO train is inoperable.

• The fuel handling SRO requests 1A NO train be secured to allow a fuel assembly to be placed near the cold leg nozzle.

1. How long can 1A NO train remain shutdown per Technical Specification 3.9.4 (Residual Heat Removal (RHR) and Coolant Circulation-High Water Level)

2. What are the requirements associated with making additions to the reactor coolant system at this time?

A. 1. 30 minutes

2. All additions must have a boron concentration greater than the COLR minimum.

B. 1. 30 minutes

2. Any addition is allowed provided NC system/refueling cavity boron concentration remains greater than the COLR minimum.

C. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

2. All additions must have a boron concentration greater than the COLR minimum.

O. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

2. Any addition is allowed provided NC systemlrefueling cavity boron concentration remains greater than the COLR minimum.

Wednesday, October 08, 2008 Page 189 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 95 c General Discussion TS says 'The required RHR loop may be removed from operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided no operations are permitted that would cause introduction of coolant into the Reactor Coolant System with boron concentration less than required to meet the minimum required boron concentration ofLCO 3.9.1." The 30 minutes is the completion time for AFD and several other TS and Safety limits. It ensures the correct answer of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is not telegraphed by having a greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action and not giving the TS as a reference. Additions must be

>COLR limit since there is no mixing with no ND in service.

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

~ Developed Development References Student References Provided TS 3.9.4 and basis o OPT Approved TS 3.2.3 OOPS Approved o NRC Approved QuestionBank # KA system KA number 601 GEN2.1 2.1.36 KA desc Conduct of Operations OK now ledge of procedures and limitations involved in core alterations. (CFR: 4l.l0 / 43.6 / 45.7)

Wednesday, October 08, 2008 Page 190 of200

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

1. JKA I QUESTION 96 A 602 I GEN2.2 JI 2.2.15 I KA KA desc Equipment ControlDAbility to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.1 0/43.3 /45.13)

As the WCCSRO you have received the following for consideration:

• An accurate red tag package to be approved for the weekly change out of Amertap balls on Unit 1.

• An accurate Boundary Change Notification Form (BCNF) to be approved to revise tagout boundaries for the 2A Hotwell Pump.

1. Are red tags required per NSD 500 for the Amertap ball change out?

2. Should you approve the BCNF?

A. 1. No

2. Approve the BCNF; overall approval is done by the OCG.

B. 1. No

2. Do not approve the BCNF; overall approval is done by the WCG.

C. 1. Yes

2. Approve the BCNF; overall approval is done by the OCG.

D. 1. Yes

2. Do not approve the BCNF; overall approval is done by the WCG.

Wednesday, October 08, 2008 Page 191 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 96 A General Discussion NSD 500 states a tagout is not required for changing the Amertap balls and the Operational control Group is responsible for approving the BCNF. Red tagsa rae genrarll required for opening systems for work. This is an exception.

Answer A Discussion ICORRECT Answer B Discussion IThe BCNF should be approved, Answer C Discussion

\the RA tagout should not be approved.

Answer D Discussion the RA tagout should not be approved, the BCNF should be Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided

~ Developed NSD500 0 OPT Approved 0 OPS Approved 0 NRC Approved QuestionBank # lKA [KA system lKA

[KA number I 601GEN2.2 6021GEN2.2 12.2.15 1 KA desc Equipment ControlDAbility to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 4l.l0 / 43.3/45.13)

Wednesday, October 08, 2008 Page 192 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination IKA QuestionBank # IKA system IKA number JI QUESTION 97 B 603 I GEN2.2 I 2.2.3 I

KA KA desc Equipment ControlD(multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 /41.6/

41.7/41.10/45.12)

Both units are operating at 60% power. IAE has placed B S/G NR Level Channel 1 bistables in trip on each unit for testing. The RO on each unit notes another channel of S/G NR level unrelated to the IAE work drifting up.

Assuming no actions are taken and the drifting channel on both units match each other (% NR level) as they increase, which turbine will trip first and what is the basis of that trip?

A. Unit 1 / Limit energy release into containment following a steam line break B. Unit 2 / Limit energy release into containment following a steam line break C. Unit 1 / Maintain offsite dose within assumed limits following a SGTR D. Unit 2/ Maintain offsite dose within assumed limits following a SGTR Wednesday, October 08, 2008 Page 193 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 97 B General Discussion Unit 1 P 84%, Unit 2 -77%. Basis for P-14 is"to prevent damage to the turbine due to water in the steam lines, stop the excessive flow of feedwater into the SGs, and to limit the energy released into containment" Reason that SAl and 4 are closed on S/G TR with loss of VI (which invovles hi S/G level as well)

Answer A Discussion IWrong unit Answer B Discussion Answer C Discussion IBoth wrong - psychometric balance.

Answer D Discussion IWrong reason Job Level Cognitive Level QuestionType Question Source SRO Memory NEW

~ Developed Development References Student References Provided TS3.3.2 and basis D OPT Approved EPINTRO D OPS Approved D NRC Approved QuestionBank # IKA system IKA IKA number II 6031GEN2.2 12 .2 .3 12.2.3 J1 KA desc Equipment ControlD(multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 141.6 I 41.7 I 41.10 I 45.12)

Wednesday, October 08, 2008 Page 194 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA IKA_system IKA number system .IKA_number I QUESTION 98 c 604 I

I GEN2.3 1I 2.3.13 I KA KA desc Radiation ControlDKnowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12/

43.4 / 45.9 / 45.10)

Unit 2 is operating at 100% power. Maintenance has requested entry into the lower airlock. The work will require propping open the airlock vestibule door (CAD door) and the outer airlock door. The inner airlock door will remain closed.

For this situation, whose approval is required and what is inoperable based on Technical Specifications?

A. WCC SRO and RP Supervisor; the Annulus Ventilation System B. RP manager and Station Manager; the Annulus Ventilation System C. WCC SRO and RP Supervisor; the Reactor Building D. RP manager and Station Manager; the Reactor Building Wednesday, October 08, 2008 Page 195 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 98 c General Discussion Per SD 3.1.2 sect 4.2 if inner airlock door is not opened then not a containment entry and RB/Annulus entry requirements are needed. Sect 5.1.4 says approval from RP and WCC. RP mananger and station manager are need if enter lower containment at >5% RTP Sect 5. I .4.2 tells that if door open for reasons other than normal transit - RB inop. Not VE.

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

~ Developed TS3.6.10 D OPT Approved TS3.6.16 SD3.1.2 D OPS Approved D NRC Approved IKA QuestionBank # IKA system IKA IKA_number number II 60~GEN2.3 6041GEN2.3 12.3.13 1 KA desc Radiation ControlDKnowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.121 43.4/45.9/45.10)

Wednesday, October 08, 2008 Page 196 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QuestionBank # IKA 605 IKA system IKA I GEN2.3 IKA number 1I 2.3.14 II I

QUESTION 99 c KA KA_desc desc Radiation ControlDKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12/43.4 / 45.10) 2 A contract worker is performing a task in an area with 5000 dpm/100 cm (beta, gamma) contamination. His coworkers have reported he is acting erratic and believe he is "on" something. While waiting for supervision and security to arrive the individual falls and is injured. The individual is contaminated and must be transported offsite for medical treatment.

What is the correct posting for the area where the work was occurring and what is the required NRC notification time for this event?

A. Contaminated Area; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Highly Contaminated Area; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. Contaminated Area; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. Highly Contaminated Area; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Wednesday, October 08, 2008 Page 197 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 99 c General Discussion FFD issue is a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification. >50,000 is Highly.

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

~ Developed RP/13 D OPT Approved NSD507 D OPS Approved D NRC Approved QuestionBank # #JKA IKA system IKA number I 605jGEN2.3 605!GEN2.3 12.3.14 12.3.14 j1 KA desc Radiation ControlOKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 4l.l2 1 43.41 45.10)

Wednesday, October 08, 2008 Page 198 of200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination jKA system IKA number QuestionBank # IKA I QUESTION 100 A 606 I GEN2.4 I J 2.4.3 I KA desc I Emergency Procedures / PlanDAbility to identify post-accident instrumentation. (CFR: 41.6/45.4)

Ii Given the following conditions:

• Unit 2 has experienced a small break LOCA

• The crew has transitioned to EP/2/A/5000IES-1.2 (Post LOCA Cooldown and Depressurization)

• Containment pressure is 4.5 psig and decreasing slowly

• Present pressure indications are:

o PZR PRESS Channel 1 - 1815 psig o PZR PRESS Channel 2 - 1795 psig o PZR PRESS Channel 3 - Failed High o PZR PRESS Channel 4 - Failed High o LOOP B HOT LEG WIR PRESS - 1920 psig o LOOP C HOT LEG W/R PRESS - Failed Low

1. Which instrument(s) above will provide the most reliable indication of current primary system pressure?

2. What is the basis for having the NCS pressure instrument(s) that provide this reliable indication?

A. 1. LOOP B HOT LEG W/R PRESS

2. For operator diagnosis of primary system conditions following an accident B. 1. PZR PRESS Channels 1 and 2

2. For initiating automatic actions that allow safety systems to perform their function C. 1. LOOP B HOT LEG WIR PRESS

2. For initiating automatic actions that allow safety systems to perform their function D. 1. PZR PRESS Channels 1 and 2

2. For operator diagnosis of primary system conditions following an accident Wednesday, October 08, 2008 Page 199 of 200

FOR REVIEW ONLY - DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 100 A General Discussion Per OMP I -7, PAM isntruments provide the most reIianble indication In ACC conditions. The basis of PAM instruments is for operator diagnosis of primary system parameters. W!R pressure does not initiate auto actions associated with accidents, but does provide input to L TOP circuitry. PZR pressure channels input ESFAS but are not PAM instruments.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source SRO Memory NEW

~ Developed Development References Student References Provided TS3.3.3 and basis o OPT Approved OMPI-7 OOPS Approved NRC Approved QuestionBank # KA system KA number 606GEN2.4 2.4.3 KA desc Emergency Procedures / Plan 0 Ability to identify post-accident instrumentation. (CFR: 41.6/45.4)

Wednesday, October 08, 2008 Page 200 of 200