ML090270038

302 RO Written Exam

ML090270038
Person / Time
Site:	Brunswick
Issue date:	11/10/2008
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
50-324/08-302, 50-325/08-302
Download: ML090270038 (102)

Text

Draft Submittal (Pink Paper)

Reactor Operator Written Exam

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/U nit:

Region: I D II D III D IV 0 Reactor Type: W D CE D BW D GE D Start Time: Finish Time:

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

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'plicant Certification AliwOI own. I have neither given nor received aid.

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~ Applicant's Signature

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\ults Examination Vb. Points Applicant's Score Points Applicant's Grade Percent

1. Unit One reactor startup is in progress. Control rod 34-43 is stuck at position "00".

OP-07, Reactor Manual Control System Operating Procedure, directs attempting control rod withdraw by raising CRD drive water pressure to 300 psid drive header differential pressure.

Which ene of the following iEJeAtifies component manipulations-#la-t will raise drive header differential pressure'r A. throttle open CRD fl()w control valve C11-F002 and/or throttle open CRD pressure control valve C11-PCV-F003 B!'" throttle open CRD flow control valve C11-F002 and/or throttle closed CRD pressure control valve C11-PCV-F003 C. throttle closed CRD flow control valve C11-F002 and/or throttle open CRD pressure control valve C11-PCV-F003 D. throttle 'closed CRD flow control valve C11-F002 and/or throttle closed CRD pressure control valve C11-PCV-F003

REFERENCE:

SD-08, CRD Hydraulic System, Section 3.1 Component Control Big Note BN-08.0.01 Control Rod Drive Hydraulics EXPLANATION:

Using a CRD system diagram, the system configuration is such that closing the F003 or opening the F002 will raise CRD drive pressure differential.

CHOICE "A" - Incorrect. Throttling open the F003 will lower CRD drive pressure differential.

CHOICE "B" - Correct Answer CHOICE "C" - Incorrect. Throttling closed the F002 will lower CRD drive pressure differential.

CHOICE "D" - Incorrect. Throttling closed the F002 will lower CRD drive pressure differential.

Page 1 of 99

201003 Control Rod and Drive Mechanism A 1. Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:

(CFR: 41.5/45.5)

A1.02 CRD drive pressure ................................... 2.B /2.B SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-OB, Obj. 6F. Given plant and CRDHS conditions, predict the values for the following CRDH system parameters: Drive Water Header Pressure.

COG LEVEL: Low

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Page 2 of 99

2. While placing the 2B Recirculation Pump in service, a complete failure of the #1 seal occurs.

Which one of the following identifies the expected system indications for this failure?

A. #1 seal pressure - 0 psig;

1. 2 seal pressure - 500 psig; Seal Staging Flow Hi annunciator in alarm B. #1 seal pressure - a psig;

1. 2 seal pressure - 500 psig; Outer Seal Leakage Flow Detection Hi annunciator in alarm

, I C~ #1 seal pressure - 1000 psig;

1. 2 seal pressure - 1000 psig; Seal Staging Flow Hi annunciator in alarm D. #1 seal pressure - 1000 psig;

1. 2 seal pressure - 1000 psig; Outer Seal Leakage Flow Detection Hi annunciator in alarm

REFERENCE:

SD-02 Reactor Recirculation System APP A-O? (4-5) Outer Seal Leakage Flow Detection Hi APP-A-O? (5-5) Pump B Seal Staging Flow Hi EXPLANATION:

Normal seal pressures at rated conditions are 1000 psig for seal #1 and 500 psig for seal #2. A failure of seal #1 will cause seal pressures to equalize at rated pressure of 1000 psig. Seal Staging Flow Hi alarm will be received on a failure of either seal.

Outer Seal Leakage Flow Detection Hi alarm requires the #2 seal failure.

CHOICE "A" - Incorrect. A failure of seal #1 does not cause its associated seal pressure to drop to zero.

CHOICE "B" - Incorrect. A failure of seal #1 does not cause its associated seal pressure to drop to zero.

CHOICE "C" - Correct Answer CHOICE "0" - Incorrect. A failure of seal #1 will not cause the Outer Seal Leakage Flow Detection alarm

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Page 3 of 99

202001 Recirculation A 1. Ability topredi;t~nd/or monitor changes in parameters associated with operating the RECIRCULATIONSYSTEMc..2!JJLqls including: (CFR: 41.5/45.5)

A1.09 Recirculation pump seal pressures ...................... 3.3/3.3 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-02, Obj. 15a. Given plant conditions, determine if the following Reactor Recirculation System failures/malfunctions have occurred: #1 Recirculation Pump seal failure.

COG LEVEL: High

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Page 4 of 99

3. Given the following plant conditions:

Reactor water level -25 inches Reactor pressure 55 psig Vessel Injection 4500 gpm from'RHR I;

Which one of the following identifies the current status of Adequate Core Cooling and the operational implications of these conditions?

A. Adequate Core Cooling IS met; Clad temperatures are expected to exceed 1500° F B:-" Adequate Core Cooling IS met; Clad temperatures are expected to remain :::1500° F C. Adequate Core Cooling IS NOT met; Significant Fuel Damage will occur above 1500° F fuel clad temperature D. Adequate Core Cooling IS NOT met; Significant Hydrogen generation will occur above 1500° F fuel clad temperature

REFERENCE:

Introduction to ECCS Student Handout CLS-LP-1108 Introduction to ECCS EXPLANATION:

Four viable methods of Adequate Core Cooling (ACC) exist within the EOPs.

Core Submergence (Level above TAF),

Steam Cooling with Injection (Level above LL4),

Steam Cooling without Injection (Level above LLS) and Reactor water level at jet pump suction with core spray flow of at least 4700 gpm.

The conditions listed satisfy the ACC requirements for Steam Cooling with Injection.

If reactor water level were to drop below LL4, and RHR injection were maintained, ACC would not be meet. 8y maintaining this method of ACC , the core will generate sufficient steam to preclude any clad temperature from exceeding 1S00F.

CHOICE "A" -Incorrect. Clad temperatures will remain below 1S00F CHOICE "8" - Correct Answer CHOICE "C" - Incorrect. ACC is maintained.

CHOICE "D" - Incorrect. ACC is maintained

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Page 5 of 99

203000 RHRlLPCI: Injection Mode KS. Knowledge of the operational implications of the following concepts as they apply to RHRlLPCI:

INJECTION MODE (PLANT SPECIFIC) : (CFR: 41.S / 4S.3)

KS.02 Core cooling methods .................................... 3.S / 3.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-110B, Obj. 1A. Define the following terms: Adequate core cooling.

COG LEVEL: High Page 6 of 99

4. -FeI10Wir:lg a dual unit loss of off-site power, the only energized~ 4KV E-Bus is E2.

Which one of the following pumps has an available power supply?

A. 1A RHR Pump B. 2C RHR Pump C~ 1D RHR SW Booster Pump D. 2B RHR SW Booster Pump

REFERENCE:

SD-17 Residual Heat Removal System EXPLANATION:

Each of the above listed pumps is powered from a different plant 4KV Emergency bus.

The 1D RHR SW Booster Pump is powered from E-2.

CHOICE "A" - Incorrect. Powered from E3 CHOICE "B" - Incorrect. Powered from E1 CHOICE "C" - Correct Answer CHOICE "D" - Incorrect. Powered from E4 205000 Shutdown Cooling K2. Knowledge of electrical power supplies to the following: (CFR: 41.7)

K2.01 Pump motors ....................................... 3.1 * / 3.1

• SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-17, Obj. 17a. List the normal and emergency power sources for the following: RHR pumps.

COG LEVEL: Low Page 7 of 99

5. If suppression pool water level cannot be maintained above -6.5 feet, Primary Containment Control Procedure gives specific direction regarding HPCI operation.

Which one of the following identifies this direction) and its bases?

Secure HPCI:

A'! irrespective of adequate core cooling, tErpreveAt primary containment failure due tQ overpressurization.

B. irrespective of adequate core cooling, te-pre*yeffl HPCI turbine damage due to high exhaust pressure C. unless required to maintain adequate core cooling, t-fr1.JreveA-t primary containment fa~~uredue to overpressurization.

D. unless required to maintain adequate core cooling, to prevent HPCI turbine damage due to high exhaust pressure.

REFERENCE:

001-37.8 Primary Containment Control Procedure Basis Document EXPLANATION:

Per the PCCP, steps SP/L-26 and 27, if suppression pool level cannot be maintained above -6.5 feet then secure HPCI irrespective of ACC. Per 01-37.8, the bases for these steps is to prevent primary containment failure due to overpressurization.

CHOICE "A" - Correct Answer CHOICE "B" - Incorrect. High Turbine exhaust pressure will cause a HPCI turbine trip but is not a concern under these conditions.

CHOICE "C" - Incorrect. HPCI must be secured irrespective of ACC. Under other degraded conditions, such as NPSH limits, you would continue to run HPCI to maintain ACC CHOICE "D" - Incorrect. HPCI must be secured irrespective of ACC. Under other degraded conditions, such as NPSH limits, you would continue to run HPCI to maintain ACC 206000 HPCI 2.4.18 Knowledge of the specific bases for EOPs. (CFR: 41.10/43.1 /45.13)

IMPORTANCE RO 3.3 SRO 4.0 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-300L, Obj. 13. Explain why HPCI operation is not allowed (irrespective of adequate core cooling) if suppression pool level is below -6.5 feet.

COG LEVEL: High

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Page 8 of 99

6. During a small break LOCA with a failure of HPCI to start,m)s-BHlteRlatiealtv1n1ttme Plant conditions are as follows:

Reactor level -20 inches Reactor Pressure 400 psig and lowering ECCS pumps 2A and 2B Core Spray pumps running ADS SRV's 7 ADS valves OPEN with control switches in AUTO A dual unit loss of off-site power occurs and all DGs tie onto their respective E buses to restore E Bus power.

Which one of the following describes the expected ADS valve response?

A. remain open B. close and will not automatically re-open C~ close then re-open as soon as low pressure ECCS pumps sequence on D. close then re-open 83 seconds after low pressure ECCS pumps sequence on

REFERENCE:

SD-20 ADS Section 3.3 Logic, Section 4.3.4 AC Power EXPLANATION:

ECCS pumps will trip on l,JV will LOOP. With Control Switches in AUTO, valves will close due to loss of ECCS permissive in ADS logic. Since RPV water level is still below LL3, valves will re-open when ECCS pumps sequence back on and re-satisfy the ECCS permissive. ADS timer stays sealed in (timed out) when ECCS permissive is lost.

CHOICE "A" - Incorrect. Valves will close. If power were not lost, the valves would remain open.

CHOICE "6" - Incorrect. Valves will auto re-open. If level were above LL3 they would not re-open.

CHOICE "C" - Correct Answer CHOICE "0" - Incorrect. Would be correct if ADS timer needed to be re-satisfied.

Page 9 of 99

209001 Low Pressure Core Spray K3. Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: (CFR: 41.7/45.4)

K3.02 ADS logic. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 3.8 3.9 SOURCE: Bank LOI-CLS-LP-020-A*007(28)

LESSON PLAN/OBJECTIVE:

CLS-LP-020, Obj. 11. Given plant conditions, determine if an automatic initiation of ADS should occur.

COG LEVEL: High Page 10 of 99

7. Following a DBA LOCA on Unit Two, plant conditions are as follows:

Reactor water level 55 inches and rising Reactor pressure 150 psig Torus temperature 220 0 F Suppression Chamber pressure 10.5 psig Torus level -4.6 feet 2A Core Spray pump flow 5000 gpm 2B Core Spray pump flow 2000 gpm 2A RHR pump flow 8000 gpm 2B RHR pump flow 6000 gpm (reference provided)

Which one of the following identifies the ECCS pumps operating within their NPSH limit?

A. All listed pumps B!'" 2B Core Spray Pump ONLY C. 2A Core Spray and 2B Core Spray ONLY D. 2B Core Spray, 2A RHR and 2B RHR ONLY

REFERENCE:

Unit Two Core Spray and RHR NPSH limit graphs provided in EOP flow charts EXPLANATION:

The student will need to plot each point on NPSH limit graph.

Torus pressure must be corrected down 1 psig to obtain the proper restriction line.

=

The correct torus pressure is 10.5 psig - 1.0 psig 9.5 psig.

This correction must be performed for both the RHR and CS graphs.

CHOICE "A" - Incorrect. If student fails to adjust torus pressure on both graphs, this answer would be correct.

CHOICE "8" - Correct Answer CHOICE "C" - Incorrect. If student fails to adjust torus pressure on CS graph, this answer would be correct.

CHOICE "D" - Incorrect. If student fails to adjust torus pressure on RHR graph, this answer would be correct.

Page 11 of 99

209001 Low Pressure Core Spray 2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7/43.5/45.12)

IMPORTANCE RO 3.6 SRO 4.6 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-300B, Obj. 17. Given plant condition and the NPSH and vortex limit graphs for the RHR and CS, determine if the NPSH and/or vortex limits have been exceeded for either of the two systems.

COG LEVEL: High

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Page 12 of 99

8. Following an ATWS on Unit Two, Standby Liquid Control is manually initiated to assist in reducing reactor power.

Which one of the following describes the operational implications a Loss of Instrument Air wHH1ave on the SLC system?

A. Storage tank sparging will not be available.

B~ SLC storage tank level indication reading lower than actual level.

C. SLC storage tank level indication reading higher than actual level.

D. Increased hydraulic pulsations due to depressurized system accumulators.

REFERENCE:

SD-05 Standby Liquid Control System, Section 4.3.2 Instrument Air EXPLANATION:

The instrument air system provides air to the bubbler tube in the SLC storage tank level instrumentation.

Low/loss of air flow will cause the level indication to be lower than actual.

CHOICE "A" - Incorrect. Sparging air is provided from the service air system only.

CHOICE "B" - Correct Answer CHOICE "C" - Incorrect. Higher than normal air flow would cause indications to be higher than normal.

CHOICE "0" - Incorrect. SLC accumulators are precharged with Nitrogen.

They are not supplied from Instrument air.

211000 SLC K5. Knowledge of the operational implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM: (CFR: 41.5/45.3)

K5.06 Tank level measurement .................................... 3.0 3.2 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-05, Obj. 9d. Describe the operation of the following: SLC Tank level measurement system COG LEVEL: Low Page 13 of 99

9. OPT-01.1.6, Reactor Protection System Manual Scram Test, is in progress.

Manual Reactor Scram System A pushbutton has been depressed and the following annunciator is in alarm:

/'

Reactor Manual ScralTl Sys A P-riortElresetting the half scram signal, Drywell Pressure Transmitter PT-N002D (input to RPS) fails upscale.

WhiCtroneof the following is the effect this failure will have on RPS?

Auto Trip Channel B2 _ _ _ __

A. energizes; full scram occurs.

B~ de-energizes; full scram occurs.

C. energizes; ,no full scram occurs since AUTO and MANUAL scram logics act independently.

D. de-energizes; no full scram occurs since AUTO and MANUAL scram logics act independently.

REFERENCE:

SD-03 Reactor Protection System, Section 1.3 EXPLANATION:

The RPS trip system logics are normally energized. It is a fail safe system such that de-energizing a trip system causes a trip in that system. There are two RPS trip systems. Trip system A and Trip system 8.

Each trip system contains two auto trip channels and one manual trip channel. (A1/A2/A3 and 81182183)

If anyone trip channel in each system de-energizes, a full scram will occur. With the 'A' Scram pushbutton depressed, the A3 trip channel has de-energized the A RPS trip system.

When drywell pressure transmitter 'D' fails upscale, the 8 RPS trip system will de-energize causing a full scram.

CHOICE "A" - Incorrect. RPS de-energizes to actuate. Other plant logics (i.e. ECCS) are energize to actuate.

CHOICE "8" - Correct Answer CHOICE "C" - Incorrect. RPS de-energizes to actuate. Other plant logics (i.e. ECCS) are energize to actuate.

CHOICE "D" - Incorrect. Auto and Manual RPS trip channels work together to cause a scram. A misconception of the logic would cause a student to pick this answer.

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Page 14 of 99

212000 RPS A4. Ability to manually operate and/or monitor in the control room:

(CFR: 41.7/45.5 to 45.8)

A4.02 Perform system functional test(s) ............................. 3.63.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-03, Obj. 14. Given plant conditions and control room indications, determine whether a reactor scram has actuated properly.

COG LEVEL: High Page 15 of 99

10. Which one of the following parameters is a direct input into the RPS logic?

A. Main condenser vacuum B. Main Steam line Radiation C. PAM (Pressure Averaging Manifold) pressure D~ RETS (Relayed Emergency Trip Supply) pressure

REFERENCE:

SD-03 Reactor Protection System EXPLANATION:

RETS pressure is utilized by the RPS system to detect a fast closure of the turbine control valves, for input into the TCV fast closure scram logic.

CHOICE "A" - Incorrect. Main condenser vaccum inputs to the turbine trip logic.

CHOICE "B" - Incorrect. Main steam line radiation lJsed to input to the MSIV closure logic.

CHOICE "C" - Incorrect. PAM pressure inputs EHC logic. Turbine 1st stage pressure inputs to RPS.

CHOICE "D" - Correct Answer 212000 RPS K1. Knowledge of the(physical connections and/or cause effect relationships between REACTOR PROTECTION SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.12 Reactor/turbine pressure control system: .................... 3.4 3.6 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-03, Obj. 8. List the RPS trip signals, including setpoints and how/when each signal is bypassed.

COG LEVEL: Low Page 16 of 99

11. TIP traces are in progress with the "A" TIP probe at the top core limit.

A small steam leak in containment causes drywell pressure to rise to 2.7 psig.

Which one of the following identifies the expected final position of the TIP ball valves and the available location( s) for verifying this position?

A. Open; Back Panel ONLY.

B. Closed; Back Panel ONLY.

C. Open; Control Room Panel and Back Panel.

D~ Closed; Control Room Panel and Back Panel.

REFERENCE:

SD-09.5 Traversing In-Core Probe (TIP) System, section 3.1 Indications, section 3.2.2 Interlocks EXPLANATION:

If drywell pressure reaches the PCIS Gp 2 isolation setpoint of 1.7 psig, TIP logic will initiate an automatic probe retract to the in-shield position and the TIP ball valves will auto close.

Indication of TIP ball valve position can be found on the P601 panel in the control room and the TIP back panel.

CHOICE "A" - Incorrect TIP ball valves will auto close on PCIS Gp 2 isolation Signal.

The TIP shear valve remains open. Confusion between these valves would cause a student to select this answer.

CHOICE "8" - incorrect TIP ball valves will auto close on PCIS Gp 2 isolation signal.

The TIP shear valve remains open. Confusion between these valves would cause a student to select this answer.

CHOICE "C" - Incorrect TIP valve position verification can be made from the P601 panel in the control room and the TIP back panels.

CHOICE "D" - Correct Answer Page 17 of 99

21S001 Traversing In-Core Probe 2.1.31 Ability tolocate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR: 41.10/ 4S.12)

IMPORTANCE RO 4.6 SRO 4.3 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-09, Obj. Sb. explain the effects of the following on the TIP System: High Drywell Pressure COG LEVEL: High Page 18 of 99

12. Unit One is commencing a startup with all SRM's fully inserted and reading approximately 1 x 105 cps. The IRM's are reading the following:

IRMA 20 on Range 1 IRME 21 on Range 1 IRMB 28 on Range 1 IRMF 19 on Range 1 IRMC 21 on Range 2 IRMG 23 on Range 2 IRMD 25 on Range 1 IRMH 20 on Range 1 The operator inadvertently takes the range switch for IRM B from Range 1 to Range 3.

Which one of the following sytem responses would verify proper IRM system operation?

A. Rod Out Block alarm only B. IRM downscale white light illuminated only C. No Rod Block alarm or IRM downscale white light illuminated D!' Rod Out Block alarm and IRM downscale white light illuminated

REFERENCE:

SO-9.1 Startup Range Monitor System APP A-OS (2-2) ROD OUT BLOCK EXPLANATION:

Taking the range switch from Range 1 to Range 3 will cause the IRM reading to drop by a factor of ten.

IRM "B" will be reading 2.8 which will cause the IRM downscale light to illuminate. (setpoint of 3.S cps) A ROD OUT BLOCK will be generated from any downscale IRM not on Range 1.

CHOICE "A" - Incorrect. IRM downscale light will also illuminate for these conditions.

CHOICE "B" - Incorrect. A Rod Out Block alarm will also be received for these conditions CHOICE "C" - Incorrect. Both responses will occur.

CHOICE "0" - Correct Answer 21S003 IRM A4. Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 4S.S to 4S.8)

A4.07 Verification of proper functioning / operability ................... 3.6/ 3.6 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-9.1, Obj. 3a. List the SRM/IRM system signals/conditions that will cause the following actions and the conditions under which each is bypassed: Rod Blocks.

COG LEVEL: High Page 19 of 99

13. A reactor startup is in progress following a refueling outage.

- The RPS shorting links are installed.

The operator notes the following SRM readings:

SRM Channel A 6.0 x 105 cps SRM Channel B 1.0 x 105 cps SRM Channel C 7.0 x 104 cps SRM Channel D 8.0 x 104 cps AlllRMs are on Range 4.

Which one of the following( design features should have occured?

A. SRM Upscale Alarm only B~ SRM Upscale Alarm and Rod BLock only C. SRM Upscale Alarm, Rod Block and 1/2 Scram D. SRM Upscale Alarm, Rod Block and Full Scram

REFERENCE:

SD-9.1 Neutron Monitoring System (Startup and Intermediate Range)

APP-A-05(2-2) ROD OUT BLOCK APP-A-05(2-3) SRM UPSCALE/INOP EXPLANATION:

SRM Upscale alarm setpoint is 2.0 x 105 cps. An SRM Upscale alarm with any IRM below range 8 will also cause a Rod Out Block. With shorting links installed, the SRM RPS function is bypassed. No scram or half scram can occur.

CHOICE "A" - Incorrect. Rod Block will also occur. If IRMs were on range 8 or higher this answer would be correct.

CHOICE "B" - Correct Answer CHOICE "C" - Incorrect. RPS function bypassed with shorting links installed.

If RPS function were active, student may choose this answer since only one SRM channel is above the high setpoint.

CHOICE "D" - Incorrect. This answer would be correct if shorting links were not installed. RPS SRM scram is non-coincident.

Page 20 of 99

215004 Source Range Monitor K4. Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

K4.01 Rod withdrawal blocks ................................. 3.7/3.7 SOURCE: Bank LOI-CLS-LP-009-A*03A (10)

LESSON PLAN/OBJECTIVE:

CLS-LP-9.1, Obj. 3a. List the SRMIIRM system signals/conditions that will cause the following actions and the conditions under which each is bypassed: Rod Blocks.

COG LEVEL: High Page 21 of 99

14. Unit Two is operating at 100% rated power.

Which one of the following plant transients will cause the APRM aDA display to automatically shift to the stability screen?

A. "8" SRV fails full open

8. Inadvertant RCIC injection C~ "A" Recirculation Pump Trip D. Control Rod drifting into the core

REFERENCE:

SD-9.6 Power Range Neutron Monitoring And Rod Block Monitor APP-A-05(4-8) OPRM TRIP ENABLED EXPLANATION:

The stability screen will be automatically displayed on the ODA for both APRMs when either APRM enters the power-flow map region where instability can occur as defined by the OPRM trip enabled setpoint.

(reactor power greater than or equal to 25% and recirc. flow less than or equal to 60%)

The student must know what causes the APRM ODA to shift to the STABILITY screen. -

If they do not, any of the given transients is a plausible selection.

CHOICE "A" - Incorrect. at lower power this would cause instabilities.

CHOICE "B" - Incorrect. cold water injection could damage fuel, but does not cause instabilities.

CHOICE "C" - Correct Answer CHOICE "0" - Incorrect. a control rod insertion moves power straight down the power to flow map and not toward the OPRM enabled region.

215005 APRM / LPRM A3. Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM inciuding:(CFR: 41.7/45.7)

A3.03 Meters and recorders ................................... 3.3/ 3.3 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS=LP-9.6, Obj. 28. Given plant conditions and entry into one of the following Power to Flow Map regions, use procedures to determine the actions required to control and/or mitigate the consequences of the event: OPRM Enabled Region.

COG LEVEL: High Page 22 of 99

15. Unit Two is at rated power when a faulty CST level instrument initiates a false low CST level input to the RCIC logic.

The following annunciator is received:

RCIC Suct Xfer CST Lo Lvi Which one of the following identifies the correct RCIC system suction valves response?

Suppression Pool Suction Valves, F029 and F031 _ _ _ _ _ __

CST Suction Valve, F010_ _ _ _ _ _ __

A. auto open; auto closes when both suppression pool suction valves are not full closed.

B:' auto open; auto closes when both suppression pool suction valves are full open.

C. auto opel')s when CST suction valve is not full open; auto clos~s.

D. auto opens when CST suction valve is full closed; auto closes.

REFERENCE:

SD-16 Reactor Core Isolation Cooling, section 3.2 APP-A-02(3-8) RCIC SUCTION TRANS CST LO LVL EXPLANATION:

The normal RCIC suction valve configuration is the CST suction (F010) open and the suppression pool suction valves (F029 and 31) closed. If a low CST level is sensed, with reactor pressure above the RCIC isolation setpoint, the F029 and 31 will auto open. When they are both full open, the F010 will auto close.

If reactor pressure is below the RCIC isolation setpoint, the valves respond differently.

CHOICE "A" - Incorrect. Has to see both valves full open not when they start to open.

CHOICE "B" - Correct Answer CHOICE "C" - Incorrect. Suppression pool suctions open first then the CST valve to make sure that a suction flowpath exists.

CHOICE "D" - Incorrect. Suppression pool suctions open first then the CST valve to make sure that a suction flowpath exists.

Page 23 of 25

217000 RCIC K1. Knowledge of the physical connections and/or cause effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: (CFR: 41.2 to 41 .9 / 45.7 to 45.8)

K1.01 Condensate storage and transfer system .................... 3.5/3.5 SOURCE: Bank LOI-CLS-LP-016-A*010 (6)

LESSON PLAN/OBJECTIVE:

CLS-LP-16, Obj. 10. Given a RCIC system valve, list the interlocks/automatic actions associated with that valve.

COG LEVEL: High Page 24 of 99

16. Following a small steam line break in the drywell, plant conditions are as follows:

Drywell Pressure 20.8 psig Drywell Average Air Temp. 292 0 F Torus Pressure 19.0 psig Reactor Pressure 675 psig Reactor Water Level 100 inches HPCI System Unavailable RCIC System Started at LL2 and injecting Given these conditions, what is the impact on-the ADS Initiation Timer and what operator action must be taken in accordance with Emergency Operating Procedures?

v ADS Initiation Timer started; Befor~ Drywell Average Air temperature reaches 300 0 F, _ _~_ _ _ _ __

A. has; Drywell Spray required B:' has not; Drywell Spray required C. has; Emergency Depressurization required D. has not; Emergency Depressurization required

REFERENCE:

SO-20 Automatic Depressurization System, section 3.3 Logic PCCP EXPLANATION:

The conditions required to start the ADS timer have not been meet. (LL3/45 inches)

The conditions listed require entry into PCCP. Per the direction of PCCP, before drywell average air temperature reaches 300F, spray the drywell.

CHOICE "A" - Incorrect. ADS timer has not started CHOICE "8" - Incorrect. ADS timer has not started CHOICE "C" - Correct Answer CHOICE "0" - Incorrect. Per PCCP, emergency depress is required if drywell temp cannot be restored and maintained below 300°F.

Page 25 of 99

218000 ADS A2. Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations

(CFR: 41.5/45.6)

A2.01 Small steam line break LOCA .............................. 4.1 / 4.3*

SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-020, Obj. 11. Given plant conditions, determine if an automatic initiation of ADS should occur.

COG LEVEL: High Page 26 of 99

17. Unit Two is operating at full power.

"B" RHR pump and "B" RHR SW pump have been placed in Suppression Pool Cooling to lower torus temperature.

A subsequent LOCA causes reactor water level to drop rapidly.

Plant conditions are as follows:

Drywell Pressure 18.1 psig, Torus Pressure 13.7 psig Reactor Pressure 885 psig Reactor water level 36 inches Which one of the following describes the effect these conditions will have on the status of Suppression Pool Cooling?

A. Suppression Pool Cooling will remain in service in the current lineup.

,B~ HX Bypass Valve E11-F048B will auto open and cannot be closed for 3 minutes-C. HX Bypass Valve E11-F048B will auto open and cannot be closed for 5 minutes D. HX Bypass Valve E11-F048B will auto open and cannot be closed for 10 minutes

REFERENCE:

SD-17 Residual Heat Removal System, section 3.9 EXPLANATION:

The student must first recognize that an RHR initiation Signal is present. (LL3) Upon receipt of the initiation signal, the HX bypass valve will receive an auto open signal and will be prevented from closing for 3 minutes.

CHOICE "A" - Incorrect. Would be correct if reactor water level were above LL3.

CHOICE "8" - Correct Answer CHOICE "C" - Incorrect. 5 minutes is a time delay associated with the RHR injection valve, F017.

CHOICE "D" - Incorrect. 10 minutes Is a time mentioned in SD-17, section 4.2.8 associated with equipment condition. 10 seconds is a time associated with the RHR min flow bypass valve.

Page 27 of 99

219000 RHRlLPCI: Torus/Pool Cooling Mode K1. Knowledge of the physical connections and/or cause effect relationships between RHRlLPCI: TORUS/Sl,jPPRESSION POOL COOLING MODE and the following:

CFR: 41.2 to 41.9 /45.7 to 45.8)

K1.09 Nuclear boiler instrumentation ........................... 3.3/3.4 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-17, Obj. 9. given an RHR pump or valve, list the interlocks, permissives and/or automatic actions associated with the RHR pump or valve, including setpoints.

COG LEVEL: High

(

Page 28 of 99

18. In the RC/L leg of Level/Power Control Procedure, circuit alterations are performed on Unit Two per EOP-SEP-1 0, Circuit Alteration Procedure, to prevent a Group I Isolation from occ.urring.

Which one of the following Group I Isolation signals is defeated by this circuit alteration?

A. Main Steam Line Low Pressure B. Main Steam Line High Flow C~, Reactor Water low Level 3..

D. Low Condenser Vacuum

REFERENCE:

SEP-10 Circuit Alterations EXPLANATION:

The LL3 Gp 1 Isolation signal is defeated in these conditions to prevent a closure of the MSIVs as reactor water level is intentionally lowered to assist in controlling power.

CHOICE "A" - Incorrect. Gp 1 Isolation signal, but it is not defeated.

CHOICE "B" - Incorrect. Gp 1 Isolation signal, but it is not defeated.

CHOICE "C" - Correct Answer CHOICE "0" - Incorrect. Gp 1 Isolation signal, but it is not defeated.

223002 PCIS / Nuclear Steam Supply Shutoff K4. Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

K4.08 tManual defeating of selected isolations during specified emergency conditions .. :. . .............. 3.3/ 3.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-300K, Obj. 18e. Explain the reasons for installation of jumpers to defeaUactuate the following:

MSIV LL3lsolation.

COG LEVEL: High

(

Page 29 of 99

19. Unit Two is operating at full power.

A failure to "self check" during clearance activities results in the feeder breaker to 2A RPS MG set being inadvertently opened.

Which one of the following describes the effects of this mis-operation?

A. RPS bus "A" remains energized due to flywheel operation and automatic transfer of bus to the alternate power supply.

B. RPS bus "A" momentarily ,de-energizes until automatic transfer of bus to alternate power supply is complete:'

C!' RPS bus "A" de-energizes; transfer to alternate power supply requires manual actions; Group 1 AlC logic trips; no MSIV movement D. RPS bus "A" de-energizes; transfer to alternate power supply requires manual actions; Group 1 Ale logic trips; Inboard MSIV closure

REFERENCE:

SD-3.0 Reactor Protection System, section 4.1.4 EXPLANATION:

Opening the feeder breaker to the 'A' RPS MG set will cause RPS bus 'A' to deenergize. RPS MG Flywheel action will not keep the bus energized. This loss will cause a trip of the GP1 AlC logic, however no MSIV movement will occur.

Re-energization of the RPS bus from the alternate supply requires manual action.

CHOICE "A" - Incorrect. Flywheel maintains voltage and frequency for 1 second only; manual transfer to alternate is required CHOICE "B" - Incorrect. manual transfer to alternate is required CHOICE "C" - Correct Answer CHOICE "D" - Incorrect. No MSIV closure occurs 223002 PCIS / Nuclear Steam Supply Shutoff K6. Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: CFR: 41.7/45.7)

K6.08 Reactor protection system. . . . . . . . . .. . ................... 3.5 / 3.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-03, Obj. 18a. State the power supplies for the following: RPS MG Set A.

COG LEVEL: High Page 30 of 99

20. On Unit Two, the SRO directs the RO to place drywell sprays in service per OEOP-01-SEP-02, Drywell Spray Procedure.

During the execution of SEP-02, SW-V111, Conv SW to Vital Header Vlv trips on magnetics and remains in the full closed position.

Which one of the following describes the impact this failure will have on

_RHRlDryweH Spray system and the procedural-actions necessary to mitiga.te these consequences?

A. loss of cooling water to RHR Room Coolers only; Open SW-V117, Nuc SW to Vital Header Vlv.

B. loss of cooling water to RHR Room Coolers only; Open SW-V118, Vital Header Crosstie Vlv.

C~ loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V117, Nuc SW to Vital Header Vlv.

D. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V118, Vital Header Crosstie Vlv.

REFERENCE:

SEP-02 Orywell Spray Procedure SD-17 Residual Heat Removal System EXPLANATION:

SEP-02 directs supplying cooling water to the vital header by opening either the SW-V111 valve or the SW-V117 valve. If one is unavailable or trips, the procedure will direct opening the other valve. Opening the SW-V118 is not an option provided in SEP-02. The loads supplied by the vital header include the RHR Room Coolers and the RHR Pump Seal Coolers.

CHOICE "A" - Incorrect. Cooling is also lost to the RHR Pump seal coolers CHOICE "8" - Incorrect. Cooling is also lost to the RHR Pump seal coolers; Opening SW-V118 is not a procedural option.

CHOICE "C"_ Correct Answer CHOICE liD" - Incorrect. Opening SW-V118 is not a procedural option.

Page 31 of 99

226001 RHR/LPCI: CTMT Spray Mode A2. Ability to (a) predict the impacts of the following on the RHRlLPCI: CONTAINMENT SPRAY SYSTEM MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /45.6)

A2.03 Valve closures ...................................... 3.1 / 3.1 SOURCE: New LESSON PLAN/OBJECTIVE:

COG LEVEL: High Page 32 of 99

21. OAOP-38.0, Loss of Fuel Pool Cooling, gives direction to maintain fuel pool level between the Fuel Pool Level High and Fuel Pool Level Low annunciators using a variety of makeup sources.

Which one of the following is the preferred makeup source?

A. Demin water header stations B. Fire Protection Hose Stations C. Demin water from BLoop RHR keepfill D~ Demin water makeup via skimmer surge tank makeup valve

REFERENCE:

AOP-38.0 Loss of Fuel Pool Cooling SD-13 section 4.2.1 EXPLANATION: The preferred order of the makeup sources is from the normal fill, Demin water hose stations, Fire protection hose stations, and then other sources that are not service water.

CHOICE "A" - Incorrect. although this is a makeup source it is not the preferred source.

CHOICE "B" - Incorrect. although this is a makeup source it is not the preferred source.

CHOICE "C" - Incorrect. although this is a makeup source it is not the preferred source.

CHOICE "D" - Correct answer.

233000 Fuel Pool Cooling / Cleanup 2.4.6 Knowledge of ~9P mitigation strategies. (CFR: 41.10/43.5/45.13)

IMPORTANCE RO 3.7 SRO 4.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-13, Obj. 11. State the sources of makeup water for the Fuel Pool in order of preference.

COG LEVEL: Low Page 33 of 99

22. Lowering condenser vacuum results in the Unit SRO directing a reactor scram.

A subsequent ATWS occurs.

Plant conditions are as follows:

Reactor Power 12%

Reactor Pressure 1100 psig Reactor Water Level 100 incbes and lowering Condenser Vacuum 8 inches Hg SLC Pumps Injecting Boron Torus Temperature 98° F Torus Level -2.2 feet In accordance with the Level Power Control Procedure, which one of the following means of pressure control is currently available to stabilize pressure below 1050 psig?

A. HPCI B~ SRV's C. Steam Jet Air Ejectors D. Main Turbine Bypass Valves

REFERENCE:

Level Power Control Procedure EXPLANATION:

From the choices given for pressure control, SRVs are the only available option for the given conditions.

CHOICE "A" - Incorrect. With level below LL2 HPCI cannot be placed in pressure control mode.

CHOICE "8" - Correct Answer CHOICE "C" - Incorrect. MSIV closure on low vaccum prevents using SJAE for pressure control CHOICE "D" - Incorrect. With MSIVs closed on low vacuum, bypass valves are not available Page 34 of 99

239001 Main and Reheat Steam K3. Knowledge of the effect that a loss or malfunction of the MAIN AND REHEAT STEAM SYSTEM will have on following: (CFR: 41.7/45.4)

K3.09 Steam bypass capability ................................ 3.6 / 3.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-300E, Obj. 11. Given plant conditions and the LPC procedure determine the operator actions required to stabilize or reduce reactor pressure.

COG LEVEL: High Page 35 of 99

23. Which one of the following describes the effect that a loss of E8 will have on the Unit Two Safety Relief Valve system?

A. Inability to manually operate SRV's from the RTGB B. Inability to manually operate SRV's from the RSDP C~ Loss of SRV position indication on the RTGB '

D. Loss of SRV position indication on the RSDP

REFERENCE:

SD-20 Automatic Depressurization System, section 4.3.4/4.3.5 EXPLANATION:

SRV position indication on the RTGB is powered thru the acoustic sensors which are powered from E6/E8.

CHOICE "A" - Incorrect. powered from 125 VDC CHOICE "B" - Incorrect. powered from 125 VDC CHOICE "C" - Correct Answer CHOICE "D" - Incorrect. powered from 125 VDC 239002 SRVs K6. Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES: (CFR: 41.7/45.7)

K6.03 A.C. power: Plant-Specific .............................. 2.7* 12.9*

SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-20, Obj. 15c. Given plant conditions, predict how ADS/SRVs will be affected by the following:

Loss of AC power.

COG LEVEL: Low Page 36 of 99

24. Unit Two is in power ascension following a refueling outage.

Reactor power is currently 22%.

The generator has been synchronized with the grid.

GP-04, Increasing Turbine Load to Rated Power, directs increasing turbine Load Set to 100%.

The RO inadvertently sets Load Set to 90% and continues with power ascension.

All other turbine controls are normal.

As reactor power is raised to full power, which one of the following describes the expected plant response?

A. When turbine load reaches 90%, reactor pressure will increase and cause a reactor scram.

8. With the 110% Load Limit Set in effect, reactor power and turbine load can be raised to 100%.

C!' When turbine load reaches 90%, bypass valves will open to control turbine inlet pressure.

D. When turbine load reaches 95%, Turbine Supervisory will sense a load imbalance causing a turbine trip to occur.

REFERENCE:

SD-26.3 EHC Electrical System EXPLANATION:

Load Set is a reference signal set from the RTGB. When sensed turbine load reaches the Load Set setting, additional turbine load is restricted. Any additional steam produced as a result of continuing to raise reactor power is diverted to the condenser via bypass valves.

CHOICE "A" - Incorrect. Bypass valves will open and control reactor pressure.

CHOICE "B" - Incorrect. Load limit set is used to limit how far the turbine control valves could actually open, especially during abnormal operation and testing. Load Set will still control load.

CHOICE "C" - Correct Answer CHOICE "D" - Incorrect. Incorrect interpretation of power/load imbalance Page 37 of 99

241000 ReactorlTurbine Pressure Regulator (EHC)

K5. Knowledge of the operational Implications of the following concepts as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM:

(CFR: 41.5/45.3)

K5.05 Turbine inlet pressure vs. Turbine load. . . . . . . . . . . . . .. . 2.8* 2.9*

SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-26.3, Obj. 9a. Given plant conditions, including manipulation of one of the following EHC control or parameter changes, predict the expected response of the main turbine and/or reactor protection system: Load Limit Set potentiometer.

COG LEVEL: High Page 38 of 99

25. A failed Feedwater Heater level control valve has caused level in the 2A Feedwater Heater to reach the Hi Hi Level setpoint.

Which one of the following describes the automatic system response, and the effect on feedwater temperature?

Moisture Removal Valves will open to drain extraction steam lines to the

______ and feedwater temperature will _ _ _ _ _ __

A. Condenser; Increase B~ Condenser; Decrease C. Heater Drain Deaerator; Increase D. Heater Drain Deaerator; Decrease

REFERENCE:

SD-34 Extraction Steam, section 3.1.1 EXPLANATION:

A high-high level condition in the 2A FW Heater will cause the associated MRVs to open, directing 11th stage extraction steam to the condenser, and allowing the extraction line check valves to close.

Feedwater heating is lost for this heater causing overall feedwater temperature to decrease.

CHOICE "A" - Incorrect. FW temperature will decrease CHOICE "B" - Correct Answer CHOICE "C" - Incorrect. MRVs open to the condenser; other FW heaters direct flow to the HOD CHOICE "0" - Incorrect. MRVs open to the condenser; other FW heaters direct flow to the HOD 256000 Reactor Condensate A3. Ability to monitor automatic operations of the REACTOR CONDENSATE SYSTEM including:(CFR:

41.7/45.7)

A3.08 Feedwater temperature. . . .. . ........................ 3.1 /3.1 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-34, Obj. 6a. Describe the effects of the following on the feedwater heater operation and feedwater temperature: High feedwater heater level.

COG LEVEL: High Page 39 of 99

26. Reactor pressurization is in progress per OGP-02, Approach to Criticality and Pressurization of the Reactor.

The feedwater system is aligned as follows:

A RFP in Service SULCV in Auto Feedwater Heater 4A and 4B inlet isolation valves are closed FW-FV-177, Feedwater Recirc Valve, throttled open Which one of the following describes the effect of throttling the FW-V177 in the OPEN direction?

If the operator throttles FW-FV-177 in the open direction, the SULCV will throttle in the

_ _ _ _ _ direction. Opening the FW-FV-177 too far could result in voiding of the feedwater system piping of the SULCV.

A. open upstream B. closed upstream C!' open downstream D. closed downstream

REFERENCE:

GP-02 Approach to Criticality and Pressurization of the Reactor SD-32 Condensate and Feedwater System EXPLANATION:

Throttling open the FW-V177 will divert flow from the reactor back to the condenser.

This will require the SULCV to open further to provide the needed flow to maintain set reactor water level.

A Caution in GP-02 warns against opening FW-V117 to far, causing voiding of the piping downstream of the SULCV.

CHOICE "A" - Incorrect. concern is for downstream piping CHOICE "8" - Incorrect. SULCV will open to maintain level; concern is for downstream piping CHOICE "C" - Correct Answer CHOICE liD" - Incorrect. SULCV will open to maintain level; Page 40 of 99

259002 Reactor Water Level Control A1. Ability to predict and/or monitor changes in parameters associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.05 FWRV/startup level control position: Plant-Specific ............ 2.9/2.9 SOURCE: Bank LOI-CLS-LP-32* (22B)

LESSON PLAN/OBJECTIVE:

CLS-LP-32, Obj. 2ge. Given plant conditions predict the changes in the Condensate and FW system parameters associated with operating the following equipment or controls: FW recirc to condenser valve, FW-FV-177.

COG LEVEL: High Page 41 of 99

27. Unit Two is operating at rated power with the following containment parameters:

Drywell Pressure 0.8 psig Torus Pressure 1.2 psig Torus venting is placed in service per 20P-1 0, Standby Gas Treatment System Operating Procedure, to lower torus pressure.

Which one of the following describes the response of drywell pressure to the torus venting operation?

Drywell Pressure will _ _ _ _ _ _ __

A'! remain steady B. rise and equalize with torus pressure

c. lower at the same rate as torus pressure D. lower at a faster rate than torus pressure

REFERENCE:

20P-10 Standby Gas Treatment System EXPLANATION:

This is an evolution that is periodically performed on shift. There are independent lineup's for venting the torus vs. the drywell air space. Venting the torus will have no effect on drywell air space pressure. Student misconceptions of the different venting flowpaths make all the options plau$jble.

CHOICE "A" - Correct CHOICE "B" - Incorrect CHOICE "C" - Incorrect CHOICE "D" - Incorrect 261000 SGTS A 1. Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including:

(CFR: 41.5/45.5)

A 1.02 Primary containment pressure. . . . .. . .................... 3.1 / 3.2 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-04, Obj. 8. Describe the operation of the Suppression Chamber to Drywell Vacuum breakers.

COG LEVEL: High Page 42 of 99

28. Unit Two has ~est-Qff-sitepower with DG3 and DG4 unavailable.

No electrical buses have been cross-tied.

Assuming normal alignment of UPS prior to the station blackout, the UPS primary inverter is currently being fed from DC Switchboard _ _ _ _ __

If the primary inverter fails, _ _ _ _~---

A'!'2A.

UPS loads will be de-energized ..

B. 2B.

UPS loads will be de-energized.

C. 2A.

UPS will auto transfer to an alternate source.

D.2B.

UPS will auto transfer to an alternate source.

REFERENCE:

SO-52 120 VAC Distribution and UPS EXPLANATION:

DC input to primary inverter is from Div. I DC (2A). With the STBY unit in Bypass Test (normal), ,If the primary inverter fails UPS loads will be de-energizea.Multiple UPS lineups are avaIlable dependent upon plant condition, making any of the answer options plausible.

CHOICE "A" - Correct Answer CHOICE "B" - Incorrect CHOICE "C" - Incorrect CHOICE "0" - Incorrect 262001 AC Electrical Distribution K3. Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: (CFR: 41.7 /45.4)

K3.04 Uninterruptible power supply .............................. 3.1 / 3.3 SOURCE: Bank LOI-CLS-LP-052-B*005 (1)

LESSON PLAN/OBJECTIVE:

CLS-LP-52, Obj. 9. Describe the effect that a loss or malfunction of the following will have on the UPS system: AC / DC Electrical distribution.

COG LEVEL: High

(

Page 43 of 99

29. Unit One is operating at full power with the following plant conditions:

DG2 Under clearance Suppression Pool 96° F due to HPCI Surveillance RHR B Loop in SPC (maximized cooling)

RHRSW B Loop in service NSW B pump in service CSW Band C pumps in service A Loss of Offsite Power (LOOP) occurs on both Units.

Which one of the following is-the impaet-e.f-.t-Re-b.QG.l2-GA BLoop of-RHR;-aAG-wI::l.Elt action should the RO take in accordance with OAOP-36.1, Loss of any 4160V Buses or 480V E-Buses? "

A. RHR and RHR SW pumps have lost power.

Crosstie E1 to E2.

B. RHR SW has lost its suction source.

Crosstie E5 to E6.

C~ Torus Cooling Valves, B RHR pump and B RHR SW pump have lost power.

Crosstie E2 to E4:*

D. Torus Cooling Valves, D RHR pump and D RHR SW pump have lost power.

Crosstie E6 to E8.

REFERENCE:

OAOP-36.1 Loss of Any 4160V Buses or 480V E-Buses SD-43 Service Water SD-17 Residual Heat Removal SD-50.1 4KV Distribution EXPLANATION: With DG2 under clearance it will de-energize on the loss of offsite power. both RHR and RHR SW pumps D lose power. B NSW pump loses power and the A pump will auto start. CSW pumps lose power due to the LOOP. RHR Loop B valves lose power.

CHOICE "A" Incorrect. Not all pumps have lost power, E1 and E2 cannot be crosstied procedurally.

CHOICE "B" Incorrect. B loop is normally cooled by NSW, 480 V busses are not crosstied unless unable to crosstie 4 kV.

CHOICE "C" correct answer.

CHOICE "D" Incorrect. 480 V busses are not crosstied unless unable to crosstie 4 kV.

Page 44 of 99

262001 AC Electrical Distribution A2. Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5/45.6)

A2.03 Loss of off-site power .................................. 3.9/4.3*

SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-50.1, Obj. 9. List the major equipmenVloads on each of the 4160 VAC buses.

COG LEVEL: High

(

Page 45 of 99

30. Unit Two is operating at 30% reactor power when a complete loss of UPS occurs?

Which one of the following describes how this loss will affect RFPT operation?

A. RTGB trip pushbutton function is lost.

B. overspeed trip circuit will lose power causing RFPT Trip.

C. vibration instrumentation will lose power causing RFPT Trip.

Dot RFPT electrical trip circuits will be powered from their redundant power supplies.

REFERENCE:

AOP-12 Loss of UPS 01-50.5 EXPLANATION:

RFPT trip circuits are powered from UPS with redundant power supplies from non-UPS 120VAC supplies.

The RFPT trip pushbutton is powered from 125 VDC.

CHOICE "A" - Incorrect. RFPT rip pushbutton powered from 125 VDC CHOICE liB" - Incorrect - Trip circuit will be powered from redundant source; no RFPT trip will occur CHOICE "C" - Incorrect. Trip circuit will be powered from redundant source; no RFPT trip will occur CHOICE liD" - Correct Answer 262002 UPS (AC/DC)

K1. Knowledge of the physical connections and/or cause effect relationships between UNINTERRUPTABLE POWER SUPPLY (A.C'!D.C.) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.02 RFPT Control .................................. 2.8/3.0 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-32.3, Obj. 2. State the electrical power supplies for the RFPT DCS.

COG LEVEL: Low Page 46 of 99

31. Which one of the following describes the effect that a complete loss of UPS will have on the Level Setpoint Adjustment and Level Setdown functions of the Digital Feedwater Level Control System controllers?

Level Setpoint adjustment is _ _ _ _ _ __

Level Setdown occur following a reactor scram.

A. available; will B. available; will not C. not available; will D~ not available; will not

REFERENCE:

SO-52 Section 4.2.1 Vital UPS Failure EXPLANATION:

A Loss of UPS will cause the RFPT controller screens to go blank. The backup DC power supplies will allow continued operation however, the operator will be unable to adjust level setpoint. Reactor Water level setdown will not occur in the event of a reactor scram.

CHOICE "A" - Incorrect. level setpoint adjustment is not available; level setdown will not occur CHOICE liB" - Incorrect. level setpoint adjustment is not available; CHOICE "C" - Incorrect. level setdown will not occur CHOICE "0" - Correct Answer 262002 UPS (AC/OC)

K3. Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C.lO.C.) will have on following:

(CFR: 41.7 /45.4)

K3.01 Water Level Control ......................3.1 /3.3 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-52, Obj. 8e. describe the effect that a loss or malfunction of the UPS system will have on plant operations, including the following: Feedwater level control.

COG LEVEL: Low Page 47 of 99

32. Which one of the following is the power supply to the Outboard MSIV's DC solenoids on Unit One?

A. Diy 1 Switchboard 21A.

B. Diy 2 Switchboard 22B.

c. Diy 1 Switchboard 1A.

D!' Diy 2 Switchboard 1B.

REFERENCE:

01-50.0 DC Load List, page 44 EXPLANATION:

Unit 1 Outboard MSIV DC solenoids are powered from Div.2 Switchboard 1B CHOICE "A" - Incorrect. Wrong Division of DC CHOICE "B" - Incorrect. Wrong switchboard, however 22B is a Unit 1 panel CHOICE "C" - Incorrect. Wrong Division of DC CHOICE "D" - Correct Answer c: 263000 DC Electrical Distribution K2. Knowledge of electrical power supplies to the following: (CFR: 41.7)

K2.01 Major D.C. loads ...................................... 3.1 /3.4 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-25, Obj. 5. List the power supplies (division and voltage) for the MSIV solenoids.

COG LEVEL: Low Page 48 of 99

33. Unit Two experiences a Loss of Off-Site Power (LOOP) with DG4 under clearance.

Which one of the following describes how the Nl,lclear Service Water (NSW) and Conventional Service Water (CSW) pumps will-respondas DG3 output breaker closes and* energizes bus E3? i A. NSW pump 2A and CSW pump 2A start immediately.

B. NSW pump 2A and CSW pump 2A start after a 5 second time delay.

C~ NSW pump 2A starts immediately and CSW pump 2A does not start.

D. NSW pump 2A starts after a 5 second time delay and CSW pump 2A does not start.

REFERENCE:

SD-43 Service Water, section 3.2.1 /3.2.2 EXPLANATION:

2A NSW pump and 2A CSW pump are both powered from emergency bus E3. On a LOOP they will loss poweX until bus E3 is reenergized from DG3. Immediately following reenergization of E3, 2A NSW will start.~ith a concurrent LOCA, a 5 second time delay exists. 2A CSW will remain off.

CHOICE "A" - Incorrect. CSW pump remains OFF CHOICE "B" - Correct Answer CHOICE "C" - Incorrect. CSW pump remains OFF, NSW pump starts immediately CHOICE "D" - Incorrect. NSW pump starts immediately 264000 EDGs K5. Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET) : (CFR: 41.5/45.3)

K5.06 Load sequencing ..................................... 3.4 / 3.5 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-39, Obj 8. Describe how an EBus will sequence load if the unit has a LOCA signal.

COG LEVEL: High Page 49 of 99

34. Unit Two is operating at rated power with the A SJAE train in service at Full Load.

A clearance tagging error results in the closure of the SJE-V15, Recombiner Preheater Steam Supply Valve followed by the following alarm:

Recombiner Inlet Temperature Low Which one of the following describes the effect these conditions will have on Main Condenser vacuum and downstream Hydrogen concentrations?

Main Condenser vacuum will - - - - - - - -

Hydrogen concentrations will _ _ _ _ _ __

A~ remain steady; increase B. remain steady; decrease C. degrade; increase D. degrade; decrease

REFERENCE:

SO-30 Condenser Air Removal and Off-Gas Recombiner System, fig. 30-4 APP-UA-44 (3-2) RECOM81NER INLET TEMP LOW EXPLANATION:

The closure of SJE-V15 will have no effect on operation of the SJAEs and no effect on condenser vacuum. The loss of the recombiner Preheater steam source and resultant low recombiner temperature will cause recombiner efficiency to drop, causing downstream hydrogen concentrations to rise.

CHOICE "A" - Correct Answer CHOICE "8" - Incorrect. H2 concentrations will increase CHOICE "C" - Incorrect. vacuum will remain steady CHOICE "0" - Incorrect. vacuum will remain steady; H2 concentrations will increase Page 50 of 99

271000 Offgas K3. Knowledge of the effect that a loss or malfunction of the OFFGAS SYSTEM will have on following:

(CFR: 41.5/45.3)

K3.01 Condenser vacuum. . . . . . . . . .. . ...................... 3.5/3.5 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-30, Obj. 11. Given the necessary plant conditions, describe the effect that a malfunction or loss of the CARlAOG system would have on the following: Main condenser Vacuum.

COG LEVEL: High

(

Page 51 of 99

35. Which one of the following identifies the power supplies for the Electric Driven F=ir$

Pump?

The normal power supply is from:

A. E2, with an automatic transfer to E4 on loss of power B. E4, with an automatic transfer to E2 on loss of power C~ E2, must be manually transfered to E4 on loss of power D. E4, must be manually transfered to E2 on loss of power

REFERENCE:

SD-41 Fire Protection System, section 2.1.3 Electric Fire Pump EXPLANATION:

The electric fire pump is normal powered from E2 with a manual transfer capability to E4. the transfer was designed to be an automatic transfer, but is disabled so that it has to be performed manually.

CHOICE "A" - Incorrect, see explanation.

CHOICE "B" - Incorrect, see explanation.

CHOICE "C" - Correct Answer CHOICE "D" - Incorrect, see explanation.

286000 Fire Protection K2. Knowledge of electrical power supplies to the following: (CFR: 41.7)

K2.02 Pumps. . . . . . . . . . . .. . ............................. 2.9/3.1 SOURCE: Bank LOI-CLS-LP-041 *11 B LESSON PLAN/OBJECTIVE:

CLS-LP-41, Obj. 11 b. Identify the distribution system which supplies power for the following components:

Motor driven fire pump.

COG LEVEL: Low Page 52 of 99

36. A plant transient and subsequent safety relief valve malfunction results in reactor steam dome pressure reaching 1300 psig.

Which one of the following describes the effect of the pressurization transient on the reactor pressure vessel?

A. Reactor pressure yessel design presslJ(e..ha~tnQtJ)ee~xce-adeg, and the Reactor Coolant System Safety Limit has been exceeded.

B. Reactor pressure vessel design pressure and the Reactor Coolant System Safety Limit have both been exceeded.

C. Neither reactor pressure vessel design pressure nor the Reactor Coolant System Safety Limit have been exceeded.

D'! Reactor pressure vessel design pressure has been exceeded, and the Reactor Coolant System Safety I::::imit has not been exceeded.

REFERENCE:

Tech Spec bases for Safety Limits EXPLANATION:

Per TS Bases, the RCL pressure safety limit is 1325 psig steam dome pressure and the reactor vessel design pressure is 1250 psig. 1325 psig steam dome corresponds to 1375 psig bottom head pressure which is 110% of the reactor design pressure. 110% of design pressure is th,e maximum pressure allowed by ASME standards.

CHOICE "A" - Incorrect, see explanation.

CHOICE "B" - Incorrect, see explanation.

CHOICE "C" - Correct Answer CHOICE "D" - Incorrect, see explanation.

290002 Reactor Vessel Internals K6. Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR VESSEL INTERNALS: (CFR: 41.7/45.7)

K6.06 Relief/safety valves ................................. 3.0/3.2 SOURCE: New LESSON PLAN/OBJECTIVE:

COG LEVEL: Low Page 53 of 99

37. Unit Two is operating at full power when the following indications are observed:

SJAE Trains Both in half load AOG System Outlet Flow 80 scfm and slowly rising Which one of the following is an action that needs to be taken based on the increasffig-off gas flow?

A'! Reduce power to maintain condenser vacuum.

B. Start the mechanical vacuum pump to-i*Aefeas~ondensef vacuum.

C. Place one SJAE Train in full load to handle the increased off gas flow.

D. Throttle open the SJAE Condensate Recirculation Valve, CO-FV-49, to increase S-JAE effeciency.

REFERENCE:

SD-30 pages 28-29 2APP-UA-48 5-3 EXPLANATION:

Increase in off gas flow is an indication of a loss of vacuum condition. So power should be reduced to maintain vacuum greater than 25 inches HG.

CHOICE "A" correct answer CHOICE "B" Starting a mechanical vacuum pump would help in removing air from the condenser except it is not allowed to be put into service with the unit at power.

CHOICE "C" Placing a SJAE train in full load would not help with the loss of condenser vacuum. This is an action in the AOP if a train is thought to be malfunctioning. High off gas flow is not a malfunction of the train.

CHOICE "0" At low power this is an option to increase the effeciency. At greater than 50% power this is manually isolated so as to have no effect on the system under these conditions. Action from the AOP.

295002 Loss of Main Condenser Vacuum AK1. Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM: (CFR: 41.8 TO 41.10)

AK1.04 Increased Offgas Flow .......................... 3.0/3.3 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-30, Obj. 11. Given the necessary plant conditions, describe the effect that a malfunction or loss of the CARlAOG system would have on the following: Main condenser Vacuum.

COG LEVEL: Higher order Page 54 of 99

38. A DBA LQCA occurs on Unit One concurrent with a Loss of Offsite Power on both Units.

A 4160 VAC bus E3 lockout occurs due to protective relay actuation.

What is the response of the Unit One Low Pressure ECCS systems?

A'! Injection from both loops of Core Spray and 2 RHR pumps running and injecting in only one loop.

B. Injection of only one loop of Core Spray and 2 RHR pumps running and injection in only one loop.

C. Injection from both loops of Core Spray and 3 RHR pumps running and injection in both loops.

D. Injection of only one loop of Core Spray and 3 RHR pumps running and injection in both loops.

REFERENCE:

Station Load lists EXPLANATION:

4 KV Bus E3 supplies power to bus E7 which supplies power to RHR Loop A injection valve F017A With this valve de-energized only loop B will inject. Both Core Spray loops are powered from Unit 1 buses E1 and E2.

CHOICE "A" Is incorrect because both loops of core spray have power from buses E1 and E2. Possible distractor if the examinee is thinking Unit Two.

CHOICE "B" Is incorrect because both loops of core spray have power from buses E1 and E2 and the Unit 1 A side RHR injection valve is closed with a loss of power. Possible distractor if the examinee is thinking Unit Two and does not apply the power supply to the injection valve.

CHOICE "C" Correct Answer.

CHOICE "0" Is incorrect because the Unit 1 A side RHR injection valve is closed with a loss of power.

295003 Partial or Complete Loss of AC. Power AK1. Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF AC. POWER: (CFR: 41.8 to 41.10)

AK1.03 Under voltage/degraded voltage effects on electrical loads ............... 2.9/3.2 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-17 Obj. 18. Given plant conditions, determine how the following will affect the RHR system: Loss of AC Power.

COG LEVEL: High Page 55 of 99

39. Unit Two is operating at rated power when a loss of DC Distribution panel12A occurs.

Which one of the following is the effect of a loss of DC Distribution Panel 12A?

The Alternate Rod Insertion System CARl) will:

A. not auto initiate but can be manually initiated.

B:' not auto initiate and cannot be manually initiated.

C. initiate automatically or can be initiated manually.

D. initiate automatically but cannot be manually initiated.

REFERENCE:

OAOP-39, Attachment 3.

EXPLANATION:

As stated in Attachment 3 of OAOP-39, for a loss of 12A ARI will have no manual or auto initiation.

CHOICE "A" ARI will not operate manually.

CHOICE "B" Correct answer.

CHOICE "C" ARI will not auto initiate.

CHOICE "0" ARI will not operate manually.

295004 Partial or Complete Loss of D.C. Power AK1. Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: (CFR: 41.8 to 41.10)

AK1.02 Redundant D.C. power supplies: Plant-Specific ........ 3.2/3.4 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-302-G Obj. 2, List the automatic actions expected to occur in accordance with the following AOP's: OAOP-39, Loss of DC Power.

COG LEVEL: Higher Order Page 56 of 99

40. Unit Two is operating at full power.

Which one of the following state the reason that the Turbine Bypass Valves will open following a main turbine trip signal?

A. Prevent overspeeding of the main turbine during coastdown.

B. Prevent over pressurization of the MSR cross-over piping.

C~ Prevent over pressurization of the reactor vessel.

D. Prevent damage to the Non-Return valves.

REFERENCE:

SD-26 EXPLANATION:

Bypass valves open to prevent overpressurization of the reactor when the turbine control valves close on a turbine trip signal.

CHOICE "A" The intermediate stop valves close on a turbine trip to prevent overspeeding the main turbine. Extraction steam will be lost following a turbine trip and bypass steam is directed to the main condenser.

CHOICE "B" over pressurization is a function of the cross over relief valves.

CHOICE "C" correct answer CHOICE "D" Non-returns will close to prevent flashing of steam to cause overspeeding of the turbine.

295005 Main Turbine Trip AK3. Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP: (CFR: 41.5/45.6)

AK3.07 Bypass valve operation ............................... 3.8 / 3.8 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-26 Obj. 4f, Describe the operation of the following Main Turbine related components: Bypass Valves.

COG LEVEL: low/Fund Page 57 of 99

41. The EOP Users Guide defines what the Control Operator Immediate Operator Actions are and the setpoints for each of the actions.

Which one of the following Control Operator Immediate Actions have different setpoints between Unit One and Unit Two?

A. Tripping of the main turbine.

B. Tripping of the first feed pump.

C. Master level controller setpoint setdown.

D~ Placing the reactor mode switch to Shutdown.

REFERENCE:

OEOP-01-UG (pg. 22)

EXPLANATION:

The mode switch on Unit Two is not placed to shutdown until steam flow is less than 3 Mlbs/hr. This requirement does not exist on Unit One.

CHOICE "A" When APRM's are downscale <<2%) the main turbine is tripped. (Same on both units)

CHOICE "B" If two feed pumps are running, and reactor water level is above +160 inches, then trip one feed pump. (Same on both units)

CHOICE "G" Ensure the master reactor level controller setpoint is +170 inches. (Same on both units)

CHOICE "D" Unit One - Place the reactor mode switch to Shutdown. Unit Two - After steam flow is less than 3 Mlbs/hr, place the reactor mode switch to Shutdown.

295006 SCRAM 2.2.3 (multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5/41.6 141.7 I 41.10 I 45.12)

IMPORTANCE RO 3.8 SRO 3.9 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-300-C Obj. 2, List the immediate operator actions for a reactor scram.

COG LEVEL: fund Page 58 of 99

42. Unit One was operating at full power when a scram ocurred due to a loss of drywell cooling with the following plant conditions.

Reactor water level 155 inches (slowly lowering)

Drywell pressure 2.1 psig (slowly rising)

High water Trip A amber light Out High water Trip B amber light Lit High water Trip C amber light Lit Which one of the following is the status of the reactor feed pumps and HPCI system?

The Reactor feed pump turbines:

A. are running and HPCI is injecting to the vessel.

B. are tripped but HPCI is injecting to the vessel.

C. are running but HPCI is tripped.

D~ and HPCI are both tripped.

REFERENCE:

SO-19 page 33 / SO-32 EXPLANATION:

The reactor feed pumps and HPCI will trip on a two out of three logic. The high water trip amber lights feed into the RFP trip logic and provide indication that a high level condition exists. With drywell pressure greater than 2 psig HPCI should have auto started, but it had tripped on high level and will not restart automatically until LL2, with level lowering is also an indication that it is tripped. These must be manually reset to restart the pumps with the exception of HPCI which will auto restart if level is below LL2.

CHOICE "A" Feed pumps and HPCI would be tripped on the two out of three logic. Hi OW pressure does not auto reset the trip logic, LL2 would.

CHOICE "8" HPCI would be tripped. Hi OW pressure does not auto reset the trip logic, LL2 would.

CHOICE "C" Reactor feed pumps would be tripped on the two out of three logic.

CHOICE "0" Correct answer.

Page 59 of 62

295008 High Reactor Water Level AK2. Knowledge of the interrelations between HIGH REACTOR WATER LEVEL and the following: (CFR:

41.7/45.8)

AK2.03 Reactor water level control ........................... 3.6/3.7 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-19 Obj 16a, Given plant conditions, determine if the following actions should occur: HPCI Turbine automatic trip.

COG LEVEL: Higher Order Page 60 of 62

43. Unit One is at rated power when a scram signal is received.

Reactor water level drops and RWCU isolates.

Which one of the following listed RTGB level indicators will be available for the RO to use to verify that water level is now rising?

A. Fuel Zone instruments only B. Wide range instruments only C~ Fuel Zone and Wide Range instruments D. Fuel zone and Wide Range instruments are not on scale.

REFERENCE:

SD-01.2 EXPLANATION:

RWCU isolates at LL2 (105 inches) with the Wide Range (N026A & B) indications from 0-210 inches and the Fuel Zone (N036 & 37) indicators onscale due to the Recirc pumps tripping at LL2.

CHOICE "A" Wide range indicators have a scale from 0-210.

CHOICE "B" Fuel Zone indicators are on scale since the Recirc pumps have tripped.

CHOICE "C" Correct answer.

CHOICE "D" both indicators are on scale.

295009 Low Reactor Water Level AK2. Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following: (CFR:

41.7/45.8)

AK2.01 Reactor water level indication ........................ 3.9/ 4.0 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-01.2 Obj. 4a, List the systems which recieve input from the Vessel Instrumentation system for the following: Level signal.

COG LEVEL: Higher Order Page 60 of 99

44. Unit Two was operating at 100% power when a large break LOCA occurred in containment.

Which one of the following describes what will happen with the vessel level instrument legs?

A~ The compensated level instrument legs are at a higher temperature than the uncompensated legs, the compensated level instrument legs will boil first.

B. The uncompensated level instrument legs are at a higher temperature than the compensated legs, the uncompensated level instrument legs will boil first.

C. Both instrument legs are at the same temperature. There is a thermal time constant of approximately 4 to 6 minutes for the uncompensated legs, the compensated level instrument legs will boil first.

D. Both instrument legs are at the same temperature. There is a thermal time constant of approximately 4 to 6 minutes for the compensated legs, the uncompensated level instrument legs will boil first.

REFERENCE:

SD-01.2 page 11-12 EXPLANATION:

If an accident should occur that causes drywell temperature to increase and reactor pressure to decrease, boiling can take place in the level instrument legs. The question is; which arrangement, compensated or uncompensated, will boiling most likely occur in first? Since the compensated level instrument legs are at a higher temperature than the uncompensated legs, they will reach a higher temperature first. It should be pointed out that the legs do not heat up to drywell temperature immediately, as there is a thermal time constant that can be 4 to 6 minutes. A time constant is the amount of time required for a signal or a parameter to reach 63.21 % of the final value. After 5 time constants the signal is > 99% of the final value.

A 4 to 6 minute time constant means that it can take from 20 to 30 minutes for the reference legs to heat up to drywell temperature.

CHOICE "A" Correct answer.

CHOICE "B" The compensated legs are at a higher temperature than the uncompensated legs.

CHOICE "C" Both instrument legs are not at the same temperature.

CHOICE "D" Both instrument legs are not at the same temperature.

Page 61 of 99

295010 High Drywell Pressure AK1. Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: (CFR: 41.8 to 41.10)

AK1.03 Temperature increases ................................. 3.2/3.4 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-01.2 Obj. 5C, Explain the effect that the following will have on reactor vessel and/or pressure indications: High containment (primary and secondary) temperatures.

COG LEVEL: Fund Page 62 of 99

45. A turbine trip and reactor scram occurs on Unit One. After completing the immediate operator actions associated with the scram the RO notes that the RWM Confirm Shutdown screen is reading:

All Rods In: NO Shutdown: YES Rods Not Full In: 005 Based on the RWM Shutdown confirmation criteria, which one of the following was determined to be the position of the control rods that were not fully inserted?

The control rods are inserted at or beyond position:

A'! 02.

B. 04.

C. 02, with not more than one rod withdrawn past position 02.

D. 04, with not more than one rod withdrawn past position 04.

REFERENCE:

SD-07.1 page 53 Criteria for reactor shutdown is defined as: No rod is withdrawn beyond position N, where N is selectable as a set parameter variable. The value of N is defined in the current Cycle Management Report. (This value is 02).

EXPLANATION:

The RWM screen indicated that all rods are not inserted (5 rods) but does indicate that the unit is shutdown. This signifies that all of the rods are not past the position of 02, otherwise the screen would indicate the the unit was not shutdown.

CHOICE "A" Correct answer CHOICE "8" If any of the rods were at position 04 then the shutdown criteria would be NO. Recent change with power uprate from 04 to 02 for shutdown.

CHOICE "c" One rod could be at any position based on SDM, but not if 4 rods were at position 02 would you meet the shutdown criteria.

CHOICE "D" One rod could be at any position based on SDM, but not if 4 rods were at position 04 or 02 would you meet the shutdown criteria.

Page 63 of 99

295015 Incomplete SCRAM AA2. Ability to determine and/or interpret the following as they apply to INCOMPLETE SCRAM: (CFR:

41.10/43.5/45.13)

AA2.02 Control rod position .................................. 4.1 * / 4.2*

SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-07.1 Obj. 12, Describe the conditions necessary to cause the Shutdown Confirmation screen to display YES for All Rods In.

COG LEVEL: fund Page 64 of 99

46. While performing OAOP-32.0, Plant Shutdown from Outside Control Room, the following reactor pressure readings were recorded at the indicated times:

1200 1000 psig 1300 425 psig 1400 100 psig 1500 25 psig Based on the information given, which one of the following statements is correct concerning the reactor cooldown rate?

Technical Specification limits:

A. have not been exceeded.

B. were exceeded between 1200 and 1300.

C!' were exceeded between 1300 and 1400.

D. were exceeded between 1400 and 1500.

REFERENCE:

OAOP-32 Steam Tables can be used as reference.

EXPLANATION:

Tech Spec requires cooldown at <100 deg F ,cooldown from 1000-425 is 95 deg, from 425-100 is 115 deg and 100-25 is 90 deg per RPV saturation curve of OAOP-32.0.

CHOICE "A" The 100°F cool down limit was exceeded between 1300 and 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.

CHOICE "B" The cooldown between this time period is 95°F.

CHOICE "C" The cooldown between this time period is 115°F.

CHOICE "0" The cooldown between this time period is 90°F.

295016 Control Room Abandonment AA1. Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:

(CFR: 41.7 / 45.6)

AA1.08 Reactor pressure ...................................... 4.0/4.0 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-302-E Obj. 4, Given plant conditions (past and present) and OAOP-32, Plant Shutdown from Outside the Control Room, plot cooldown rate.

COG LEVEL: Higher order Page 65 of 67

47. Unit Two is operating at rated power when a loss of TBCCW occurs to the Recirculation MG Sets.

Which one of the following describes how this loss of cooling will affect the Recirculation MG Sets?

High lube oil temperature of:

A. 190 0 F will lock the scoop tube only.

B. 1900 F will trip the drive motor breaker and lock the scoop tube.

C. 210 0 F will lock the scoop tube only.

D~ 210 0 F will trip the drive motor breaker and lock the scoop tube.

REFERENCE:

SO-02 page 33-34 Breaker trip SO-02 page 35 scoop tube lock EXPLANATION:

Loss of cooling to the Recirculation MG Set will cause the temperature to rise and the drive motor breaker to trip and the scoop tube will lock at 210 0 F. The 1900 F is the hi temperature alarm setpoint.

CHOICE "A" The scoop tube will not lock until 210 F. 190 F is the hi temperature alarm setpoint.

0 0 CHOICE "B" The scoop tube will not lock and the drive motor will not trip until 210 0 F. 190 0 F is the hi temperature alarm setpoint.

CHOICE "C" At 210 F the drive motor breaker will also trip.

0 CHOICE "0" Correct answer.

295018 Partial or Complete Loss of Component Cooling Water AK1. Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

(CFR: 41.8 to 41.10)

AK1.01 Effects on component/system operations ................ 3.5/3.6 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-44 Obj 8a, Describe the effects that a loss or malfunction to the TBCCW system would have on the following: Reactor Recirculation System.

COG LEVEL: memory Page 66 of 99

48. Which one of the following is the reason that Backup Nitrogen System would initiate?

To supply an independent, safety-related pneumatic source to the _ _ _ _ _ __

during conditions when the PNS is isolated from the Drywell.

A. Inboard MSIV's, the SRV Accumulators, and the Hardened Wetwell Vent Isolation Valves B. Inboard MSIV's, the Suppression Chamber to Drywell Vacuum Breaker Isolation Valves, and the Hardened Wetwell Vent Isolation Valves C~ SRV Accumulators, the Reactor Building to Suppression Chamber Vacuum Breaker Isolation Valves, and the Hardened Wetwell Vent Isolation Valves D. SRV Accumulators, the Reactor Building to Suppression Chamber Vacuum Breaker Isolation Valves, and the Suppression Chamber to Drywell Vacuum Breaker Isolation Valves

REFERENCE:

SO-46 page 8 EXPLANATION:

Following a core Spray LOCA and containment isolation signal the PNS supply to the OW will be isolated.

The Backup Nitrogen System would supply pneumatics to SRV Accumulators, the Reactor Building to Suppression Chamber Vacuum Breaker Isolation Valves, and the Hardened Wetwell Vent Isolation Valves CHOICE "A" does not supply the inboard MSIV's CHOICE "B" does not supply the inboard MSIV's or the Suppression Chamber to Orywell Vacuum Breaker Isolation Valves CHOICE "C" Correct answer.

CHOICE "0" does not supply the Suppression Chamber to Orywell Vacuum Breaker Isolation Valves 295019 Partial or Complete Loss of Instrument Air AK3. Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR: 41.5/45.6)

AK3.01 Backup air system supply: Plant-Specific ............. 3.3/3.4 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-46 Obj. 6, List the pneumatic loads supplied by the Nitrogen Backup System.

COG LEVEL: memory Page 67 of 99

49. Unit One shutdown is in progress with the following plant conditions:

RWCU is in service.

Recirc Pumps are tripped.

SDC has been lost.

Natural circulation has been established.

Feed and bleed has been established.

Reactor Coolant Temperature is 190 0 F and lowering slowly.

Under the above conditions, in accordance with 1PT-01.7, Heatup/Cooldown Monitoring, which one of the following is the preferred indication to use to determine vessel metal temperature response?

A. Recirc Suction Temperature B. Bottom Head Metal Temperature

c. Reactor Steam Dome Temperature D~ Vessel Bottom Drain Coolant Temperature

REFERENCE:

1PT-01.7, Heatup/Cooldown Monitoring EXPLANATION:

During cooldown, Bottom Head coolant temperature is the preferred source due to coolant temperature response leading vessel metal temperature response. If RWCU flow exists then use vessel bottom drain coolant temperature. If RWCU does not exist and recirc pumps are running then use recirc pump suction temperature. If RWCU and Recirc are not running then use bottom head metal temperature. Steam dome temperature would be used to determine coolant temperature if psat >212° F.

CHOICE "A" If RWCU does not exist and recirc pumps are running then use recirc pump suction temperature CHOICE "B" If RWCU and Recirc are not running then use bottom head metal temperature.

CHOICE "C" Steam dome temperature would be used to determine coolant temperature if psat >212° F.

CHOICE "0" Correct answer 295021 Loss of Shutdown Cooling AA2. Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING

(CFR: 41.10 /43.5/45.13)

AA2.05 Reactor vessel metal temperature ...................... 3.4 / 3.5 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-307-B, Obj. 1G - Given plant conditions, monitor cooldown rate per PT-01.7.

COG LEVEL: Higher Order Page 68 of 99

50. Unit One has entered the EOP's due to a LOCA with the following primary containment conditions:

Drywell Pressure 5 psig and rising What is the first Drywell pressure that Drywell Integrity can not be assured?

A. 11.5 psig

8. 30 psig C. 49.4 psig D!' 62 psig

REFERENCE:

SO-04 page 7/8 EXPLANATION: The calculated peak containment pressure is 49.4 psig which is increased by 25% to establish the drywell design pressure of 62 psig.

CHOICE "A" Incorrect. this is the pressure that sprays are to be initiated by.

CHOICE "B" Incorrect. this is the pressure that is required to isolate CAC-4409 and 4410 in accordance with PCCP.

CHOICE "C" Incorrect. This is the calculated maximum drywell pressure.

CHOICE "0" Correct answer.

295024 High Orywell Pressure EK1. Knowledge of the operational implications of the following concepts as they apply to HIGH ORYWELL PRESSURE: (CFR: 41.8 to 41.10)

EK1.01 Orywell integrity: Plant-Specific .................... 4.1 /4.2*

SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-04, Obj. 2. State the PC design bases, including temperature and pressure limits for the OE and Suppression Chamber, as given in the FSAR.

COG LEVEL: low Page 69 of 72

51. Unit Two is operating at rated power with EHC in the following alignment:

PAM Pressure 956 psig Pressure Regulator A In control Pressure Regulator B In standby (3 psig bias)

Max Combined Flow Limiter 100%

Load Limit 100%

An operator realizes that the Max Combined Flow Limiter setpoint should be at 110%.

The operator turns the setpoint dial the wrong direction.

The Max Combined Flow Limiter is set for 90%.

Which one of the following is the expected plant response?

A. Bypass valves will open and Pressure Regulator B will control pressure at 959 psig.

B. Bypass valves will open and Pressure Regulator A will control pressure at 953 psig.

C. Reactor pressure will decrease and a scram will occur on a Group I Isolation.

D~ Reactor pressure will increase and a scram will occur on high pressure.

REFERENCE:

( SD-26.3 page 38 EXPLANATION:

The Max combined flow limiter will limit the total steam flow. This will cause steam flow to be restricted, reactor pressure to increase, and reactor power to increase due to void concentration. The result will be a reactor scram on either high pressure or high flux.

CHOICE "A" This would be correct for a failure of Pressure Regulator A.

CHOICE "B" A reduction of 10% steam flow would be the equivalent of a 3# drop in pressure as the pressure gain unit converts 1 psid to 3.33% steam flow.

CHOICE "C" This would be correct response for a failure of the pressure regulator in the high direction.

CHOICE "D" Correct Answer.

Page 70 of 99

295025 High Reactor Pressure EK2. Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: (CFR:

41.7/45.8)

EK2.08 Reactor/turbine pressure regulating system: Plant- Specific ......... 3.7/3.7 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-26.3 Obj. 9b - Given plant conditions, including manipulation of one of the following EHC control or parameter changes, predict the expected response of the main turbine and/or reactor protection system: max Combined Flow Limit potentiometer.

COG LEVEL: Higher Order Page 71 of 99

52. Unit One failed to scram with the following plant conditions:

Reactor Power 3%

RPV Water Level -55 inches (N036)

RPV Pressure 800 psig Suppression Pool 115 0 F Which one of the following actions is required to place suppression pool cooling in service?

A. By overriding the RHR SW Pump LOCA trip signal and then placing the Think Switch to Manual only.

B. By bypassing the 2/3rd core height interlock and then overriding the RHR SW Pump LOCA trip signal only.

C. By overriding the RHR SW Pump LOCA trip signal, placing the Think Switch to Manual, and then bypassing the 2/3rd core height interlock.

D~ By bypassing the 2/3rd core height interlock, overriding the RHR SW Pump LOCA trip signal, and then placing the Think Switch to Manual.

REFERENCE:

SD-17 page 53 and figure 12 (page 112)

EXPLANATION:

LOCA signal is sealed in due to being less than LL3 (45 inches) RPV water level is less than 2/3rd core height (-47 inches) therefore the keylock switch and then the Think switch is required (sequencing is essential). The RHR SW pumps tripped on LL3 and can be overriden anytime (no sequence required).

CHOICE "A" The 2/3rd core height must also be overriden.

CHOICE "B" The Think Switch must also be placed in Manual.

CHOICE "C" The sequence of the Think switch has to be after the 2/3rd core height interlock.

CHOICE "D" Correct answer.

295026 Suppression Pool High Water Temperature EA1. Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.7/45.6)

EA1.01 Suppression pool cooling .............................. 4.1 /4.1 SOURCE: bank LESSON PLAN/OBJECTIVE:

CLS-LP-17 Obj 9, Given an RHR pump or valve, list the interlocks, permissives and/or automatic actions associated with the RHR pump or valve, including setpoints.

COG LEVEL: higher order Page 72 of 99

53. Which one of the following colors on the SPDS display for Suppression Pool Temperature would indicate that the Primary Containment Control Procedure would need to be entered?

A~ Red B. Cyan C. Yellow D. Magenta

REFERENCE:

SD-60 pg 20 /101 EXPLANATION:

SPDS display will typically be green, when the temperature is >92 and <95 the indication will turn yellow and when it is >95 it will turn red which is an entry condition to PCCP.

CHOICE "A" Correct answer. (SD-60 page 101)

CHOICE "B" Cyan is used to indicate that the data is not validated.

CHOICE "C" Torus temperature changes to yellow when the temperature is between 92 and 95, which is not an entry condition for PCCP. At 95 it turns red. (SD-60 page 101)

( CHOICE "D" Magenta indicates that the data is bad or not measured.

f 295027 High Containment Temperature (Mark III Containment Only)

EK2. Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following: (CFR: 41.7/45.8)

EK2.04 SPDS/ERIS/CRIDS/GDS: Mark-ilL ....................... 2.6/3.2 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-60 Obj. 4a, Describe the methods used to do the following on the ERFIS/SPDS Computer:

Evaluate EOP entry conditions.

COG LEVEL: memory Page 73 of 99

54. Conditions on Unit Two have degraded to where the Drywell Air Temperature is 340 0 F.

Which one of the following identifies the component that is affected and the concern with this temperature?

A. Inboard MSIV's Inability to fully seat the valves B:' SRV solenoids equipment environmental qualification C. Torus to Drywell Vacuum Breakers downcomer pipe chugging is likely to occur D. CAG 4409 and 4410 Hydrogen Analyzers preclude damage to pumps and subsequent release to secondary containment

REFERENCE:

001-37.8 page 22 EXPLANATION:

From the Bases document: Temperature should not be allowed to exceed the SRV maximum qualification temperature of 340 F.

0 CHOICE "A" MSIV's are not a zero leakage isolation point, so even without the high temperature there will be leakage.

CHOICE "B" Correct answer CHOICE "C" chugging is not based on temperature.

CHOICE "0" this is the operating philosophy to transfer the heat to the torus so as not to challenge the containment.

295028 High Drywell Temperature EK1. Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: (CFR: 41.8 to 41.10)

EK1.02 Equipment environmental qualification ................. 2.9/3.1 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-302L Obj. 4h, State the effect on Primary Containment if the following limits are exceeded:

Drywell Design Temperature Limit.

COG LEVEL: higher order Page 74 of 99

55. The level in the suppression pool is -30 inches and lowering.

Which one of. the following is the highest suppression pool level that a manual reactor scram must be inserted if suppression pool level continues to lower in accordance with the Primary Containment Control Procedure?

A. -31 inches B~ -5.5 feet C. -6.5 feet D. -7.16 feet

REFERENCE:

01-37.S page 46 EXPLANATION:

A manual scram has to be inserted before level drops below the downcomer vent openings.

The reactor is not permitted to remain at pressure if suppression of steam discharged from the reactor cannot be assured.

CHOICE "A" This is the enter condition for PCCP.

CHOICE "B" correct answer CHOICE "C" Must secure HPCI irrespective of adequate core cooling at this level.

CHOICE "D" Actual level of the HPCI discharge sparger.

295030 Low Suppression Pool Water Level 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5/43.5/45.12/45.13)

IMPORTANCE RO 4.4 SRO 4.7 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-300L Obj Sa, Given the PCCP and plant conditions, determine if the following actions are required: Manual Reactor Scram COG LEVEL: memory Page 75 of 99

56. During a low reactor water level emergency on Unit One, the Reactor Vessel Control Procedure directs the operator to enter the Steam Cooling Procedure.

Which one of the following describes the reason Steam Cooling Procedure is performed?

The Steam Cooling Procedure utilizes steam cooling heat transfer:

A. with injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed 1500°F.

B. with injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed 1800°F.

C. without injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed 1500°F.

D~ without injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed 1800°F.

Reference:

001-37.7 Section 2.0 overview and step 017 basis Explanation: Steam Cooling is entered when level drops below the minimum steam cooling reactor water level (LL4) and no injection sources are available. LL4 calculations are based on peak clad temperature of 1S00°F. Steam cooling is meant to delay emergency depressurization with no injection sources until peak clad temperature reaches 1800°F, the basis for the minimum zero injection reactor water level or LLS. Note that if entry into steam cooling is required, peak clad temperature has already reached 1S00°F by definition of LL4 Choice A is incorrect but plausible since this would be correct for LL4 providing adequate core cooling.

LL4 is defined as steam cooling with injection Choice B is incorrect because steam cooling is without injection but plausible since LLS allows peak clad temperature to rise to 1800°F Choice C is incorrect because peak clad temperature can rise to 1800°F but plausible since LLS calculations are based on zero injection sources Choice D is correct 29S031 Reactor Low Water Level EK3. Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL: (CFR: 41.S/4S.6)

EK3.04 Steam cooling ......................................... 4.0 / 4.3*

SOURCE: 08 NRC Exam LESSON PLAN/OBJECTIVE:

CLS-LP-300-G /Objective 1,11 COG LEVEL: LOW Page 76 of 99

57. Secondary Containment Control Procedure requires Emergency Depressurization if two or more areas exceed the Maximum Safe Operating Temperature and a primary system is discharging reactor coolant into secondary containment.

Which one of the following statements explain the reason for this action?

A. The rise in secondary containment parameters indicate a wide-spread problem which may pose a potential threat to secondary containment integrity or preclude personnel access required for the safe operation of the plant.

B. The rise in secondary containment parameters indicate substantial degradation of the primary system and may lead to fuel failure if the leaks are not isolated.

C~ The rise in secondary containment parameters indicate a wide-spread problem which may pose a direct and immediate threat to secondary containment integrity or equipment located in secondary containment.

D. The rise in secondary containment parameters indicate substantial degradation of the primary system and emergency depressurization effectively isolates the leak.

REFERENCE:

001-37.9 page 6, 37 EXPLANATION:

The MSOT values are the area temperatures above which equipment necessary for the safe shutdown of the plant will fail. These area temperatures are utilized in establishing the conditions which reactor depressurization is required. The criteria of more than one area specified in this step identifies the rise in reactor building parameters as a wide spread problem which may pose a direct and immediate threat to secondary containment integrity, equipment located in the RB, and continued safe operation of the plant.

CHOICE "A" Incorrect since condition pose a DIRECT threat to containment, not an INDIRECT threat.

CHOICE "B" Incorrect since this condition does not indicate substantial primary system degredation.

CHOICE "C" Correct answer CHOICE "D" Incorrect since this condition does not indicate substantial primary system degredation.

295032 High Secondary Containment Area Temperature EK3. Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: (CFR: 41.5/45.6)

EK3.01 Emergency/normal depressurization ..................... 3.5/3.8 SOURCE: bank LESSON PLAN/OBJECTIVE:

CLS-LP-300-M Obj. 13a, Given plant conditions and the SCCP, determine the required actions if the following limits are exceeded: Maximum Safe operating values with a primary system discharging into secondary containment.

COG LEVEL: memory Page 77 of 99

58. Unit Two is in Mode 1 with preparations in progress for a refueling outage.

Refuel bridge testing in progress Drywell purge is in progress A test weight is dropped onto the Spent Fuel Pool which resulted in the following conditions:

Refuel Floor Area Radiation Monitors in alarm Refueling Platform Radiation Monitor 120 mr/hr RB Ventilation Exhaust Plenum Radiation Monitor 3 mr/hr Which one of the following describes the status of the RB Ventilation System?

A. RB Ventilation has isolated.

Drywell Purge and Vent valves are open.

B. RB Ventilation has isolated.

Drywell Purge and Vent valves are closed.

C~ RB Ventilation has not isolated.

Drywell Purge and Vent valves are open.

D. RB Ventilation has not isolated.

Drywell Purge and Vent valves are closed.

REFERENCE:

APP UA-3 3-5, Process Rx Bldg Vent Rad Hi Hi 3-7, Area Rad Refuel Floor High 4-5, Process Rx Bldg Vent Rad Hi EXPLANATION:

RB Vent will trip and isolate at 4 mr/hr in the RB and will also close the OW vent and purge valves. Hi Refuel floor rad does not result in an isolation signal.

CHOICE "A" RB vent has not isolated yet.

CHOICE "B" RB ventilation has not isolated and OW purge and vent valves are open.

CHOICE "C" correct answer CHOICE "0" OW purge and vent valves are open.

Page 78 of 99

295034 Secondary Containment Ventilation High Radiation EA1. Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: (CFR: 41.7/45.6)

EA1.03 Secondary containment ventilation ..................... 4.0 / 3.9 SOURCE: bank LESSON PLAN/OBJECTIVE:

CLS-LP-37.1 Obj. 8h, State how the RB Ventilation is affected by the following: High Area Radiation.

COG LEVEL: higher order Page 79 of 99

59. An ATWS has occurred on Unit One with the following plant conditions:

Both SLC pumps have been started.

Instrument/Service Air system has failed.

Which one of the following methods is available to determine level in the SLC Tank?

A. Direct the AO to valve in the local sight glass to obtain the level.

B. Have the AO read the level gauge on the local instrument rack.

C. Use the indication on the Level/Power Control ERFIS Screen.

D~ Direct the AO to measure the distance from the surface of the liquid to the top of the SLC Tank.

REFERENCE:

1OP-OS Section 8.6, Manual Volume Determination EXPLANATION:

Without the instrument air system the level indicator will fail downscale, no dp to measure.

The operating procedure has a section to determine the volume by measuring the air gap in the tank and comparing that to a graph to determine how much volume is left in the tank.

CHOICE "A" The main tank does not have a local sight glass, but the test tank does.

CHOICE "B" The local guage will also be failed downscale.

CHOICE "C" The input to ERFIS is from the control room indicator which is failed downscale.

CHOICE "0" correct answer 29S037 SCRAM Condition Present and Reactor Power Above APRM Downscale or unknown EA2. Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.10/ 43.S /4S.13)

EA2.03 SBLC tank leveL ...................................... 4.3* / 4.4*

SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-OS Obj 8g, Given plant conditions determine the effect that the following will have on the SLC System: Loss of plant air system.

COG LEVEL: higher order Page 80 of 99

60. Unit Two is operating under accident conditions with the following plant conditions due to a steam leak on HPCI:

Reactor Water Level -20 inches Reactor Pressure 900 psig Injection sources available HPClonly Offsite Release Alert declared HPCI Area Temperatures All <140 0 F Suppression Pool Temperature 1300 F Concerning HPCI operation in accordance with RRCP, which one of the following is the action that should be taken and why?

A'I HPCI should be left running It is required to be operated by the EOP's B. HPCI should be isolated It should have isolated on area high temperature C. HPCI should be isolated To isolate the primary system that is discharging D. HPCI should be isolated To prevent damage to the HPCI pump due to high suppression pool temperatures

REFERENCE:

001-37.10 page16 EXPLANATION:

RRCP normally has the operators isolate a primary system discharging except if it is needed to maintain adequate core cooling. with level below top of active fuel and required for EOP's this is the case. If there was a valid PCIS signal then this should not prevent the operator from making sure that the isolation occurs.

CHOICE "A" correct answer CHOICE "S" area temperature isolation would be at 165 F 0 CHOICE "C" IF HPCI was not needed for adequate core cooling this would be correct CHOICE "D" pump damage could occur at greater than 140 F 0 Page 81 of 99

295038 High Off-Site Release Rate EK3. Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: (CFR: 41.5/45.6)

EK3.02 System isolations ..................................... 3.9 /4.2 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-300N, Obj. 3. describe the conditions under which a system that is the source of a radioactive release is not permitted to be isolated.

COG LEVEL: high Page 82 of 99

61. During normal full power operation of Unit Two the following alarms and indications are noted:

Air Compressor D Trip alarm Sealed In Air Compressor 2B Under Clearance Service Air Press Low alarm Sealed In Instrument Air header pressure 100 psig Per the direction of OAOP-20, Pneumatic System Failures, which one of the following actions should be taken?

The operator should verify:

A. Reactor building standby air compressors have started.

B. Backup nitrogen rack isolation valves PV-5481 and 5482, have automatically opened.

C~ Service air isolation valves, PV-706-1 and PV-706-2, have automatically closed.

D. Service air dryer bypass pressure control valve, PV-5067 has automatically opened.

REFERENCE:

AOP-20 Pneumatic System Failures EXPLANATION:

As service/instrument air pressures lower, a series of events occurs.

105# SA - Service Air Isolation Vlvs 706-1 &2 auto close.

98# SA - Service Air Dryer Bypass PCV 5067 begins to open.

95# IA - Backup N2 rack Isolation Valves auto open.

95# IA - RB Stby air compressors start.

CHOICE "A" - Incorrect, see explanation.

CHOICE "B" - Correct Answer CHOICE "C" - Incorrect, see explanation.

CHOICE "0" - Incorrect, see explanation.

Page 83 of99

300000 Instrument Air 2.1.20 Ability to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12)

IMPORTANCE RO 4.6 SRO 4.6 SOURCE: Bank LOI-CLS-LP-046.0*OBA LESSON PLAN/OBJECTIVE:

CLS-LP-302K, Obj. 4. Given plant conditions and AOP-20, determine the required supplementary actions.

COG LEVEL: Low Page 84 of99

62. Which one of the following identifies the sample location of the RBCCW liquid process radiation monitor and the protective function(s) it provides?

At;! RBCCW return header; alarm function only B. RBCCW return header; alarm and isolation function C. RBCCW head tank; alarm function only D. RBCCW head tank; alarm and isolation function

REFERENCE:

SO-21 RBCCW System EXPLANATION:

The RBCCW system is continuously monitored by a process radiation monitor.

The monitor is located in the RBCCW return header. The monitor provides indication and alarm response. No isolation functions are provided.

CHOICE "A" - Correct Answer CHOICE "B" - Incorrect. No isolation function provided. Other plant rad monitors (ie Radwaste Effluent) do provide isolation functions.

CHOICE "C" - Incorrect. wrong location.

CHOICE "0" - Incorrect. No isolation function provided.

400000 Component Cooling Water K1. Knowledge of the physical connections and / or cause-effect relationships between CCWS and the following:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.03 Radiation monitoring systems .......................... 2.7/3.0 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-11, Obj. 4g. Describe the interrelationship between the PRM and the following systems: Closed Cooling Water.

COG LEVEL: high Page 85 of 99

63. The SS has determined that the control room personnel must don SCBA's due to smoke in the control room from a plant fire on site.

Which one of the following is an indication that a SCBA is low on air?

A. Air regulator bypass valve auto opens.

B. Air leakage out past the face piece seals.

C. Audible high pitched beep emitting from face piece.

D~ Vibralert alarm in the regulator that vibrates the face piece.

REFERENCE:

EXPLANATION:

Low pressure will activate Vibralert, heads up display and bell if installed.

CHOICE "A" this is a manual action for failure of a regulator CHOICE "B" this is indication of an improper seal of the face piece CHOICE "C" Some of the SCBA's have an audible bell but do not have a beeping device. the bell is not mounted in the face piece.

CHOICE "D" correct answer, some also have a HUD (heads up display) with indicating lights for tank pressure.

600000 Plant Fire On Site AA 1 Ability to operate and/or monitor the following as they apply to PLANT FIRE ON SITE:

AA 1.01 Respirator air pack .......................................... 3.0 / 2.9 SOURCE: new LESSON PLAN/OBJECTIVE:

COG LEVEL: Memory Page 86 of 99

64. Due to grid disturbances the generator is operating in an under-excitation condition when the following alarm is received:

Gen Loss of Exc Which one of the following is the operational implication of operating the Main Generator without a field?

A'I Excessive heating of the rotor.

B. Induced vibrations in the low pressure turbine blades.

c. Overheating of the last stage buckets and exhaust hood.

D. Overheating of the Main Transformer and/or Unit Auxiliary Transformer.

REFERENCE:

SD-27 EXPLANATION:

when the field excitation is lost, the generator tends to overs peed and operates as an induction motor.

Induction motoring will produce slip frequency currents in the rotor. the rotor currents will cause extremely high temperatures in a very short time, particularly where the currents flow across the wedges at the ends of the rotor body.

CHOICE "A" correct answer CHOICE "B" this is a cause from under frequency conditions.

CHOICE "C" this is caused from reverse power conditions CHOICE "0" This is caused from static over excitation of the generator stator conditions due to the core iron saturation from the magnetic field overfluxing within a very short time 700000 Generator Voltage and Electric Grid Disturbances AK1. Knowledge of the operational implications of the following concepts as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:

(CFR: 41.4,41.5,41.7,41.10 /45.8)

AK1.03 Under-excitation .................................... 3.3/3.4 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-27, Obj. 11f. Given plant conditions, describe the effect that a loss or malfunction of the following may have on the Main Generator: Voltage Regulation (including Under and Over excitation).

COG LEVEL: Low Page 87 of 99

65. A grid disturbance occurs with the following Unit Two plant parameters:

Generator Load 940 MWe Generator Reactive Load 260 MVARs, out Generator Gas Pressure 55 psig (Reference provided)

Which one of the following is the operator action that is required to maintain the Unit within the Estimated Capability Curve?:

A. Lower Gas Pressure.

B~ Lower MVARs.

C. Raise MVARs.

D. Raise MWe.

REFERENCE:

10P-27 Figure 1 (provided to the examinee)

EXPLANATION:

Based on the conditions the student should plot the current location on the graph. Based on 55 psig gas pressure have to use the 50# line. This puts the operation outside of the safe area. would have to lower MWe, raise gas pressure, or Lower MVARs.

CHOICE "A" By lowering gas pressure you would be getting farther away from being within the spider graph. Pressure would have to be raised.

CHOICE "B" Correct Answer CHOICE "C" raising MVARS moves you up on the spider graph which moves you away from the safe area. Lowering MVARs would be correct.

CHOICE "0" raising MWe would move you to the right on the graph, need to move to the left to be in the safe area. Lower output would be a correct action.

700000 Generator Voltage and Electric Grid Disturbances M2. Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:

(CFR: 41.5 and 43.5/45.5,45.7, and 45.8)

AA2.04 VARs outside capability curve ............................ 3.6 3/ .6 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-27, Obj. 9. Given the Generator estimated capability curves, hydrogen pressure and either MVARS, MW, or power factor, determine the limit for MW and MVARS.

COG LEVEL: High Page 88 of 99

66. Which one of the following is not a situation where two-handed operations are approved in accordance with the conduct of operations manual.

A. As directed by the Unit SeQ.

B. As directed by the procedure.

e~ When performing steps in an AQP.

D. When required for proper system operation.

REFERENCE:

001-01.02 page 27 EXPLANATION:

manipulations of control switches by the use of both hands at the same time is normally not permitted because it challenges the operators ability to effectively perform STAR or Touch STAR. However, two-handed switch operation is sometimes necessary for proper operation or time constraints associated with multiple switch operations. Therefore, two-handed switch operation should only be used in the following circumstances: 1) As directed by procedure. 2) When required for proper system operation. 3)

As directed by the SCO.

CHOICE "A" Incorrect. See Explanation.

CHOICE "B" Incorrect. See Explanation.

CHOICE "C" Correct. See Explanation.

CHOICE "D" Incorrect. See Explanation.

2.1.1 Knowledge of conduct of operations requirements. (CFR: 41.10/45.13)

IMPORTANCE RO 3.8 SRO 4.2 SOURCE:

new LESSON PLAN/OBJECTIVE:

GNF0001 B, Obj. 3. Identify Error prevention tools.

COG LEVEL:

memory Page 89 of 99

67. Which one of the following is the correct first leg of a control room three way communication of initial reactor water level from Bob (the RO) to Tony (the SCO) in accordance with OAP-50, Site Command, Control and Communications Procedure?

A. Tony, this is Bob, Reactor water level is 100 inches.

B. Reactor water level on the N026 Alpha is 100 inches.

C~ Tony, Reactor water level is 100 inches and slowly lowering.

D. Reactor water level on the N026 Alpha is slowly lowering, Tony.

REFERENCE:

AP-SO Section 6.3.2 page 16 EXPLANATION:

In the control room would be a face to face communication. This requires the first name first, the parameter, the value, and the trend.

CHOICE "A" The senders name is not required for face to face communications (it is required for non face to face communications). Trend is not used.

CHOICE "B" First name is not used. Trend is not used. The channel is not required.

CHOICE "C" correct answer CHOICE "0" First name first is not used. The channel is not required.

2.1.17 Ability to make accurate, clear, and concise verbal reports.

(CFR: 41.10/ 4S.12 /4S.13)

IMPORTANCE RO 3.9 SRO 4.0 SOURCE: new LESSON PLAN/OBJECTIVE:

CLS-LP-401-A Obj 8e, State the AP-SO guidelines for: Face to face communications.

COG LEVEL: memory Page 90 of 99

68. While demanding a Core Mon, the Reactor Operator notes that one of the flow inputs from the Feedwater system is cyan (blue).

Which one of the following does this color coding indicate?

The process parameter:

A. is displaying bad data.

B. is displaying safe data.

c. is exceeding a high alarm limit.

D~ has a substitute value inserted.

REFERENCE:

01-72 page 59/68 EXPLANATION:

If inputs to a composed or calculated value are substituted, the computer point for the value may appear in Cyan. This will indicate to the operator that an input has been substituted to that point.

CHOICE "A" Bad data is displayed in magenta.

CHOICE "B" safe data is displayed in green.

CHOICE "C" alarm or unsafe conditions are displayed in red.

CHOICE "0" correct answer.

2.1.19 Ability to use plant computers to evaluate system or component status.

(CFR: 41.10/45.12)

IMPORTANCE RO 3.9 SRO 3.8 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-055 Obj 2e, Describe the basic operation of the Process Computer, including the use of the following: Monitor Display Color Code.

COG LEVEL: Memory Page 91 of 99

69. A small break LOCA with an ATWS has occurred on Unit Two with the following plant conditions:

Reactor Water Level 130 inches (stable)

Injection Systems CRD Reactor Power APRM downscales (19 rods not full in)

SRV's All closed Suppression Pool Temp. 92° F (very slow rise)

In accordance with the Q (power) leg of Level Power Control Procedure which one of the following mitigation strategies should be implemented?

A. Initiate ARI, Inject SLC, and inhibit ADS.

B. Initiate ARI, trip both recirc pumps, and inhibit ADS.

C. Place the mode switch to shutdown, trip both recirc pumps, and perform OEOP-01-LEP-02, Alternate Control Rod Insertion.

D!" Place the mode switch to shutdown, initiate ARI, and perform OEOP-01-LEP-02, Alternate Control Rod Insertion.

REFERENCE:

LPC (Q Leg)

EXPLANATION:

Per the Q leg of LPC the mode switch is placed to shutdown, ARI is initiated, If injection is from RFP, HPCI, or RCIC then recirc speed controllers are placed to 10%, If power is > than 2% then both recirc pumps are tripped, If the reactor cannot be shutdown before the torus reaches 110° then SLC is initiated, and ADS is inhibited (although this is done in the level leg anyway), then perform LEP-02. For the conditions given, the mode switch and ARI would have to be performed along with LEP-02.

CHOICE "A" ADS is not inhibited and SLC is not injected per the Q leg if torus will not reach 110° F.

CHOICE "8" Recirc pumps are only tripped if power is >2% (APRM downscales) ADS is not inhibited per the Q leg if torus will not reach 110° F.

CHOICE "C" Recirc pumps are only tripped if power is >2% (APRM downscales)

CHOICE "0" correct answer Page 92 of 99

2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10/43.5/45.13)

IMPORTANCE RO 3.8 SRO 4.2 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-300E, Obj. 19. Given plant conditions and a copy of the LPC procedure determine the required operator actions.

COG LEVEL: High Page 93 of 99

70. A transient has occurred on Unit Two in which "8" Loop of RHR has been placed into Suppression Pool Cooling mode Of operation.

The following annunciators are received:

RHR Hx B Outlet Hi Conductivity Service Wtr Effluent Rad High Which one of these annunciators should receive the highest priority and why?

A"!' Service Wtr Effluent Rad High This indicates a radiation release.

8. RHR Hx 8 Outlet Hi Conductivity This indicates there is a fuel failure.

C. RHR Hx 8 Outlet Hi Conductivity This indicates tube leak in either RHR "8" or "0" pump seal cooler.

O. Service Wtr Effluent Rad High This indicates leak in either RHR SW "8" or "0" 800ster Pump Motor Cooler.

REFERENCE:

2APP-UA-03 5-5 Service Wtr Effluent Rad High 2APP-A-03 2-10 RHR Hx B Outlet Hi Conductivity EXPLANATION:

RHR Hi conductivity would be from a tube leak into RHR from CSW. Service water hi rad is monitoring the release path, this would be from a leak into SW from RHR Hx, RHR Pump cooler or RBCCW.

CHOICE "A" correct answer CHOICE "B" A tube leak would be into the heat exchanger, hi conductivity would not be an indication of fuel failure.

CHOICE "C" fuel pool cooling would not leak into SW.

CHOICE "0" pump seal coolers would not leak into the heat exchanger outlet.

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

(CFR: 41.10/43.5/45.3/45.12)

IMPORTANCE RO 4.1 SRO 4.3 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-300N, Obj 19. Given plant conditions and RRCP, determine the following: Release path.

COG LEVEL: higher order Page 94 of 99

71. Which one of the following identifies the differences between Unit One and Unit Two Main Steam Systems?

Unit One has _....,....-_ _ bypass steam chest(s) containing _ _ _ _ bypass valves, while Unit Two has bypass steam chest(s) containing bypass valves.

A. two, ten one, four B!'" one, four two, ten C. one, seven two, eleven D. two, eleven one, seven

REFERENCE:

OEOP-01-LEP-02 Section 4 page 19/20 EXPLANATION:

Unit 1 has one bypass steam chest with 4 bypass valves providing 20.6% capacity while Unit 2 has two bypass steam chests with 5 bypass valves on each for a total of 10 bypass valves with a capacity of 69.6%.

CHOICE "A" this is the opposite of the correct answer.

CHOICE "B" correct answer.

CHOICE "C" this is correct for the number of bypass steam chests. 7 is the number of ADS valves and eleven is the number of SRV's.

CHOICE "0" The bypass steam chests numbers are the opposite of the correct answer while seven is the number of ADS valves and eleven is the number of SRV's.

2.2.4 (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

(CFR: 41.6/41.7 / 41.10/45.1 /45.13)

IMPORTANCE RO 3.6 SRO 3.6 SOURCE: new LESSON PLAN/OBJECTIVE:

COG LEVEL: Memory Page 95 of 99

72. Considerin9 a monthly surveillance, which one of the following is last day that the surveillance can be performed and meet the requirements of SR 3.0.2?

The last day the surveillance must be performed by is within ____ of the previous performance of the surveillance.

A. 31 days B. 34 days C~ 38 days D. 45 days

REFERENCE:

TS SR 3.0.2, Surv. is met if performed within 1.25 times the interval specified in the frequency EXPLANATION:

Have to know that a monthly surveillance is 31 days (TS 5.5.6) and then from SR 3.0.2 that the surv.

requirement times 1.25 is when the surveillance has to be performed. This equals 38.75 days.

CHOICE "A" This is the monthly CHOICE "B" this uses a standard of 10% greater than the 31 days.

CHOICE "C" correct answer CHOICE "D" This uses 1.5 times the requirement of 31 days.

2.2.12 Knowledge of surveillance procedures. (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.7 SRO 4.1 SOURCE: New LESSON PLAN/OBJECTIVE:

CLS-LP-200B, Obj. 8. Explain the frequency rules for periodic actions and apply these rules to determine when a periodic action must be performed.

COG LEVEL: Low Page 96 of 99

73. During outage conditions, an operator may use hand tools to perform specific simple maintenance tasks, provided the necessary skills are possessed to do the job.

Which one of the following is a maintenance activity that is not allowed?

A. Addition of lubriGating oil.

B:t Changing of lubricating oil.

C. Adjustment of packing on non-automatic, manually operated valves.

D. Adjustment of operating parameters specified in operating procedures.

REFERENCE:

001-01.02 page 41 EXPLANATION:

Operator Performance of Minor Maintenance

1. An operator may use hand tools to perform the simple maintenance tasks described below, providing the necessary skills are possessed to do the job:

a. Adjustment of packing on non-automatic, manually operated valves.

b. Addition of lubricating oil.

c. Adjustment of operating parameters within or to within the range specified in operating procedures or instructions.

CHOICE "A" Incorrect, see explanation.

CHOICE "B" Correct answer.

CHOICE "c" Incorrect, see explanation.

CHOICE "D" Incorrect, see explanation.

2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

(CFR: 41.10 143.5/45.13)

IMPORTANCE RO 2.6 SRO 3.9 SOURCE: New LESSON PLANIOBJECTIVE:

COG LEVEL: Low Page 97 of 99

74. A valve lineup is to be performed in a locked high radiation area that has the following conditions:

Area temperature 110 0 F Area radiation 40 mr/hr Independent verification of this valve lineup is expected to take 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Which one of the following is correct per OPS-NGGC-1303, Independent Verification, for this evolution?

Independent verification of this lineup:

A. shall not be waived.

B:' may be waived due to excessive radiation dose only.

c. may be waived due to the presence of extreme temperature only.

D. may be waived due to the presence of extreme temperature or due to excessive dose.

REFERENCE:

NGGC-1303 EXPLANATION:

IV may be waived if the dose will be excessive (as a guideline 10 mrem is excessive) or if personnel safety issues exists (e.g. temperature is above 120 F). IV of this lineup would result in a dose of 20 0

mrem.

CHOICE "A" Incorrect. Would be allowed to be waived based on dose.

CHOICE "B" Correct answer.

CHOICE "C" Incorrect. Would be allowed to be waived based on dose not temperature.

CHOICE "D" Incorrect. Would be allowed to be waived based on dose only.

2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12/45.9/45.10)

IMPORTANCE RO 3.2 SRO 3.7 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-201 C, Obj. 10b. Describe the following regarding OPS-NGGC-1303: Exem ptions from Independent Verification.

COG LEVEL: High Page 98 of 99

75. Which one of the following is the basis for the Maximum Safe Radiation Levels specified in Secondary Containment Control Procedure?

Maximum Safe Radiation Level is the:

A. radiation level at which installed radiation monitors peg upscale.

B. highest radiation level expected to occur during normal plant operation.

C. radiation level above which equipment necessary for safe shutdown will fail.

D!' radiation level above which personnel access necessary for safe shutdown will be precluded.

REFERENCE:

EOP User Guide definition of max safe radiation level EXPLANATION:

CHOICE "A" CHOICE "B" CHOICE "C" CHOICE "0" 43:12-Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41)2 / 4:yO 45.J,ej)

IMPORTANCE RO 3:4 SRO 3.8 SOURCE: Bank LESSON PLAN/OBJECTIVE:

CLS-LP-300M, Obj. 4c. Define the following: Maximum safe operating.

COG LEVEL: mem Page 99 of 99