ML072960530

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July-August Exam - 214, 324/2007-301, Draft SRO Written Exam with Answers, Senior Reactor Operator Written Exam
ML072960530
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/31/2007
From:
- No Known Affiliation
To:
Office of Nuclear Reactor Regulation
References
50-324/07-301, 50-325/07-301, ES-401-5 50-324/07-301, 50-325/07-301, NUREG-1021, Rev 9
Download: ML072960530 (53)
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Text

Draft Submittal (Pink Paper)

Senior Reactor Operator Written Exam BRUNSWICK JULY-AUG EXAM - 325,324/2007-301 DRAFT SRO WRITTEN EXAM WITH ANSWERS

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #76 Tier# 1 Group # 1 KIA # 295001 AA2.01 Importance Rating 3.8 (K&A Statement) Ability to determine and/or interpret the following as"they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Power/flow- map.

Proposed Question: Unit Two (2) is operating at rated power when the field breaker for 2A Reactor Recirculation Pump trips OPEN due toa malfunction.

Plant conditions have been stabilized and are as follows:

Reactor Power Jet Pump Flow Loop A (R611A) 13 Mlbm/hr Jet Pump Flow Loop 8 (R611 8) 57 -Mlbm/hr T ot~1 Core Flow Recorder (R6t3) 44 Mlbm/hr Computer Point U2CPWTCF 44.6 Mlbm/hr (Valid)

H"ow is the current operating point on the Power/Flow Map determined?

A. -I"n accordance with 2AOP-4.0 "Low Core Flow" use Computer Point U2CPWTCF for stability region compliance.

8. In accordance with 2AOP-4.0 "Low Core Flow" "lJ§e r~corder 2821-PDR/FR"-R613, located on H12-P603, for Stability Region Compliance.

C. In accordance with 20P-02, Reactor Recirculation System, Section 8.1 Transferring from Two-Pump, Two-Loop Operation to Qne-Pump, One-Loop Operation use Core

'Support Plate delta P, Figure 1 to determine core flow.

D. -tn-accordance with 20P-02, Reactor Recirculation Syst-em, Section- 8.1 Transferring from Two-Pump, Two-Loop Operation to One-Pump, One-Loop Operation u~e recorder 2821-PDR/FR-R613, located on H12-P603 to determine core flow.

Proposed a. In accordance with 2AOP-4.0 "Low Core Flow" use Computer Point Answer: U2CPWTCF for stability region compliance.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation: The Total Core Flow Recorder is subtracting the idle loop flow as per design however, per 1AOP-4.0 Process Computer Point 8018, Total Core Flow, and recorder 821-PDR/FR-R613 (P603) will read lower than Process Computer Point U1 CPWTCF as the stability region is approached. Q*QJDPuter Point U1 CPWTCF is the primary indication of total core flow and sh.o.uld be used for stability region comp.liance.

I

b. is incorrect because recorder B21-PDR/FR-R613 (P603) will read lower than' Process Computer Point U1CPWTCF.
c. is incorrect although there is a section for signal loop operation and identical guidance for determining core flow, 2AOP-04 is entered based on the APPs and AOP entry conditions.

Additionally core support plate dIp figure 1 is only used if Computer Point U1 CPWTCF is NOT available.

d. is incorrect although there is a section for signal loop operation and identical guidance for determining core flow, 2AOP-04 is entered based on the APPs and AOP entry conditions.

Additionally recorder B21-PDR/FR-R613 (P603) will read lower than Process Computer Point U1 CPWTCF.

Technical Reference(s): 2AOP-04, 20P-02 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: None Learning Objective: LOI-CLS-LP-302-C, Objs 1 & 4 (As available)

Question Source: Bank# LOI-AOPBank LOI-CLS-LP-302-C*011 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowl~dge Comprehension or Analysis - X --

10 CFR Part 55 Content: 55.4.1 55.43 5

  • Comments:

NUREG-1 021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #77 Tier # 1 Group # 1 KIA # 295003,2.1.14 Importance Rating 3.3 (K&A Statement) Knowledge of system status criteria which require the notification of plant personnel.

Proposed Question: The Brunswick plant has entered OAOP-36.2 Station Blackout, Per AOP-36.2, which qne of the following are the MINIMUM notifications required within one hour?

Notify:

A. System Dispatcher and the NRC B. Security, and Manager - Operations (or Manager - Shift Operations)

C. Security, Manager - Operations (or Manager - Shift Operations) and NRC D. System Dispatcher, Security, and the Manager - Operations (or Manager - Shift Operations) .

Proposed D. System Dispatcher, Security, and the Manager - Operations (or Manager-Answer: Shift Operations)

Explanation: OAOP-36.2 Station Blackout, requires notification of System Dispatcher, Security. '

001-01.07, Notifications requires notification of the Manager - Operations or Manager - Shift Operations within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. There is mention of notifying the NRC Resident, however the determination of the time frame for notification is left with the Manager - Operations.

a. is incorrect because Security, and Manager - Operations (or Manager - Shift Operations) must be notified and notification of the NRC is required within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b. is incorrect because the System Dispatcher must be notified.
c. is incorrect because the System Dispatcher must be notified and notification of the NRC is required within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Technical Reference(s): 001-01.07, OAOP-36.2 (Attach if not previously provided)

NUREG-1 021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination:

Learning Objective: _L_O_'_-C_L_S_-L_P_-_30_2_-F_*_O_03 (As available)

Question Source: Bank#

Modified (Note changes Bank # or attach parent)

New x

_ _ _..........::Q=...::uestion History: Last NRC Exam N/A*

Question Cognitive Level: Memory or Fundamental Knowledge - X --

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

ES-401 Sample Written Examination Form ,ES-401-5 Question Worksheet Examination Outline Cross-ref~rence: Level RO SRO SRO #78 Tier # 1 Group # 1 KIA # 295024 2.4.31 Importance Rating 3.4 (K&A Statement) Knowledge of annunciators alarms and indications, and use of the response instructions.

Proposed Question: Following a partial loss of drywell cooling, primary containment conditions are:

The following annunciators have alarmed:

CONTAINMENT PRESSURE AT 1.5 PSIG (UA-25 '1-5)

PRI CTMT HI/LO PRESS (A - 05 5-5)

Drywell pressure is confirmed as 1.5 psig and slowly rising Drywell temperature is135°F, slowly rising What operator action is required?

A. Enter AOP-14 and vent the drywell using SBGT per OP-10.

B. Enter EOP-02-PCCP and vent the drywell using SBGT per OP-10.

C. Enter AOP-14 and vent the drywell using Purge Fans per SEP-01.

D. Enter EOP-02-PCCP and vent the drywell using Purge Fans per SEP-01.

Proposed A. Enter AOP-14 and vent the drywell using SBGT per OP-10.

Answer:

Explanation: Entry into PCCP is required at 1.7 psig drywell pressure or 150°F drywell temperature. Since drywell pressure is below 1.7 psig and drywell temperature is < 150°F, SBGT can be used to vent the drywell per OP-10.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

b. is incorrect EOP entry is not required because drywell pressure is <1.7 psig and drywell temperature is <150°F.
c. is incorrect SEP-01 is used to vent the drywell to maintain pressure below PCPL-A..
d. is incorrect EOP entry is not required because drywell pressure is <1.7 psig and drywell temperature is <150°F and SEP-01 is used to vent the drywell to maintain pressure below PCPL-A..

Technical Reference(s): APPs, AOP-14 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (As available)

---Q_u~e_stio_n_SJ)urce~: - ==B-=-a:. .:. . . : n- =- =-k. . .: . : . #_ _--=-LO-=--=-I=-E..=Jop~B~n.::...::..k _

LOI-CLS-LP-300-L*08C 001 Modified (Note changes Bank # or attach parent) .

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 Comments:

NUREG-1021, Revision 9'

ES~401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #79 Tier # 1

,Group # 1 KIA # 295025 2.4.6 Importance Rating 4.0 (K&A Statement) Knowledge symptom based EOP mitigation strategies. (High Reactor Pressure)~

Proposed Question: Unit One (1) has the following plant conditions:

Reactor is shutdown (all rods in)

Reactor pressure is 800 psig Demineralized Water is injecting to the RPV using SLC per LEP-01 eNt-'f-1-A-C-er-e-S19F-ay~-+s-r-lffi-AiRg--------

Reactor water level reaches LL4 and continues to lower Based on these conditions, which ONE of the following actions is required?

A. Continue LEP-01 demin water injection per 1EOP-01-RVCP, Step RC/L-30 until other injection systems become available. '

B'. Emergency Depressurize and then align the SLC system to inject only boron per 1EOP-01-RVCP.

C. Secure the SLC pumps then Emergency Depressurize per EOP-01-STCP, per RC/L-36.

1.

D. Secure LEP-01 and initiate SLC per 1OP-05 then Emergency Depressurizing Step RC/L-36.

1 Proposed B. Emergency Depressurize and then align the SLC system to inject only Answer: boron per 1EOP-01-RVCP.

Per 1EOP-01-RVCP with one injection system available you go straight to ED per step RC/L-29, then perform alternate source term actions

a. is incorrect because no other injection systems are needed with CS available
c. is incorrect because ED is required first and not per steam cooling.
d. is incorrect because there is no need to shift from LEP-01 because LEP-01 provides for injecting from the SLC tank and ED is required prior to SLC.

Technical Reference(s): Ooi-37.4, 1EOP-01-RVCP, OEOP (Attach if not previously NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet LEP-01 provided)

Proposed references to-be provided to applicants during examination: 1EOP-01-RVCP Learning Objective: _L_O_I_-C_L_S_-L_P_-_30_0_-D_*_O_3_E (As available)

Question Source: Bank# LOI-CLS-LP-300-D*03E Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5

  • Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # 295028 EA2.01 SRO #80 Importance Rating 4.1 (K&A Statement) Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell temperature.

Proposed Question: Following a small break LOCA on Unit Two (2) the following conditions exist:

Drywell temperature 270°F

- - - - -----Qr-y-we~-I_pressufe SJJ-Psig!'-t------ _

Suppr Chamber pressure 2-.5 psig Suppr Pool level +5 inches -

Containment H2 Monitors CAC-AT-4409 & 4410 are not available at this time. Chemistry has been called but has not sampled the drywell.

RHR Pump "A" is operating in suppression chamber spray in accordance with OEOP-01-SEP-03.. ;

Which ONE of the following describes the required actions?

A. Initiate a-drywell purge per primary containment purging OEOP-01-SEP-05.

B. Defeat drywell coolers LOCA logic using OEOP-01-SEP-10 and restart the drywell coolers.

C. Remain in suppression chamber spray in accordance with OEOP-01-SEP-03 and wait for H2 analysis. I D. SeGure.suppression chamber sprays an~place RHR Pump "A" in Drywell Spray in accordance with OEOP-01-SEP-02.

C.

Proposed Answer:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

  • Explanation: Drywell spray in this condition is in the UNSAFE region of the Drywell Spray Initiation Curve so the drywell cannot be sprayed. The drywell cannot be purged because there is no indication of H 2 at this time. T.he drywell coolers cannot be. restarted with drywell LOCA
  • conditions. The drywell is still below it's design temperatures, the high temperatures and

. pressure'appear to be a *gas which is not condensing. This condition can remain until the monitors are working or chemistry can take a sample.

a. is incorrect because drywell cannot be purged because there is no indication of H2 at this time.
b. is incorrect becausedrywell coolers can only be used if LOCA conditio'ns do NOT exist in the drywell, drywell pressure is above 1.7 psig.
d. is incorrect because drywell spray in this condition is in the UNSAFE region of the Drywell Spray Initiation Curve so the drywell cannot be sprayed.

Technical Reference(s): OEOP-02-PCCP & OEOP (Attach if not previously provided)

SEP-=-10--:n-STL-Curve Proposed references to be provided to applicants during examination: OEOP-02-PCCP

  • Learning Objective: CLS-LP-300-L, 20. Given plant conditions, determine if any of the following Primary Containment Limits are being exceeded:
g. Drywell Spray Initiation Limit (As available)

Question Source: Bank #

Modified (Note changes Bank # or attach parent).

New x Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis -X- - -

10 CFR Part 55 Content: 55.41 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #81 Tier # 1 Group # 1 KIA # 295030 EA2.02 Importance Rating 3.9 (K&A Statement) Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Suppression pool temperature.

Proposed Question: On Unit Two (2) following a LOCA coincident with a failure to scram all control rods have been manually inserted and the following conditions exist:

_ _ _ _ _ _R_e_a---.:c_tor wa!er lev~l_ 55 inches (N036/N037) and rising Supp. Chamber Press 6.5 psig -

Core Spray One Loop injecting at 4500 gpm RHR One loop injecting at 7000 gpm Supp pool level - 5.5 feet Supp pool temp 1960 F As sca which one of the following a~tions should be directed?

A. Shutdown both the cere spray and RHR pump(s) to comply with the Vortex Limifs.

B. Lower core spray to 3200 gpm and lower RHR flow to 4,000 gpm to cOffiply*~w-jt-l+.tl:le NPSH limits.

C. Raise core spray to 5200 gpm and shutdown the RHR pump(s) to complywi-th1'he NPSH and Vortex Limits.

D. Raise core spray flow to 5200 gpm and raise RHR flow to 11,000 gpm as- allo'ed by tRe NPSH and Vortex Limits..

C. Raise core spray to 5200 gpm and shutdown the RHR pump(s) to comply with Proposed the NPSH and Vortex Limits.

Answer:

C. is correct because the NPSH curve must be lowered below to the 5 psig curve because suppression pool level is below -31 inches. For each foot below -31 inches the pressure must be lowered 0.5 psig. 5 and one half foot is 3 feet below -31 inches therefore the NPSH curve is 5 psig.This results in 5200 gpm for core spray. However a suppression pool level of 5.5 feet is below the RHR vortex limit of 5.25 feet. Since water level is above TAF/-aflG. RPV level is rising) the SCO should direct securing the RHR pump(s) .

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

  • a.

b.

is incorrect because core spray can continue to inject to maintain or restore RPV level.

is incorrect because core spray flow should be reduced a little further to 2,800 gpm and RHR should be secured.

c. Correct
d. is incorrect because the NPSH curve must be lowered below the 5 psig curve D.ecause suppression pool level is below -31 inches and these flows are based on the 5 psig curve.

And RHR should be secured.

Technical Reference(s): OEOP-02-PCCP, 001-37.8, and (Attach if not previously provided)

CLS-LP-300-B.

Proposed references to be provided to applicants during examination: EOPs - Vortex and NPSH Limits Learning Objective: (As available)

Question Source: Bank#

Modified (Note changes Bank # or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 Comments:

  • NUREG-1 021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #82 Tier # 1 Group # 1 KIA # 295038 2.1.23

~Importance Rating 4.0 (K&A Statement) Ability to perform specific system and integrated plant procedures during different modes of plant operation. (High Off-site Release Rate)

Proposed Question: Following fuel failure, a main steam line leak in the Turbine Building results in an off-site release in excess of the Alert classification per Table 1 of EOP-04-RRCP

-- ,.__~lhen should the MSIVs NOT be closed? "

WMen the crew has:

A. entered OEOP-01-RXFP, Reactor Flooding Procedure.

B. e,Atered EOP-01-LPC and the main turbine is operating.

  • C.

D.

inf*tiate Alternate Emergency Depressuri~ation in accordance with EOP-01-RVCP.

  • i'fl1*ttated steps for the Anticipation of Emergency Depressurization in accordance wjth EOP-01-RVCP. .

C. initiated Alternate Emergency Depressurization in accordance with EOP Proposed RVCP.

.Answer:

RRCP directs bypassing the step to isolate primary systems discharging if required for EOP actions. AEDP directs bypassing all group 1 isolations and depressurizing the RPV irrespective of steam line break or fuel failure.

a. is incorrect because reactor flooding directs closure of MSIVs.
b. is incorrect because LPC does not authorize opening of MSIVs if steam break or fuel failure.

d: is incorrect because anticipating ED can only.' be performed if no steam leak or fuel failure.

Technical Reference(s): OEOP-04-RRCP (Attach if not previously provided)

  • Proposed references to be provided to applicants during examination: _N_O_N_E NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

'Learning Objective: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (As available)

Question Source: Bank# LOI EOPbank LOI-CLS-LP-300-N*003 001 Modified (Note changes Bank # or attach parent)

New Question History: Last NRC Exam N/A

. _. ._. 9ue_~tion Cog!!~~~~e Level: Memory or Fundamental Knowledge Comprehension or Analysis ----x--------.-.

10 CFR Part 55 Content: 55.41 55.43 5 Comments: .

ES-401 Sample Written Examination Form ES-401-5

, Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #83 Tier # 1 Group # 2 KIA # 295008 AA2.02 Importance Rating 3.4 (K&A Statement) Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL: Steam flow/feedflow mismatch.

Proposed Question: Unit Two (2) is operating at.70% power with both RFPT Speed Controllers in Auto, and 3-Element control selected.

A mistake on instrument rack lineup partially isolates Main Stea"m flow transmitter C32-PDT-N003A, 'changing its indicated flow to 0 0/0.

Annunciator, FW CTL SYS TRBL (A-07, 4-2) has alarmed The RO has verified Feedwater control has shifted to Single Element Control

  • A.

Which one of the following directions is required at this time?

Per 2APP-A-07, PLACE the FEEDWATER CONTROL MODE SELECT switch in 1 ELEM and OBSERVE automatic functions.

S". Per 2APP-A-07, verify proper Feedwater Control System operat,ion, THEN PRESS the ACK button the workstation (local) keyboard and reset the annunciator.

C. Enter OAOP-23, Condensate/Feedwater System Failure and verify proper Feedwater Control System operation until the steam flow transmitter can be returned to service. '

D. Enter OAOP-23, Condensate/Feedwater System Failure and MANUALLY CONTROL reactor feed pumps to restore normal until the steam flow transmitter can be returned to service.

C. -Enter OAOP-23, Condensate/Feedwater System Failure and verify proper Proposed Feedwater Control System operation until the steam flow transmitter can be Answer: returned to service.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Feed flow permissive is >20%, no steam/feed flow mismatch inputto 3 element permissive,-

individual steam flows must be within 10°A> of average so a steam flow transmitter failing will remove the 3 element permissive causing an AUTOMTIC swap to Single Element Control. The

,Feed Flow/Steam Flow mismatch is an entry condition into OAOP-23, Condensate/Feedwater System Failure. Because the feedwater control system will remain in AUTO it will continue to maintain reactor water level. The operators must monitor the system to determine IF any further actions will be required; however with the conditions stated in the stem no further action is required until the steam flow instrument is restored.

a. Is incorrect because APP-A-07 does not direct placing the FEEDWATER CONTROL MODE SELECT switch in 1 ELEM. This step is in AOP-23, however the step'is only taken to prevent level overshoot.
b. is incorrect because this action is only taken for a module failure'. In this case all modules are operating anda transmitter has failed.
d. is incorrect because there is no requirement or need under these circumstances to operate the feedwater control system in MANUAL. '

Technical Reference(s): 2APP-A-07, OAOP-23, SD-32.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: _N_/A _

Learning Objective: CLS-LP-300 I, 2. Given plant conditions with a (As available)

Condensate System failure in progress, determine if the appropriate automatic actions have occurred in accordance with the following Question Source: Bank#

Modified (Note changes or Bank # attach parent)

New x Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis _X _

10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-S Question Worksheet

  • Examination Outline Cross-reference:

SRO #84 Level Tier #

Group #

RO 2

SRO 1

KIA # 29S029 2.1.32 Importance Rating 3.8 (K&A Statement) Conduct of Operations: Ability to explain and apply all system limits and precautions. (High Suppression Pool Water Level).

Proposed Question: During ATWS conditions, Terminating and Preventing has been completed and HPCI injection has been restored. HPCI is injecting to the RPV to maintain RPV level. HPCI suction has automatically transferred to the suppression pool due to high suppression-'pool

.-----leueLS-up-p.ressioll-P_o_oJ_temp_e[aiure is 1-=----,3=-.=S,,--o-=--F+-==.;an~d~ri.=..:si:..:...:.n~g_-=--._'

7 _

Which ONE of the following actions are required to maintain continued HPCI system operation?

A. In accordance with EOP-01-LPC, lower HPCI flow to less than 2000 gpm if suppression, pool temperature approaches 140°F.

It B. In accordance with EOP-01-LPC, lower HPCI flow to less than 2000 gpm if suppression pool temperature approaches 170°F.

C. Enter EOP-01-SEP-10 and defeat the automatic suction transfer logic and transfer HPCI suction to the CST if suppression pool temperature approaches 140°F.

D. Enter EOP-01-SEP-10 and defeat the automatic suction transfer logic and transfer HPCI suction to the CST if. suppression pool temperature approaches 170°F.

Proposed c. Enter EOP-01-SEP-1 0 and defeat the automatic suction transfer logic and Answer: transfer HPCI suction to the CST if suppression pool temperature approaches 140°F.

Explanation:

The lube oil and control oil for both HPCI and RCIC are cooled by the water being pumped.

Very high lube oil temperatures can result in loss of lubricating qualities in the oil and thus cause damage to the bearings.

Suction for HPCI and RCIC is aligned to the Condensate Storage Tank (CST) if it is available.

The HPCI automatic suction transfer logic can be defeated to allow this lineup if necessary provided suppression pool temperature is approaching 140°F.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

a. is incorrect because HPCI NPSH is not the concern.
b. is incorrect because HPCI NPSH is not the concern and HPCI suction is shifted back to the CST if temperature approaches 140°F.
d. is incorrect because HPCI suction is shifted back to the CST is temperature approaches 140°F.

Technical Reference(s): 001-37.5, 1EOP-01-LPC (Attach if not previously provided)

Proposed references to be provided to applicants during examination: _'_N_/A _

Learning Objective: CLS-LP-300E, 19. Given plant conditions and the (As available)

Level/Power Control Procedure, determine the required operator actions.

Question Source: Bank# LOI-SYSTEMS Bank S206000 A2.08 Modified (Note changes or Bank # attach parent)

  • Question History:

New Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge _X _

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #85 Tier # 1 Group # 2 KJA# 295032 EA2.02 Importance Rating 3.5 (K&A Statement) AbiHty to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Equipment operability.

Proposed Question: Following an unisolable RCIC steam supply line in the South RHR Room the following conditi'ons exist:

- - - ....-----.~JluthRHR Eguig- room

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

280 mr _ -.-

South RHR Equip room 355°F . ' ----

RCIC Equip Room 298°F North RHR Equip room 212. mr North RHR Equip room 280 Q F Which ONE of the following describes the operability of equipment in Secondary Containment required for safe shutdown, and what action is required.

In accordance with OEOP-03-SCCP, Secondary Containment Control Procedure:

A. Table 1; RHR Loop B ONLY will fail, enter EOP-01-RVCP and perform emergency depressurization in accordance with step RC/P-11.

B. Tables 1 and 3; RHR Loops A and B will fail, enter EOP-01-RVCP perform emergency depressurization in accordance with step RC/P-11.

C. Table 1; RHR Loop B only will fail, enter EOP-01-RVCP and consider anticipation of emergency depressurization in accordance with step RC/P-05.

D. Table 1 and 3; RHR Loops A and B will fail, enter EOP-01-RVCP and consider anticipation of emergency depressurization in accordance with step RC/P-05.

Proposed C. Table 1; RHR Loop B only will fail, enter EOP-01-RVCP and consider Answer: anticipation of emergency depressurization in accordance with step RC/P-05.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation:

South RHR Equip Room is above max safe (295°F) as show in Table 1, although only the temperature in that room is above max safe (RCIC Equipment Room is also above 295°F but it is in the same area. Max safe etteHs based on equipment operability. The southeastern corner room contains RHR Loop B (Pumps B and D). One area above max safe requires cooldown not to exceed 100°F/hour and considering anticipation of ED (can be done since all rods are in).

Two areas above max safe require emergency depressurization.

a. is incorrect because emergency depressurization is not required and should not be performed until required, alternate emergency depressurization is available and may be performed at this time.
b. is incorrect because RHR Loop A is still available at this time and emergency depressurization is not required and should not be performed until required, alternate emergency depressurization is available and may be performed at this time.
c. is incorrect because

--~-.~~~~~be~~a~R~~~j~~wila~b~le~a~t~t~h~is~t~im~e~. _

Technical'.Reference(s): 001-37.9, OEOP-03-SCCP (Attach if not previously provided)

Proposed references to be provided to applicants during examination: OEOP-03-SCCP, EOP-01-RVCp/

Learning Objective: OI-CLS-LP-300-M*04C 5 (As available)

Question Source: Bank# LOI-SYSTEMS Bank S295036 A2.01 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis -X- - -

10 CFR Part 55 Content: 55.41 55.43 X Comments:

NUREG-1021, R*evision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #86 Tier # 2 Group # 1 KIA # 2030002.1.23 Importance Rating 4.0 (K&A Statement) Ability to perform specific system and integrated plant procedures .during different modes of plant operation. (RHR/LPCI)

Proposed Question: RHR Loop A is operating in suppression pool cooling mode per OP-17 with one RHR Pump (Pump A). A large line break results in a LPCI initiation signal.

~ ' "'~_'" RHR Loop A LPCllogic fails to initiate due to a blown control logic

-.---.------------..- - fuse~RR-RLoop BLPCnog IC has Inlliatea:--Tne-~-P\1~s---. --**-------------

depressurized and RPV level is below TAF.

Assuming. RHR Loop A responds with no additional failures, what must be directed to achieve design LPCI injection?

A. Manually isolate the suppression pool cooling path and open the heat exchanger bypa~s valve. RHR Pump C will automatically start and the injection valve (F015A) will automatically open.

B. RHR Loop A must be manually placed in LPCI mode in accordance with OP-17. The suppression pool cooling path will automatically isolate and the heat exchanger bypass valve will automatically open.

C. Manually isolate the suppression pool cooling path. The heat exchanger bypass valve will automatically open. RHR Pump C will automatically start and the injection valve (F015A) will automatically open.

D. RHR Loop A must be manually placed in LPCI mode in accordance with OP-17.

Manually isolate the suppression pool cooling path and open the heat exchanger bypass valve. All automatic actions will fail to occur.

Proposed a. Manually isolate the suppression pool cooling path and open the heat Answer: exchanger bypass valve. RHR Pump C will automaticaUy start and the injection valve (F015A) will automatically open.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation:

Only those actions necessary for a LPCI loop to inject from a standby alignment during a LOCA will occur from either loops initiation logic (pump start, injection valve opens, recirc discharge/discharge bypass valves close). Since SPC is not standby mode, the SPC valves will not close based on the_B side logic failure. This will divert RHR flow to the Suppression Pool.

T~ establish full RHR LPCI fl.ow the Suppression Pool Cooling one valve must be manually closed and the bypass around the heat exchanger opened.

b. is incorrect because RHR does NOT require a manual initiation, Pump A is already operating but its flow is being diverted to the Suppression Pool. The suppression pool cooling path will NOT automatically isolate.
c. is incorrect because the heat exchanger bypass valve will NO*T automatically open.
d. is incorrect because RHR does NOT require a manual initiation, Pump A is already operating but its flow is being diverted to the Suppression Pool. All automatic actions except the isolation of Suppression Pool cooling will occur Technical Reference(s): OP-17, SO-17 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

-N/A Learning Objective: (As available)

Question Source: Bank# LOI Systems LOI-CLS-LP-017-A*18N Modified (Note changes or Bank # attach parent)

New Questien History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or 'Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO ---SRO SRO #87 Tier # 2 Group # 1 KIA # 212000 A2-.02 Importance Rating 3.9 (K&A Statement) Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based -on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RPS bus power supply failure Proposed Question: Unit Two (2) is at 100°A> power, Bus E7 must be removed *from service for required maintenance Assuming LCO conditions for _Bum-outage are met, w~Ol\IEOf the following actions~will be required if it becomes necessary to supply power to RP$ A?

A. RPS bus A must be de-energized and cannot be- supplied from the alternate power source. Anticipate a shutdown in accordance with T.S. 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.

B. Shift the RPS bus alternate power supply sources using 20P-03 while still supplying RPS Bus "A" from alternate power. None of the trips and isolations on TABLE 1 of 20P-03 will occur.

C. Swap the normal feed to the alternate supply in accordance with 20P-03, then re-establish the alternate supply for RPS A with 20P-03. All the trips and isolations on TABLE 1 of 20P-03 will occur.

D. Swap the normal feed to the alternate supply in accordance with 20P-03, then re-establish the alternate supply for RPS A with 20P-03. The trips and isolations on TABLE 1 of 20P-03 will not occur.

Proposed C. Shutdown the normal feed to the alternate supply in accordance with 20P-Answer: 03, then re-establish the alternate supply with 20P-03. All the trips and isolations on TABLE 1 of 20P-03 will occur.

Explanation:

However 20P-03 cautions that the RPS bus cannot be supplied from the alternate-supply while the AC sources are shifted. Therefore the alternate supply must be secured then the AC sources shifted and the RPS alternate source realigned. It is a dead bus transfer.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

a. Incorrect - because the alternate'AC supply is available to the RPS alternate supply.
b. Incorrect - 20P-03 cautions that the RPS bus cannot be supplied from'the alternate

,supply while the AC sources are shifted. Additionally, RPS trips will occur.

c. Correct
d. Incorrect - All isolations will occur (break before make)

Technical Reference(s): 20P-03 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: _ _ _ _ _ _ _ _ _ _ _ _---'-- (As available)

Question Source: Bank#

Modified (Note changes or Bank # attach parent)

New x Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis _X _

10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #88 Tier # 2 Group # 1 KIA # 215003 A2.01 Importance Rating 3.2 (K&A Statement) Ability to (a) predict the impacts of the following on the INTERMEDIATE

, RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Power supply degraded.

Proposed Question: Unit One (1) is in Mode 2 withdrawing control rods during a startup.

AlllRMs are operable and on Range 1.

IRMs"C" and u-P'areQownscale.

All other IRMs are'responding as expected.

SRM "0" is rising and has reached 5 x 105 cps.

You are the SCO, which ONE of the following actions is required?

a. In accordance with GP-02 notify the reactor engineer and addre'ss T.S. 3.3.1.1.
b. Bypass SRM "0" and continue the startup observing IRMs "c" and "F" for proper response.
c. Halt the startup and perform 10P-09, Section 8.6 SRM/IRM Response Check on IRMs "c" and "F".
d. Bypass SRM "0" continue the startup and perform 10P-09, Section 8.6SRM/IRM Response Check on IRMs "c" and "F".

Proposed a. In accordance with GP-02 notify the reactor engineer and address T.S.

Answer: 3.3.1.1.

Explanation:

Per GP-02, SRM/IRM overlap must be demonstrated prior to withdrawing SRMs from the fully inserted position. SRM/IRM overlap exists when at least three-IRM channels in each RPS trip system show an increase to at least twice their pre-startup levels AND indicate at least tOeA> of scale (Le., 12.5 on the digital readout 0-125 scale) before the first SRM channel reaches 5 x 105 cps. (TS SR 3.3.1.1.6)

IF correct SRM/IRM overlap is NOT verified, THEN the Reactor Engineer shall be notified AND Technical Specification LCO 3.3.1.1 referenced.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

b. Is incorrect because the startup may NOT continue.
c. Is incorrect because the Section 8.6 SRM/IRM Response Check is only performed at with reactor power at maximum achievable power.
d. Is incorrect because the startup may NOT continue and Section 8.6 SRM/IRM Response Check is only performed at with reactor power at maximum achievable power.

Technical Reference(s): GP-02, 20P-09 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: _N_/A _

Learning Objective: (As available)

Question Sourc"e: B-ank-#---------------------

Modified (Note changes or Bank # attach parent)

New x Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis -X- - -

10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #89 Tier # 2 Group # 1 KIA # 215004 2.4.11 Importance Rating 3.6 (K&A Statement) Knowledge of abnormal condition procedures. (SRMs) _

Proposed Question: A core reload sequence is in progress in accordance with OFH-11, Refueling. The initial loading of fuel bundles around each SRM centered 4-bundle cell was completed with all four SRMs fully inserted and reading 50 cps.. '

Refuel o.perations are in progress. During loading of fuel bundles, me following SRM read-ings are logged:

Bundles Loaded SRM Counts 520 A - 140 B - 190 C - 175 D- 180 521 A- *.-t-8-0---- --B - 225-"-----C -250- D- 195 522 A - 200 B - 250 C - 275 D- 200 523 A - 190 B - 260 C - 280 D- 250 Which one of the following actions is required?

A.

No actions are required fuel bundle loading may continue.

B. Fuel bundle loading should have been suspended at step 521'*and the 'ReactOr Ellgirleer C. Fuel bundle loading should have been suspended at step 522 and,the-,ReactorErrgineer D. Fuel bundle loading should have been suspended at step 523 and tRe~'~E~Aeer eoft~

Proposed b. Fuel bundle loading should be suspended at step 521 and the Reactor Answer: Engineer contacted.

Explanation: FH-11 requires suspending fuel movement if an SRM increase by.f~ctor of 3 relative to initial base-line SRM reading or doubles with any single bundle. FH-11, Precaution &

Limitation 4.29.2.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

a. Incorrect because Fuel bundle loading should be suspended at step 521 and the Reactor Engineer contacted on step 521 when SRM C reached .~ times the baseline count rate.
b. Incorrect because Fuelbundle loading should be suspended at step 521 and the Reactor Engineer contacted on step 521 when SRM C reached 3 times the baseline count rate.
c. Incorrect because Fuel bundle loading should be suspended at step 521 and the Reactor Engineer contacted on step 521 when SRM C reached 3 times the baseline count rate.

Technical Reference(s): FH-11 (Attach if not previously provided)

Learning Objective: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (As available)

Question Source: Bank# LOI Systems GEN 2.2.26 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory 'or Fundamental Knowledge Comprehension or Analysis -X- - -

10 CFR Part 55 Content: 55.41 55.43 6 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #90 Tier # 2 Group # 1 KIA # 300000 2.4.6 Importance Rating 4.0 (K&A Statement)--.k~u:rent EOPs symptom based (Instrument Air)

Proposed Question: An ATWS has occurred on Unit Two (2) it has been determined that -

although the HCU Scram Valves are de-energized the air is NOT being ported from the scram valves.

Which one of the following should be directed to attempt to insert the control rods?

In accordance with OEOP-01-LEP-02, Alternate Control Rod Insertion" per _

A. .Section 7.e-. Vent the over piston area by closing the Withdrawal-Riser Isolation Valve; isolating the air to the Scram Outlet Valves and opening the Scram Discharge line to the Scram Discharge Volume Isolation Valve.

B. Section 7.a. Vent the Scram Air Header by isolating the Backup Scram Valves Isolation Valve, then remove the pipe cap on the pressure switch test connection, then open the pressure switch instrument drain valve.

C. Section 7.e. Vent the over piston area by closing the Withdrawal-Riser Isolation Valve, -

failing the air to the Scram Pilot Solenoid Valves and opening the Scram Discharge-line to the Scram Discharge Volume Isolation Valve.

D. Section 7.a. Vent the Scram Air Header by isolating the Backup Scram Valves Isolation Valve, then remove-the pipe cap on the air supply to the Scram Discharge Volume vent and drain valves, and then open the instrument air drain valve.

Proposed b. Section 7.a. Vent the Scram Air Header by isolating the Backup Scram Valves Answer: Isolation Valve, then remove the screw pipe cap on the pressure switch test connection, then open the pressure switch instrument drain valve.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation:

In accordance with OEOP-01-LEP-02 the majority of alternate control rod insertion methods involve opening the scram valves, since they have already been opened with no success and air has NOT been bled off the scram valves manually venting the scram air header is warranted.

The methods listed above are incorrect methods of venting only removing the screw pipe cap on the pressure switch test conn~en opening the pressure switch instrument drain valve is .

the correct method of venting the scram air header.

a. Is incorrect because Section 7.e. Venting the over piston area involves hydraulically venting the rod drive over piston area. NOT venting the withdraw header.
c. Is incorrect because Section 7.e. Venting the over piston area involves hydraulically venting the rod drive over piston area. NOT failing the air to the Scram Pilot Solenoid Valves.
d. Is incorrect because the air' header is vented at pressure switch test connection, NOT

______ -------tbe-air_s_u-P-PJy to the Scram Discharge Volume vent and drain valves.

Technical Reference(s): OEOP-01-LEP-02 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: -NONE ---------

Learning Objective: (As available)

Question Source: Bank#

Modified (Note changes or Bank # attach parent)

New x Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis -X- - -

10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level*** RO SRO Tier # 2 Group # 2 KIA # 206000 2.4.7 Importance Rating 3.8 Knowledge of event based E.OP mitigation strategies Proposed Question: SRO 91 During an ATWS on Unit Two (2), RPVlevel has been lowered. E4 is de-energized due to an electrical fault,and the 2A-CRDpump is under cle~rance*.

Plant conditions are:

- -_ _.._~. _~~te[Je"_=v_=_e.:__1 ~T~A~F~-------------------------

Reactor power 6%

Reactor pressure 550 psig Suppr pool temp 125°F Suppr pool level Hi-Hi in alarm Reactor Bldg Ventilation Isolated HPCI Area Temperature 150 Degrees F.

RCIC Area Temperature 170 Degrees.F.

To maintain RPV level above LL4.

Which ONE of the following actions is required.

A. InJect'with RCIC per SEP-10, defeat of isolations is not required.

B. Inject with HPCI per Table 1 of EOP-01-LPC, defeat of isolations is not required.

C. *Maximize CRD flow *per SEP-09: .

D. Place the "A" loop of RHR in service per Table 1 of EOP-01-LPC.

Proposed Answer: B Explanation (Optional):

A. . Incorrect - RCIC is isolated on high temperature (>165degrees F.)

B. Correct Response C. Incorrect - "B" CRD pump has no power on E4 loss, "A" is under clearance.

D. Incorrect - Rx pressure is higher than the shutoff head of RHR (237 psig) (SD-17)

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): EOP-01-LPC (Attach- if not previously-provided)

Proposed references to be provided to applicants during examination: EOP-01-LPC Learning Objective: _ _ _ _ _ _ _ _ _ _ _ _ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X

Q-uesti-on-l:ijst.o.ry:-------Las-L~ RC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 .Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 KIA # 290001 A2.03 Importance Rating 3.6.

Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High area radiation Proposed Question: SRO 92 RWCU is discharging into Secondary Containment and has resulted in one area exceeding the Maximum Safe Operating Radiation Level.

After the radiation level in this area is reduced below the Maximum Safe value a second

a.r:ea-e.x.ce-e-ds-its~-a.}(imum Safe ORerating. Radiation Level.

What acti.on is required by the EOPs?

A. Shutdown the reactor per GP-05.

B. Scram the reactor and cooldown <1 OO°F/Hr.

C. Scram the reactor and cooldown ~100°F/Hr.

D. Scram the reactor and open seven ADS valves.

Proposed Answer: B Explanation (Optional): Since max safe rad based on personnel access (not equipment if EQ not exceeded), if area goes below max safe and 2nd area subsequently exceeds max safe, action for 1 area is taken per definition in EOP-UG attachment 5~ With .primary system discharge, this would be scram and cooldown at normal rate per SCCP Technical Reference(s): EOP-UG attachment 5 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: -NONE -.-;.---------

Learning Objective: (As available)

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# CLS-LP-300-M*04C-#2 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 KJA# 226001 2.1.9 Importance Rating 4.0 Conduct of Operations: Ability to apply tech specs for a system Proposed Question: SRO 93 Unit 1 is at 100% power. The plant is operating with one required ADS valve inoperable and the 1B RHR pump is out of service for emergent maintenance. An unexpected trip of the breaker for the 1C RHR pump has just occurred. The field operator and electrician you sent to investigate determine that a mechanical problem exists within the breaker that will require several hours to' repair.

In accordance with Technical Specifications _

A. 'Entry into TS 3.0.3 is immediately required.

B. Restore the ADS valve or one RHR pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

C. Restore the ADS valve or one RHR pump to operable status within 7 days.

C. Restore the ADS valve or both RHR pumps to operable status within 7 days.

Proposed Answer: A Explanation (Optional):

Outside the bounds of TS 3.5 therefore enter TS 3.0.3 B. Incorrect- only true if one ECCS subsystem is inop.

C. Incorrect - 7 days is only for 1 RHR pump inop D. Incorrect - condition not addressed in TS 3.5.2 Technical Reference(s): TS 3.5.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: (As available)

NUREG-1021, Revision 9

ES~401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge _X _

Comprehension or Analysis 10 CFR Part 55 Content 55.41 55.43 2 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross:-reference: Level RO SRO I

SRO #94 Tier # 3 Group # 1 KIA # 2.1.12 Importance Rating 4.0 (K&A Statement) Ability to apply technical specifications for a system.

Proposed Question: Unit Two (2) is operating at rated power with SBGT Fan 28 under clearance and in a 7 day action statement per LCO 3.6.4.3 Condition A.

___________' ,~__~ ., 4_8_0_V_A_C-'-----,_S_u_b_st_a_ti_on_E_7_tr---..!ip_s_o_n_f_a_u_lt_. . ~_,_ . _.., ._

What Cl.dditional Condition(s) are re,quired to be entered by Technical Specifications?

A. LCO 3.8.7 Condition B ONLY.

B. LCO 3.8.7 Condition B, and LCO 3.6.4.1 Condition A, ONLY.

C. LCO 3'.8.7 Condition B, and LGO 3.6.4.3 Condition B ONLY.

D. LCO 3.8.7 Condition B, and LCQ3.6~4.3 Condition B, and LCO 3.6.4.1 Condition A.

Proposed d. LCO 3.8.7 Condition B, and LCO 3.6.4.3 Condition B, and LCO 3.6.4.1 Answer: Condition A.

Explanation: 80th Standby Gas Trains are Inoperable. Per LCO 3.0.6, the required actions for the Inoperable SBGTs must be entered if a loss of safety function occurs. Per the Safety Function Determination Program loss of safety function exists for both SBGT (LCO 3.6.4.3)"and Secondary Containment (LCO 3.6.4.1)

a. is incorrect because the loss of E-7 inops SBGT A which requires entry into 3.6.4.3.

Condition 8 and 3.6.4.1 Condition A.

b. is incorrect because the loss of E-7 inops SBGT A which requires entry into 3.6.4.3.

Condition B.

c. is incorrect because the loss of E-7 inops SBGT A which requires entry into 3.6.4.3.

Condition A.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form E$-401-5 Question Worksheet Technical Reference(s): .Unit 2 TS LCO 3.0.6, 3.6.4.1 (Attach if not previously provided)

Proposed references to be provided to applicants TS 3.6 during examination:

Learning Objective: _C_L_S_-_L_P-_2_00_-_B_*0_0_9_0_0_5 (As available)

Question Source: Bank# LOI SYSTEMS LOI-CLS-LP-200-B*009 005 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis -X --

10 CFR Part 55 Content: 55.41 55.43 2 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO NRC# 95 Tier # 3 Group # 1 KIA # 2.1.25 Importance Rating 3.1 (K&A Statement) Ability to ab1ain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

Proposed Question: Unit Two (2) is operating at 96% power when Recirculation Pump 2A trips resulting in the following conditions:

Total Core Flow (P603) > 28.3 Mlbm/hr.

Total Core Flow (U2CPWTCF) NOT AVAILABLE

~-~~~~~~lr~~~~-~re-~ate~~Be4~~~~3.~~id~~~~.~~~-~~~_

APRMs 50%

Indications of THJ None OPRM System INOPERABLE Determine the region of the Power/Flow Map Map where the plant is operating AND determine- the required operator action.

A. In accordance with 2AOP-04.0 insert a manual scram.

B. Exit the region by inserting control rods or' raise core flow in accordance with OENP-24.0.

C. In accordance with 2AOE~:04.0 enter 20P-02 land re-start the 2A Recirculation Pump then raise core flow.

D. Increase monitoring nuclear instrumentation for THI.

Proposed b. Lower reactor power by inserting control rods in accordance with 2AOP-04.0 Answer: and raise core flow.

Explanation:

In accordance with 2AOP-04.0 following the trip of a Recirculation Pump if a valid total core flow is NOT available from U2CPWTCF OR U2NSSWDP, THEN DETERMINE total core flow using . which is the Estimated Total Core Flow using the Core Support Plate dIp. Since U2CPWTCF is NOT available the dIp must be used. This will provide a higher core flow t{1an the P603 indication. Examining the Figure 14 from the COLR or OENP-24.0 the SCO should determine the unit is at -35 Mlb/hr flow and 50% power which place it just inside the right hand portion of Region B. Exit from this region is accomplished by insertrng control rods in accordance with OENP-24.0 or raising core flow.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

a. is incorrect because a manual scram is.not required.
b. correct
c. is incorrect because a recirculation pump cannot be started while operating in Region B.
d. is incorrect because this is action when in the 5°k buffer region Technical Reference(s): 2AOP-04.0, 20P-02 (Attach if not previously provided)

Proposed references to be provided to Figure 13 thru 18 from the COLR or OENP-24.0 and applicants during examination: Attachment 1, Estimated Total Core Flow uSing the Core Support Plate dIp from 2AOP-03.~.

Learning Objective: CLS-LP-302-C, 004 (As available)

Question Source: Bank#

Modified (Note changes or Bank # attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 1 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO NRC # 96 Tier # 3 Group # 2 KIA # 2.2.7 Importance Rating 3.2 (K&A Statement) Knowledge of the process for conducting tests or experiments not described in the safety analysis report.

Proposed Question: Unit Two Reactor WaJer Level trip units 821-LTM-N024A-1-1 (Low Level 2) and B21-LTS-N024A-1-2 (Low Level 3) are being placed in an inoperable status to perform SR 3.3.6.1.2 and SR 3.3.6.1.3. All

___ ot_her instrumentation is Operable.

Which ONE of the.following is correct per Technical Specification 3.3.6?

A. Entry into LCO 3.3.6.1, Condition A may be delayed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform the surveillance testing.

B. Entry into LCO 3.3.6.1, Condition A may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform the surveillance testing.

C. LCO 3.3.6.1, Condition A must be entered immediately, the channels must be placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. LCO 3.3.6.1, Condition A must be entered immediately, the channels must be placed in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Proposed b. Entry into LCO 3.3.6.1, Condition A may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Answer: perform the surveillance testing.

Explanation:

Per the note under surveillance requirements for LCO 3.3.6.1, entry into the associated conditions and required actions may be delayed for either up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> depending on the function. LL2 and LL3 are functions 5g and 1a, the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> applies (provided trip capability is maintained). LCO 3.3.6.1 Condition A ~ require the channel be placed in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (versus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) since the instrumentation is not shared with RPS.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

a. is incorrect because these functions do not appear under the two hour requirement in the NOTES section of T.S. 3.3.6.1 .

.c. is incorrect because six hours are allowed by the NOTES section of T.S. 3.3.6.1.

d. is incorrect because six hours are allowed by the NOTES section of T.S. 3.3.6.1.

Technical Reference(s): T.S. 3.3.6.1 and TS Instrument (Attach if not previously provided)

List for Table 3.3.6.1-1 Proposed references to be provided TS sections 3.3.6 to applicants during examination:

Learning Objective: (As available)

Question Source: Bank # - BOBANK S212000 A2.03 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #97 Tier # 3 Group # 2 KIA # 2.2.25 Importance Rating 3.7 (K&A Statement) Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. '

Proposed Question: Unit Two has just been placed in Mode 4 to comply with LCO 3.5'.1 Condition J and LCO 3.0.3 due to both Core Spray Loops, and one LPCI Pump being Inoperable. Current ECCS System status: .

Gel"e-Spr-ay-J2u.mp-.2A-isunder-C1earance_" _

Core Spray Pump 28 is under clearance RHR Loop 2A'is in standby, except for RHR Pump 2A which is under clearance RHR Loop 28 is operating in Shutdown Cooling Which ONE of the following describes whether LCO 3.5.2, ECC*S.-

Shutdown is currently met, and if not met, what- Actions are required?

A. LCO 3.5.2 is met.

8. LCO 3.5.2 is NOT met, Actions for Condition A only are required.

C. LCO 3.5.2 is NOT met, Actions for Condition C only are required.

D. LCO 3.5.2 is NOT met, Actions for both Conditions A and Care required/ "

Proposed Answer: a. LCO 3.5.2 is met.

Explanation:

Per B 3.5.2, only one LPCI Pump is required for the subsystem to be considered operable, unlike LCO 3.5.1 which requires both pumps. Also per B 3.5.2, and SR 3.5.2.4, one LPCI subsystem may be considered operable during alignment for and operation in shutdown cooling, therefore two low pressure injection/spray subsystems are operable and LCO 3.5.2 is 'met.

b. is incorrect because RHR Loop A and B are considered operable.
c. is incorrect because RHR Loop A and B are considered operable.
d. is incorrect because RHR Loop A and B are considered operable.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): TS Bases 3.5.2. (Attac.h if not previously provided)

Proposed references to be provided to applicants during examination: TS 3.5.2 Learning Objective: (As available)

Question Source: Bank# LOI SYSTEMS S205000 GEN 2.2.25 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental KnoWledge _X _

Compre.hension or Analysis 10 CFR Part 55* Content:

10CFR55.43 2 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #98 Tier # 3 Group # 3 KIA # 2.3.3 Importance Rating 2.9 (K&A Statement) Knowledge of SRO responsibilities for auxiliary systems that are outside the

'control room (e.g. / waste disposal and handling systems).

Proposed Question: A core reload sequence is in progress in accordance with OF'H-11, Refueling. The neutronic bridge has NOT yet been established.

The Outage Center has requested that the Control Room perform control rod timing in conjunction with core reload .

Which ONE of the following is required?

A. Authorize control rod timin'g, . f uel movement is not allowed until the neutronic bridge) is established. .

B. Direct that fuel assemblies be unloaded until the bridge is established then authorize control rod timing.

C. Authorize fuel movement and insure control rod withdrawal does not oc'cur until the neutronic bridge is established.

D. Direct that control rod timing may be performed only in cells containing blade guides and that fuel moves may also occur.

c. Authorize fuel movement and insure control rod withdrawal does not Proposed occur until the neutronic bridge is established.

Answer:

Explanation: OFH-11, 4.3. 4 To help ensure that an unmonitored criticality will not occur, control rod withdrawal is not allowed during the core reload sequence until a neutronic bridge is established. The neutronic bridge ensures that two SRMs are neutronically coupled, thus monitoring the loaded area of the core. The reload sequence has three basic steps. Four fuel bundles are loaded around each of the four SRMs, the neutronic bridge is established and a spiral reload of the other fuel bundles completes the sequence.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

a. is incorrect because the neutronic bridge must be established before control rod movement.
b. is incorrect because fuel must be moved into the core to establish a neutronicbridge.
c. is correct
d. is incorrect because the neutronic bridge must be established before any control rod movement.

Technical Reference(s): FHP-11 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

(A-s-avaHab*le}--*-----******------

Question Source: Bank# LOI-CLS-LP-305-C*023 Modified (Note changes Bank # or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge _X _

Comprehension or Analysis 10 CFR Part 55 Content:

10CFR55.43 6 Comments:

NUREG-1021 Revision 9 J

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO SRO #99 Tier # 3 Group # 3 KIA # 2.3.4 Irl)portance Rating 3.1 (K&A Statement) Knowledge of radiation exposure limits and contamination control I including permissible levels in excess of those authorized.

Proposed Question: During accident conditions, an auxiliary operator is needed to enter the Reactor Building for local emergency actions to prevent fuel damage. Due to elevated Reactor Building radiation levels, it is estimated the operator will receive 7.5 rem.

Which ONE of the following describes if the estimated 7.5 rem will . -._.._-_... __ . -~.

exceed applicable limits and can be authorized?

A. The estimated 7.5 rem will not exceed EPA-400 limits. This dose may be authorized by the Site Emergency Coordinator.

B. The estimated 7.5 rem will exceed EPA-400 limits. Exceeding EPA-400 limits cannot be authorized to prevent fuel damage.

C. The estimated 7.5 rem will exceed 10 CFR 2~ '1 limits. Exceeding 10 CFR 20 limits 2

cannot be authorized to prevent fuel damageX D. The estimated 7.5 rem will not exceed 10 CFR 20 limits for emergency conditions. This dose may be authorized by the Site Emergency Coordinator.

Proposed a. The estimated 7.5 rem will not exceed EPA-400 limits. This dose may be Answer: authorized by the Site Emergency Coordinator.

Explanation:

Per PEP-03.7.6, emergency limits follow EPA-400 guidelines of 10 rem for protection of valuable property and 25 rem for life saving action. Exceeding 10 CFR 20 limits (5 rem) requires authorization of the SEC for on site activities.

b. is incqrrect because the 7.5 rem does NOT exceed the EPA-400 limits and it can be authorized.
c. is incorrect because it can be authorized.
d. is incorrect because the 7.5 rem does exceed the 10 CFR 20 limits.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPEP-03.7.6 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: None Learning CLS-LP-301, (As Objective: 10. Given PEP-03.7.6, Emergency Exposure Controls, determine available) exposure limits and approval authority for:

a. Lifesaving Actions (SRO Only).
b. Protecting Valuable Property (SRO Only).
c. Protection of Large Populations (SRO Only).

_._Q uestion--Sou rc-e. B-ank-#--I-Let-S-'fS-=r-EM-&-6£N-2-:B-:4~-------*_------------- - - - - ------~

Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N?A Question Cognitive Level: Memory or Fundamental Knowledge _X _

Comprehension or Analysis 10 CFR Part 55 Content:

10CFR55.43 4 Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-refere*nce: Level RO- SRO SRO #100 Tier # 3 Group # 4 KIA # 2.4.4 Importance Rating 4.3 (K&A Statement) Ability to recognize abnormal indications for system ope'rating parameters which are entry~level conditions for emergency and abnormal operating procedures.

Proposed Question: Unit Two (2) was operating at 96°A> power when the following occurred:

@ 1900, the Unit 2 SAT trips and locks out, DGs 1-4 auto statt

_._.. ._~ __.__.__,,_. . _@ 1901, a maDual reactor scram is inserted, ,RPS A fails to trip, no rod motion . ---"-------- ....

@ 1902, manual ARI initiation is attempted, ARI fails to initiate .

@ 1904, SLC is initiated; SLC Pump 2A starts, SLC Pump*28 fails to start

@ 1907, RPS trip system A is tripped using RPS test switches, all rods insert .

@ 1908, the turbine trips, DG3 ties to E3, 'DG4 trip~ and locks out It is now 1910 and you are reviewing the Emergency Action Levels per PEP-02.1. Which ONE of the following describes the event classification and notifications required to be made to off-site agencies?

A. Declare an Alert and notify off-site agencies of this classification;"only,~

8. Declare an Unusual Event and notify off-site agencies of this classification .Qnly.

C. Declare an Unusual Event and notify off-site agencies that the EAL for an Alert was briefly exceeded, but no longer exists.

D. Declare an Alert and notify off-site agencies that the EAL for a Site Area Emergency was briefly exceeded, but no longer exists.

Proposed c. Declare an Unusual Event and notify off-site agencies that the EAL for an Answer: Alert was briefly exceeded, but no longer exists.

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation:

Per PEP-2.1 EAL 06.01.01 is currently exceeded.

Per PEP-02.1.1, If the declared emergency is the result of an emergency action lever requiring a high classification (e.g., Site Area Emergency) that after a brief period is downgraded to a lower classification (e.g. Unusual Event), the off-site notification must indicate the current classification and it must also indicate the period of time that the higher classification existed and the mitigating conditions that caused the emergency classification to be downgraded.

a. I is incorrect because an Alert classification is not warranted EAL 05.02.02 (failure to scram) was exceeded, but no longer applies.
b. is incorrect because OPEP-02.1.1 requires reporting that a higher classified event temporarily existed.
d. is incorrect because there is nothing occurring that requires a Site Area Emergency. EAL 06.02.02 was not exceeded since DG3 ties to E3. Prior to event classification EA'L 05.03.01 was not exceeded since one SLC pump functioned Proposed references to be provided to applicants during examination: Attachment 1 of OPEP-2.1 Learning CLS-LP-301, (As Objective: 4. Given PEP-02.1, Initial Emergency Actions, discuss/perform the available) following actions:
a. Implementation requirements.
c. Classify emergency events (SRO Only).
d. Post-classification actions (SRO Only).
e. Action required for short duration emergency events (SRO Only).
5. Given PEP-02.1.1, Emergency Control - Notification of Unusual Event, Alert, Site Area Emergency and General Emergency discuss the following:
a. Site Emergency Coordinator (SEC) Responsibilities (SRO Only).
b. Implementation actions (SRO Only).

Question Source: Bank# LOI SYSTEMS S295003 GEN 2.4.30 Modified (Note changes or Bank # attach parent)

New Question History: Last NRC Exam N/A NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

~ Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X --

10 CFR Part 55 Content:

10CFR'55.431 5, Comments:

NUREG-1021, Revision 9

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet NUREG-1021, Revision 9

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