IR 05000341/1998301

NRC Operator Licensing Exam Rept 50-341/98-301OL(including Completed & Graded Tests) for Tests Administered on 980406- 0520.Six Applicants Were Administered Exam,Two Failed Written Exam,Two Failed Operating Exam & One Failed Both

ML20249C847
Person / Time
Site:	Fermi
Issue date:	06/29/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20249C836	List: IR 05000341/1998301 ML20249C835 ML20249C844
References
50-341-98-301OL, NUDOCS 9807010296
Download: ML20249C847 (200)

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l U.S. NUCLEAR REGULATORY COMMISSION REGION lll l r l

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Docket No: 50-341 i License No: NPF-43 i

l Report No: 50-341/98301(OL) .  !

Licensee: The Detroit Edison Company i

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Facility: Fermi 2 l l

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!- Location: 6400 North Dixie Highway l l Newport, MI 48166 l l Dates: April 6 - 17,1998 l Telephone Exam Results May 20,1998

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l . Inspectors: H. Peterson, Chief Examiner, Rlli D. Muller, Examiner, Rlli l D. Roth, Examiner Rlli

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! Approved by: M. Leach, Chief, Operator Licensing Branch ,

< Division of Reactor Safety )

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9907010296 990629 PDR ADOCK 05000341 V PDR '

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l EXECUTIVE SUMMARY Fermi 2 Nuclear Power Plant NRC Examination Report 50-341/98301 The Fermi 2 training department developed an initial operator licensing examination that was administered to twelve license applicants by NRC examiner Results:

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Four Reactor Operator and two Senior Reactor applicants passed their examinations and were issued operator licenses. Two Reactor Operator applicants failed the written I examination, one Senior Reactor Operator applicant and two Reactor Operator applicants failed the operating examination, and one Senior Reactor Operator applicant failed both the written and operating examination Reoort Summarv:

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Control Room operators displayed proper professionalism and demonstrated an appropriate level of attentiveness to the operating panels and were knowledgeable of plant conditions. (Section 01.1) j

. Several procedures reviewed by the examiners contained weaknesses. The weaknesses were considered an inspection followup item. (Section 03)

. The licensee's knowledge of the examination development guidelines, attention to detail during examination development, and the ability to develop technically accurate JPMs i and written examination material in accordance with the examination guidelines was i considered satisfactory. Several deficiencies were identified by the examiners, the most j significant being the need to increase the difficulty level of the examination. (Section 05.2)

. Training staff members demonstrated a lack of attention to detail when they failed to properly prepare the simulator for administration of the operating test. The simulator did not always respond correctly during the examination. Examiners were able to complete the examination and properly evaluate applicants despite the simulator problem (Section 05.3)

. The high failure rate on the examination suggested that the applicants were not well prepared for the examination. Control and supervision of reactivity manipulations was considered a strength. SRO ability to determine protective action recommendations and the ability to review and use the dose projection report were considered Administrative JPM weaknesses. Applicant performance in annunciator response, event diagnosis, command and control, and the use of and familiarity with operating procedures needed improvement. (Section O5.4)

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Twice, the licensee's simulation facility failed to operate. The simulator froze once for i no apparent reason during the performance of the simulator scenario examination. On another occasion, during the examination validation week, the simulator failed when the licensee attempted to back track the scenario to review a system response to a i

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malfunction. (Section O5.6)

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o a Reoorts Details 1. Operations 01 Conduct of Operations 01.1 Control Room Observations insoection Scone (71707)

The inspectors observed routine control room activities during full power operations, performed a panel walk-down, reviewed control room logs, and questioned operators about plant and equipment statu Observations and Findings

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The examiners found that the control room operators conducted themselves in a i professional manner and were attentive to their respective panel indications. The i

control room noise level was minimal and no annunciator alarms were left unattended or in a prolonged alarm state. Upon questioning by the inspectors, the operators i demonstrated satisfactory knowledge of plant conditions and equipment status, i Conclusions The inspectors concluded that an appropriate level of awareness and professionalism existed in the control roo Operations Procedures and Documentation Insoection Scoast During both the examination validation and administration weeks, the examiners reviewed numerous procedures. The procedures were reviewed to ascertain procedural adequacy and note any potential concern Observations and Findings The examiners identified several procedural concerns. The following are examples of procedure problems identified during the examination:

• The licensee's administrative criteria defined two classifications of procedures i that indicated how to use that procedure. The two classifications were,

" Continuous Use and Reference Use." However, the examiners identified at least two procedures with conflicting guidance on how the procedure was to be used. The two procedures were,20.300.03, " Loss of Offsite Power," Rev 12, and 20.000.18, " Control of the Plant from the Dedicated Shutdown Panel," Revision 23. The procedures' cover page noted the definition of " Continuous Use":

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"This procedure shall be performed as written. Each step shall be read ;

by the user before performing that step; performed in the sequence given; and when required, signed off as it is completed before proceeding to the next step."

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However, a subsequent note in the same procedures conflicted with the above stated definition:

"At the discretion of the Control Room SRO, steps of this procedure may be performed simultaneously."

• Procedure 20.000.18, Revision 23, noted that there was no operator "Immediate Actions." This procedure directed the evacuation of the Control Room and established control from the Dedicated Shutdown Panel if conditions degrade The procedure directed the performance of several important actions for Control Room evacuation. These actions were noted as Step 7 of the " Subsequent  ;

Actions." Step 7 of the " Subsequent Actions" required the following actions be I performed from the Main Control Room prior to having all Operations personnel l assemble at the Dedicated Shutdown Panel. The actions were, (1) to scram the reactor by depressing the manual scram, (2) trip the Main Turbine, (3) Open Generator Output Breakers CF and CM, and (4) verify Generator Field Breaker Open. The examiners considered if these " Subsequent Actions" were in practice

"Immediate Actions" for control room evacuatio I e The examiners noted that there was no guidance in the annunciator response procedure (ARP) 2D59, "HPCI Pump Disch Flow Low," Revision 5, telling the user to attempt manual control of the high pressure coolant injection (HPCI)

system if a low system flow condition was received. At the end of the examination week, the licensee was evaluating the HPCI procedures to add such guidanc * The examiners noted that there was no clear guidance for applicants (operators)

to determine the degrees separation of the emergency planning zone (EPZ)

sectors, if the emergency response information system (ERIS) was inoperabl In post-exam discussions with the licensee, the examiners determined that the exact degrees of the sectors were generally unknown. Furthermore, when the licensee did find the listings, the values were not easy-to-remember round numbers or simple multiples. This made the assessment of identifying downwind affected sectors for plume direction and input for PARS implementation very difficult. The examiners asked the training staff about what was done in real life 4 if ERIS was nonfunctional. The licensee stated that the shift technical advisor (STA) would then determine the downwind sectors, but did not provide any guidance about how the STA would avoid the same problems the applicant encountered. The examiners concluded that the lack of information about what defined each sector was a potential procedure weaknes _ -_. _ -_ _ __ -_ _

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. . Conclusions The examiners determined that a few of the procedures reviewed had some weaknesses but that these concerns alone may not constitute an inadequate procedur These issues on procedure weaknesses were considered an inspection followup item pending further NRC review. (50-341-98301-01(DRS))

05 Operator Training and Qualification 05.1 General Comments - Initial Ooerator License Examination Operator initial licensing examinations were administered to four Senior Reactor Operator (SRO) applicants and eight Reactor Operator (RO) applicants. The operating examination was administered by the examiners during the weeks of April 6 and April 13,1998. The written examination was administered by the licensee's training staff with approval from and observation by the NRC examiners on April 6,199 The licensee developed the initial operator license examination in accordance with guidance prescribed in NUREG 1021, " Operator Licensing Examination Standards for Power Reactors," Interim Revision 8. The examiners reviewed and approved all examination material that the licensee developed prior to its administratio .2 Examination Development and Validation Examination Scoce The licensee developed the examination material in accordance with the prescribed examination development guidelines. The examiners reviewed, revised, and validated the written and operating examination material during the week of March 23,199 Observations and Findinas Examination Outline:

The licensee satisfactorily submitted the proposed examination outline based on the quantitative requirements of ES-201-2," Examination Outline Quality Assurance Checklist,"in NUREG 1021, Interim Revision 8. The examiners identified the following deficiencies with the examination outline:

• There were no Knowledge and Abilities (K/A) referenced for the Administrative Topics Outlin * The Administrative Topics were not generally performance based and included memory or direct look-up question * There were no K/A rating factors for the Systems Job Performance Measure (JPM) task _-_

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L e Over half the Systams JPM questions were either simple memory type or direct look-up, depending on reference availabilit e All Systems JPM questions for both RO and SRO were the same, there were no specific RO or SRO questions. The proposed JPM questions appeared not to be discriminating enoug ,

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l * The proposed six simulator scenarios (including one spare scenario) had i the minimal number of malfunctions; however, it appeared that at least I three scenarios did not have malfunctions either after the major transient or after the emergency operating procedure (EOP) entr * None of the simulator scenarios had significant (realistic) initial conditions, (e.g., no existing technical specification limiting condition for operation (LCO), no equipment out-of-service (OOS)).

• The level of difficulty of simulator scenarios was marginal, based only on ,

outline titles. The scenarios were straight forward and not very challengin Although the outline met the quantitative minimal requirements, the examiners determined that the outline also indicated that the examination material would require some enhancements to reach the appropriate scope, depth (challenging),

and complexity (discriminating) for an NRC examination. Prior to and during the examination prep week, the examiners informed the licensee to upgrade the examination material based on the proposed outline. The examiners requested the licerisee to develop more performance-based JPMs instead of simple questions for the Administrative section. A few replacements of systems JPMs were suggested to replace less challenging tasks. Also, realistic initial conditions, additional malfunctions, and in-depth performance into EOPs were !

suggested for the simulator scenario . Dynamic Simulator Examination The examiners reviewed and assessed the material content of six simulator scenarios. The examiners noted the following regarding the dynamic simulator scenarios:  !

e The dynamic simulator scenario events were generally well integrated and would enable all the applicants to be evaluated on all the required competencies and rating factor e in several instances, the expected operators' actions documented on Form ES-301-4, " Operator Actions," were not sufficient to provide an i objective method for evaluating the applicants' performance, which was not in accordance with NUREG 1021, ES-301, Section D. j i

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i e Following the examiners' recommendations, the licensee submitted scenarios with added realistic initial condition * Several enhancements were made to the scenarios to increase the level of difficulty, including more challenging and discriminating events. For example: (1) added a nuclear instrument (intermediate range monitor (IRM)) out-of-service as part of initial conditions, which made SROs' use  ;

of technical specification more challenging when an additional IRM failed during the scenario; (2) changed a normal evolution from placing torus cooling on line to restoring offsite power to an engineering safety feature (ESF) bus and securing an emergency diesel generator (EDG); (3) added an EDG failure to start on a loss of offsite power major transient; and (4) j replaced a reactor feedwater pump turbine (RFPT) trip with an RFPT controller failure, the controller failure was harder to diagnose and required the operators to take manual control of the RFPT to avoid a level 8 or level 3 trip; and (5) added a failure of the lower recirculation pump l seal along with the failure of the upper seal, this required the operator to i trip and isolate the recirculation pum * The licensee incorrectly considered the task of placing torus cooling in i service following a loss of coolant accident (LOCA) as a normal evolutio A normal evolution should not be used after a major transient. Also, a required mitigating action for a malfunction cannot be considered as a normal evolutio * The examiners proposed changes to several fai!ures (instrument and component) because the failures did not require verifiable significant operator actions. For example: (1) a control rod drive (CRD) flow indication fails low, the operator would use other indicators to monitor CRD system; and (2) a minor recirculation pump upper seal failure, the operator would merely inform the SRO and monitor the situatio * The examiners replaced or changed malfunctions due to similarity of problems from one set of scenarios to the other. For example: (1) a similar reactor core isolation cooling (RCIC) spurious initiation was replaced with a failure of RCIC to auto start; and (2) a similar process radiation monitor (PRM) failure with a failure of the control center heating ventilation and air conditioning (CCHVAC) fan to start was changed to a PRM failure with a failure of a division of standby gas treatment (SBGT)

to star Overall, with six scenarios originally submitted, three scenarios required minor changes, two scenarios required major changes, and one scenario selected as the spare required no changes. Minor changes included adding additional out-of-services in the initial conditions, replacement of some normal evolutions, slightly increasing the level of difficulty, end adding details to the expected operators' actions. Major changes included replacing nondiscriminating events l

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l with discriminating events, significantly increasing the level of difficulty, adding normal evolutions for scenarios that lacked or inappropriately placed a normal

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evolution, replacing events based on possible duplication, and increasing the safety significance of operator error . Job Performance Measure (JPM) Walkthrouah Examination l The licensee submitted one set of ten systems JPMs and a set of administrative

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JPMs specific for SRO and RO applicants. The examiners found the administrative and systems JPM material lacked some qualitative attributes, as described in Form ES-301-3," Operating Test Quality Assurance Checklist." This resulted in several items identified by the examiners, during examination validation and administration, that did not meet the guidance of NUREG 1021, ES-301, Section D.2 and 3. The discrepancies included the following:

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e Three systems JPM tasks were replaced due to the tasks being

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nondiscriminator ;

• Some JPMs needed better initiating cues and a natural termination point for better use of simulator indication * Some JPMs needed minor changes in sequencin o One JPM required adding a missing step based on plant procedure * Systems and Administrative JPM tasks were missing the associated K/ * Out of 26 systems JPM questions originally submitted,15 questions were replaced or not used, due to problems with the questions. The problems included: low level of discrirnination, direct look-ups, and too many I closed reference / memory level questions.

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• Four administrative sections with two questions each were replaced with more operationally based and discriminating JPM task * Three originally submitted administrative JPM tasks were significantly modified to be more challenging and safety significan The following are some specific examples of the deficiencies that the examiners identified regarding the administrative and systems JPMs:

• A set of two closed reference fire protection questions, concerning fire doors and fire watch requirements, were replaced with a faulted technical specification surveillance to calculate torus average temperatur * The originally submitted JPM for SRO applicants to determine the emergency classification was not discriminating enough. The JPM only

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required a classification of an " Unusual Event." The JPM was upgraded to a " General Emergency," and required the determination of protective action recommendations (PAR) based on the Dose Assessment Repor Also, the SRO applicants' ability to determine PARS was an identified weakness during the examination (Section 05.4).

l *- A set of two open reference questions conceming plant status requirements for HPCI and a power range calibration, were replaced with a JPM to perform a thermal limits technical specification surveillanc * A set of two open reference questions conceming radiation hazards and a JPM to determine contaminated area dress-out requirements from a radiation work permit (RWP) was replaced with a more detailed and challenging JPM. The new JPM had more knowledge requirements for entry conditions into a locked high radiation and contaminated are e A systems JPM to startup an uninterruptible power supply (UPS) inverter was not discriminating. The UPS inverter was already aligned to the required startup and operating conditions of the JPM. The JPM was replaced with an abnormal condition to startup the combustion turbine generator (CTG) number 11 from the Dedicated Shutdown Pane * A systems JPM to retum HPCI to test mode was replaced with manually initiating HPCI with the auto flow controller failed. Also, the applicants'

(both SRO and RO) ability to perform the manual control of HPCI to establish injection during a casualty condition was an identified weakness during the examination (Section 05.4).

Overall, with 26 originally submitted systems JPM questions,13 were closed reference / memory level and four were direct look-ups. The as administered JPM examination, with 21 questions,1 RO only question and 1 SRO only question, contained five closed reference / memory level questions and no direct look-up . Written Examination The examiners reviewed all 130 questions from the originally submitted written examination. The examiners identified that several questions reviewed did not meet the written examination question development guidance stated in NUREG 1021, Interim Revision 8. During the on-site validation week, additional effort was made to ensure the required changes and enhancements were made to properly reflect the examination guidance to allow for exam administration. The identified deficiencies included:

• Several questions had distractors that did not reflect homogenous options and some contained implausible distractors, contrary to guidance of NUREG 1021, Appendix B, Section C. !

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e Some questions had distractors that required rearrangement of content to l have logical sequence, in accordance with the guidance of NUREG 1021, Appendix B, Section C. * Passive wording in some question stems was changed to reflect positive wording. - For example: (1) replaced "possible result" to " result"; (2)

replaced "could" to "would"; (3) replaced "should" to "shall" or "must"; (4)

removed the statements of "most appropriate."

• Two questions were written as multiple choice, but the stem was formatted as a " MATCHING" type question. The questions required matching of setpoints and power supplies to select components. The four distractors were sets of different matched selections. Only multiple choice questions were acceptable per guidance of NUREG 1021, ES-l 401, Section D.2.e, and Appendix B, Section e The distractors for one question were formatted to include "All of the above" type distractor. The question stem required selecting a set of valve configurations and sequences based on the given plant conditio There were five different conditions to choose from. The four distractors were a combination of one or more of the five valve choices, with the last distractor that listed all five choices (all of the above). This was contrary to the guidance of NUREG 1021, Appendix B, Section C. e The stem and distractors of one question gave supporting information or was very similar in contents to another question that could potentially influence the answer selected. This condition would also open the possibility of " double jeopardy." The examiners revised two such  !

question Changes were made to approximately 50% of the 130 written examination

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questions. The changes included improvements in question knowledge level, stem, and distractors. A few questions were deleted due to incorrect format or i were nondiscriminatory. The as-administered examination also contained some deficiencies identified by the licensee during the post examination review, see Section 05.6 of this repor Conclusions The licensee's knowledge of the examination development guidelines, attention to detail  ;

during examination development, and the ability to develop technically accurate JPMs and written examination material in accordance with the examination guidelines was, in general, considered satisfactory. However, several deficiencies were identified by the examiners, including the need to make the examination more discriminatin l

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05.3 Examination Administration Examination Scone

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The examiners administered the operating examination during the weeks of April 6 and April 13,1998. The written examination was administered on April 6,1998, by the licensee's training staff with approval from and observation by the examiners, Observations and Findinos i Job Performance Measure Walkthrouah Examination The examiners identified the following examples of examination administration deficiencies:

e No radiological survey map for the assigned area was attached to the Radiological Controls Administrative JPM. The examiners had to acquire a representative survey map from the Radiological Protection (RP) group :

to satisfactorily administer the JP !

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e The piping, electrical, and logic prints, for the simulator and the Main Control Room, were not located in the same place. This caused a minor delay with several applicants to find the prints in the Main Control Roo * The simulator's emergency response information system (ERIS) display was not set up with the required parameters for the RO's Emergency Plan Administrative JPM. The examiner identified this error during the JPM administration; however, the examiner gave the written JPM cues ,

for the expected parameters to satisfactorily evaluate the applicant. The l

ERIS set up was subsequently correcte '

• The simulator was set up incorrectly for the Turbine Bypass Valve Operability Test. The 6N heater drain system was set up with the heater drain valves, both normal and emergency dump valves, open. One of the applicants identified the lineup discrepancy while following up on an annunciator alarm. The applicant informed the examiner that only one of the drain valves (normal or emergency) should be open and not bot The licensee's training staff indicated that apparently this configuration set up was to avoid nuisance alarms associated with the cycling of the dump valves. The valve error was considered a potential simulator fidelity item; however, it was still considered poor simulation set u Overall, the configuration change of the heater drain valves did not negatively affect the JPM task.

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I Dynamic Simulator Examination

The examiners identified the following examples of examination administration deficiencies i

e The simulator failed to operate during the performance of one scenari l The simulator was restored to operation in 30 minutes; however, the l cause of the failure was unknown. The simulator failure and the 30- i minute delay did not adversely affect the scenario. The failure occurred  !

at a logical break point and the scenario was resumed without affecting j the evaluatio !

• The Main Turbine Load Demand Limiter was not operating satisfactoril Duririg an evolution to reduce reactor power and subsequently shutdown the Main Turbine, the operators attempted to reduce the demanded load limit on the turbine to verify bypass valve operation. When the load limiter setpoint was lowered (it would not lower less than 55 MWe) the  !

turbine did not shed its load to allow the bypass valves to operat * During an ATWS condition, the scenario was designed to fail the control air to the operating CRD flow control valve (FCV). This malfunction was intended to require shifting the standby FCV to allow continued control rod insertion. However, due to the apparent residual system pressure, the control rods continued to be inserted without any operator action to I correct the malfunction. To ensure the proper number of malfunctions were evaluated, a Silure of the CRD pump was added to evaluate the applicants'schon on the alternate method of shutting down the reactor, Conclusions

The weaknesses in the abilities to establish and maintain correct conditions for JPMs and simulator scenarios were isolated to a few instances. However, these weaknesses resulted in unnecessary delays in examination administratio .4 License Acolicant PerformaDra Examination Scoce Operator initial licensing examinations were administered to four SRO and eight RO applicants. The examiners evaluated the applicants' performance in three general areas (dynamic simulator, plant walkthrough (systems and administrative JPMs), and written examination).

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,. . Observations and Findinas l Dvnamic Simulator Examination l

l The examiners observed four license applicant crews' performance during the

initiallicense examination. Each crew consisted of three license applicants occupying the positions of SRO, RO, and BOP operator. The dynamic simulator j examination consisted of routine and emergency activities evaluated on two to j three dynamic simulator scenarios on the plant specific simulation facilit '

The crews performed adequately during routine activities, including the performance of surveillance testing and normal reactor power changes. Shift briefs were numerous and conducted professionally; however, some briefs were held at inopportune times during the mitigation of emergency condition Communk,ations between the applicants were satisfactory to ensure that appropriate mitigating actions were performed; however, there were instances of inappropriate directions by the SROs. In general, the crews adequately performed their associated tasks identified in the simulator scenario One SRO applicant failed the dynamic simulator examination; however, other j l applicants also demonstrated some areas of weaknesses. The examiners had l the following observations (both strengths and weaknesses) regarding the applicants' performanc ,

I Strengths I

• During all reactivity changes, the applicants ensured that a good brief was conducted, and that everyone was aware of and concurred with any i reactor recirculation flow changes, turbine load changes, and control rod movements prior to the evolutio : * Communications between applicants, in general, were good. Three way l communications were generally consistent. The number and quality (details) of shift briefings held by the SROs during the simulator scenanos were good. However, there were instances where the briefs were held at inopportune times and not all operators were attentive.

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Weaknessas  ;

• The applicants displayed some unfamiliarity and weakness in implementing normal and abnormal operating procedures. For example:

(1) An SRO failed to take action to restore cooling to the operating control rod drive (CRD) pumps. The applicant wanted to avoid declaring the service water system inoperable and not enter a technical specification limiting condition for operation (LCO). His decision to not restore cooling until a problem occurred to the pumps was considered non-conservative and poor operational decision. (2) During a loss of off-site power, the

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BOP operator was directed to perform AOP 20.300.03 to mitigate the loss of off-site power and to restore power to essential (needed) 1 equipment. Although the BOP operator started to perform the procedure, !

the BOP operator only performed a small portion of the procedure before

, informing the SRO that the procedure was too long and detailed l (cumbersome) to be completed in a timely manner. The SRO did not , !

l adequately prioritize needed actions to restore power to essential plant l equipment, e.g., standby feedwater pumps and secondary plant l equipment to control plant depressurization. (3) An SRO failed to i oversee and direct the RO to stop inserting control rods when reactor power and turbine loads reached 55 MWe in accordance with step 4.12 of GOP 22.000.04. The RO continued to insert rods during the BOP's slow process of unloading and shutting down the main turbine. The crew i eventually unloaded and shutdown the turbine with the indicated reactor l power and turbine load at approximately 18 to 19 MWe. Allowing the continued rod insertion before shutting down the turbine could have ;

l potentially placed the plant in an unnecessary reverse power trip i l conriition on the main turbin l

• The applicants displayed some unfamiliarity and weakness in performing

emergency operating procedures (EOPs). For example

(1) An SRO

! incorrectly decided to use safety relief valves (SRVs) to perform an i anticipatory (preempted) depressurization. This was contrary to the ,

! EOPs. According to the EOPs, a preempted depressurization was l intended to use bypass valves to reduce the challenge to the torus by i diverting the steam energy to the secondary side heat sink before an j t emergency depressurization (ED) was required. (2) During the l anticipated transient without scram (ATWS) power / level control, the SRO was unaware that at zero inches he could use outside the shroud l injection sources to maintain reactor water level between -24 and +5 i inches, as required by the EOPs. Without any injection sources, except CRD flow and standby liquid control (SLC), the level decreased below-24 inches and the reactor was emergency depressurized. (3) Crews l were slow to respond to the steps of EOP 29.100.01 SH2, " Primary Containment Control," to initiate the required Torus and Drywell spray The lack of expediting the initiation of Torus and Drywell sprays, in ;

accordance with the symptoms indicated in the EOPs, potentially placed '

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undue stress and challenge to the primary containment.

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i e SROs, on occasions, gave briefs without the complete attention of the ,

operators and gave briefs during inopportune times. For example:

(1) during a scenario the SRO was discuss!ng problems with the emergency essential cooling water (EECW) and EDG while the RO was busy restoring CRD system flow parameter following a malfunction of the CRD flow instrumentation; and (2) while the SRO was discussing the

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t corrective actions for a failed IRM the RO was busy looking at the nuclear instruments and incorrectly ranged down an IRM and caused an i unnecessary reactor scram.

l e Some applicants demonstrated errors in diagnosing events. Examples included: (1) The applicants were unclear why the Main Turbine did not unload when the load limiter was dialed down to 55 MWe. They

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misdiagnosed the problem, thinking it was a bypass valve failure. The actual cause was the load demand controller (a potentiometer dial) was not operating correctly. The controller was not reducing the turbine load demand. Additionally, this malfunction caused some confusion and delay in unloading and shutting down the turbine. (2) The ability to diagnose l and apply the correct technical specification LCO for a given plant condition was at times weak. One applicant failed to understand that technical specification 3.0.3 applied when both HPCI and RCIC systems were declared inoperabl . Job Performance Measure Walkthrouah Examination Two SRO and two RO applicants failed the examination's JPM Walkthrough section. One RO applicant failed the examination's Administrative Topics section. All other applicants passed these sections, but demonstrated some weaknesse The examiners had the following observations regarding the applicants'

performance on the examination's JPM Walkthrough and Administrative Topics:

e Some applicants demonstrated unsatisfactory performance on the JPM to l manually initiate HPCI and inject water into the reactor vessel. The i applicants failed to recognize and diagnose the failure of the automatic HPCl flow controller and were unable to take manual control of HPC l

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e Three out of four SRO applicants demonstrated unsatisfactory performance on the Emergency Plan Administrative Topics JPM. All four SRO applicants could correctly classify the event as a " General Emergency." However, three SRO applicants failed to identify the appropriate Protective Action Recommendation (PAR) for the given conditions using the Dose Projection Report. One SRO failed to use the Dose Projection Report. The applicants determined to perform only a default evacuation of Area 1 and evacuate out to 5 mile radius. The correct answer required the evacuation of Areas 1,2, and 3, and evacuate out to 10 mile radius. The error would have resulted in communicating the incorrect PARS to the local and state authorities and potentially cause undue risk to public health and safet e The applicants received several annunciator alarms on 3D18, "PCS Monitored inputs Abnormal." Often this alarm was due to spurious

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I signals from a " Spare" alarm. This was a common occurrence during all modes of simulator operation throughout the overall NRC examinatio {

Some applicants accepted this alarm as a nuisance alarm and continued j with their activity. However, legitimate alarms from 3D18 did occur during !

the partial loss of rod position indication system (RPIS) JPM when a non-peripheral rod was setected and when the RPIS JPM fault occurre '

Some ignored the 3D18 alarm, apparently rationalizing it <>was another

" Spare" nuisance alarm. Those applicants who responded to the alarm found the alarm was for the PCS monitored rod block monitor (RBM)

channel bypass alarm. The applicants were unfamiliar with the 3D18 annunciator noting a condition for the RBM, and some applicants thought the PCS alarm was faulted. The PCS alarms were expected to annunciate when a rod was withdrawn, and when a non-peripheral rod was selected, because the selection of a non-peripheral rod engaged the RB e Annunciator 4D91, " Electric Govemor Trouble," was received during the performance of the turbine bypass valve surveillance JPM. The annunciator was not listed in the surveillance procedure as an expected alcrm. Some applicants stopped the test and determined that they would consult their supervisor before continuing the test, unsure of why the j alarm annunciated. Some applicants ignored the alarm, and continued to perform the JPM. The examiners questioned the applicants on the alarm, which prompted the applicants to refer to the ARP. Subsequently, the j applicants determined that the alarm may be due to the Mod F failure !

noted in the ARP. This alarm condition was based on the discrepancy between actual and computed unitized actuator ram position for the ,

bypass valves. This alarm was expected as noted in the JPM expected J response * The examiners identified potential weaknessos in the RO applicants'

performance concerning the Emergency Plan implementation. The applicant was given an emergency plant condition and a JPM cue for wind direction, due to ERIS being inoperable. He was then tasked to determine the affected sectors to complete the Michigan Notification Form. However, the applicant had difficulty determining the affected downwind sectors because he could not expeditiously find a document that showed the degrees separation of the sector e Applicants demonstrated weaknesses in the Radiological Controls ;

Administrative JPM. Several applicants had difficulty reading a radiological area survey map. Several survey map figures and acronyms

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were unfamiliar to the applicants. For example: (1) applicants thought l NE (no entry) meant " Neutron Exposure"; (2) some applicants were unfamliiar in reading the survey markings for area swipes; and (3) an applicant determined to enter a locked high radiation and contaminated area in street clothes.

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• During JPM questions, the applicants displayed knowledge weaknesse For example, the applicants were unfamiliar of the existence and operation of the reactor building to torus and torus to drywell vacuum breakers. The applicants demonstrated knowledge weaknesses in the ability to monitor automatic operation of these primary containment system and auxiliaries, and design features and/or interlocks that maintain primary containment integrit Concerning the inconsistency in annunciator responses, the examiners

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questioned the licensee's training staff on alarm 4D91. The examiners were informed that alarm 4D91 apparently did not occur during the last performance of the actual surveillance in the control room. The licensee noted that it was potentially a simulator fidelity problem due to sensitivity of the rate of change on the bypass valve position. The training staff wrote a condition assessment resolution document (CARD) to investigate this concer . Written Examination One SRO and two RO applicants failed the written examination and all other applicants passed. There were 16 written examination questions (3 on the RO examination only,3 on the SRO examination only, and 10 that were common to both examinations) that a significant number (50% or more) of the applicants answered incorrectly. These questions were considered potential generic knowledge weaknesses and are being provided to the Fermi training staff for consideration and implementation into their Systematic Approach to Training based program. Questions marked with (*) were identified by the licensee as i potential applicant knowledge weaknesse l Question # Knowledae Weakness i

RO#06 Understanding the purpose of the Minimum Suppression Chamber Water Volum *RO#11/SRO#10 Understanding of the differences between the Reactor Building to Torus Vacuum Breakers and the Drywell to Torus Vacuum Breakers, including the design base of eac RO#14/SRO#13 Understanding the requirements for and how to manually start the RCIC following a RCIC turbine trip on high water level.

l l *SRO#18 Knowledge of the conditions that require 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> NRC notification l l

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• RO#25/SRO#23 Understanding the requirements to control and bypass the Rod Worth Minimizer.

l *RO#27 Understanding of the effect the HPCI Turbine Exhaust Diaphragm rupture has upon HPCI system operatio RO#38/SRO#37 Knowledge of signals required to start the Emergency Diesel Generator Digital Load Sequence RO#56/SRO#55 Knowledge of signalinputs to the Main Turbine Tripped annunciato RO#59/SRO#58 Understanding the effects and controls of the Reactor Mode Switc SRO#67 Understanding how to establish decay heat removal from the core when normal residual heat removal (RHR) shutdown cooling is unavailabl SRO#87 Understanding the conditions and requirements for exiting emergency operating procedures following an ATWS conditio RO#88 Knowledge of the prerequisites for i purging /deinerting the primary containmen l RO#92/SRO#91 Understanding the effects on emergency diesel generator control from the Dedicated Shutdown Pane *RO#94/SRO#93 Knowledge and ability to convert and i calculate dose using Derived Air Concentration (DAC) and Total Effective Dose Equivalent (TEDE).

c. Conclusions The high failure rate on the examination suggested that the applicants were not well prepared. During the operating examination, the applicants control and supervision of reactivity manipulations, in particular the shift briefing, was considered a strengt However, several potential generic weaknesses were identified. The SRO applicants'

ability to determine the required PARS for a given event, and their ability to review and use the dose projection report were considered Administrative Topics weaknesse l l

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1 Overall, the examiners considered the applicants' performance in annunciator response, event diagnosis, command and control, and the use and familiarity of operating

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procedures were, at times, weak and needed some improvement O5.5 Post Examination Activities Scope The examiners reviewed the written examination grading that was performed by the l

licensee in accordance with Form ES-403-1, " Written Examination Grading Quality Assurance Checklist," contained in NUREG-1021, Interim Revision 8. The examiners also reviewed the post written examination comments submitted by the license Observations and Findinas l

The licensee submitted a comprehensive analysis of the written examination result The submittal included all the required documentation as required per the guidance of NUREG-1021 ES-501. The analysis included the percentages of applicants who answered the questions incorrectly, including the selected distractors. The licensee also submitted a brief evaluation or, the potential written examination knowledge weaknesse The examiners reviewed the licensee's submitted post written examination comment The licensee's comments and the NRC resolution of the comments are detailed in Enclosure 2," Post Written Examination Facility Comments and NRC Resolution." Conclusions The examiners accepted five of the ten licensee's post written examination comment Overall, the licensee's submittal of the post examination documents was considered timely and goo O5.6 Simulator Fidelity l

l During this examination, the examiners identified several potential simulator fidelity issues. The simulator discrepancies were identified as described below and other i fidelity issues are noted in Enclosure 3. In general, the examiners concluded that the ,

simulator deficiencies did not preclude the applicant's evaluation ]

l e The simulator froze on one occasion for no apparent reason during the  !

performance of the simulator scenario examination. The scenario was  !

unnecessarily delayed for approximately 30 minutes in order to reset the machine. The examiners failed to observe the applicants' performance on all the g required evolutions prior to the simulator fault. However, the scenario was  !

satisfactorily completed after the simulator was rese l

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e The simulator crashed on one occasion during the examination validation week.

I During a simulator scenario validation, a scenario back track was attempted to review the system response to a malfunction. However, when the back track was initiated the simulation failed. The cause was unknown.

l 08 Miscellaneous Operations issues (Closedt insoection Follow un Item 341/95004-04: EOP Writer's Guides did not ensure that the presentation of information was consistent and benefit to the operators. By letter dated July 3,1995, Detroit Edison committed to review the comments generated by the NRC and internal audits, and revise the Writer's Guides and EOP flowcharts based on their review. The required revisions of the Fermi 2 Writer's Guides for the EOPs and the Emergency Support Procedures (ESP) were completed on February 7, 1997. All EOPs and 16 of 26 ESPs required revision because of the Writer's Guides changes. All EOP flowcharts and identified ESPs were processed through the verification and validation process in confom1ance with the Boiling Water Reactor Owner's Group (BWROG) Emergency Procedure Guidelines. As of August 20,1997, the licensee has taken the corrective actions to revise the Writer's Guides for the EOPs and ESPs. The actions taken by the licensee were sufficient to maintain the quality of the EOPs and ESPs over time. This inspection follow-up item was considered close V. Management Meetings X1 Exit Meeting Summary The examiners conducted an exit meeting with members of licensee management on April 17, 1998, and the licensee was contacted by telephone on May 20,1998, to inform licensee management of the examination results. The licensee acknowledged the findings presented and indicated that the materials reviewed were not considered proprietar _ _ _ _ _ - _ __ _ _ _ _ _ - __

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PARTIAL LIST OF PERSONS CONTACTED l

Licensee j D. Gipson, Senior Vice President, Nuclear Generation A. Antrassian, Nuclear Licensing P. Borer, Vice President, Nuclear Generation J. Davis, Director, Nuclear Training K. Hlaraty, Superintendent, Operations W. O'Connor, Nuclear Assessment Manager S. Peterman, Operations N. Peterson, Director, Nuclear Licensing L. Sander, Supervisor Operations Training NBC G. Harris, Senior Resident inspector N. O'Keefe, Resident inspector INSPECTION PROCEDURES USED IP 71707, " Plant Operations" l

ITEMS OPENED, CLOSED, AND DISCUSSED i l

Ooened 50-341/98301-01(DRS) Several concems pertaining to procedure weaknesses that l potentially may contribute to inadequate procedure Closed  !

50-341/95004-04(DRS) EOP Writer's Guides did not ensure that the presentation of information was consistent and benefit to the operator ;

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LIST OF ACRONYMS USED CFR Code of Federal Regulations CST Condensate Storage Tank DRS Division of Reactor Safety EDG Emergency Diesel Generator EOP Emergency Operating Procedure ES Examination Standards HPCI High Pressure Coolant injection IFl Inspection Follow up Item IP inspection Procedure JPM Job Performance Measure K/A Knowledge and Abilities LOCA Loss of Coolant Accident NASS Nuclear Assistant Shift Supervisor NRC . Nuclear Regulator Commission NRR NRC Office of Nuclear Reactor Regulation NSS Nuclear Shift Supervisor OTP Operations Training Policy PDR Public Document Room RO Reactor Operator SALP Systematic Assessment of Licensee Performance SRO Senior Recctor Operator STA Shift Technical Advisor

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Enclosure 2 l

Eacility Post Written Examination Comments and NRC Resolution EXAMINATION QUESTION RO #41/SRO #40 LICENSEE COMMENT Due to typographical errors on the answer keys, the correct answer is distractor NRC RESOLUILOB Correct answer B is accepte . EXAMINATION OUESTION SRO #48 LICENSEE COMMENT l Due to typographical errors on the answer keys, the correct answer is distractor NRC RESOLUTION Correct answer B is accepte . EXAMINATION OUESTION RO#62/SRO #61 LICENSEE COMMENT Due to typographical errors on the answer keys, the correct answer is distractor NBC RESOLUTION Correct answer D is accepte . EXAMINATION OUESTION SRO #8 LICENSEE COMMENT Also accept distractor ;

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AOP 20.710.01 requires immediate evacuation of all personnel from the Refuel Floor  :

"except those persons who are performing manipulations that immediately terminate the condition or mitigate the circumstances." This statement allows the SRO to determine that lowering the grapple to minimum position could mitigate the circumstances of the even NRC RESOLUTION:

Additional answer C is not accepted. Procedure AOP 20.710.01 states that,

"immediately evacuate all personnel from the Refuel Floor..." It is understood that certain personnel may stay behind as the procedure further states, "except those persons who are performing manipulations that immediately terminate the condition or mitigate the circumstances." However, the problem (an adjacent fuel bundle lifted and subsequently falls back into the core) occurred and terminated once it fell into the cor After the bundle had fallen, bubbles start coming to the pool surface. The damage to either bundle had occurred and there was no way to terminate or mitigate it. This condition indicates that inserting the selected fuel bundle still in the refueling machine

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back into the core will not terminate or mitigate the condition of fission gases coming to the pool surface from either the fallen or the selected fuel bundles. It may maximize shielding from the selected bundle, but the alarming condition is due to the gases escaping from a damaged fuel bundle and not the radiation shine from the selected bundl Distractor C notes that the selected bundle is lowered and then the control room notified before evacuating the Refueling Floor. This sequence of action is contrary to the procedural step that states evacuate first and then notify the control roo Question History: Using the same rationale given by the licensee, the original question as submitted would have potentially accepted all distractors for being somewhat correc The question stem was the same as in the original, distractors C and D were modified by the licensee because they were too simila . EXAMINATION QUESTION RO'#35/SRO#34 LICENSEE COMMENT Also accept distractor The question stem does not state the reason for P4400-F603B failing closed. If the valve closure was caused by a logic system failure, operation of the manual override '

keylock switch would be required to override the initiation signal prior to opening P4400-F60 NRC RESOLUTION Additional answer D is not accepted. The procedure AOP 20.127.01," Loss of Reactor Building Closed Cooling Water System," stated that actions are necessary to restore cooling water to the CRD pumps. The first thing in the procedure step to return cooling to the CRD pumps stated,"If high DW Pressure is present place P4400-M004, DIV 2 EECW lso Override Sw, keylock switch in MANUAL OVERRD." The question stem  ;

does not give or indicate any condition that a high drywell pressure exists. The applicant may not assume added conditions in the question, which was not given in the original question stem, to justify his selected answer. The question must be answered with only the information given in the question ste l Question History: The question was the same as originally submitted, including the i answer and distractor D. Only distractor A, an incorrect answer, was modifie j

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I 6. EXAMINATION QUESTION RO #56/SRO #55 LICENSEE COMMENT Delete the questio l I

i The way the correct answer was stated, it was interpreted to mean the main steam isolation valves (MSIVs) had failed to isolate a Main Steam Line which is an incorrect i response. Consequently, there is no correct answe i i

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l NRC RESOLUTION Question is not deleted, accept the original answer as submitted. Procedure ARP 4D46,

" Main Turbine Tripped," indicates the alarm is in when all relays deenergized with at l

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least one valve (stop, throttle, or intercept) in each steam line to the turbine is close With a steam line not isolated to the turbine it indicates that the main steam stops are open, the turbine control, stop, and intercept valves are still open. Therefore not all relays are deenergized and will not actuate the Main Turbine Tripped annunciator. The question stem did not specifically characterize that the steam line to the turbine meant only the MSIV Question History: The question was identical to the originally submitted question. Only distractor D (incorrect answer) was modified. Answer A was not changed from the original question along with the licensee's bases for the answe . EXAMINATION QUESTION SRO #33 LICENSEE COMMENT Also accept distractor Student Text Appendix A - Govemor/ Pressure Control Design Bases states the system operates the steam bypass system to keep reactor pressure within limit NRC RESOLUTION Accept answer A, but reject original answer B. The lesson plan ST-OP-315-0045-001, Appendix A, " Governor / Pressure Control Design Bases," states that, "Govemor/

Pressure Control System operates the steam bypass system to keep reactor pressure within limits, . ." It does not state that part of its design bases is to maintain a condenser heat load. The Governor / Pressure Control System may be used to provide features which limit the maximum Turbine Generator loading and by that control total heat load on the Main Condenser. However, it is not part of the design bases, it is not specifically used to maintain the condenser within design limit Question History: The question was unmodified from the originally submitted examinatio . EXAMINATION QUESTION SRO #63 LICENSEE COMMENT Also accept distractor With a small steam / water leak on the 'A' variable leg, indicated RPV level would be slightly lower on the A and C instruments. With 'A' selected for Level Control, the A and C instruments would control at 197 inches which would result in actual RPV level increasing. Therefore the B levelinstrument which is not affected by the leak would indicate a higher leve _ _ _ _ _ _ _ _ _ _ _ _ - _ - _

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NRC RESOLUTION Accept C as an additional correct answe Question History: The question stem and answer were not modified. Distractors A and D were modified (incorrect answers). The two distractors B and C, indicated by the licensee as two correct answers, were the originally submitted distractors, with only B as the correct answe . EXAMINATION QUESTION SRO #84 LICENSEE COMMENT Also accept distractor It is a subjective decision to manually scram the plant. AOP 20.129.01 states only if the NSS determines that plant operation is too unstable to continue, place the Mode Switch in Shutdown. Based on given conditions, there is no information provided that states plant conditions are degrading, or that equipment necessary to complete an orderly shutdown has been affected. Due to this, the decision can be made to commence an orderly plant shutdow NRC RESOLUTION Additional answer C is not accepted. Given the plant condition in the question stem, it indicates the loss of DIV 2 NIAS and that it cannot be restored. The condition starts to degrade, including loss of DIV 2 drywell pneumatics. According to procedure AOP 20.129.01," Loss of Station and/or Control Air,"it states that,"If at anytime the NSS determines that plant operation is too unstable to continue due to the loss of air, place the Reactor Mode Switch in SHUTDOWN." Based on the degraded plant condition the correct answer was to place the mode switch in shutdown, not to reduce power first and commence a reactor shutdown. The statement," commence a reactor shutdown," is to perform a norms' plant shutdown per procedure. Placing the mode switch in shutdown results in an immediate reactor scra Question History: The question stem, distractors, and answer were not changed. Only item changed was the word "should" to "must."

10. EXAMINATION QUESTION RO #87/SRO #86 LICENSEE COMMENT Also accept distractor B as correc ARP 3D123 states that a low #2 Seci pressure indicates either a possible outer seal failure or blockage of the inner seal restricting orific NRC RESOLUTION Additional answer B is not accepted. Given just the plant conditions, it is possible per the ARP 3D123, *Recirc PMP A Staging Seal Flow High/ Low," that either a #2 seat failed or that #1 seal labyrinth (restricted orifice) was plugged. With the supporting

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annunciator 3D123 and the staging flow indicating 0.4 gpm it supports the indicated condition that the low pressure indication for Seal #2 is due to a plugged labyrint Question History: During the preparation week, the examiners raised a concem that this question had two correct answers. The licensee assured the examiners that it was not the case due to the low pressure alarm condition with the labyrinth. The question, stem,

. distractors, and answer, were the same as originally submitted. Only one item was

- added, the staging seat flow indicating 0.4 gpm.

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Enclosure 3 SIMULATION FACILITY REPORT l

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Facility Licensee: Fermi 2 l

Facility Licensee Dockets No: 50-341 Operating Tests Administered: April 7 -16,1998

! This form is to be used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future I evaluations. No licensee action is required in response to these observation While conducting the simulator portion of the operating tests, the following items were observed (if none, so state):

ITEM DESCRIPTION 6N heater drain system Both normal and emergency dump valves were aligned to be open. Only one of the drain valves (normal or emergency) should be open and not both. The licensee's training staff indicated that apparently this configuration set up was to avoid nuisance alarms associated with the cycling of the dump valves. The valve error was considered a potential simulator fidelity ite Main Turbine Load Demand The load demand limiter was not operating satisfactoril Limiter During an evolution to reduce reactor power and subsequent shutdown of the Main Turbine, the operators attempted to reduce the demanded load limit on the turbine to verify bypass valve operation. When the load limiter setpoint was lowered (it would not lower less than 55 MWe) the turbine did not shed its load to allow the bypass valves to operat Simulator froze The simulator froze on one occasion for no apparent reason during the performance of the simulator scenario examinatio I Simulator failed The simulator failed on one occasion during the i examination validation week. During a simulator scenario validation, a scenario back track was attempted to review the system response to a malfunction. However, when the back track was initiated the simulator failed. The cause ;

was unknow !

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EXECUTIVE SUMMARY Fermi 2 Nuclear Power Plant NRC Examination Report 50-341/98301 The Fermi 2 training department developed an initial operator licensing examination that was administered to twelve license applicants by NRC examiner Results:

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Four Reactor Operator and two Senior Reactor applicants passed their examinations and were issued operator licenses. Two Reactor Operator applicants failed the written examination, one Senior Reactor Operator applicant and two Reactor Operator applicants failed the operating examination, and one Senior Reactor Operator applicant failed both the written and operating examination Reoort Summarv:

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Control Room operators displayed proper professionalism and demonstrated an appropriate level of attentiveness to the operating panels and were knowledgeable of plant conditions. (Section 01.1)

. Several procedures reviewed by the examiners contained weaknesses. The weaknesses were considered an inspection followup item. (Section 03)

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The licensee's knowledge of the examination development guidelines, attention to detail during examination development, and the ability to develop technically accurate JPMs and written examination material in accordance with the examination guidelines was considered satisfactory. Several deficiencies were identified by the examiners, the most significant being the need to increase the difficulty level of the enmution. (Section 05.2)

. Training staff members demonstrated a lack of attention to detail when they failed to properly prepare the simulator for administration of the operating test. The simulator did 1 not always respond correctly during the examination. Examiners were able to complete i the examination and properly evaluate applicants despite the simulator problem l (Section 05.3) l

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The high failure rate on the examination sugger,ted that the applicants were not well I prepared for the examination. Control and supervision of reactivity manipulations was considered a strength. SRO ability to determine protective action recommendations and the ability to review and use the dose projection report were considered Administrative JPM weaknesses. Applicant performance in annunciator response, event diagnosis, command and control, and the use of and familiarity with operating procedures needed improvement. (Section 05.4)

ES-401 Site-Specific Written Examination Form ES-401-7

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Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Infonnation Name: MASTER EXAMINATION Region: ill Date: 04/06/98 Facility / Unit: Ferml 2 License Level: RO Reactor Type: GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected four hours after the examination start Applicant Certification All work done on this examination is my own. I have neither given nor received ai Applicant's Signature Results Examination Value 100 Points Applicant's Score Points Applicant's Grade Percent NUREG-1021 1 of 1 Interim Rev. 8, January 1997

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REACTOR OPERATOR-

" QUESTION: 1 When a LOCA signal is received,.the Core Spray Inboard and outboard Isolation Valves.will receive an Open signal:

I a. when the CS pumps start, b. after a 5 second time dela c. wisen RPV pressure decreases to'461 psi d. when the CS pump. discharge pressure increases to 145 psi POINT VALUE: '1.00

. ANSWER: REFERENCE: 23.203

'K/A 209001 A3.01.[3.6/3.6]

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COGNITIVE LEVEL:- 1 OBJECTIVE: OP-315-0040-001-01-05 EXAM BANK NO: None SOURCE: Ban USE: 1993 RO Written, Ques. 57

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REACTOR OPERATOR QUESTION: 2

=Whenever HPCI is to be operated for surveillance testing, torus cooling is required to be placed in service as a prerequisite to starting HPC Insuring that. torus cooling is in service before operating HPCI:

~ allows the maximum average suppression pool water temperature limit to be increased to 105'F.

ensures adequate thermal mixing of the water in the suppression pool to limit stress on the torus shell due to differential thermal expansio + extends the operating time for HPCI testing before the maximum average temperature limit is reached and testing is required to be stopped, d'. ensures that heat added to the suppression pool does not increase torus air space pressure to the point where the suppression Chamber l- .to Drywell vacuum breakers cycl POINT VALUE: 1.00 ANSWER: c.

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REFERENCE: Tech Specs 3.6.2.1 l-

K/A 295013 AK2.01 [3.6/3.7]

COGNITIVE LEVEL: 1 i OBJECTIVE: OP-315-0016-001-01-05f i

EXAM BANK NO: None SOURCE: New USE: N/A l

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. REACTOR OPERATOR QUESTION: 3

, Following a complete loss of off-site power, RHR pump C will become a load I- on which one of the following?

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EC ED POINT VALUE: 1.00 ANSWER: REFERENCE: 23.205 K/A: '203000 K2.01 [3.5/3.5)

COGNITIVE LEVEL: l OBJECTIVE: OP-315-0041-001-01-04 EXAM BANK NO: None SOURCE: New USE: N/A l

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REACTOR OPERATOR QUESTION: 4 A pressure transient has occurred with reactor pressure reaching 1097 psig and initiating a reactor scra Which~one of the following describes the expected indications if this transient resulted in a leaking SRV? SRV Tailpipe temperature approximately 210*F; red SRV OPEN light O SRV Tailpipe temperature approximately 215'F; SRV OPEN Annunciator 1D61 O SRV Tailpipe temperature approximately 220*F; red SRV OPEN light O SRV Tailpipe. temperature approximately 225'F; SRV OPEN Annunciator 1D61 O POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 1D61 K/As- 295025 EK1'.03 [3.6/3.8)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0005-001-01-24C EXAM BANK NO: None SOURCE: New USE: N/A 1

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I u__.._____.___=__________-.... - - . . . _ REACTOR OPERATOR QUESTION: 5 What action would an operator use to deal with a nuisance alarm caused by work on the N Aux Boiler Water Level control? Use the defeat matrix on the side of the H11-P60 Defeat the annunciator in the relay room, Place a maintenance placard by the alarm windo Place a CRIS Dot by the alarm window.

POINT VALUE: 1.00 ANSWER: c.

REFERENCE: MOPO4 K/A 234001 2.1.01 [3.7/3.8)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-4101-0025d EXAM BANK NO: None SOURCE: New USE: N/A

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REACTOR OPERATOR QUESTION:- 6 Which one of the following is the basis for the Technical Specifications, Minimum Suppression Chamber Water Volume in Operation Conditions 1, 2 and 37

.a. Ensures.that a sufficient supply of water is available in the event of a LOCA to permit recirculation cooling flow to the cor , Establishes a sufficient supply of water available to permit a shutdown with boron injection without exceeding Containment Design limit Ensures adequate heat capacity to bring the plant to Cold Shutdown with one Safety Relief Valve stuck'open.

! ' Provides sufficient supply of water that, with the Minimum CST Volume, Long Term Cooling is available for the design basis acciden POINT VALUE: 1.00 i ANSWER: REFERENCE: Tech Specs B3/4.5.3

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'K/A: 295030 2.2.25 [2.5/3.7)

l COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0016-001-01-09 EXAM BANK NO: None SOURCE: New USE: N/A (.

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REACTOR OPERATOR

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QUESTION: 7 i

From full power operation, a transient has occurre The following l annunciators were received: j 3D73, Trip Actuators A1/A2 Tripped 3D74, Trip Actuators B1/B2 Tripped 3D99, APRM Upscale Neutron / Thermal Trip j l

Immediately after receipt of these annunciators, the following parameters were reported to the NASS:  !

Reactor Power 48% and stable RPV Level 164 inches, decreasing slowly Reactor Pressure 1085 psig, increasing slowly  ;

i With these plant conditions, what is the first action that must be j performed, and which indication must be observed to verify proper response? j 1 Manually operate SRVs to stabilize pressure at less than 1050 psig; i observe Div 1 and 2 post-accident recorder ) Place the SVLCV Bypass Valve Mode Switch in STARTUP, and verify RPV level is not increasing, Initiate Alternate Rod Insertion; perform CD-7 option j Place the Reactor Mode switch in SHUTDOWN; verify blue group scram i

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lights are Of POINT VALUE: 1.00 ANSWER: l REFERENCE: 20.000.21, ST-OP-802-3003-001 K/A: 295037 EA1.01 (4.6/4.6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3003-001-01-13f EXAM BANK NO: None SOURCE: New USE: N/A i.

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-REACTOR OPERATOR QUESTION: 8 .'

l l 'Following a Reactor Scram from full power total feedwater flow is 15%. The !

l ' operator must verify the Recirculation Pumps have run back to:

l 1 to 30% to.37% to 40%

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, to 48%

POINT VALUE: 1.00 ANSWER . @ gg REFERENCE: 20.000~21, ARP 3D126/3D150 .

K/A 295006 AK3.06 - [3.2/3.3)

I COGNITIVE. LEVEL: 1 OBJECTIVE: OP-315-0004-001-01-03k EXAM BANK NO: -None SOURCE: New USE: N/A l

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REACTOR OPERATOR

. QUESTION: 9 During'a LOCA, the A and-C RHR Pumps are injecting in the LPCI Mode. An operator attempts to place the A loop of RHR in Torus Spray / Cooling by depressing the open pushbuttons for valves E1150-F028A, Div 1 RHR To ms Iso Vlv; E1150-F027A, Div 1 RHR Torus Spray Iso Vlv; and E11-F024A, Div 1 RHR Torus C1g Iso Vl .Which one of.the'following will occur? The valves will NOT open due-to a LPCI initiation signal still presen The valves may be opened but will'immediately~close due to a LPCI Initiation interlock signa E1150-F028A and F027A will open, but E11-F024A will NOT ope All.three' valves can be opened after the LPCI Loop Selection Circuitry has timed ou POINT VALUE:' 1.00 ANSWER:, REFERENCE: 23.205 K/A 230000 K4.03 (3.5/3.6)

COGNITIVE L2 VEL: 2 OBJECTIVE: OP-315-0041-001-01-03 EXAM BANK NO: None-SOURCE: New USE:- N/A

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REACTOR OPERATOR QUESTION: .10-which one of the following statements describes the effects on RPS of shifting the Reactor Mode Switch from START / HOT STANDBY to RUN? Removes APRM Neutron Flux-Upscale, Setdown trip Enables MSIV Closure and RPV High Pressure trips Bypasses Startup Range Nuclear Monitoring trips

' Bypasses IRM High and Inop trips

. Removes APRM Neutron Flux-Upscale, Setdown trip Enables MSIV Closure and APRM Downscale/IRh Upscale trips

. Enables MSIV Closure Removes APRM Neutron Flux-Upscale, Setdown trip I Removes SDV High Level bypass capability Bypasses IRM High and Inop trip Removes SDV High Level bypass capability Enables MSIV Closure and'APRM Downscale/IRM Upscale trips )

POINT VALUE: 1.00 ANSWER:- '

' REFERENCE:

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22.000.02, ST-OP-315-0027-001 K/A: 212000 A2.16 [4/4.1]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0027-001-01-04a EXAM BANK NO None SOURCE: New USE: N/A L_______-_-____-- _ _ _ _ - _ - . _ _ _ - -__

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REACTOR OPERATOR QUESTION: 11 The drywell to torus vacuum breakers are set to maintain the drywell to torus differential I,ressure within set limits to:

a. Prevent expansive failure of the downcomer between the drywell and torus, b. Minimize impact loading on the torus in the event of a rapid drywell pressure increase due to an acciden c. Prevent exceeding the design differential pressure between primary and secondary containment, d. Minimize the pump head differential for the RHR pumps taking a suction from the torus and discharging through the torus and drywell spray header POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-315-0016-001 K/A: 295010 AK2.02 [3.3/3.5)

COGNITIVE LEVEL: 1

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OBJECTIVE: OP-315-0016-001-01-04a EXAM BANK NO: None SOURCE: New USE: N/A

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' REACTOR OPERATOR l-l QUESTION: 12 l

20 minutes after a LOCA, the following conditions exist:

Reactor' Water Level 17 inches l Reactor Pressure 42 psig l Main Steam Line Pressure 38 psig Control' Air Pressure 85 psig Which one of the following conditions must be met to initiate Div 1 of the MSIV Leakage. Control System (MSIVLCS)?

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' Initiate keylock switch placed in INITIATE and reactor pressure less than 44 psi ,

i Initiate keylock switch placed in INITIATE and Control Air-pressure greater than 95 psig.

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c. : Initiate keylock switch placed in INITIATE and reactor pressure f-less than 32.9 psi Initiate keylock switch placed in INITIATE and main steam pressure between the inboard and outboard MSIVs less than 30 psi i l- POINT VALUE: 1.00 i-ANSWER:

' I-REFERENCE: 23.137.01 Sect ~K/A 239003 A4.01 (3.2/3.2)'

l COGNITIVE LEVEL 2 -i

.LOBJECTIVE: OP-315-0005-001-01-30 .

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EXAM BANK NO: None-SOURCE . New-

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QUESTION: 13 Following a small break LOCA the following conditions exist:

l Drywell pressure 11 psig, increasing Reactor-Level 140 inches, increasing Reactor Pressure 83 psig, decreasing Div 1 RHR Loop operating in the LPCI Mode Div 2 RHR Loop operating in the Torus Spray Mode l What are the minimum manipulations required to initiate Drywell Spray with

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Div 2 RHR, assuming the above conditions are true? Depress open pushbutton for-E1150-F021B, Div 2 RHR DW Spray Inbd Iso Viv

- Depress open pushbutton for E1150-F016B, Div 2 RHR DW Spray Otbd Iso Vlv, to throttle open valve b. .- Depress open pushbutton for E1150-F021B, Div 2 RHR DW Spray Inbd I Iso Viv

- Place keylock switch for E1150-F016B, Div 2 RHR DW Spray Otbd Iso Viv, to OPERATE

- Depress open pushbutton for E1150-F016B, Div 2 RHR DW Spray Otbd i . Iso Viv, to throttle open valve l- Place keylock switch for E1150-F021B, Div 2 RHR DW Spray Inbd Iso f

Viv,.to OPERATE ( - Place keylock switch for E1150-F016B, Div 2 RHR DW Spray Otbd Iso

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Vlv, to OPERATE

[ Place keylock switch for E1150-P021B, Div 2 RER DW Spray Inbd Iso Viv, to OPERATE

- Depress open pushbutton for.E1150-F021B,.Div 2 RHR DW Spray Inbd-Iso Vlv

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- Depress open pushbutton for E1150-F016B, Div 2 RHR DW Spray Otbd Iso Viv, to throttle open valve

. POINT VALUE: 1.00

~ ANSWER: REFERENCE: 23.205 i K/A EK2.11 [4.2/4.2)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0041-001-01-12 l I

EXAM BANK NO: None SOURCE: New USE: N/A l i

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REACTOR OPERATOR l'

QUESTION: 14 Following a Scram and MSIV Isolation, Reactor Level decreased to 142 inches, then momentarily spiked to 215 inches when the SRVs opened. Currently Reactor Level is 182 inches and slowly lowering. You have been directed to place RCIC in servic Which of the following actions is required to start RCIC under these conditions?

a . . Open F0 9 5, RCIC Stm Inlet Bypass Valve, wait 15 seconds and open F045, RCIC Steam Inlet Valve.

I- Close and re-open F059, RCIC Turbine Inlet Trip Throttle Valve, then open F045, RCIC Steam Inlet Valv Depress the Level 9 reset button, open F095, RCIC Stm Inlet Bypass Valve, wait 15 seconds and open F045, RCIC Steam Inlet Valve, d.~ Depress the Logic A and B Isolation reset buttons and open F059,

!- RCIC Turbine Inlet Trip Throttle Valv POINT VALUE: 1.00 ANSWER:. . REFERENCE: 23.206

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K/A: 295008 AK2.06 [3.4/3.6]

COGNITIVE LEVEL: 2

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OBJECTIVE: OP-315-0043-001-01-04a, 06d- )

i EXAM BANK NO: .None l l

SOURCE: New  !

- USE: N/A )

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REACTOR OPERATOR ,

QUESTION: 15 The plant is in Mode 3 with RHR Div 1 in Shutdown Cooling operatio Annunciator 1D33, RHR System Overpressure, is received. The Shutdown Cooling Inboard and Outboard Isolation valves, E1150-F008 and F009, have closed, and the operating RHR pump has trippe The basis for these automatic actions is to prevent:

J a. Overpressurizing the RHR pump seals, b. Overpressurizing the shutdown cooling suction pipin l c. Establishing a drain path from the RPV to the torus, l

d. Steam voiding in the RHR pump seal POINT VALUE: 1.00 ANSWER: REFERENCE: 23.205, ARP 1D33, ST-OP-315-0041-001 I

K/A: 295007 AK3.05 (3/3.2)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0041-001-01-03 EXAM BANK NO: None SOURCE: New USE: N/A l I

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REACTOR OPERATOR QUESTION: 16 During core alterations, the SRM shorting links are required to be removed EXCEPT when?

a. less than 16 fuel bundles have been installed in the core b. SRM signal-to-noise ration-is greater than 20 c. special movable detectors are being used until the installed SRMs indicate greater than 3 cpm d. adequate shutdown margin has been demonstrate . POINT VALUE: 1.00 ANSWER: REFERENCE: /4. '

.K/A:- 215004 K4.02 [3.2/3.2)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0022-001-01-05c-EXAM. BANK NO: None  ;

SOURCE:- New

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REACTOR OPERATOR

' QUESTION: 17 Following a transient at power, a Reactor Scram has occurred,.and annunciator 3D12, Div I/II Off Gas Radn Monitor High-High, has alarme Channel A and B Off Gas Radiation Monitors are both reading 1100 mr/h Based on these indications, what action (s) must be performed?

i a. Verify Radiation Protection surveys the Scram Discharge Volum b. Ensure-the scram is reset within 5 minutes.

i Isolate the Main Steam lines, and initiate MSIVLC d. Verify or initiate a trip of the Mechanical vacuum pump POINT VALUE: l' 00'

ANSWER: REFERENCE: 20.000.21 Caution ,

K/A: 295006 2.1.02 [3/4]

COGNITIVE LEVEL: 2 l OBJECTIVE: OP-802-2002-001-01-07 EXAM BANK NO: None

' SOURCE: New USE: N/A

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REACTOR OPERATOR QUESTION: 18 The operating solenoid for Backup Scram Valve C11-F110A has failed. Which one of the following describes the operational significance of this failure?

a. C11-F110A will fail to its deenergized position and vent the air pressure from the Scram Pilot Air Header, resulting in a reactor scra b, C11-F110A will not open, preventing the Backup Scram Valves from venting pressure from the Scram Pilot Air Header if a scram signal is received, c. C11-F110A will not reposition, but C11-F110B will shift to isolate the air supply and vent the Scram Pilot Air Header through a check valve around C11-F110A, if a scram signal is receive d. C11-F110A will fail to,the vent position but will NOT vent air from the Scram Pilot Air Header because it is isolated from the header by Backup Scram Valve C11-F110 POINT VALUE: 1.00 ANSWER: REFERENCE: 20.300.09, ST-OP-315-0010-001 Fig 1 K/A 201001 K2.03 [3.5/3.6)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0010-001-01-04m EXAM BANK NO: None SOURCE: New USE: N/A l

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i QUESTION: 19 The plant is operating at full power. Several annunciators have been ,

received in the last few minutes, including 3D5, CRD Charging H2O Pressure l Low, and 3D10, CRD Accumulator Trouble. The following information is j

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available:

E41-R609.,'HPCI Pump Suction Pressure Indicator, indicates O psig, i- C11-PDIS-N002, CRD Drive Water Filter Differential Pressure, indicates O psi C11-R603, Cooling Water to Reactor Differential Pressure Indicator, indicates o pai :

.C11-R800, CRD Hydraulic Flow Ind, indicates 1 gp !

l which one of the following is the reason annunciators 3D5 and 3D10 were

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received? The operating CRD pump has trippe C11-F034, Charging Header Isolation Valve, has been close The in-s.ervice CRD flow control valve has failed close C1152-F003, CRD Drive / Cooling Water PCV, has been close POINT VALUE: 1.00 J ANSWER: REFERENCE: 20.106.01 l

K/A: 295022 AA2.02 [3.3/3.4] I l

COGNITIVE LEVEL: 3 i OBJECTIVE: OP-802-2004-001-01-02 l EXAM BANK NO: None SOURCE: New j USE: ,

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REACTOR OPERATOR l

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QUESTION: 20

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l During normal full power operation, Recirc Pump A trips. Recirc Loop B flow indicates'21,600 gpm, and thermal power is approximately 40%. l What action'is required due to these plant conditions? )

l a. ' Place the Reactor Mode Switch in SHUTDOW j Insert control rods using the CRAM array or at the direction of the SN ,

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! For these power and flow conditions, the only action required is to I l -monitor for neutron flux instabilit Raise operating loop flow to greater than 50%.

. POINT VALUE: 1.00 l

ANSWER: REFERENCE: 20.138.01 K/A: 295001 AKl.02 [3.3/3.5) i

COGNITIVE LEVEL: ' -2 OBJECTIVE: OP-802-2003-001-01-15g 1 EXAM BANK NO: None SOURCE: New

.USE: N/A l

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l REACTOR OPERATOR QUESTION: 21 During a plant startup, the Bypcas Valve Mode Switch is placed to RUN when RPV level control is shifted to the RFPTs from the SULC A mechanical failure of this switch (switch contacts remaining in the START position)

. occurre With these conditions, which one of the following is expected to occur when a scram signal is recieved? Level setdown to approximately 150 inches at 3 seconds after the scram SULCV transfer to Auto 30 seconds after the scram Auto closure of N2100-F607 and F608, N and S RFP Discharge Line Isolation Valves 30 seconds after the scram RFPT speed limited'to approximately 2300 rpm 60 seconds after the scram POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 5D93, 23.107 K/A: 259001 A2.07 (3.7/3.8)

. COGNITIVE LEVEL: 3 OBJE'OTIVE : .OP-315-0046-001-01-04h EXAM BANK NO: None SOURCE: New USE: N/A I

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REACTOR OPERATOR

_ QUESTION: 22

. ADS uscs input from the Nuclear Boiler Instrumentation as part of the initiation logic. ADS level inputs are 31 inches from Wide Range

. instrumentation with a confirmatory level indication of:

c. 110 inches from Narrow Range instrumentation, b. 110 inches'from the redundant division Wide Range instrumentation.

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.c. 173 inches from Narrow Range instrumentatio d. 173 inches from redundant division Wide Range instrumentatio POINT VALUE: 1.00 ANSWER: REFERENCE: 23.201 Sect 7.0, ST-OP-315-0021 Table 4 l

l' K/A: ' 218000.K1.03 [3.7/3.8)

l COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0042-001-01-09e EXAM BANK NO:' None SOURCE: New l l

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QUESTION: 23 EDG-11 is paralleled to EDG Bus 11EA and is loaded to 1800kW. Heavy snow and high winds cause-a loss of off-site power. Which of the following

- describes the Emergency Diesel Generator System response?

a. ' EDG continues with current loads on its bus.- The diesel output breaker opens; EDG continues to run; output breaker must be closed manually.

, The diesel output breaker opens; EDG trips off; EDG must be started-l manually then will load normally.

d. - The diesel output breaker opens; EDG continues to run; output breaker closes automaticall POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-315-0065-001 K/A: 264000 A3.05 [3.4/3.5]

COGNITIVE LEVEL: 1 OBJECTIVE- OP-315-0065-001-01-1Bf EXAM RANK NO: None ,

- SOURCE: . Bank USE:l 1993 RO Written, Ques. 39 r

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l REACTOR OPERATOR QUESTION: 24 l

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An Alert has been declared, and the Operations Support Center (OSC) becomes uninhabitable. The NSS directs the Alternate Operations Support Center to be manne Where would the operators assemble?

a. Technical Support Center b. Northeast entrance to the Turbine Building ist floor

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c. Office Service Building Machine Shop area d. The' Dedicated Shutdown Panel on 2nd floor Radwaste Building POINT VALUE: 1.00 ANSWER: REFERENCE:' EP-301-01

K/A: 294004 2.4.39 [3.3/3.9)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-4101-0018a EXAM BANK NO: None SOURCE: New USE: N/A

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REACTOR OPERATOR QUESTION: 25 l

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The plant is operating at 14% reactor power. A non-selected control rod drifts in from position 36 to position 00. The Rod Worth Minimizer (RWM)

has identified this control rod as an insert error and produced a rod bloc Which one of the following statements describes the action which must be taken with regard to the RWM in order to continue the startup? With only one rod inoperable, station a second operator to verify rod motion, bypass the RWM, and continue the plant startu Remove the control rod from the enforcement sequence by using the RWM control rod bypass function and restore the control rod to its original positio The rod must be declared inoperable and substitute position data l entered into the RWM until power has been increased above the LPS Correct the cause of the rod drift, bypass the RWM, and restore the ,

control rod'to its original position using another operator for I second verificatio POINT VALUE: 1.00 ANSWER: REFERENCE: 23.608, 24.608 K/A: 201006 A2.03 [3/3.2]

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COGNITIVE LEVEL: 3 j OBJECTIVE: OP-315-0013-001-01-04a EXAM BANK NO: None SOURCE: New USE: N/A

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QUESTION: 26 i

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! Which one of the following is a correct safety Limit statement per the Technical Specifications?

a. The Reactor Vessel Water Level shall be above the top of the active irradiated fuel in Operational Conditions 3, 4, & 5.

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b. The Minimum Critical Power Ratio shall not be less than the Safety Limit MCPR of 1.08 for two recirculation loop operatio c. The reactor coolant system pressure shall not exceed 1375 psig as measured in the reactor vessel steam dom d. Thermal Power shall not exceed 25% of Rated Thermal Power with the reactor vessel steam dome pressure less than 785 psig or core flow less than 15% of rated flo POINT VALUE: 1.00 ANSWER: l l

REFERENCE: Tech Specs j i

i K/A: 294001 2.1.10 [2.7/3.9) '

l COGNITIVE LEVEL: 2-  !

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l OBJECTIVE: OP-804-4001-0005 1 l i EXAM BANK NO: None .

SOURCE: New j: USE: N/A l '

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REACTOR OPERATOR QUESTION: 27 l During a small break LOCA, HPCI has auto initiated and is being used for RPV l injection when annunciator 2D61, HPCI Turbine Exh Diaph Pressure High,

! alarms. Which one of the statements below describes the HPCI system operation?

a. HPCI Turbine trips. As the turbine stop valve closes, the High Exhaust Diaphragm pressure clears and HPCI re-initiates and resumes injectio h. HPCI Turbine trip If further HPCI operation is needed, depress the HPCI Turbine Trip Reset pushbutton. HPCI will restart if the High Exhaust Diaphragm Pressure alarm has cleare c. The HPCI System isolates and the HPCI Turbine trip If further HPCI operation is directed by the NSS, verify 2D61 is clear, turn the HPCI Logic A and B keylock isolation trip switches to RESET to clear the isolation. HPCI isolation valves will auto open and the turbine re-initiates and resumes injectio d. The HPCI System isolates and the HPCI Turbine trip If further HPCI operation is directed by the NSS, verify 2D61 is clear, turn the HPCI Logic A and B keylock isolation trip switches to RESET to

clear the isolation. Manually reopen HPCI isolation valves to re-initiate HPCI and resume injectio POINT VALUE: 1.00 ANSWER: REFERENCE: 23.202, ST-OP-315-0039-001 K/A: 206000 Kl.11 [3.5/3.5]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0039-001-01-06d EXAM BANK NO: None SOURCE: New USE: N/A

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' REACTOR OPERATOR QUESTION ~ 28 .

l A temporary change is appropriate'for which of the following conditions?.

a. ~ To correct a valve lineup, To correct-incorrect Source Reference Changes to administrative procedure To revise surveillance acceptance criteria when the surveillance is performed as-m-post maintenance test ite POINT VALUE: 1.00

' ANSWER: )

REFERENCE: MGA04 K/As- 294002 2.2.11 [2.5/3.4)

COGNITIVE LEVEL: 1 l

OBJECTIVE: OP-802-4101-0014a I

EXAM BANK NO: EQ-OP-802-4101-0007-002

. SOURCE: Bank USE:. OC&P Exam 1 .

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REACTOR OPERATOR f

QUESTION: 29 l

'The plant is operating at full power when the following annunciators are

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received: I i

! '9D17, Div 1 ESS 130V Battery 2PA Trouble

.1D6, Div 1 CSS Logic Power Failure 1D8, RHR Logic A Power Failure 1D62, Stm Lk Det HPCI Logic Power Failure Based upon this information, determine which of the'following components / systems will NOT function as designe a. 345kV breakers CM and CF control power b. Scram Pilot Air Hdr Backup Scram SOV, C11-F110A c. HPCI Barometric Condenser Vacuum Pamp, E4101-C003 d. Outboard MSIV control logic POINT VALUE: 1.00 l

ANSWER: REFERENCE: 20.300.09

,_ K/A: 295004 AA1.01. [3.3/3.4)

COGNITIVE LEVEL: 3

.. OBJECTIVE: OP-315-0064-001-01-03a l

!- EXAM BANK NO: None j' SOURCE: New USE: N/A

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REACTOR OPERATOR-QUESTION '. 30 Portions-of a Surveillance procedure requiring step sign-offs must be performed in a contaminated are Which'of the following is an acceptable method of completeing the required actions of the procedure?

a. A detailed briefing on the steps to be performed by the Tagging Center Supervisor and sign off the pertinent. steps pror to entering l the contaminated are b, signing off the procedural steps'immediately upon leaving the contaminated area.

i c. Contact the Control Room to have the steps logged upon leaving the contaminated are ~

d. Take a copy of the procedure section to be performed into the contaminated area and transcribe the sign-offs on leaving the are POINT VALUE: 1.00 ANSWER: REFERENCE: MGA03 Encl A L K/A 294004 2.4.11 [3.4/3.1).

. COGNITIVE LEVEL: 1 JOBJECTIVE: OP-802-4101-0025a i' EXAM BANK NO: 'None-SOURCE: New l

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l REACTOR OPERATOR QUESTION: 31 While the plant is operating at full power, annunciator 7D50, Div I/II control Air Compressor Auto Start, is receive Immediately following receipt of this annunciator, plant conditions were ,

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RPV Pressure 1024 psig and stable

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Reactor Power 90% and stable

- Both RR MG Sets 77% speed with no limiter in effect Assuming all plant system / components function as designed, which one of the following identifies the cause of the annunciator and the inistal response to take? The Control Air Compressor started on an RPV Level 2 initiation signa Enter 29.100.01, RPV Control, b. The control Air Compressor started on Control Air header pressure less than 80 psig. Dispatch an operator to cross-connect IAS to Div 2 NIA The Control J.ir Compressor has started on Control Air pressure less than 85 psig. Enter 20.129.01, Loss of Station and/or Control Ai . The Control Air Compressor started on Station Air header pressure less than 90 psig. Enter 20.129.01, Loss of Station and/or Control Ai POINT VALUE: 2.00 ANSWER: REFERENCE: ARP 7D50 K/A: 295019 2.4.10 (3/3.Al COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-2009-001-01-01 EXAM BANK NO: None SOURCE: New USE: N/A i

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REACTOR OPERATOR QUESTION: 32

- The plant is operating at full powex.

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- A reactor scram occurs due to a spurious MSIV closure.

l - All Control Rods do not fully insert into the Core based on the RWM.

I which one of the following determines the reactor is shutdown? Control Rod 10-19 at position 02 and Control Rod 42-59 at position 0 Annunciators 3D103, APRM Downscale in alarm and 3D63, IRM Upscale, clea APRM recorders indicate Downscale, and IRMs recorders indicate 19 on range Process Computer displays XX for all Control Rod positions with a scram signal presen POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 1A K/A: 295015 A2.01 (4.1/4.3)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3003-001-01-021 EXAM BANK NO: None SOURCE: New USE: N/A

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1 '. REACTOR OPERATOR I

i QUESTION: 33 j The following initial conditions exists

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Reactor Power 96%

l Control' Room Pressure +0.175" H2O l Reactor Building Pressure -0.10" H2O-Turbine Building Pressure 0" H2O (atmospheric)

Which one of the following actions is required?

l Trip RBHVAC and start SGTS per ARP 8D46, Div I Reactor Bldg Press l High/ Low.

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j Start SGTS and enter 29.100.01, Secondary Containment and

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Radioactive Releas )

l Enter 20.413.01, Control Center HVAC System Failur )

l Enter 20.000.11, Loss of Secondary Containment and verify proper RBHVAC Fans running or start SGT i POINT VALUE: 1.00 ]

ANSWER: ' l

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. REFERENCE: 29.100.01 SH 5 295035 EA2.01 (3.8/3.9)

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COGNITIVE LEVEL: 1

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4 OBJECTIVE ' OP-802-3005-001-01-02 EXAM BANK NO: None j SOURCE: New USE: N/A l

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I ( REACTOR OPERATOR i

I QUESTIONS. 34

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L With the plant operating at' full power, HPCI is running in full flow test I for surveillance testing, and Div 1 RHR is operating in Suppression Pool

! Cooling. Annunciator 17D8,'.Div II Hydrogen Concentration High, is

[ received. .The CRNSO reports hydrogen reading 2.5% on T50-CRE-R806B, l Suppression.. Chamber Atmosphere Analysis, and confirms that the Div 2 l

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' Atmosphere monitor is aligned to the Torus. , Hydrogen Water Chemistry has t- 'been shut down for two weeks.

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l Which one of the following actions is appropriate at this time?

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l- Isolate the HPCI System to prevent furtner exhaust into the suppression pool per 23.20 Immediately shift Div 1 RHR lineup to provide torus spray per ARP l 17D8.

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l If a chemistry-sample confirms the high hydrogen concentration, isolate HPCI per 23.202 and shift Div 1 RHR to the torus spray mode per 23.20 ' d. ' Vent the torus per 29.100.01.

ll (. POINT VALUE: 1.00 ANSWER: d.

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! ~ REFERENCEt ARP 17D8 t

l K/A: 500000 2.4.11 [3.4/3.6] l

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l< COGNITIVE LEVEL: 2 i j OBJECTIVE: OP-802-3004-001-01-04 EXAM BANK-NO: None SOURCE: New USE: N/A i

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' REACTOR OPERATOR i

QUESTION: 35 i With the plant operating at full power, P4400-F603B, Div 2 EECW Supply Iso i Vlv, .has failed close l Which one of the following actions must be taken to restore cooling water to

.the CRD Pumps?: Verify EECW initiation. EECW will automatically supply RBCCW load j i

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b. . Verify auto start of Div. II EECW and EESW pumps, depress Div. II EECW Iso Reset Switch, and open P4400-F604, Div 2 EECW To CRD Sply Iso Vlv l Close P4400-F601B, Div 2 EECW Return Iso Vlv, manually start Di II EECW and EESW pumps, and open P4400-F604, Div 2 EECW To CRD Sply Iso Vl Place Div 2 EECW Iso Override Sw keylock switch in MANUAL OVERRD, depress Div. II EECW Iso Reset Switch, and open P4400-F604, Div 2 EECW To CRD Sply Iso Vl POINT VALUE: 1.00 ANSWER: b . 4 ,$ w g / W 8M8[ mad REFERENCE: 20.127.01 l

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K/A 295018 AK3.07 [3.1/3. 2] )

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' COGNITIVE LEVEL: 3 l, OBJECTIVE: OP-315-0067-001-01-02h,'01-03a, 01-04 EXAM BANK NO: None

' SOURCE: New ,

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REACTOR OPERATOR QUESTION: 36 During a plant startup, the four NSSSS Condenser Low Vacuum Trip Bypass switches have been verified placed in BYPASS. With preparations to establish condenser vacuum about to commence, one of the four switches malfunctions REMOVING the bypass signa Which one of the following statements describes the result of this malfunction? Some MSIVs close and no 1/2 Scram occurs, Some MSIVs close and a 1/2 Scram occurs, The MSIVs remain open and a 1/2 Scram occur The MSIVs remain open and no 1/2 Scram occur POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 1D47 K/J.: 239001 K6.06 [3.8/3.9)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0005-001-01-09a EXAM BANK NO: None SOURCE: New USE: N/A l

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l REACTOR OPERATOR i

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QUESTION: 37 Which one of the following actions is required when a vioible break cannot be demonstrated for disconnecting a piece of electrical equipment from its

'. . power supply?

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' In'ependen d verification of deenergization is required and a blocking device approved by the Protection Leader must be installe b. An approved grounding device must be used and the Protection Leader and Operating Authority must approve the ground installation.

An approved non-visible break device may be used provided the non-l visible break is secured with an approved blocking device and the Protection Leader and Operating Authority must approve a method for determining that power is remove The. Operating Authority may permit work to proceed provided the circuits are independently verified deenergized and an observer is

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positioned at the power' suppl POINT VALUE:-- 1.00 ANSWER: REFERENCE: MOP 12 K/A: 294002 2.2.13 [3.6/3.8)

COGNITIVE LEVEL's 1

, OBJECTIVE: OP-802-4101-0030b EXAM BANK NO: None

~ SOURCE:- New USE: N/A

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REACTOR OPERATOR QUESTION: 38 Following a Loss of Off-Site Power, the EDGs have started. With the EDG breaker closed, which one statement below contains the additional signal required to start the EDG Digital Load Sequencer? (

l EDG bus undervoltage EDG bus lockout relays reset EDG bus underfrequency EDG bus load shed relay deenergize POINT VALUE: 1.00 ANSWER: REFERENCE: 23.321 K/A 295003 AK3.03 [3.$/3.6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0065-001-01-15c EXAM BANK NO: None SOURCE: New USE: N/A

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l REACTOR OPERATOR-QUESTION: 39 l

During a refueling outage, fuel has been almost completely reloaded into the core when it becomes necessary to withdraw a control ro Which one of the.following precautions must be taken? Verify the Reactor Mode switch is locked in SHUTDOWN and 1 rod out interlock is operabl The refueling crew must remove all fuel from the adjacent core cell ! All personnel must remain out of the line-of-site of the core when the rod is withdraw The shorting links must be installed to provide non-coincidence protectio POINT VALUE: 1.00 ANSWER: REFERENCE: 24.623

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K/At '. 234000 2.2.32 [3.5/3.3] .

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0090-001-01-10 EXAM BANK NO: None SOURCE: New USE: N/A l

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QUESTION: 40

During a LOCA,'the following conditions exist:

All. control rods are fully inserte Reactor Pressure'is 420 psig and stable. Reactor Level is .-7 inches and decreasing at about 3' inches per minut ;

No' sources of injection are currently availabl ')

b in 15 minute '

RHR Systems can be made'availa'le I ,

. . Based on present conditions, which one of the following mechanisms is i

reqdired?

a. Steam Cooling b. Emergency Depressurization-c. Primary Containment Flooding

.d. RPV Flooding i' POINT VALUE: 1.00 l-ANSWER: a.

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! REFERENCE: 29.100.01 SH 1 Step L-12

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! K/A: 295031-EA2.04 [4.6/4.8)

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.' COGNITIVE LEVEL: 3 ~ OBJECTIVE: -OP-801-0000-001-0007; OP-B02-3003-001-13e EXAM BANK NO: .None

- SOURCE: New

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REACTOR OFERATOR

QUESTION: 41 .

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During a loss of Condenser Vacuum, condenser pressure has increased to . psia. . ,

lWhich one of the following will be the next function to occur as condenser 'l pressure continues to increase?

a. - Reactor Feed Pump Turbine Trip i

b. MSIV Closure Main Turbine Trip

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- Main Turbine Bypass Valve closure POINT VALUE: ' 1.00 ANSWER: /. p, REFERENCE: 20.125,01

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K/A 295002 AK2.04 [3.2/3.3)

COGNITIVE LEVEL ' 1 OBJECTIVE: OP-802-2010-001-01-01 EXAM BANK NO: EQ-OP-802-3004-0012-003'

SOURCE: Ban .USE: OCP Comp

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t REACTOR OPEPATOR QUESTION: 42 Due to an error in' performing a surveillance, an MSIV isolation has occurred

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.while operating at. full powe If no operator, action is taken, which of the following. indicates the expected range of reactor pressure 30 minutes after the MSIVs have closed. Assume all' systems and automatic actions function as designe to 150 psig b. ' 905 to 1017 peig to 1047 psig to 960 psig POINT VALUE: 1.00 ANSWER: REFERENCE: 23.201 K/A 295020 AA2.04 [3.9/3.9)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0005-001-01-27'

EXAM BANK NO: .None SOURCE:- New USE N/A

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REACTOR OPERATOR QUESTION: 43 29.100.01, SH 5, Secondary Containment and Rad Release, directs operating available sump pumps whenever secondary containment area or sump levels exceed.their Max Normal Operating levels. This action is based on; Minimizing the spread of contamination within the Secondary containmen b. 1 Containing leakage from a primary system within systems designed for storage of radioactive liquid c. ' Preventing the uncontrolled release of liquid radioactive effluents from the Secondary Containmen , Maintaining water levels below the point at which equipment required for safe shutdown will fai J

POINT VALUE: 1.00 ANSWER:- s REFERENCE: ARP 2DB2, 29.100.01 SH 5 K/A 295036 EK3.04 [3.1/3.4)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-3005-001-01-05 EXAM BANK NO: None l

SOURCE: New I USE: N/A l

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t REACTOR OPERATOR l QUESTION: 44 l

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' ' Which one of the following describes the parameters compared in checking for a' reactivity anamoly?

' Core Thermal Power and APRM indications l

b. - Core Thermal Power and Calculated Control Rod Worth c. ' Actual Control Rod Density and Predicted Control Rod Density

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l Total Control Rod Worth and Calculated Control Rod Worth

^ POINT VALUE: 1.00 ANSWER: REFERENCE: 54.000.02 K/A: 295014 AKl.02 (3.3/3.7)

COGNITIVE LEVEL: 1 J

OBJECTIVE: OP-315-0011-001-01-18 EXAM BANK NO: None

. SOURCE: New USE: N/A

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REACTOR OPERATOR QUEST 70N: 45 The following conditions exist after a LOCA has occurred:

' Torus Water Temp 130*F Torus Pressure -23 psig

- Torus Level +16 inches RPV Level 112 inches and rising RPV Pressure ~249 psig Drywell Pressure 25 psig which one of the following concerns requires action to be taken? ECCS pump suction vortex limits loss of drywell to suppression chamber vacuum breaker function RCIC high exhaust pressure' trip on elevated torus pressure d c

- plugging of low pressure ECCS suction strainers POINT VALUE: .1.00 ANSWER: REFERENCE: 29.100.01 SH 2'-

K/A 295026 2.1.32 [3.4/3.8)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-802-3004-001 01-08 EXAM BANK NO: None SOURCE: New -

USE: N/A

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REACTOR OPERATOR-QUESTION: 46 With the plant operating at' full power,.a steam leak occurs in the drywell resulting in a reactor. scram due to high drywell' pressur The increasing drywell temperatures are a concern for which one of the following RPV Level instruments?. Core Level detectors b, Flood'Up Level detector c.-. Narrow Range Level detectors d .' Wide Range Level detectors

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POINT VALUE: 1.00'

'. ANSWER : REFERENCE: 29.100.01 SH 6 K/A;- -295028.EK2.03 [3.6/3.8)

COGNITIVE LEVEL: 1 OBJECTIVE:' OP-802-3002-001-01-05b

- EXAM BANK NO: None SOURCE: New USE N/A i

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REACTOR OPERATOR QUESTION: 47

. With the plant at full power, which'one of the following describes the

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- effects of a loss of the Rod Position Indicating System on Control Room indication?

-a. All red " full out" and green " full in" indication will deenergize on the full core displa b, If a rod is selected, the white " rod selected" light on the full core display will not energiz c. The LPRM indicators on the 4 rod display will all indicate downscal d. The rod select switch for the selected rod will not light on the rod select matri POINT VALUE .00 ANSWER: REFERENCE: 20.106.08 K/A:' 214 000 A4. 02 - [3.8/3.8)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2005-001-01-01 EXAM BANK NO: None SOURCE: New

' USE: N/A

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REACTOR OPERATO l QUESTION:- 48 Following a Main Steam Line. Break in the Steam Tunnel, how will the room pressure be relieved? Select one answer from the choices' belows Pressure is' automatically relieved through hinged steel doors to l

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relieve the pressure to the Auxiliary Buildin Pressure is automatically relieved to'the Reactor Building through l an equalizing lin l

! Pressure is manually aligned to vent through Relief Hatches in the first floor of the Auxiliary Building, Pressure is manually relieved to the Turbine Building through an  !

equalizing lin POINT VALUE: 1.00 4

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ANSWER: REFERENCE: DWG M-2319 K/A: 295034 EK1.02 (4.1/4.4]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0016-001-01-03j EXAM BANK NO: None SOURCE: New l USE: N/A

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REACTOR OPERATOR i

QUESTION: 4 ;

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During a Reactor Heatup,.on IRM Range 7, the collet fingers on a Control Rod Drive stick in the withdraw position. The control rod is being withdrawn ,

from position 08 to 1 !

Which one of the following statements describes the consequences of this

. event?  ! The rod will drift into the core reducing power and heatup rat b.__ The rod will remain at position 12, and power and heatup rate will stabiliz ' The rod will drift out of the core, and power and heatup rate will I increas The rod will remain at position 08 until drive header pressure has I been increased sufficiently to free the colle POINT VALUE: 1.00

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ANSWER: . REFERENCE: 20.106.07

, K/A: 201003 A1.01 (3.7/3.8)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0009-001-01-05e EXAM BANK NO: None SOURCE: 'New USE: N/A i ,

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REACTOR OPERATOR QUESTION: 50 An Alert level radioactive release is attained whenever a computerized dose assessment indicates a dose rate in~ excess of 10 mrem /hr TEDE at which one of the following locations? Site boundary b. Main Control Room Primary Access Portal d. At any point within the RCA POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 5 K/A: 295038 EA2.02 [3.5/4.3]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3005-001-01-17 EXAM BANK NO: None-

. SOURCE:- New USE: N/A

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REACTOR OPERATOR QUESTION: 51 With the plant at full power, Standby Gas Treatment (SGTS) is operating to

' decrease Drywell Pressure per Section 5.0 of SOP 23.406, Primary Containment Nitrogen Inerting and Purge System through the 6 inch lin Which one of the following ic a concern when operating SGTS in this mode?

a. Exceeding the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> Technical Specification limitation on operation with these valves Ope b. Excessive D/P between the Primary Containment and the Reactor Buildin c. Excessive use of Nitrogen, reducing available nitrogen stores below Tech spec allowed levels, d. Excessive flow through SGTS increasing the D/P across filters and charcoal beds requiring removal of SGTS from servic POINT VALUE: 1.00 ANSWER: REFERENCE: 23.406 K/A: 261000 A1.02 [3.1/3.2)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0020-001-01-05c EXAM BANK NO: None SOURCE: New USE: N/A j

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REACTOR OPERATOR

. QUESTION: 52 Which one of the following statements describes the SLC Squib Valve Continuity circuit and alarm? Current flow through the squib valves is monitored and an alarm is received if current flow in the bridge circuit becomes unbalanced between the firing primer Current through the squib valves is monitored and alarmed if current lowers below a setpoin Resistance of the squib valves is monitored and an alarm is received if resistance in the bridge circuit becomes unbalanced between the firing primer Resistance of the squib valves is monitored and an alarm is received if resistance in the firing primers becomes too hig POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 3D11 K/A: 211000 A4.03 [4.1/4.1)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0014-001-01-04d EXAM BANK NO: None SOURCE: New USE: N/A

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l REACTOR OPERATOR l

l QUESTION: 53 i During plant startup, with reactor pressure at 650 psig, the SULCV has  ;

reached 80% open and an operator is preparing to feed the vessel by placing )

the North RFPT in service. In preparing to feed the RPV using the RFPT, the operator has verified the SULCV M/A station in AUTO and the A Feedwater Flow Control M/A Station in MANUAL. The operator becomes distracted while using )

the OPEN pushbutton at the Feedwater Flow Control M/A station to increase j RFPT speed and increases RFP discharge pressure to 150 psig higher than '

reactor pressur If no other operator action is taken, what will be the RPV water level  ;

response? j l RPV level will increase at a constant rate until the RFPT trips on Level i RPV level will increase resulting in a reactor power increase and I APRM setdown scra RPV level will increase initially, and then fluctuate as the SULCV l attempts to throttle flow with an excessive pressure differentia I RPV level will increase until the SULCV begins to respond and throttle closed to return level to the tape setpoin !

POINT VALUE: 1.00 ANSWER: REFERENCE: 23.107 K/A: 259002 A1.01 [3.8/3.8)

COGNITIVE LEVEL: 2

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OBJECTIVE: OP-315-0046-001-01-04b  ;

EXAM BANK NO: None l SOURCE: New USE: N/A i

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REACTOR OPERATOR QUESTION:' 54 Heavy thunderstorms just' caused a-load-reject from 100% power. The reactor conditions: are '

- APRM Power stable at 20%

- No indications of control rod position

- Recirc pumps tripped

- 'All MSIVs are open

- Reactor Level being maintained by feedwater

- Reactor Pressure being maintained through Turbine Bypass Valves

--

Mode switch in SHUTDOWN'

The NSOs first' actions should bei -

a. Initiate. ADS

. ' Initiate ARI

- Inject SLC d. Drive control rods in POINT VALUE: 1.00 ANSWER' REFERENCE: 29.100.01 SH 1A K/As 212000 A4.16 [4.4/4.4]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-802-3003-001'-01-21 EXAM BANK NO: None SOURCE: Bank USE: 1993 RO Written, Ques. 74 l

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REACTOR OPERATOR l

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l QUESTION: 55 l

l Which one of the following describes the effects of a loss of Div 1 and Div 2 Control Air (NIAS) to the Standby Gas Treatment System (SGTS) ? T4600-F407, RBHVAC to SGTS Iso Vlv, fails Ope SGTS is operable

,

for Secondary Containment only.

1 T4600-F406, HPCI to SGTS Iso Viv, fails Open. SGTS will Auto start and is available for HPCI operatio T4600-F410, RB 5 Air Inlet Iso Vlv, and T4600-F407, RBHVAC to SGTS Iso Vlv, fail Open, T4600-F406, HPCI to SGTS Iso Vlv, fails Closed; SGTS is inoperabl T4600-F410, RB 5 Air Inlet Iso Vlv, and T4600-F407, RBHVAC to SGTS Iso Vlv , fail Closed, T4600-F406, HPCI to SGTS Iso Viv, fails Open; SGTS is inoperabl POINT VALUE: 1.00 ANSWER: REFERENCE: 20.129.01 K/A: 300000 K3.02 [3.3/3.4]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2009-001-01-3e EXAM BANK NO: None SOURCE: New USE: N/A i

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REACTOR OPERATOR QUESTION: 56

i l Following a Turbine Trip, the MAIN TURBINE TRIPPED unciator has NOT alarme Which one of the following conditions would ca se this? /

One of the Main Steam lines to the turbine is NOT isolate /

Reactor power was less than 0% when the turbine trippe This annunciator is only, deceived when the manual trip pushbutton is used to trip the turbin w Pressure Stop Valves failed to clos One of the Turbin/e POINT VALUE: !

ANSWER: a REFERENCE: ARP 4D46 K/A: 295005 AA2.03 [3.1/3.1)

COGNITIVE LEVE : 1 OBJECTIVE: OP-315-0029-001-01-04 EXAM BANK 'O : None SOURCE: New USE: N/A

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,

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_ _ _ - _ - - _ - _ - _ - _ - _ _ - _ _ _ - _ _ _ _ _ - _ - - _ _ _ - _ - . . . _ - _ _ _ _ _ - - _ , _ _ - _ - - . - . -. - - .= _. - - _ . - - _ - _ _ _ _

l REACTOR OPERATOR <

l

. QUESTION: 57-I

Which one of the following states the basis for the Scram Discharge Instrument Volume-(SDIV) high level scram? A reactor scram is inserted to isolate an open flow path connecting the primary coolant boundary to the Secondary containmen A reactor scram is inserted before the scram discharge volume fills and the ability to insert a scram is los c. : A level increase in' the SDIV during power operation is indicative-of multiple leaking scram outlet valves, A level increase in the SDIV during power operation is indicative of a primary coolant boundary leakage flow path.in excess of Tech spec allowable limit POINT VALUE: 1.00 ANSWER' REFERENCE: ARP 3D2, ST-OP-315-0010-001 K/A: 201001 K4.11 [3.6/3.6)

LCOGNITIVE LEVEL: '2 OBJECTIVE: OP-315-0010-001-01-09 EXAM BANK NO: None SOURCE: New- -

USE:L N/A

-:_.._-____-:--__ - __ - _ _ _ _ _ _ - _ _ - - - - .- _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ . _ - _ - _ _ _ _ _ _ - _ - _ - _ - - - _ - _ _ _ _ - --

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REACTOR OPERATOR QUESTION: 58 I-I Which'one of the following' states the significance of reaching +60 inches l Torus water level? Torus level increasing to this point following a LOCA will compress the non-condensables exhausted from the drywell to the torus, l resulting in opening the drywell to suppression chamber vacuum breakers. Opening the vacuum breakers could allow steam flow from j the drywell directly into the torus air space.

I Torus venting cannot be performed above this level if it becomes necessary to vent the Primary Containment to maintain pressure within design limit ' The Suppression Chamber to Drywell Vacuum Breakers will be covered with water and unable to relieve torus pressure to the drywell, thereby posing a threat to containment integrity by allowing the external differential pressure limits to be exceede Above this level there is insufficient free volume to accommodate the non-condensable gases driven into the torus by a LOQ Vibrational, or " chugging", stresses that result from torus spray initiation have not been analyzed for this conditio POINT VALUE: 1.00 ANSWER:- REFERENCE: 29. ESP.01, ST-OP-802-3004-001

'K/A: 295029 EK1.01 {3.4/3.7)

COGNITIVE LEVEL: 2

"0BJECTIVE: OP-802-3004-001-01-02  ;

-EXAM BANK NO:- None SOURCE: New

.USE: N/A I

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REACTOR OPERATOR

^ QUESTION: 59 If the Reactor Mode switch is in START / HOT STANDBY, which one of the following instruments is NOT required to be operable? Reactor Vessel Level 1 for ADS Reactor Vessel Pressure High for ARI , Reactor Vessel Pressure for High Pressure Scram l Reactor Vessel Level 2 RWCU System Isolation POINT VALUE: 1.00 ANSWER: REFERENCE: Tech Specs Table 3. K/A: 215:00 2.2.22 [3 . 4 /4 .1)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0021-001-01-10 EXAM BANK NO: None SOURCE: Bank modified USE: 1993 RO Written, Ques. 28 l

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I REACTOR OPERATOR QUESTION:. 60

'which'one'of the following components positions the Directional control Valves on a CRD Hydraulic ~ Control Unit? Reactor Manual" Control System Timer

! Reactor Protection System Scram Bus Rod Out Notch Override Switch d .' -Control Rod Drive Flow Controller POINT VALUE: 1.00 ANSWER: REFERENCE: 23.623 K/A: 201002 2.1.27 [2.8/2.9)

COGNITIVE LEVEL: 1 OBJECTIVE:  : OP-315-0011-001-01-08g EXAM BANK NO: None SOURCE: New USE: 'N/A

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REACTOR OPERATOR I l QUESTION: 61 ,

1 ) .

i

! Following 'a'_ total loss of the Uninterruptible Power Supply (UP ') at full l power, which one of the following transients would occur?

!  ! Plant scram caused by MSIV isolatio ] Loss of AC Power caused by loss of Generator Control j i i Plant scram caused by a loss of Feedwater, RPV Pressure transient caused by TSV and TCVs failing ope POINT VALUE: 1.00

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ANSWER:- I REFERENCE: 20.300.12- l

~K/A: 262002 K3.01 [3 .1/3 . 3 )

COGNITIVE LEVEL: 3 ( ' OBJECTIVE: OP-315-0062-001-01-06

)

EXAM BANK NO: None l t I j SOURCE: New e USE: N/A

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REACTOR OPERATOR L

QUESTION: 62 A fuel failure.is suspected with the plant operating at full power. The following conditions exists

- Main Steamline Radiation Monitors A,B,C, and D all indicate 19,000 mr/hr

- Off Gas Radiation Monitor indicates 800 mr/hr increasing

- RBHVAC Exhaust Radiation Monitor indicates 11,000 cpm

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What is the expected plant response? /2 Scram and 1/2 Group 1 isolation MSIV Isolation, Reactor Scram and Off Gas Isolation

! RBHVAC System Isolation and SGTS Initiation Reactor Scram on Group 1 Isolation l POINT VALUE: 1.00 ANSWER: g. M , #*g g 7

~ REFERENCE: ARPs 3D12, 3D32, 3D82 ,

K/A: 295017 AK3.01 [3.6/3.9)

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COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0050-001-01-03 EXAM BANK NO: None SOURCE: New

- USE: N/A \

' i a-_.:. - - - _ - -_ - - ---- - - - - . -- - - - - - - - - - - - - - - - --,.r---------s-- _ - - - - - --- ---u-- - - - -- --- . - . - . _ - . - - - . - - --.- u -_ _ - - - . - - . - - - -- .------- - - - - - - _ - _ - _ - _ - - - - - - - - - - . - - _ _ _ _ - - _ - - - , - -

REACTOR OPERATOR QUESTION: 63 During control of the plant from the Dedicated Shutdown Panel, the EF1 Supervisory Control and EF2 System Transfer Switches are placed in LOCA Which one of the following statements describe how this effects SRV operation? SRV G can be operated from the Dedicated Shutdown Panel, automatically if Low-Low set is initiated, or in the Safety Relief Mod SRV G can be operated from the Dedicated Shutdown Panel, or in the Safety Relief Mode, but SRV G Low-Low Set logic is disable SRV A can be operated from the Dedicated Shutdown Panel, automatically if Low-Low Set is initiated, or in the Safety Relief Mod SRV A can be operated from the Dedicated Shutdown Panel, or in the Safety Relief Mode, but SRV A Low-Low Set logic is disabled.

POINT VALUE: 1.00 ANSWER: s REFERENCE: 20.000.18 K/A: 239002 K5.01 [3.4/3.5)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0005-001-01-10b EXAM BANK NO: EQ-OP-802-2017-0001-004 SOURCF: Bank USE: OC&P Exam 4

_ _ _ _ _ - - _ _ - _ . - -____________-_____ _ ___- ___________ ______________ _ _ - ____ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ - _,

REACTOR OPERATOR

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QUESTION: 64 i The plant is operating at 38% power when a piping rupture requires immediate shutdown of the Turbine Building closed Cooling Water (TBCCW) system, i

How will this affect plant operations? An immediate scram and MSIV isolation is require A rapid turbine shutdown and reactor shutdown is require Turbine / Generator load and reactor power must be reduced to 25% to maintain reactor steam production within turbine bypass valve capabilit Peactor power must be reduced to maintain the Off Gas aftercooler outlet temperature within limits to prevent a hydrogen explosio POINT VALUE: 1.00 ANSWER: REFERENCE: 23.128 K/A: 400000 2.4.24 [3.3/3.7)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0037-001-01-06 EXAM BANK NO: None SOURCE: New USE: N/A

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REACTOR OPERATOR QUESTION: . 65 During a small break LOCA with a loss of Feedwater, RCIC is in operation inaintaining RPV level. RCIC suction realigns to the torus. What signal

. caused the RCIC' pump suction to swap from the CST to the Suppression Pool? Suppression Pool level greater than +2 inche RCIC pump suction pressure less than 20" Hg vacuu Condensate Storage Tank Level less than 32". ,

i RCIC pump flow less than 90 gpm causing the minimum flow valve to be open greater than 30 second POINT VALUE: 1.00 ANSWER:. j REFERENCE: ARP 2D48, ST-OP-315-0043-001 K/A: 217000 K6.04 [3.5/3.5]

COGNITIVE LEVEL: 2 OBJECTIVE: 'OP-315-0043-001-01-05d EXAM BANK NO: None SOURCE New j USE: N/A

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REACTOR OPERATOR QUESTION:66 A plant startup is in progress with reactor power at 32%. When withdrawing a control rod from position 08 to position 16 using Rod Out Notch Override, the reactor operator becomes distracted and continues to withdraw the control ro :Which one of the following will function to prevent exceeding thermal limits

'of the fuel? Rod Worth Minimizer' rod block Rod Block Monitor rod block l

I APRM rod block Doppler coefficient of reactivity. No system protection is available because the RWM is in the transition zone.

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POINT VALUE: 1.00 ANSWER: REFERENCM: 23.607 K/A: 215002 2.1.28 [3.2/3.3]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0026-001-01-01 EXAM BANK NO: None SOURCE: Bank USE: 1993 RO Written, Ques. 46

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- - _ - . - - - . - _ - _ _ _ _ - _ - - _ __ . REACTOR OPERATOR QUESTION: 67 You are on shift in the Control Room when a fire alarm on panel H11-P816 involving the halon system is received. Alarm bells and a 45 second pre-discharge horn actuates in the Relay Roo Which of the following additional automatic actions occur when Halon initiates? No additional automatic actions occu HVAC interlocks activate, and the CCHVAC system isolates, HVAC interlocks activate, and the CCHVAC system shifts to purg HVAC interlocks activate, and the CCHVAC system shifts to recirculatio POINT VALUE: 1.00 ANSWER: l REFERENCE: 23.501.03 Sect l K/A: 290003 A3.01 [3.3/3.5]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0073-001-01-06d EXAM BANK NO: None SOURCE: Bank USE: 1993 RO Written, Ques. 58 l

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___ ___ _ _ _ _ _ REACTOR OPERATOR QUESTION: 68 Main Condenser hotwell temperature is required to be maintained greater than 40*F when hotwell level is in the normal operating band.

This limit is based on:

a. nil-ductility limits for the aondenser hotwell reactivity transients caused by cold water addition during startup maintaining operating efficiency of the LP turbines preventing brittle fracture of the condenser pump seals POINT VALUE: 1.00 ANSWER: a.

REFERENCE: 23.107, ST-OP-315-0006-001 K/A 294001 2.1.32 [3.4/3.8}

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0006-001-01-06 EXAM BANK NO: None SOURCE: New USE: N/A

REACTOR OPERATOR QUESTION: 69 The plant is stable at full power. Surveillance 24.106.01, Operable Control Rod Check, is in progress with control rod 26-27 selecte APRM Channel F has the following operable LPRM inputs by level:

Level A 4 Level B 5 Level C 2 Level D 3 One of the Level C LPRM inputs to APRM F fails downscale.

What protective functions, if any, automatically occur? No protective functions occur, Control Rod Block due to RBM INO Control Rod Block due to APRM downscale, Control Rod Block and Half Scram due to APRM INOP.

POINT VALUE: 1.00 ANSWER: d.

REFERENCE: 23.605, ARP 3D93 K/A: 215005 K1.01 [4/4]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0024-001-01-04 EXAM BANK NO: None SOURCE: New USE: N/A

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I REACTOR OPERATOR QUESTION: 70 The plant has been operating at full power with the following conditions:

l Reactor power 96%

RPV level 197-inches j Both RR pumps 79% speed Following a trip of the A Reactor Recirculation Pump,.the following conditions exist -

Reactor Power 62%

RPV Level 190 inches increasing 1 Recirc A.& B Flow Limiter 2/3 Defeat Switch in NORMAL which one of the following describes the Recirculation System's response to these conditions?

i B Recirculation Pump runs back to 30% spee B Recirculation Pump runs back to 45% spee B Recirculation Pump runs back to 75% spee B Recirculation Pump continues to operate at 79% spee POINT VALUE: 1.00 ANSWER: REFERENCE: 20.138.01, 23.138.01 K/At 295009 AA1.03 [3/3.1) j COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2003-001-01-15f EXAM BANK NO: None SOURCE: New USE: N/A i

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REACTOR OPERATOR QUESTION: 71 A station blackout has occurred. The following plant conditions exists

- Breakers GD, GK,'amd GM are ope Breaker GH is close Performance of AOP 20.300.01, " Loss of Offsite and Onsite Power" is in progres An NPPO has placed the breaker control switches for GD and GM in

"NON-AUTO".

- The breaker control switch for breaker GK is in AUT The control' room operator has started CTG-11 and subsequently closes the

. output breaker energizing transformer 1 Which one of the following

.offsite sources has become a load on CTG-117

< Swan Creek Luzon Shoal Brownstown 2 POINT VALUE: 1.00-

' ANSWER: REFERENCE: 20.300.01 K/A: 262001 K2.01 (3.3/3.6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0057-001-01-02c, d EXAM BANK NO: None SOURCE New USE: 'N/A i_____-________-_-- _ _ . . - __ _-__ -_ _ _ _ ____________--_

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l i-REACTOR OPERATOR

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QUESTION: ' 72 A reactor startup is in progress. Power is approximately 1% and is on IRM Range 7. Which of the following conditions will cause annunciators 3D59,  !

'IRM CH A/E/C/G UPSCALE TRIP /INOP, and 3D73, TRIP ACTUATORS A1/A2 TRIPPED, to  !

be received? i

. Loss of Div 2 48/24 VDC power to the IRM drawers l Loss of~DC voltage to the IRM A fission chamber

Loss of signal from IRM E-detector

). Ground.in the IRM C range switch '

POINT VALUE: 1.00  !

ANSWER: REFERENCE: 20.300.11 j K/A: 215003 K6.02 [3.6/3.8) l CCGNITIVE LEVEL: 1 i

OBJECTIVE: OP-315-0064-001-01-051 j EXAM BANK NO:- None  ;

i SOURCE: Bank  !

USE: 1993 RO Written, Ques. 26 l

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REACTOR OPERATOR QUESTION: 73

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The plant is shut down. RHR Loop A was in Shutdown Cocling, but tripped and could NOT be restarted. RHR Loop B is NOT available. You have been directed to verify RPV level greater than 215 inche Which one of the following is the reason for this action? Assures adequate NPSH for starting a Recirc Pum Assures adequate NPSH to the RHR Pumps for subsequent restart Verifies the necessary pressure head to prevent boiling in the cor Assures a flow path through the steam separators for natural circulatio I

<

POINT VALUE: 1.00 ANSWER: REFERENCE: 20.205.01 K/A: 295021 AK1.02 [3.3/3.4]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-2011-001-01-04 EXAM BANK NO: None SOURCE: New USE: N/A l

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< REACTOR OPERATOR I:

l QUESTION: 74-l With the plant at 5B% power, an operator is preparing to start Reactor Recirculation Pump A in preparation for returning to two loop operatio Which one of the following parameters meets the requirements for starting Recirculation Pump A?

a. Bottom Head Drain temperature is 360*F b. Recirc loop A temperature is 505'F c. Recirc loop B flow is 24,500 gpm

- Thermal power is outside of the scram region of the power to flow map ' POINT VALUE: 1.00 ANSWER: REFERENCE: -23.138.01 K/A: 294002 2.2.01 {3.7/3.6)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0004-001-01-0 EXAM BANK NO: None SOURCE: New USE: N/A

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REACTOR OPERATOR l

QUESTION: 75 The plant is operating at full power when annunciator 1D66, Steam Leak Detection Ambient Temp High, is received, and RWCU isolates. An operator sent to RR H11-P614 reports the following:

I G33-TSE-N600A, RWCU Pump Rm A, indicates 181* G33-TSE-N600B, RWCU Pump Rm B, indicates 138' G33-TSE-N600C, RWCU Hx Rm, indicates 122* Which one of the following actions is required?

l Restore RWCU System operation using only RWCU Pump Verify RWCU System is isolated in Pump Room Msace the Mode Switch in SHUTDOW Place the Mode Switch in SHUTDOWN, and initiate Emergency Depressurizatio POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 K/A: 295032 EA1.02 [3.4/3.5)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-3005-001-01-03 EXAM BANK NO: None SOURCE: New USE: N/A u_____ _ - . _ _ _ _ _ _ _ _ _ _ _ - . - - - - - - . _ _ _ _ _

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REACTOR OPERATOR QUESTION: 76

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The plant is operating at 80% reactor power. All equipment required to

'

support 100% power operation is available. The standby pressure regulator is out of service. The in service pressure regulator begins to slowly shut the turbine control valve Which one of the following will occur without operator action? Reactor pressure will begin increasing causing reactor pc.mr increase. MWe will decrease, and the reactor will scram on high pressure or high powe Reactor power will stay the same. Recirc flow control will automatically control reactor power and reactor pressure at the pressure regulator setpoin Reactor pressure will begin decreasing. This will cause reactor power to also decrease. The two will decrease until MSIV low steam pressure isolation is reache ' Reactor power will stabilize at a lower level. Closure of the turbine control valves will reduce steam flow to the LP turbines and consequently to the feedwater heaters. The loss of feedwater heating will produce a Recirc pump runback which will reduce core flow more than enough to compensate for the minor pressure increas POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-315-0045-001  :

K/A: 241000 K3.01 [4.1/4.1]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0045-001-01-13h EXAM BANK NO: None SOURCE: Bank modified USE: 1993 RO Written, Ques. 68

~

-__-_ .-._ _ - _ _ - - _ - _ _ _ - _ - _ - - _ _ _ _ _ _ _ _ _ _ . . . - - - - - _ _ . _ _ _ - - - - - - - _ _ - _ _ - _ _ . - _ _ _ . _ - _ _ _ _ _ _ _ _

l REACTOR OPERATOR QUESTION:- 7 Contact K4G in the Div II Low-low Set Logic (see attached Figure 1) has failed in the closed position. With reactor pressure starting at 944 psig and continuing to increase, at what pressure will the first SRV open?

a, 1017 psig-b. - 1047 psig psig

, psig POINT VALUE: 1.00 ANSWER: ' : REFERENCE: 23.201 K/A 239002 K4.01 [3.9/4]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0005-001-01-27 EXAM BANK NO: None SOURCE: Ne ~ USE: NA

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REACTOR OPERATOR l'

'

QUESTION: 78

Which one of the following signals will actuate the Emergency Diesel Generator (EDG) Fire Suppression System?

'

?

.a. 2 of 7.EDG area smoke detectors activate b. Air temperature within the EDG Room between 215'F and 235' of 7 combination ionization and smoke detectors activate Any smoke detector activated confirmed by a temperature above 1906 ,

' POINT VALUE: 1.00 ANSWER: REFERENCE: 23.501.02 K/A: 206000'K5.05 (3/3.1]

COGNITIVE LEVEL: 1 OBJECTIVES- OP-315-0072-001-01-03c EXAM BANK NO: Non SOURCE: New'

USE: N/A

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l REACTOR OPERATOR i

QUESTIONi 7 I With the' plant. operating at full power, which of the following are expected after a. trip.of RPS Bus A? Inboard MSIV control power and position indication is lost.

,. RBHVAC and TBHVAC will isolate l Div 1 SGTS auto starts and the RWCU pumps trip i Div.1 and Div 2 Drywell Pneumatics Supply Inboard Isolation valves will close POINT VALUE: 1.00 l

l ANSWER: l

-REFERENCE: 23.316 Encl A j K/A: ' 223002 K6.08 [3.5/3.7)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0027-001-01-03d I EXAM BANK NO:- None SOURCE:- New l-l- USEs- N/A

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l REACTOR OPERATOR QUESTION: 80 The plant is in Hot Shutdown at 85 psig RPV Pressure. B loop of RHR is operating in Shutdown Cooling, and the A loop of RHR is in Standb A large break LOCA on the A Recirculation Loop suction pipe occurs causing RPV Level to drop to 18 inche RHR Valves F006 and F009 receive an isolation signal and begin to close; HOWEVER, both valves trip on Thermal Overload while partially close Which one of the following statements describes the response of the LPCI Loop Injection Outboard Isolation Valve, E1150-F017A?

l E1150-F017A can be reopened by depressing the SDC isolation reset pushbutto E1150-F017A cannot be opened until F008 and F009 are close E1150-F017A receives a CLOSE signal for 10 minutes, E1150-F017A closes and remains closed until RHR pump suction 11neup to the Torus is establishe POINT VALUE: 1.00 ANSWER: REFERENCE: 23.205 K/A: 203000 A3.01 (3.8/3.7]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0041-001-01-03 EXAM BANK NO: None SOURCE: New USE: II/A i

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_ . _ . _ _ _ _ - _ _ - _ _ - - _ _ _ - _ - _ - _ _ - _ _ - _ _ _ _ - - - _ . _ _ _ - - - - - - - - -

REACTOR OPERATOR'

l

[ QUESTION: .'81-IWith the plant operating at full power, a small steam leak has resulted in Drywell pressure increasing to 2.4 psig. Which one of the following l

identifies SRVs.which are capable of operation only in the Safety mode?

I i l- , SRVs A, D, K, R SRVs H, J, L, N j

{ SRVs'B,.F, E, R i~ ..

')

l SRVs C,--F, K, M POINT VALUE: 1.00

. ANSWERS REFERENCE

. ST-OP-315-0005-001 i

l K/A: 223001 K3.08 [2.7/2.9]

1'

COGNITIVE LEVEL: 3-OBJECTIVE: OP-315-0005-001-01-10b EXAM BANK NO: None SOURCE: New USE: N/A i

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- . - _ _ - - . _ - _ _ _ _ - _ _ - - _ - _ _ _ _ _ _ _ _ - - _ _ _ _ . _ - _ _ _ - _ _ _ . _ - - - _ _ - _ _ _

REACTOR OPERATOR QUESTION: 82 l

Following a LOCA, the action required to inhi%t ADS was missed with j subsequent automatic initiation of the syste l Which of the following methods describes the minimum action required to terminate the blowdown? Place ADS Inhibit SW Logic A or B in INHIBIT Place ADS Inhibit SW Logic A and B in INHIBIT Depress ADS Div. 1 and 2 Timer Log;Lc Reset pushbuttons and place ADS Inhibit SW Logic A or B in INHIBIT Depress ADS Div. 1 and 2 Timer Logic Reset pushbuttons and place ADS Inhibit SW Logic A and B in INHIBIT POINT VALUE: 1.00 ANSWER: REFERENCE: 23.201; DWGs I-2095-6, 7 K/A: 218000 K5.01 [3.8/3.8)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0042-001-01-04b EXAM BANK NO: None SOURCE: New USE: N/A l

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. REACTOR OPERATOR-

!

QUESTION: 83-With the plant operating normally at power, which one of the-following l statements describes the Normal Reactor Water Cleanup flow path to.and from the RPV7 l

. Suctions from RPV. Bottom Vessel Drain, A and'B Recirc Pump

' Discharges; returns'through the A Feedwater Line Suctions from A and B Recirc Pump Suetions; returns through the B Feedwater Line l- Suctions from RPV Bottoc Vessel Drain, A and B Recirc Pump

'

'

Suctions; returns through the B Feedwater Line id. Suctions from RPV Bottom Vessel Drain, A Recire Pump Discharge; returns through the A Feedwater Line POINT VALUE: 1.00 ANSWER: REFERENCE: 23.707, DWG M-5711-1 .K/A: 204000 K1.01 [3.1/3.3)

COGNITIVE LEVEL: 1- i l

OBJECTIVE' OP-315-0008-001-01-03b, i i n '

(- EXAM BANK NO: None i

' SOURCE: New USE: N/A l

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REACTOR OPERATOR QUESTION: 84 l; 1 Annunciator 2DI, Fuel Pool Water Level Low has been received followed by a trip of the FPCCU pumps. Investigation by a plant operator reports level in the Fuel Pool is 21'10".

Immediate action is taken to provide makeup to the Fuel Pool' tot j a. ensure a minimum of 8 feet of shielding over the irradiated fuel in the Spent Fuel Poo ensure sufficient water depth to remove 99% of the iodine gep activity released from a ruptured fuel assembly, l'

l provide sufficient-volume of water to assure adequate cooling to prevent exceeding pool maximum temperature limi supply adequate volume of water to allow restoring FPCCU pumps to ensure adequate decay heat remova POINT VALUE: 1.00 ANSWER:' REFERENCE: ARP 2D1, Tech Specs B3. K/A A2.02. [3.1/3.3)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0015-001-01-07 EXAM BANK NO: None-SOURCE . New l USE: N/A

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QUESTI'JN 85 h Operating procedures direct the Rod Select Matrix power switch to be placed in the OFF position when rod movement is not planned. Which of t.he following indications could be used to verify that the select matrix has actually deenergized after the switch is placed to OFF? Rod Llock Monitor rod block on loss of LPRM input I Wsndows for the 4 Rod Display are all blan Select Error (SE) displayed on the Rod Worth Minimizer due to no rod selected, The RBM resets to match reference APRM power.

.. POINT VALUE

1.00 ANSWER: ~ REFERENCE : 23.623, ST-OP-315-0011-001

'K/A 201002 A4.06 [2.8/2.8)

COGNITIVE LEVEL: 2 l

! OBJECTIVE: OP-315-0011-001-01-08b l EXAM BANK NO: None

. SOURCE: New

.USE . N/A

.

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___ _ ____________-__-_-_ ____ _. __

- _ _ . - _ - _ _ _ _-__ - -__- _ -_-- _ -- - _ - _ - _ - - - - - - - - - - - - _ - _ - _ _ - - - - - _ - - - -

REACTOR OPERATOR

- QUESTION: 86 With the plant operating at full power, a fire develops in 2PC3-17,resulting in loss of. BOP 125 VDC Powe ~

Which one of the following actions is appropriate / Verify plant equipment, control room indications, and the process computer are operating properly'and monitor remote annuciator panel Commence an immediate power reduction while restoring 2PC3-17, or aligning an alternate power supply, Verify control room indication and controls are operating properly, then commence a reactor shutdown while trying to restore power to the annunciator Reduce Core Flow to 55 - 60% of rated and place the Reactor Mode switch in SHUTDOW POINT VALUE: 1.00 ANSWER: REFERENCE: 23.621 Sect 8. .K/A: 294004 2.4.32,[3.3/3.5]

COGNITIVE LEVEL:- 2 OBJECTIVE: OP-315-0089-001, 01-07-EXAM BANK NO: 'None SOURCE: New

'USE: N/A J

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-. _ _ _ _ _ _ _ - _-_ __ __- _ _ _ _ _ _ _ _ __ _ _ __

REACTOR OPERATOR

!

l QUESTION: 87

l The plant is. operating at 96% power with the following indications on the A  ;

Recirculation Pump Seal:  !

!

l l Seal lf1 Pressure 900 psig j

!

Swal-#2 Pressure 10 psig Annunciat.or 3D123, RECIRC PMP A STAGING SEAL FLOW HIGH/ LOW is alarming

Flow indication indicates 0.4 gp . Which one of the following seal conditions exist?

l Seal # 1 has failed I

! Seal # 2 has failed # 1 Seal. Labyrinth is plugged i

i # 2 Seal Labyrinth is plugged i ,

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POINT VALUE: 1.00 l ANSWER: t,j .l, i yfyy1 M/8/Nk REFERENCE: DWG M-5702-1; ARP 3D121, 3D123 l

K/A: 202001 A1.09 [3.3/3.3) j COGNITIVE LEVEL: 3

. OBJECTIVE: OP-315-0004-001-01-03b,01-04a

! EXAM BANK NO: None 1 l

SOURCE: Bank Modified  !

USE: 9701 RO Audit Exam i

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_ . - - - _ - _ - _ - - _ - _ - - _ _ - _ _ - - - _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ - _ _ . _ _ _ - _ - _ - - _ - _ _ _ _ _ _ - _ - _ _ - _ - ,

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REACTOR OPERATOR I

l

' QUESTION: 88 l

Which one of the following is a pre-requisite to. Purging /Deinerting the

' Primary Containment?

l 'a. Both divisions of RBHVAC rad monitoring must be verified operable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to purging /deinertin . The drywell and torus pressure must be equalized within one hour prior to commencing purge /deinerting operations.

l . Both the drywell and torus must be sampled within eight hours prior l to purging /deinerting.

l j Torus must be vented for four hours prior to initiating drywell purg !

l i- POINT VALUE: 1.00

!

ANSWER: '

REFERENCE: 23.406 Sect B. '

.K/A 294003 2.3.9 (2.5/3.4}

!

COGNITIVE LEVEL: OBJECTIVE: OP-315-0019-OO1-01-08 l EXAM BANK NO: None l SOURCE: New

!

USE: N/A l

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- - - - - - - - _ _ - - _ _ . _ - _ _ - - - - - _ - _ _

REACTOR OPERATOR QUESTION: 89 During a declared emergency the NSS/NASS may, with concurrence of Radiation-Protection Supervision,~ authorize maintenance performed in a high radiation area without.a Specific F.WP provided which one of the following conditions is met?

a. All' personnel invol'ved in performing the work are volunteers and have been fully briefed on'the hazards invcived, b. The' job is provided with continuous Rad Protection coverage, c. All work is' documented in the Control Room Unit log with the total dose receive d. A full Rad Protection Survey of the area to- be worked in has been performed within the past 30 day POINT VALUE: 1.00 ANSWER: . REFERENCE: MRP05

'K/A 294003 2.3.10 [2. 9/3. 3)

COGNITIVE LEVEL: -1 OBJECTIVE: GN-508-0001-A015 l EXAM EAFK NO: None-SOURCE: New USE: N/A

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_ _ _ -.--- .,

i REACTOR OPERATOR V

, I

'

l QUESTION:- 90

A reactor'startup is in progress with the following conditions:

- Steam flow is'15%.

- Feedwater flow is 15%.

- Both Recirc Pumps are operatin ,

- Recirc MG Set A and B Generator Speed Control Stations are at 40 % demand )

'

in MANUA What is the expected speed of the Recire Pumps?

. %' %-

' %

l %

POINT VALUE: .1.00 ANSWER: REFERENCE: '23.138.01 K/A: .202002 A1.06 [3.4/3.3].

COGNITIVE. LEVEL: 1 OBJECTIVE: OP-315-0004-001-01-06 EXAM BANK NO:: None SOURCE: Bank USE: 1993 RO Written, Ques. 19 l l

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REACTOR' OPERATOR

. QUESTION: 91 4

!

'

During a Reactor heatup and pressurization, Off-Gas radiation levels are increasin Annunciator 3D24, 2 MINUTE HOLDUP PIPE RADN MONITOR UPSCALE TRIP alarm I i

j The readings at both monitors are confirmed to be greater than 1E6 cpm, and i the red TRIP 2 lights kre O Which one of the following automatic actions should have occured? l

!

a. Operating Ring Water Pump trips and isolate ) Mechanical Vacuum Pumps trip and isolat Gland Seal Exhausters trip and the system isolate Steam Jet Air Ejector Inlet Valves isolat POINT VALUE: 1.00 ANSWER:- REFERENCE: ARP 3D24, ST-OP-315-0050-001 K/A ' 271000 A2.04 [3. 7/4.1]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0050-001-01-03 EXAM BANK NO: None SOURCE: New USE: N/A L

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l-

' REACTOR OPERATOR QUESTION:: 92 Following a fire in the plant, AOP 20.000.18, Control of the Plant From the Dedicated shutdown Panel, has been entere Which one of the following will result from aligning DC panels per this procedur .

a. All EDG automatic start signals are defeate RCIC Turbine Level 8 trip is defeate Control Power has been removed from all 4160V AC Breakers supplied from the BOP buses, The EF1 Supervisory Control system will be deenergized requiring local control of CTG-11 Unit POINT VALUE: 1.00 ANSWER: REFERENCE: 20.000.18-K/A 295016 AA1.07-(4.2/4.3)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0099-001-01-05 EXAM BANK NO: None SOURCE: New USE: N/A 1-

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I

REACTOR OPERATOR' ,

p_

QUESTION: 93'

l'

l While operating at 75% power, only the in-service Reactor Pressure Regulator signal fails lo Which one of the following control valve responses is expected?

I

! a. Turbine Control: Valves fully open.

i i

' Turbine control Valves open slightly, Turbine Control Valves fully clos ' Turbine Control Valves close slightly.

!' - POINT VALUE: 1.00

ANSWER: d.

!

'

REFERENCE: 20.109.02

'

I' K/A ' 245000 A3.05 [3/3.1]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2002-001-01-13, 01-14 l EXAM. BANK NO: None SOURCE: New USE:~ N/A i '.

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- - - - _ - _ - _ - - - - . _ - _ - - _ _ _ _ - - _ . - _ . - - _ _ - - _ _ _ _ _ -_ - - _ - - _ - _ _ _ _ - _ - . _ . - _ - . _ - _ --

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REACTOR OPERATOR

-QUESTION's '94 I

( During an outage, replacement of a RWCU valve will require 3 man-hours of work without a respirator, or 5 man-hours with'a respirato External dose rate for the area is 75 mr/hr, and airborne activity is 15 DA Using TEDE ALARA principles, what.is the least dose a worker would receive performing this job? mr .5 mr .5 mr d .' 375 mr

' POINT VALUE: 1.00 ANSWER: REFERENCE: 10 CFR 20 K/A: 294003 2.3.04 [2. 5/3.1]

COGNITIVE LEVEL: 1 OBJECTIVE: GN-508-0000-001-A062 EXAM F.ANK NO: None SOURCE: Bank-USE: New i-

,__ _ _ _ _ _ _ _ _ .

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REACTOR OPERATOR QUESTION: 95 The plant is operating at full power. Annuciator BD41, Div 1 Drywell Temperature High, is received. Review of indications shows all DW Fans i operating, and that the alarm was caused by Point 16 exceeding 155'F.

!

Drywell average temperature has increased from 132*F to 135'F during the last 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Which one of the following actions is appropriate?

. Increase GSW cooling to RBCCW per ARP 8D4 Operate all available Drywell Cooling per 29.100.0 Manually initiate EECW and EESW Systems per 20.127.0 Shift DW Cooling Fans 1,2,3 and 4 to low speed per 23.41 POINT VALUE: 1.00-ANSWER: REFERENCE: 8D41, 23.415 K/A: 295012 AA1.01 [3.5/3,6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0017-001-01-05 EXAM BANK NO: None SOURCE: New USE: N/A

_ __ _ ._ - __- - - - - _ _ _ _ - - - - _ _ - - - -_ - -__ --- - -_ . - _ . . - _ - - _ . - _ _ _ _ . _ - - _ - _ _ - . _ . _ _ _ . .-

1'

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REACTOR OPERATOR QUESTION 96 l

l Which one'of the following DC loads would be lost on a loss of Div I ESS l Battery?-

l a. HPCI Turbine Speed Control l EDG #11 Local Control Main Turbine Generator Protection Recirc MG Set Emergency Oil Pump C l-POINT VALUE: 1.00

,

ANSWER: REFERENCE: 23.309, 20.300.09

'_ K/A: 263000 K2.01 [3.1/ 3 . 4]

COGNITIVE LEVEL: -1

. OBJECTIVE:- OP-315-0064 001-01-03a

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EXAM BANK.NO: None SOURCE: New USE:' N/A

_ . _ __ . _ _ ._ - _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _

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l I

REACTOR OPERATOR I

QUESTION: 97 i.

,

During a LOCA the following conditions exist:

RPV Level 138 inches, slowing rising

RPV Pressure 64 psig l Drywell Pressure 6.0 psig l Torus Water Temperature 137'F  ;

A and C RHR Pumps injecting in the LPCI Mode I l Which one of the following actions is required if RHR Pump B trips? I i

! Inunediately start RHR Pumps D and continue Torus Spray / Cooling

, Place RHR Pump B in OFF/ RESET and isolate discharge paths to the Torus.

l Shut RHR Heat Exchanger B Outlet and Bypass Valves, then start RHR Pump d. Attempt to rer'. art the B RHR Pump and reestablish Torus Spray / Coolin !

l

POINT VALUE

1.00 '

l ANSWER: b.

l REFERENCE: 23.205 {

l K/A: 294004 2.4.1 (4.3/4.6)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0041-001,.01-09 EXAM BANK NO: None SOURCE: New USE:

L l

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b

> REACTOR OPERATOR QUESTION: 98 The plant is shutdown with the following concitions:

C RHR Pump operating in Shutdown Cooling Mode-Both RHRSW Pumps are operating to supply the A RHR H/X RPV Level'is 220 inches l Which one of the following actions should be taken for.an overcurrent Trip

'

of the C RHRSW Pump?

a. Throttle E1150-F068A Div 1 RHR HX Serv Wtr Outlet FCV, in the closed direction to establish proper RHRSW flow and enter 20.205.01, loss of S/D Coolin b. Re-open E1150-F068A, Div 1 RHR HX. Serv Str Outlet FCV to restore RHRSW flow to the heat exchanger after the pump trip, and estaablish decay heat removal per 23.800.04, Alternate Coolant Circulation and Decay Heat removal.

c. Fully open E1150-F048A, RER Heat Exchanger Bypass Valve, to reduce heat exchangar load and establish decay heat removal per 23.800.05, Alternate Remote Coolant Circulation and Decay Heat Remova d. Throttle open E1150-F0068A, Div 1 RHR HX Serv Wtr Outlet FCV, to maximize service water flow and cross tie RHRSW per 23.208, RHR Complex Service Water Syste POINT VALUE: 1.00 ANSWER: REFERENCE ARP 1D45, 20.205.01 K/A 205000 K6.08 (3.5/3.7)

COGNITIVE LEVEL: 3 l OBJECTIVE: OP-315-0041-001-01-07a EXAM BANK NO: None SOURCE: New )

.USE: N/A i i  :

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________-_=_______-___-_--______-____-_- - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ .

_ _ _ ._ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

-REACTOR OPERATOR

. QUESTION: 99

.Following a LOCA with a failure of several injection sources, Condensate has been lined up as an injection system per SOP 23.10 Which one of the following lineups will provide the highest rate of Condenser Hotwell Makeup?

a. Normal Hotwell Supply Pump operating and Hotwell Normal Makeup Valve full ope b. Emergency Hotwell Supply Pump operating and Emergency Makeup Valve full ope c. Emergency Hotwell Supply Pump operating with Emergency and Emergency Makeup B/P Valves open d. Normal and Emergency Hotwell Supply Pumps operating and Normal, Emergency and Emergency Makeup B/P Valves open POINT VALUE: 1.00 ANSWERf REFERENCE: ARP 5D123 K/A: 256000 K4.08 [3.6/3.6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0006-001-01-03p, q EXAM BANK NO: None SOURCE: New USE: N/A l

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QUESTION: 100 With the plant in Mode 4 for turbine repair, shutdown cooling is allowed to l

cool the reactor coolant system to 65' Which one of the following concerns apply to this event?

a. Shutdown margin calculations are only val 1d at temperatures above 70* b. Vessel flange and head flange temperatures must be verified above 71* c. Minimum pressure vs. temperature curves are not valid below 75' d. A reactor vent path must be open through the main steam lines to I prevent exceeding low temperature pressurization limit POINT VALUE: 1.00 ANSWER: REFERENCE: Tech Specs 3/4. K/A: 290002 K5.05 (3.1/3.3]

COGNITIVE LEVEL: 3 i l

OBJECTIVE: OP-315-0002-001-01-07 EXAM BANK NO: None SOURCE: New USE: N/A

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ES-401 Site-Specific Written Examination Form ES-401-7 i

Cover Sheet i

U.S. Nuclear Regulatory Commission Site 8pecific Written Examination  !

Applicant infonnation

!

Name: MASTER EXAMINATION Region:lil  !

Date: 04/n6/98 Facility / Unit: Fermi 2 License Level: BRO Reactor Type: GE )

Start Time: Finish Time:

l Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the

,

answer sheets The passing grade requires a final Grade of at least 80.00 percent. Examination l

..

papers will be collected four hours after the examination start )

!

'

I i

Applicant Certification All work done on this examination is my own. I have neither given nor received ai l Applicant's Signature Results Examination Value 100 Points l Applicant's Score Points l

l Applicant's Grade Percent l

NUREG-1021 1 of 1 Interim Rev. 8, January 1997

-

s, I'

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SEMIOR. REACTOR OPERATOR

' QUESTION: 1 When a LOCA signal is received, the Core Spray Inboard and Outboard Isolation valves will receive an Open signal:

l- when the CS pumps start.

1 after-a 5 second time delay, when RPV. pressure decreases to 461 psig, { when the CS pump discharge pressure increases to 145 psig.

l l .

l_ POINT VALUE:- 1.00 l

ANSWER: REFERENCE: 23.203 l

K/A 209001 A3.01 [3.6/3.6)

l

'

COGNITIVE LEVEL: -1

' OBJECTIVE: OP-315-0040-001-01-05 EXAM BANK NO:' None SOURCE: Bank 1 USE RO Written, Ques, 57 .

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_ - - . . _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ - _ __ -

SENIOR REACTOR OPERATOR

!

' QUESTION: 2 Whenever HPCI is to be operated for surveillance testing, torus cooling is required to be placed in service as a prerequisite to starting HPCI.

! Insuring that torus cooling is in service before operating HPCI: allows the maximum average suppression pool water temperature limit to be increased to 105' ensures adequate thermal mixing of the water in the suppression pool to limit stress on the torus shell due to differential thermal expansio extends the operating time for HPCI testing before the maximum average temperature limit is reached and test.ing is required to be stoppe ensures that heat added to the suppression pool does not increase L torus air space pressure to the point where the Suppression Chamber to Drywell vacuum breakers cycle.

l POINT VALUE: 1.00

'

~ ANSWER: REFERENCE: Tech Specs 3.6. K/A: 295013 AK2.01 [3.6/3.7)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0016-001-01-05f EXAM BANK NO: None-SOURCE:' New l

USE: N/A l

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l_ _ _ _ _ _ _ _ _________._________________o

_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ - _

SENIOR REACTOR OPERATOR QUESTION: 3 A pressure transient has occurred with reactor pressure reaching 1097 psig and initiating'a reactor scra Which.one of the.following describes the expected indications if this  !

transient resulted'in a leaking SRV?

a. SRV Tailpipe temperature approximately 210*F; red SRV OPEN light C b. SRV Tailpipe temperature approximately 215'F; SRV.OPEN Annunciator 1D61 O c. SRV Tailpipe temperature approximately 220*F; rei SRV OPEN light O d SRV Tailpipe temperature approximately 225'F; SRV OPEN Annunciator I 1D61 O ' POINT VALUE: 1.00 ANSWER: REFERENCEt' ARP 1D61 K/A 295025 EK1.03 [3. 6/3. 8)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0005-001-01-24C EXAM BANK NO: None SOURCE: New USE: N/A l 1

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_ _ - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - -

. SENIOR REACTOR OPERATOR QUESTIONS. 4 What action would an operator use to deal with a nuisance alarm caused by work on the N Aux Boiler Water Level control?

a. Use the defeat matrix on the side of the H11-P60 Defeat the annunciator in the relay roo Place a maintenance placard by the alarm windo Place a CRIS Dot by the alarm windo .- POINT VALUE: 1.00 ANSWER: REFERENCE: MOPO4

'K/A: 294001 2.1.01 [3.7/3 B)

COGNITIVE LEVEL: 1

. OBJECTIVE: OP-802-4101-0025d EXAM BANK NO: None

. SOURCE: New-USE: N/A

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_ - . - - - - --_ -- . - - _ _ _ _ _ _ _ - _ _ _ _ - - -

SENIOR REACTOR OPERATOR-QUESTION: 5 MPU 1 is a power seeking device which will automatically transfer to its standby. power source on loss of normal power. Transfer back to its normal

. source wil1~only occur when initiated manually or on loss of power to the standby sourc ~

What is the basis for not allowing an automatic transfer back to its normal supply? The number of cycles on the logic systems powered from MPU 1 is limited ~by Tech spec This prevents paralleling power supplies out of phase if MPU 1 is being supplied by an ED Loss of power to the loads-supplied from MPU 1 will result in a loss of Div 2 Drywell Cooling fans and an auto initiation of SGT ' Transfer from Normal to Standby power supplies is "make before break" and will be initiated before power has been lost. Transfer from standby to normal power supplies requires deenergizing the standby power supply resulting in loss of power to several critical

logic systems POINT VALUE: 1.00

. ANSWER: REFERENCE: 23.308 K/A 295003 AK3.01 (3.3/3.5]

'

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0061-001-01-05 EXAM BANK NO: None SOURCE: New USE: N/A i

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SENIOR REACTOR OPERATOR QUESTION: 6 From full power operation, a transient has occurre The following annunciators were received:

3D73, Trip Actuators A1/A2 Tripped 3D74, Trip Actuators B1/B2 Tripped 3D99, APRM Upscale Neutron / Thermal Trip Immediately after receipt of these annunciators, the following parameters were reported to the NASS:

Reactor Power 48% and stable RPV Level 164 inches, decreasing slowly Reactor Pressure 1085 psig, increasing slowly With these plant conditions, what is the first action that must be performed, and which indication must be observed to verify proper response? Manually operate SRVs to stabilize pressure at less than 1050 psig; observe Div 1 and 2 post-accident recorders, Place the SVLCV Bypass Valve Mode Switch in STAkIUP, and verify RPV level is not increasin Initiate Alternate kod Insertion; perform CD-7 option Place the Reactor Mode switch in SHUTDOWN; verify blue group scram lights are Of POINT VALUE: 1.00 ANSWER: REFERENCE: 20.000.21, ST-OP-802-3003-001 K/A: 295037 EA1.01 [4.6/4.6)

COGNITIVE LEVEL: 2-OBJECTIVE: OP-802-3003-001-01-13f EXAM BANK NO: None SOURCE: New USE: N/A

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- - _ _ _ _ _ - - _ . - _ _ _ _ _ - _ - _ - _ - - - - _ - _ - - .- _ _ _ - _ - - _ _ _ _ _ _ _ _ - . _ _ _ _ -

SENIOR REACTOR OPERATOR QUESTION: 7 Following a' Reactor Scram from full power total.feedwater flow is 15%. The

- Operator must verify the Recirculation Pumps have run back tot to 30% to 37% to 40% to 4C%'

POINT VALUE: 1.00 ANSWER: REFERENCE: 20.000.21, ARP 3D126/3D150 K/A: 295006 AK3.06 [3.2/3.3]

COGNITIVE LEVEL: 1-OBJECTIVE: OP-315-0004-001-Cl-03k EXAM BANK NO:: None SOURCE: New-USE:L N/A

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- _ _ _ _ - - - - _ _ - _ _ - - - - - _ - -- - . - - - . - - - .

SENIOR REACTOR OPERATOR QUESTION: 8 Mhile performing a core shuffle evolution, an irradiated fuel bundle is being removed from the core. When the bundle is approximately 1/4 l withdrawn, it is observed that an adjacent bundle has been lifted along with the selected bundle. Fuel movement is stopped, and the non-selected bundle falls back into the core. Bubbles come to the pool surface, and the local CAM alarm Which one of the following actions is appropriate?

a. Immediately stop all activities and evacuate the Refueling Floor to an area designated by Radiation Protectio b. Evacuate the Refueling Floor except the platform crew who should continue fuel movement to the Spent Fuel Pool before evacuatin c. Lower the fuel grapple to its lowest position to maximize shielding, notify the Control Room, and evacuate the Refueling Floor, d. Reset the CAM alarm one time. If the alarm is received again, direct everyone to evacuate the Refueling Floo POINT VALUE: 1.00 ANSWER: a. 4 ..j b u 4 y7p','N MI A&[*T #[# g REFERENCE: 20.710.01 K/A: 295023 2.2.31 [1.6/3.8)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0090-001-01-06b EXAM BANK NO: 'None SOURCE: New USE: N/A

- _ _ __ _ .

-_ _ ._ _-_________ ____-____ _ _-_ _ _ _ _-

l l SENIOR REACTOR OPERATOR QUESTION: 9 L

which one of the following statements describes the effects on RPS of

'

shifting the Reactor Mode Switch from START / HOT STANDBY to RUN?

).

' Removes APRM Neutron Flux-Upscale, Setdown trip Enables MSIV Closure and RPV High Pressure trips-Bypasses Startup Range Nuclear Monitoring trips i

b' . Bypasses IRM High and Inop trips Removes APRM Neutron Flu.~.-Upscale, Setdown trip Enables MSIV Closure and APRM Downscale/IRM Upscale trips Enables MSIV Closure Removes APRM Neutron Flux-Upscale, Setdown trip Removes SDV High Level bypass capability Bypasses IRM High and Inop trip Removes SDV High Level bypass capability Enables MSIV Closure and APRM Downscale/IRM Upscale trips POINT VALUE: 1.00

- ANSWER: REFERENCE: 22.000.02, ST-OP-315-0027-001

. K/A: 212000 A2.16 (4/4.1]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0027-001-01-04a EXAM BANK NO: None SOURCE: New USE: N/A

- - - - _ _ _ _ - . _ - _ _ _ _ _ _ - - _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ - - _ _ - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ -

______- - ___ - -_ _ - _ -. _ - _ _ - _ - _ - _ - _ - - - _ - - _ _ _ - - ___ . - - _ -

SENIOR REACTOR OPERATOR QUESTION: 10 l The'drywell to torus vacuum breakers are set to maintain the drywell to l' torus differential pressure within set-limits to l Prevent expansive failure of the downcomer between the drywell and

,

torus.

b .' Minimize impact loading on the torus in the event of a rapid drywell pressure increase due to an acciden Prevent exceeding the design differential pressure between primary land secondary containmen . Minimize the pump. head differential for the RHR pumps taking a suction from the torus-and discharging through the torus and drywell spray header POINT VALUE: 1.00

' ANSWER: REFERENCE: ST-OP-315-0016-001 K/A: 295010 AK2.02 [3.3/3.5)

COGNITIVE LEVEL: 1

OBJECTIVE: ' OP-315-0016-001-01-04a EXAM BANK NO: None SOURCE New-USE: N/A

,.s

- _ . _ _ - - - - _ _ _ . - - _ . - - - - - - - - _ . - . _ - - - - - - - -- _

_____ ___ _ _ __

. SENIOR REACTOR OPERATOR-QUESTION: 11 Following a small break LOCA the following conditions exists Drywell pressure 11 psig, increasing Peactor' Level 140 inches, increasing Reactor Pressure 83 psig, decreasing Div.1 RHR-Loop operating in the LPCI Mode Div 2 RER Loop operating in the Torus Spray Mode What are the minimum manipulations required to initiate Drywell Spray with Div 2 RHR, assuming the above conditions are true? Depress open pushbutton for E1150-F021B, Div 2 RHR DW Spray Inbd Iso Viv

- Depress open pushbutton for E1150-F016B, Div 2 RHR DW Spray Otbd Iso Vlv, to throttle open valve b. ' - Depress,open pushbutten for E1150-F021B, Div 2 RHR DW Spray Inbd Iso Vl Place keylock switch for E1150-F016B, Div 2 RHR DW Spray Otbd Iso Vlv, to OPERATE

- Depress open pushbutton for E1150-F016B, Div 2 RHR DW Spray Otbd-Iso Vlv, to throttle open valve Place keylock switch for E1150-F021B, Div 2 RHR DW Spray Inbd Iso Vlv,.to OPERATE

- Place keylock switch for E1150-F016B, Div 2 RHR DW Spray Otbd Iso

. Viv, to OPERATE Place keylock switch for E1150-F021B, Div 2 RHR DW Spray Inbd Iso Vlv, to OPERATE

- Depress open pushbutton for E1150-F021B,-Div 2.RHR DW Spray Inbd Iso Viv

- Depress open pushbutton for E1150-F016B, Div~2 RHR'DW Spray Otbd Iso Vlv, to throttle open valv . POINT VALTJE 1.00 ANSWER ' REFERENCE: 23.205 K/A: 295024 EK2.11 : [4.2/4.2)

COGNITIVE LEVEL: 3

..

OBJECTIVE: OP-315-0041-001-01-12 EXAM BANK NO: None SOURCE: New USE:' N/A

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-_-___- - . -. -

SENIOR REACTOR OPERATOR QUESTION: 12 The plant is operating at 100% power when RPS A NG Set trips. Which'of the following statements describes the response of the Power Range Monitoring System? Power is lost to APRMs A,' C, & E and LPRM Group A, resulting in only a half-scram signa Power is lost to APRMs B, D, & F and LPRM Group A, resulting in only a half-scram signa Power is lost to APRMs A, C, & E and LPRM Group A, resulting in a-half-scram signal and control rod withdrawal bloc Power is lost to APRMs B. D, & F and LPRM Group A' resulting in a ,

i half-scram signal and control rod withdrawal bloc &

POINT VALUE: 1.00 ANSWER: REFERENCE: Tech Specs 3. K/A: 215005 K6.01 [3.7/3.8)

COGNITIVE LEVEL: 2

' OBJECTIVE: .OP-315-0024-001-01-08c EXAM BANK NO: None SOURCE:- New

>

USE: N/A i

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a _ _ _ _ - - , - - -- - - - , . - - - - - - - - . - - - - _ _ - - - - . - - _ _ _ _ - - - - - - - - - - - _ _ _ -

_____ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

' SENIOR REACTOR OPERATOR l QUESTION: 13 l

l Following a Scram and MSIV Isolation, Reactor Level decreased to 142 inches, l then momentarily spiked to 215 inches when the SRVs~ opened. Currently Reactor Level is 182 inches and slowly lowering. You have been directed to place RCIC in servic Which of the following' actions is required to start RCIC under these conditions? Open FD95, RCIC Stm Inlet Bypass Valve, wait 15 seconds and open F045, RCIC Steam Inlet Valv Close and-re-op;m F059, RCIC Turbine Inlet Trip Throttle Valve,

-then open F045, RCIC Steam Inlet Valv Depress the Level 8 reset button, open F095, RCIC Stm Inlet Bypass

~

Valve, wait 15 seconds and open F045, RCIC Steam Inlet Valv ; Depress _the Logic A and B Isolation. reset buttons and open F059.,

RCIC Turbine Inlet Trip Throttle Valv POINT VALUE: 1.00

' ANSWER:- REFERENCE: 23.206-

-K/A's - 295008 AK2.06 (3.4/3.6]

COGNITIVE LEVEL: 2 Ol1JECTIVE: OP-315-0043-001-01-04a, 06d EXAM BANK NO: None SOURCE: New

'USE: N/A

I-j :.

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SENIOR REACTOR OPERATOR-I i

_

QUESTION: 14 During core alterations, the SRM shorting links are required to be removed EXCEPT when? less than'16 fuel bundles have been installed in the core b. SRM signal-to-noise ration is greater than 20

'

?

c. special movable detectors are being used until the installed SRMs indicate greater than 3 cpm l ll.

<

,

d. adequate shutdown margin has been demonstrated POINT VALUE: 1.00 ANSWER: . REFERENCE: /4. 'K/A: 215004 K4.02 [3.2/3.2)

COGNITIVE LEVEL: 2 l:

OBJECTIVE: OP-315-0022-001-01-05c EXAM BANK NO: None j; = SOURCE: New USE: N/A l-t

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SENIOR REACTOR OPERATOR

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l QUESTION: 15 I

[ . BOP 29.100.01 SH 2 has a step which requires securing HPCI at a low water

- level in the Toru Which:one of the following is the reason for this step?

The level is low enough to allow air-to enter the.HPCI pump suctio a.

, Emergency depressurization is required, and HPCI injection must be j . stopped.

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'- HPCI exhaust would NOT be condensed which could over pressurize the containmen At this level HPCI will be at its vortex limi '

POINT VALUE: 1.00 i ANSWER: c.

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! REFERENCE: ST-OP-802-3004-001 Sect II.H.7 L .K/A:- 295030 EK2.01 [3.8/3.9)

COGNITIVE LEVEL: 1 I -

l OBJECTIVE - OP-802-3004-001-01-12 lr EXAM BANK NO: None SOURCE: New USE: N/A I

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SENIOR REACTOR OPERATOR QUESTION: 16 Following a transient at power, a Reactor Scram has occurred, and annunciator 3D12, Div I/II Off Gas Radn Monitor High-High, has alarme Channel A and B Off Gas Radiation Monitors are both reading 1100 mr/hr.

Based on these indications, what action (s) must be performed? Verify Radiation Protection surveys the Scram Discharge Volum Ensure the scram is reset within 5 minute \ Isolate the Main Steam lines, and initiate MSIVLC Verify or initiate a trip of the Mechanical vacuum pumps.

POINT VALUE: 1.00 ANSWER: a.

REFERENCE: 20.000.21 Caution K/A: 295006 2.1.02 [3/4]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2002-001-01-07 EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 17 The plant is operating at full powe Several annunciators have been received in the last few minutes, including 3D5, CRD Charging H2O Pressure Low, and 3D10, CRD Accumulator Trouble. The following information is available:

E41-R609, HPCI. Pump Suction Pressure Indicator, indicates O psi C11-PDIS-N002, CRD Drive Water Filter Differential Pressure, indicates O psi 'C11-R603, Cooling PJater to Reactor Differential Pressure Indicator, indicates o psi 'C11-R800, CRD Hydraulic Flow Ind, indicates 1 gp Which one of the following is the reason annunciators 3D5 and 3D10 were received?

a. The operating CRD pump has trippe b. C11-F034, Charging Header Isolation Valve, has been close c. The in-service ~CRD flow control valve has failed close d. C1152-F003, CRD Drive / Cooling Water PCV, has been close POINT VALUE: 1.00 ANSWER: REFERENCE: 20.106.01 K/A 295022 AA2.02 [3.3/3.4]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-802-2004-001-01-02 EXAM BANK NO: None SOURCE: New USE: N/A E____-.___.________ - _ _ _ _ . _ _ _ _ _ _ _ . .

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l SENIOR REACTOR OPERATOR QUESTION: 18 The reactor has been operating at 100% power. The current 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> core thermal average power is 3418 MWth. Reactor engineering delivers a CARD documenting an error in the core thermal power heat balance program. Due to the error, calculated thermal power is 15 MWth lower than actual thermal powe i What actions are presently required? l a. Reactor Power must be reduced to 3414 MWt The NRC Operations Center must be notified within an hou b. Reactor Power must be reduced to obtain an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> average of 3414 MWth. The NRC Operations Center must be notified within one hou l

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l c. Reactor Power must be reduced to 3414 MWth the NRC Operations l Center must be notified within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l d. Reactor Power must be reduced to obtain an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> average of 3414 MWth. The NRC Operations Center must be notified within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> POINT VALUE: 1.00 ANSWER: REFERENCE: MOP 03 K/A: 294001 2.1.10 [2. 7/3. 9)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-4101-0018-0023 EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 19 During normal full power operation, Recirc Pump A trip Recirc Loop B flow-indicates 21,600 gpm, and thermal power is approximately 40%.

What action is required due to these plant conditions? Place the Reactor Mode Switch in SHUTDOW Insert control rods using the CRAM array or at the direction of the SN For these power and flow conditions,'the only action required is to-monitor for neutron flux instabilit Raise operating loop flow to greater than 50%.

POINT VALUE: '1.00 ANSWER: REFERENCE: 20.139.01 K/A: 295001 AK1.02 (3.3/3.5]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2003-001-01-15g EXAM BANK NO: .None SOURCE: New USE: N/A l

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SENIOR REACTOR OPERATOR QUESTION: 20 ADS uses input from the Nuclear Boiler Instrumentation as part of the initiation logic. ADS level inputs are 31 inches from Wide Range instrumentation with a confirmatory level indication of: i inches from Narrow Range instrumentatio inches from the redundant division Wide Range instrumentatio inches from Narrow Range instrumentatio I inches from redundant division Wide Range instrumentatio POINT VALUE: 1.00 ANSWER: q REFERENCE: 23.201 Sect 7.0, ST-OP-315-0021 Table 4 f

K/A: 218000 K1.03 [3.7/3.8)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0042-001-01-09e EXAM BANK NO: None SOURCE: New USE: N/A

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l- QUESTION: 21.

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I Following a plant trip from a spurious MSIV closure, which one of the following EOP conditions would require using the High Pressure Coolant Injection (HPCI) System for reactor pressure control? Emergency RPV depressurization is anticipated.

l Terminate injection into PC from external sources.

t c , Stabilize RPV pressure <1093 psi d Torus level CANNOT be kept > -38 i ,

POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 1 K/A AA1.02 - [3.5/3.7)

. COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3003-001-01-16c

' EXAM BANK NO: None-SOURCE: New USE: N/A:

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SENIOR REACTOR OPERATOR QUESTION: 22 EDG-11 is paralleled to EDG Bus 11EA and is loaded to 1800kW. Heavy snow and high winds cause a loss of off-site power. Which of the following describes the Emergency Diesel Generator System response? EDG continues with current loads on its bu The diesel output breaker opens; EDG continues to run; output breaker must be closed manually, The diesel output breaker opens; EDG trips off; EDG must be started manually then will load normall The diesel output breaker opens; EDG continues to runs output breaker closes automaticall .

POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-315-0065-001 K/A: 264000 A3.05 (3.4/3.5]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0065-001-01-18f EXAM BANK NO: None SOURCE: Bank USE: 1993 RO Written, Ques. 39 I

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. SENIOR REACTOR OPERATOR l

' QUESTION: '23 The plant ~is operating at 14%. reactor power. A non-selected control rod drifts in from position 36 to position 0 The Rod Worth Minimizer (RWM)

has identified this control rod as an insert error and produced a rod bloc Which one of.the following statements describes the action which must be taken with regard to the RWM in order to' continue the startup?

a. . With only one rod inoperable, station a second operator to verify rod motion, bypass the RWM, and continue the plant startup, RemcVe the control rod. from the enforcement sequence by using the RWM control rod bypass function and restore the control rod to its original positio The rod must be declared inoperable and substitute position data entered into the RWM until power has been increased above the LPS i Correct the cause of the rod drift, bypass the RWM, and restore the control rod to its original position using another operator for second verificatio ' POINT VALUE: 1.00 ANSWER: REFERENCE ' 23.608, 24.608'

K/A: 201006 A2.03 [3/3.2]

COGNITIVE LCIEL: 3 7 . OBJECTIVE: OP-315-0013-001-01-04a EXAM BANK NO: None SOURCE: New USE: N/A I

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I SENIOR REACTOR OPERATOR

' QUESTION: 24 L -During operation at full power with the Torus Water Management System (TWMS)

out of service, valve leakage from the RHR and Core Spray system has resulted in a slow steady increase in Torus Leve If the Torus Level reaches the EOP entry condition, which of the following

. statements contains ALL the automatic actions expected?

l a. The HPCI and RCIC suction valves swap to the Torus.

L b. 05100-F611, TWMS Return Isolation Valve, receives a CLOSE signal.

, c. The HPCI suction valves swap to the Torus, and the TWMS pumps trip l on high level.

! d. The HPCI suction valves swap to the Torus, and G5100-F611, TWMS L Return Isolation Valve, receives a CLOSE signa POINT VALUE: 1.00

' ANSWER: d.

l REFERENCE: ARP 7D71 K/A: 206000 A1.04 (3.7/3.8]

! COGNITIVE LEVEL: 2 l OBJECTIVE: OP-315-0069-001-01-04; OP-802-3004-001-01-04, OP-315-003 EXAM BANK NO:- None

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i t l SENIOR REACTOR OPERATOR l . QUESTION: 25 i

i Which one of the following is a correct Safety Limit statement per the j

. Technical Specifications? ' The Reactor Vessel Water Level shall be above the top of the active

. irradiated fuel in operational Conditions 3, 4, & il

The Minimum Critical Power Ratio shall not be less than the Safety

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Limit MCPR of 1.08 for two recirculation loop operation.

! The reactor coolant system pressure shall not exceed 1375 psig as measured in the reactor vessel steam dome.

l l- Thermal Power shall not exceed 25% of Rated Thermal Power with the j

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reactor vessel steam dome pressure less than 785 psig or core flow less than 15% of rated flow.

l POINT VALUE: 1.00 l

- ANSWER: REFERENCE: Tech Specs

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- K/A: 294001 2.1.10 [2.7/3.9)

l COGNITIVE LEVEL: .2 l OBJECTIVE: OP-804-0001-0005 I' EXAM BANK NO: None j

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SENIOR REACTOR OPERATOR QUESTION: 26 A temporary change is appropriate for which of the following conditions?

a. To' correct a valve lineu b. To correct incorrect Source Reference c. Changes to administrative procedures, d. To revise surveillance acceptance criteria when the surveillance is performed as a post maintenance test ite POINT VALUE: 1.00 ANSWER: REFERENCE: MGA04  ;

K/A: 294002 2.2.11 (2.5/3.4]

COGNITIVE LEVEL: OBJECTIVE: OP-802-4101-0014 l EXA4 BANK NO: EQ-OP-802-4101-0007-002 SOURCE: Bank USE: OCEP Exam 1

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' QUESTION: l27 with the plant operating at full power, the N.RFPT trips resulting in a Recirc pump runback to the Number 2 Limiter. .Recirc Pump A runs back to the limiter setpoint, but Recirc Pump B fails'to respond producing a speed mismatch of greater than 25%. Investigation of the B RRMG set indicated the scoop tube has jammed and will require approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to repair. The N RF2T has wiped a bearing and will be out of service for several days.

I Which of the following actions must be.taken at this time?

I Make preparations to go to Single Loop Operation, and trip B Recirc Pum b. Trip both Recirc pumps, and place the Mode switch to SHUTDOW Place.the.2/3 Limiter Defeat switch in DEFEAT, and increase A Recirc Pump speed to within the speed mismatch limits, Insert control rods to reduce thermal power to less than 67.2%,

restore RPV' level greater than level 4 to clear the Recirc runback, and' increase A Recirc Pump speed to within the speed mismatch limit POINT VALUE: 1.00 ANSWER: REFERENCE: Tech Specs 3.4.1.3, 23.138.01 K/A: 202002 A2.04 (3/3.2)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0004-001-01-11 EXAM BANK NO: None-

SOURCE: New USE: N/A

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I QUESTION: 28 i

The plant is operating at full power when the following annunciators are j i.

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received: )

9D17, Div 1 ESS 130V Battery 2PA Trouble l l 1D6, Div 1 CSS Logic Power-Failure I

. 1DL RHR Logic A Power Failure

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1D62, Stm Lk Let HPCI Logic Power Failure Based upon this information, determine which of the following components / systems will NOT function as designe l i

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l kV breakers CM and CF control power i Scram Pilot Air Hdr Backup Scram SOV, C11-F110A  ;

! HPCI Barometric Condenser Vacuum Pump, E4101-C003 j

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, Outboard MSIV control logic ~ )

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POINT VALUE: 1.00

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ANSWER: .

REFERENCE' 20.300.09

[ . K/A 295004 AA1.01 [3.3/3.4)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0064-001-01-03a

[ EXAM BANK NO: . None SOURCE: New

- USE:. N/A  !

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SENIOR' REACTOR OPERATOR-QUESTION: 29

l i l -- While the plant is operating at full power, annunciator 7D50, Div I/II i Control Air Compressor Auto Start, is received. Immediately following I receipt of,this annunciator, plant conditions were

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- RPV Pressure 1024 psig and stable

- Reactor Power 90% and stable

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Both RR MG Sets 77% speed with no limiter'in effect Assuming all plant system / components function as designed, which one of the following identifies the cause of the annunciator and the initial response to take? i i

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The Control Air Compressor started on an RPV Level 2 initiation signa Enter 29.100.01, RPV Contro b. The Control Air Compressor started on Control Air header pressure ,

less than 80 psig. Dispatch an operator to cross-connect IAS to Div l 2 NIA The Control Air Compressor has started on control Air pressure less than 85'psig. Enter 20.129.01, Loss of Station and/or Control Ai The control Air Compressor started on Station Air header pressure less than 90 psi Enter 20.129.01, Loss of Station and/or Control Ai POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 7D50 K/A: 295019 2.4.10 [3/3.1]

COGNITIVE LEVEL: 1 OBJECTIVE OP-802-2009-001-01-01 EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 30 A Temporary Modification is being installed to correct problems with Turbine Building Area High Temperature isolation logi To implement the temporary modification the NSS is responsible for a. Verifying performance of post-modification testin Assigining a separate qualified person from Operations, Maintenance, or Modifications and Projects to verify proper installation of the Temporary Modification, Reviewing the Temporary Modification Request to determine training impact on on-shift Operations personne Reviewing and approving the Safety Evaluation for the Temporary Modification.

POINT VALUE: 1.00 ANSWER: a.

REFERENCE: MES12 K/A: 294002 2.2.14 [2.1/3]

COGNITIVE LEVEL: 1 OBJECTIVE: LP-OP-4101-001-C6 EXAM BANK NO: None SOURCE: New USR: N/A

_ _. _. _ _ _ _ _ _ - _ - - _ . - _ - _ _ _ _ - _ __ _ SENIOR REACTOR OPERATOR QUESTION: -31

- The plant is' operating at full powe A reactor scram occurs due to a spurious MSIV closur All Control Rods do not fully insert into the Core based on the RW Which one of_the following determines the reactor is shutdown? Control Rod 10-19 at position 02 and Control Rod 42-59 at position 04, b. Annunciators 3D103, APRM Downscale in alarm and 3D63, IRM Upscale, clea APRM recorders indicate Downscale, and IRMs recorders indicate 19 on range Process Computer displays XX for all Control Rod positions with a scram signal presen POINT VALUE: 1.00 ANSWER: R'dFERENCE : 29.100.01 SH 1A K/A: 295015 A2.01 [4.1/4.3)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-902-3003-001-01-021 EXAM BANK'NO: None SOURCE: New USE: N/A

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., SENIOR REACTOR OPERATOR QUESTION: 32 With the plant operating at full power, HPCI is running in full flow test for surveillance testing, and Div 1 RHR is operating in Suppression Pool Cooling. Annunciator 17D8, Div II Hydrogen Concentration High, is received. The CRNSO reports hydrogen reading 2.5% on T50-CRE-R806B, Suppression Chamber Atmosphere Analysis, and confirms that the Div 2 Atmosphere monitor is aligned to the Torus. Hydrogen Water Chemistry has been shut down for two week Which one of.the following actions is appropriate at this time?

a. Isolate the.HPCI System to prevent further exhaust into the suppression pool per 23.20 b. Immediately shift Div 1 RHR lineup to provide torus spray per ARP 17D c. If a chemistry sample confirms the high hydrogen concentration, isolate HPCI per 23.202 and shift Div 1 RHR to the torus spray mode per 23.20 d. Vent the torus per 29.100.0 POINT.VALUE: 1.00 ANSWER: . REFERENCE: ARP 17D8 K/A: 500000 2.4.11 (3.4/3.6)

COGNITIVE LEVEL: .2 OBJECTIVE: OP-802-3004-001-01-04 EXAM BANK NO: None SOURCE: Nr.sw

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l SENIOR REACTOR OPERATOR  !

l QUESTION: 33 Which of the following parameters will the Governor / Pressure Control System maintain within design limits? Reactor Steam Dome pressure Main condenser heat load Main Steam Line flow Main Generator electrical load POINT VALUE: 1.00 l ANSWER: b 4 b,. ^lf/

N IC M# [

REFERENCE: ST-OP-315-0045-001 ppggg K/A: 241000 2.1.27 [2. 8 /2. 9) g, *gpg /

COGNITIVE LEVEL: 1 m

OBJECTIVE: OP-315-0045-001-01-01 EXAM BANK NO: None SOURCE: New USE: N/A ,

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i SENIOR REACTOR OPERA'IOR QUESTION: 34 With the plant operating at full power, P4400-F603B, Div 2 EECW Supply Iso Viv, has failed close Which one'of the following actions must be taken to restore cooling water to the CRD Pumps? Verify EECW initiation. EECW will automatically supply RBCCW load Verify auto start of Div. II EECW and EESW pumps, depress Div. II EECW Iso Reset Switch, and open P4400-F604, Div 2 EECW To CRD Sply Iso Vl Close P4400-F601B, Div 2 EECW Return Iso Vlv, manually start Di II EECW and EESW pumps, and open P4400-F604, Div 2 EECW To CRD Sply Iso Vl Place Div 2 EECW Iso Override Sw keylock switch in MANUAL OVERRD, depress Div. II EECW Iso Reset Switch, and open P4400-F604., Div 2 EECW To CRD Sply Iso Vl POINT VALUE: 1.00 ANSWER: b. * 4i; ^/fifN MIdifd)ffAF 8[Md REFERENCE: 20.127.01 [

K/A: 295018 AK3.07 [3.1/3. 2)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0067-001-01-02h,01-03a, 01-04 EXAM BANK NO: None-SOURCE: New

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SENIOR-REACTOR OPERATOR QUESTION: 35 Which one of the following actions is required when a visible break cannot

'be demonstrated for disconnecting a piece.of electrical equipment from its power supply? Independent verification of deenergization is required and a blocking device approved by the Protection Leader must be installe b. ' An' approved grounding device must 'be used and the Protection Leader and Operating Authority must approve the ground installatio An approved non-vioible break device'may be used provided the non-visible break is secured with an approved blocking device and the Protection Leader and Operating Authority must approve a method for determining that power is removed, The Operating Authority may permit work to proceed provided the circuits are independently verified deenergized and an observer is positioned at the power suppl >

POINT VALUE: 1.00

ANSWER: . . REFERENCE: MOP 12

K/A: 294002 2.2.13 [3.6/3.8)

iCOGNITIVE LEVEL: 1 OBJECTIVE:' OP-802-4101-0030b

. EXAM BANK NO: None SOURCE: .New i

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QUESTION: 36 l

The plant is. operating steady state at full power. Due to multiple  ;

personnel errors, a large quantity of water has been drained from the. CST to l l

the Torus. Drainage from the CST to the torus has stopped with torus level stable at 46 inches. The NASS has directed the mode switch placed in )

shutdown and the reactor depressurized through the turbine bypass valves in )

anticipation of Emergency Depressurization due to the exceeding the SRVTPL J These actions prevent containment failure due to SRV tailpipe component damag ; torus level above the Reactor Building to Torus vacuum breaker torus level above the elevation of the highest torus vent capable of rejecting decay hea . exceeding the capability of the SRV vacuum breakers when Emergency Depressurization is initiate )

POINT VALUE: 1.00 ANSWER: l

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REFERENCE: 29.100.01, OP-802-3002-001 K/A: 294004 2.4.18 (2.7/3.6)

COGNITIVE LEVEL: 2

OBJECTIVE: OP-802-3002-001-01-06k

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EXAM BANK NO: None SOURCE: .New  :

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SENIOR. REACTOR OPERATOR-QUESTION:- 37

.Following a Loss of Off-Site Power, the EDGs have started. With the EDG breaker closed, which one statement below contains the additional signal-required.to start the EDG Digital Load Sequencer?

' EDG bus undervoltage EDG' bus' lockout relays reset EDG bus underfrequency di. EDG bus load shed relay deenergized.

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POINT VALUE: 1.00 AtSWER' REFERENCE: 23.321 K/A: 295003 AK3.03 [3.5/3.6]

COGNITIVE LEVEL: 2'

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OBJECTIVE: OP-315-0065-001-01-15c EXAM BANK No None SOURCE: New USE N/A

=

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Li__________._______.___________.______._________.___..__________.________ _ _ _ . _ - . _ _ _ . _ _ _ _ _ _ _ . _ . _ . . . _ _ _ _ _ .__ . - _ _ _ _ _ _ _ _ _ . . _ - _ _ _ . _ . _ . . _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ .

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SENIOR REACTOR OPERATOR QUESTION: 38 During a LOCA', the following conditions exist All control rods are fully inserte *-*ctor Pressure is 420 psig and stabl Reactor Level is -7 inches and decreasing at about 3 inches per minut No sources of injection are. currently availabl RHR Systetts can be made available in 15 minute Based on'present conditions, which one of the following mechanisms is required? Steam Cooling b. ' Emergency Depressurization Primary Containment Flooding RPV Flooding POINT VALUE:. 1.00 ANSWER: REFERENCE:- '29.100.01 SH 1 Step L-12 K/A: 295031 EA2.04 [4.6/4.8)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-801-0000-001-0007; OP-802-3003-001-13e EXAM BANK NO: None SOURCE: Ne USE: N/A i

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SENIOR REACTOR OPERATOR QUESTION: 39 Annunciators 3D32, Div I/II RB Vent Exh Radn Monitor Upscale, and 3D36, Div I/II RB Vent Exh Radn Monitor Upscale Trips, have been received. Review of system operations by the CRNSO indicates all systems are functioning normall Which of the following actions must be performed?

a. Verify RBHVAC tripped, the Secondary Containment isolation dampers closed, and SGTS initiate b. Direct a channel functional test performed on all RB Vent Exhaust radiation monitors, c. Declare the radiation monitors inoperable, notify Chemistry to take samples, and initiate a plant shutdow d. Direct an immediate plant shutdown because Secondary Containment integrity can no longer be verifie POINT VALUE: 1.00 ANSWER: REFERENCE: 20.000.02 K/A: 295038 2.3.11 [2.7/3.2)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2018-001-01-02 EXAM BANK NO: None SOURCE: New USE: N/A l

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SENIOR REACTOR OPERATOR QUESTION: 40 During a loss of Condenser Vacuum, condenser pressure has increased to psi Which one of the following will be the next function to occur as condenser pressure continues to increase? Reactor Feed Pump Turbine Trip MSIV Closure Main Turbine Trip Main Turbine Bypass Valve Closure POINT VALUE: 1.00 ANSWER: g b, '/ W/

REFERENCE: 20.125.01 K/A: 295002 AK2.04 [3.2/3.3]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-2010-001-01-01 EXAM BANK NO: EQ-OP-802-3004-0012-003 SOURCE: Bank USE: OCP Comp

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. SENIOR; REACTOR' OPERATOR-

. QUESTION: 41'

'29.100.01, SH 5,' Secondary Containment and Rad Release, directs operating available sump pumps whenever Secondary containment area or sump levels-exceed their Max Normal-Operating levels. This action is based on Minimizing the spread of contamination within the Secondary Containment, Containing leakage.from a primary system within systems designed for storage of radioactive liquids, Preventing the uncontrolled release of liquid radioactive effluents from the Secondary Containmen t'

- Maintaining water levels below the point at which equipment required for safe shutdown will fai ' POINT VALUE: 1.00 ANSWER: REFERENCE: -ARP 2DB2, 29.100.01 SH 5 K/A: 295036 EK3.04 [3.1/3.4]

COGNITIVE LEVEL: OBJECTIVES- OP-802-3005-001-01-05 EXAM BANK NO:. Non SOURCE: New USE: N/A

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L__-________-__--____ - - _ _ _ _ _ _ _ ___-_ ____- - - _ - - - - _ - _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ - - - - - - - - _ _ - _ - _ - - - - _ _ - - - _ - - - - - _ - _ .

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SENIOR REACTOR OPERATOR QUESTION: 42 The plant is in Mode 5 with core reload in progress. The following plant conditions exist:

- 1/4 Core Reloaded

- 3 Control Rods (with no surrounding fuel assemblies) are withdrawn for maintenance

- Spent Fuel Pool Temperature is 66*F

- Spent Fuel Pool Level is 22'1" (20'7" above RPV Flange)

- SRM Count Rates are:

A (16-45) - 45 cps B (40-45) - 45 cps C (40-21) - 50 eps D (16-21) - 50 cps After a fuel bundle is loaded into cell 47-20, SRM Count Rates are:

A- 46 cps B - 55 cps C- 80 cps D - 60 cps Refuel Activities are stopped to investigate SRM C reading. Reactor Engineering performs a Shutdown Margin Check and SDM is analytically determined to be 0.36% delta k/ Which one of the following actions should be performed? Continue core loading, SDM is required to be greater than 0.28%

delta k/ Stop core loading, insert all insertable control rods within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Stop core loading, reduce RBCCW flow to fuel pool heat exchanger and increase fuel pool temperature to 70* Stop core loading in SRM C quadrant only, declare SRM C inoperable, and perform channel check on SRMs A, B and POINT VALUE: 1.00 ANSWER: REFERENCE: Tech Spec 3.1.1, 23.708 K/A: 295023 AK1.02.[3.2/3.6]

I

' COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0003-001, 01-09 EXAM BANK NO: None t

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SENIOR REACTOR OPERATOR

( .,

[ QUESTION: 43 Which one of the following describes the parameters compared in checking for a. reactivity anamoly? Core Thermal Power and APRM indications Core Thermal Power and Calculated Control Rod Worth Actual Control Rod Density and Predicted Control Rod Density

. .

-

! Total Control Rod Worth and Calculated Control Rod Worth l POINT VALUE: 1.00 ANSWER: REFERENCE: 54.000.02 K/A: 295014 AK1.02 [3.3/3.7)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0011-001-01-18 EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR

QUESTION: 44 ,

With the plant operating at full power, a steam leak occurs in the drywell resulting in.a reactor scram due to high drywell pressure, i The increasing drywell temperatures are a concern for which one of the following RPV Level instruments? Core Level detectors Flood Up Level' detector

.c. Narrow Range Level detectors d. Wide Range Level detectors POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 6 K/A 295028 EK2.03 [3.6/3.8)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-3002-001-01-05b EXAM BANK NO: None SOURCE: New USE: N/ !

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l-l SENIOR REACTOR OPERATOR QUESTION:- 45

.. While operating at'96% power, annunciator 16D5, REAC/ AUX BLDG BSMT/SUBBSMT l-HIGH RADN f .is actuated. The CRNSO reports the following ARM readings:

Channel 07, RBSB'SE Corner 50 mr/hr Channel 08, RBSB SW Corner 55 mr/hr Channel 09, RBSB NW Corner 80 mr/hr j

,.

Channel 10, RBSB NE Corner 2000 mr/hr j l' Channel 11, SB HPCI Rm 150 mr/hr Channel 14, RBSB Torus Rm 65 mr/hr

' Channel 30, RBSB 70 mr/hr

Based on the reported readings, what is: your expected response? j

' None of the channels are greater than Max Norm Oper Rad Level Entry into EOP 29.100.01, SH 5, Secondary Containment and Rad Release,-is not require Channel 09, RBSB NW' Corner, is greater than Max Norm.Oper Rad Level. Enter EOP 29.100.01, SH 5, Secondary Containment and Rad Release, and isolate systems discharging into the area, Channel 10, RBSB NE Corner, is greater than Max Norm and Max Safe Oper Rad Levels. ' Enter EOP 29.100.01, SH 5, Secondary Containment

~

and Rad Release, and shutdown the Reacto Channel 11, SB HPCI Rm, is greater than Max Norm Oper Rad Leve Enter EOP 29.100.01,.SH 5, Secondary Containment and Rad Release, and direct HPCI isolate POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 5 K/A: 295033 EA2.01 [3. 8 /3. 9)

COGNITIVE LEVEL: 3 l

!

OBJECTIVE: OP-802-3005-001-01-02, 01-04 l l

' EXAM BANK NO: None

' SOURCE: New

~USE: N/A

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SENIOR REACTOR OPERATOR

QUESTION: 46 -

!

I With the plant at full power, which one of the following describes the i effects of a loss of the Rod Position Indicating System on Control Room )

indication? All red " full out" and green " full in" indication will deenergize on the full core displa If a rod is selected, the white " rod selected" light on the full core display will not energiz I The LPRM indicators on the 4 rod display will all indicate

'

downscal The rod select switch for the selected rod will not light on the rod select matri j POINT VALUE: 1.00 ANSWER: REFERENCE: 20.106.08 j K/A: 214000 A4.02 (3.8/3.8)

COGNITIVE LEVEL: 2 i

OBJECTIVE: OP-802-2005-001-01-01  !

EXAM BANK NO: None SOURCE: New USE: N/A l

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>.

SENIOR REACTOR OPERATOR l QUESTION: 47'

During a Reactor Heatup, on IRM Range 7, the collet fingers on a Control Rod

,- Drive stick in the withdraw position. The control rod-is being withdrawn from position 08 to 1 '

Which one of the following statements describes the consequences of this j event?  ! The rod will drift into the core reducing power and heatup rat . The rod will remain at position 12, and power and heatup rate will stabiliz The rod will drift out of the core, and power and heatup rate will increas . The rod will remain at position 08 until drive header pressure has been increased sufficiently to free the colle POINT VALUE: 1.00

. ANSWER: REFERENCE: 20.106.07 K/A: 201003 A1.01 [3.7/3.8) j COGNITIVE LEVEL: 2 )

OBJECTIVE: OP-315-0009-001-01-05e EXAM BANK NO: None SOURCE: New USE: N/A

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_

SENIOR REACTOR OPERATOR QUESTION: 48 The Reactor Building to Suppression Pool vacuum relief system is composed of a self-actuated vacuum breaker and an air operated butterfly valve in serie Which of the following describes how this system operates?

a. A Reactor Building to Suppression Pool differential pressure of 0.25 paid actuates the vacuum breaker and butterfly valve to ope )

b. A Reactor Building to Suppression Pool differential pressure of 0.25 paid actuates the butterfly valve to open, and a' Reactor Building to Suppression Pool differential pressure of 0.5 psid actuates the vacuum breaker to ope c. A Reactor Building to Suppression Pool Differential pressure of 0.25 psid actuates the vacuum breaker to open, and a Reactor Building to Suppression Pool differential pressue of 0.5 paid actuates the butterfly valve to ope d. A Reactor Building to Suppression Pool differential pressure of paid actuates the vacuum breaker to open, and the butterfly valve opens when the vacuum breaker "OPEN" limit switch close .

POINT VALUE: 1.00

' ANSWER:- f l. b, efJL /4 $h REFERENC .425.02,'ST-OP-315-0016-001 K/A: 290001 K5.01 [3.3/3.4]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0016-001-01-03d EXAM BANK NO: None  ;

SOURCE: New USE: N/A

_ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - _ - _ _ - _ _ . _ _ _ _ _ _ - - _ .___ ___ _ _ _ _

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' SENIOR REACTOR OPERATOR QUESTION: 49 An Alert level radioactive release is attained whenever a computerized dose

. assessment indicates a dose rate in excess of 10 mrem /hr TEDE at which one of the following locations? Site boundary b. ' Main Control Room Primary Access Portal At any. point within the RCA POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 5 K/A: 295038 EA2.03 [3.5/4.3)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3005-001-01-17 EXAM BANK NO: None SOURCE: New USE: N/A

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I SENIOR REACTOR OPERATOR i

QUESTION: 50 which one of the following statements describes the SLC Squib Valve continuity. circuit and alarm? Current flow through the squib valves is monitored and an alarm is received if current flow in the bridge circuit becomes unbalanced between the firing primers, Current through the squib valves is monitored and alarmed if current lowers below a setpoin Resistance of the squib valves is monitored and an alarm is received if resistance in the bridge circuit becomes unbalanced between the firing primers, Resistance of the squib valves is monitored and an alarm is

- received if resistance in the firing primers becomes too hig j PPINT VALUE

1.00 ANSWER: REFERENCE: ARP 3D11 K/A: 211000 A4.03 (4.1/4.1)

- COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0014-001-01-04d EXAM BANK NO: None SOURCE: New )

'USE: N/A

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_ - _ - , _ - _ - _ _ - _ _ _. _ _ _ _ _ _ - - _ - _ _ _ - - _ _ - _ - _ - _ _ _ _ _ _ _ - _ _ - - _ _ _ - - - - _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ _ _ _ _ - - . . _ - - _ - - - - . __ _ - - - _ _ _ _ _ _ _ _ _ _

l J

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SENIOR REACTOR OPERATOR l' QUESTION:' 51 During a full power ATWS condition EOP 29.100.01, S*I 1A, RPV Control - ATWS, requires initiating boron injection before Torus water temperature reaches the BII If a crew failed to carry out this step and continued with alternate means to shutdown the reactor, which one of the following would result?

l a. The delay in initiating boron injection will cause the fuel to operate beyond the analyzed time for power operations at low flow, b. Continued heat generation would cause the RPV depressurization to result in over pressurizing the Primary Containmen c. The delay in core shutdown time would result in RPV level boil-off requiring entry into Primary Contain'nent Floodin d. If the MSIVs closed the EOP step to " Terminate and Prevent" would l

result in a reactor water level where fuel damage would be expecte '

' POINT VALUE: .1.00-

,

'

ANSWER: b.

l I REFERENCE: ST-OP-802-3002-001 Sect IV. A, D K/A: 295026 EK3.04 [3 . 7/4 .1)

l COGNITIVE LEVEL: 2

'

OBJECTIVE: OP-802-3002-001-01 .07d l

EXAM BANK NO: None i SOURCE: New

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USE: N/A I

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I f

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SENIOR REACTOR OPERATOR t

QUESTION: 52

!

l During plant startup, with reactor pressure at 650 psig, the SULCV has reached 80% open and an operator is preparing to feed the vessel by placing the North RFPT in service. In preparing to feed the RPV using the RFPT, the operator has verified the SULCV M/A Station in AUTO and the A Feedwater Flow l

'

Control M/A Station in MANUAL. The operator becomes distracted while using the OPEN pushbutton at the Feedwater Flow Control M/A station to increase l RFPT speed and increases RFP discharge pressure to 150 psig higher than l reactor pressur If no other operator action is taken, what will be the RPV water level response?

I RPV level will increase at a constant rate until the RFPT trips on Level RPV level will increase resulting in a reactor power increase and APRM setdown scram.

l RPV level will increase initially, and then fluctuate as the SULCV attempts to throttle flow with an excessive pressure differentia RPV level will increase until the SULCV begins to respond and throttle closed to return level to the tape setpoin POINT VALUE: 1.00 ANSWER: REFERENCE: 23.107

, K/A: 259002 A1.01 [3.8/3.8)

COGNITIVE LEVEL: 2

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OBJECTIVE: OP-315-0046-001-01-04b

'

EXAM BANK NO: None SOURCE: New USE: N/A l

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' SENIOR REACTOR OPERATOR-QUESTION: 53'

Which'one of the following describes the effects of a loss of Div 1 and Div 2 control Air (NIAS) to the Standby Gas Treatment System (SGTS)? T4600-F407, RBHVAC to SGTS Iso Vlv, fails Ope SGTS is operable l for Secondary Containment only.

I i T4600-F406, HPCI to SGTS Iso Vlv, fails Open. SGTS will Auto start

!

and is available for HPCI operatio T4600-F410, RB 5. Air Inlet Iso Vlv, and T4600-F407, RBHVAC to SGTS Iso Vlv, fail Open, T4600-F406, HPCI to SGTS Iso Vlv, fails Closed;.

SGTS is inoperable, T4600-F410, RB 5 Air Inlet Iso Vlv, and T4600-F407, RBHVAC to SGTS Iso Viv , fail Closed, T4600-F406, HPCI to SGTS Iso Vlv, fails Open; SGTS is inoperabl POINT VALUE: 1.00 ANSWER: . REFERENCE: 20,129.01 K/A: 300000 K3.02 [3.3/3.4)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2009-001-01-3e l

EXAM BANK NO: None .

SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: -54 l

'

Performance of a pre-startup valve lineup will involve aligning a valve that is to be locked in position. The-valve in question is located in a

.. contaminated work area and'is known to have loose surface contaminatio In this situation, independent verification of valve position:

a. may be waived by the NASS to conserve man-rem rather than require

.

two individuals to enter the contaminated area.

l l should be performed by hands on checking of the valve position l without removing or breaking the locking device, l

l is performed by removing the locking device, checking the valve L position, and re-installing the locking device.

l l is accomplished by visual verification that the locking device is

!

properly installed.

l' POINT VALUE: 1.00

,

ANSWER: b, t

l -~ REFERENCE: MOPO2-K/A 294001 2.1.29 [3.4/3.3]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-4101-0023 j EXAM BANK NO: None l l'OURCE: ' ~New USE: N/A.

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SENIOR REACTOR OPERATOR QUESTION: 55 Following a Turbine Trip, the MAIN TURBINE TRIPPED ann iator has NOT alarme Which one of the following conditions would cause is?

a. One of the Main Steam lines to the t bine is NOT isolated, b. Reactor power was less than 30% en the turbine trippe c. This annunciator is only ree ved when the manual trip pushbutton is used to trip the turbin f,be tI^ l yk 46-4 One of the Turbine Low essure Stop Valves failed to close, f l POINT VALUE: 1.00 l ANSWER: l REFERENCE: ARP D46 ,

K/A: 2 5005 AA2.03 [3.1/3.1]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0029-001-01-04 EXAM BANK NO: None SOURCE: New USE: N/A

,,, w soep e. w easrd e a war m wbs a W,f #- pl# s

,p, gy ,

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l SENIOR REACTOR OPERATOR l

'

QUESTION: 56 Which one of the following states the significance of reaching +60 inches Torus water level? I a. Torus level increasing to this point following a LOCA will compress i

'

the non-condensables exhausted from the drywell to the torus, resulting in opening the drywell to suppression chamber vacuum  ;

breakers. Opening the; vacuum breakers could allow steam flow from 1 the drywell directly into the torus air spac i l

b. Torus venting cannot be performed above this level if it becomes i necessary to vent the Primary Containment to maintain pressure i within design limit l i

c. The Suppression Chamber to Drywell Vacuum Breakers will be covered with water and unable to relieve torus pressure to the drywell, ,

thereby posing a threat to containment integrity by allowing the  !

external differential pressure limits to be exceede .l

!'

d. Above this level there:is insufficient free volume to accommodate the non-condensable gases driven into the torus by a LOC Vibrational, or " chugging", stresses that result from torus spra I initiation have not been analyzed for this conditio POINT VALUE: 1.00*

ANSWER: REFERENCE: 29. ESP.01, ST-OP-802-3004-001 '

K/A: 295029 EKl.01 [3.4/3.7)

COGNITIVE LEVEL: 2' ,

OBJECTIVE: OP-802-3004-001-01-02 I EXAM BANK NO: None SOURCE:- New USE: N/A l

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l SENIOR REACTOR OPERATOR QUESTION: 57 Both divisions of Standby Gas Treatment System started due to a Secondary Containment Isolation signal. T46-F407, RB Exhaust System Isolation Valve, and T46-F410, Air Inlet Refueling Area Isolation Valve, have opened. RB Ventilation Supply and Exhaust Fans have tripped and isolated. SGTS flow recorders indicate 3,320 scfm for Division 1, and 3,420 scfm for Division The SGTS Exhaust Fans are running, and CCHVAC has shifted to the Recirculation Mod After reviewing these indications, the STA reports that SGTS has not  ;

initiated properl Why?

) T46-F406, HPCI Barometric Condenser Vacuum Pump Iso Valve, failed to open, Standby Gas Treatment System flow is not within required limit T46-F410, Air Inlet Refueling Area Isolation Valve, should not have opened, The SGTS Cooling Fans should have started with the exhaust fan l

i POINT VALUE: 1.00 i

ANSWER: REFERENCE: Tech Specs 3.6. K/A 261000 A4.07 [3.1/3.2)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0020-001-01-09 EXAM BANK Nor None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 58 i

l If the Reactor Mode switch is in START / HOT STANDBY, which one of the l

following instruments is NOT required to be operable?

] Reactor Vessel Level 1 for ADS Reactor Vessel Pressure High for ARI j Reactor Vessel Pressure for High Pressure Scram Reactor Vessel Level 2 RWCU System Isolation POINT VALUE: 1.00 j ANSWER: REFERENCE: Tech Specs Table 3. K/A: 216000 2.2.22 (3.4/4.1]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0021-001-01-10 EXAM BANK NO: None SOURCE: Bank modified USE: 1993 RO Written, Ques. 28

%

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SENIOR REACTOR OPERATOR QUESTION: 59 Following a total loss of the Uninterruptible Power Supply (UPS) at full power, which one of the following transients would occur? Plant scram caused by MSIV isolatio Loss of-AC Power caused by loss of Generator Controls, Plant scram caused by a. loss of Feedwate ' RPV Pressure transient caused by TSV and TCVs failing ope ' POINT VALUE: 1.00 ANSWER: REFERENCE: 20.300.12 K/A 262002'K3.01 (3.1/3.3]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0062-001-01-06

' EXAM BANK NO: None

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SOURCE: .New l

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SENIOR REACTOR OPERATOR QUESTION: 60 From full power operation, a transient has occurred resulting in a failure to scram. Reactor power is 27%.

Which one of the following conditions would require the crew to Terminate and Prevent injection to the RPV?

a. RPV Level at 158 inches, Drywell pressure 0.85 psig, torus temperature 111*F b. RPV Level at 102 inches, Drywell pressure 1.85 psig, torus ;

temperature 111*F c. RPV Level at -15 inches, SRV A is open, torus temperature 104*F d. RPV Level at 125 inches, SRV A is open, torus temperature 101*F POINT VALUE: 1.00

-.

ANSWER: REFERENCE: 29.100.01 SH 1A K/A 212000 K3.09 [3.3/3.6)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3003-001-01-13f EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 61 A fuel failure is suspected with the plant operating at full power. The following conditions exist:

- Main Steamline Radiation Monitors A,B,C, and D all indicate 19,000 mr/hr

- Off Gas Radiation Monitor indicates 800 mr/hr increasing

- RBHVAC Exhaust Radiation Monitor indicates 11,000 cpm What is the expected plant response? /2 Scram and 1/2 Group 1 isolation MSIV Isolation, Reactor Scram and Off Gas Isolation RBHVAC System Isolation and SGTS Initiation Reactor Scram on Group 1 Isolation POINT VALUE: 1.00 ANSWER: /. d, *7 f M khh REFERENCE: ARPs 3D12, 3D32, 3D82 K/A: 295017 AK3.01 [3.6/3.9)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0050-001-01-03 EXAM BANK NO: None SOURCE: New USE: N/A

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l -SENIOR REACTOR = OPERATOR-QUESTION- 62 The plant is operating at 38% power when'a piping rupture requires immediate shutdown of the Turbine Building Closed Cooling Water (TBCCW) syste How will this affect plant operations?

l

'a. ' An immediate scram and MSIV isolation is required ~.

l b. A rapid turbine shutdown and reactor shutdown is require . Turbine / Generator load and reactor power must be reduced to 25% to

.

. maintain reactor steam production within turbine bypass valve

!

capability, Reactor power must be reduced to maintain the Off Gas af tercooler outlet temperature within' limits to prevent a hydrogen explosio POINT VALUE: 1.00 ANSWER: REFERENCE: 23.128 K/A 400000 2.4.24 [3.3/3.7]

COGNITIVE LEVELi 2 OBJECTIVE: OP-315-0037-001-01-06 EXAM BANK NO: None SOURCE: New USE: N/ I l

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SENIOR REACTOR OPERATOR QUESTION: 63 Fermi II has increasing unidentified drywell leakage requiring a shutdow During the shutdown the following indications exist:

A' Narrow Range Level instrument (C32-R606A)' +197

'C Narrow Range Level instrument (C32-R606C) +197 B Narrow Range Level instument.(C32-R606B) +208 A Wide Range Level Instrument (B21-R604A) +197 B. Wide Range Level Instrument (D21-R604B) +210 With the Feedwater Control System aligned to the A Level instrument, which one of the following is the probable cause of the level indication mismatch?

a. High temperatures in the vicinity of the B side level sensing lines M#E % be-->- b. Steam leak from the B side level instruments reference leg dd C FgdF y c. Water / Steam leak from the A side level instruments variable leg

%

hM d. Loss of reference leg backfill to the A side level instruments POINT VALUE: 1.00 ANSWER: b, c,j al% <///G[U MdgMpFM REFERENCE: ST-OP-315-0021-001 Sect IV. [

K/A: 295009 AA2.01 [4 . 2 /4 . 2)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0021-001-01-03n, 01-08 EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATO QUESTION: 64 During a small break LOCA with a loss of Feedwater, RCIC is in operation maintaining RPV level. .RCIC suction realigns to the torus. What signal caused the RCIC pump suction to swap from the CST to the Suppression Pool?

a. Suppression Pool level greater than +2 inche 'b. RCIC pump suction pressure less than 20" Hg vacuu c. Condensate Storage Tank Level less than 32".

d. RCIC pump flow less than 90.gpm causing..the minimum flow valve to be open greater than 30 second POINT VALUE: ,

1.00 ANSWER: REFERENCE: ARP 2D48, ST-OP-315-0043-001 K/A: 217000 K6.04 (3.5/3.5)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0043-001-01-05d

.EXA!4 BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 65 You are on shift in the Control Room when a fire alarm on panel H11-P816 l involving the halon system is received. Alarm bells and a 45 second pre-I discharge horn actuates in the Relay Roo Khich of the following additional automatic actions occur when Halon initiates? No additional automatic actions occur, HVAC interlocks activate, and the CCHVAC system isolate HVAC interlocks activate, and the CCHVAC system shifts to purg HVAC interlocks activate, and the CCHVAC system shifts to recirculatio POINT VALUE: 1.00 ANSWER: REFERENCE: 23.501.03 Sect K/A: 290003 A3.01 [3.3/3.5)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0073-001-01-06d EXAM BANK NO: None SOURCE: Bank USE: 1993 RO Written, Ques. 58

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SENIOR REACTOR OPERATOR QUESTION: 66 .

Each APRM is required to have a minimum total number of LPRM inputs as well as a minimum number of-operable LPRM inputs from each detector level to be considered operabl What is the basis for this requirement? This specification ensures the APRM will provide a good representation of average core powe This specification ensures that the APRM averaging circuit has sufficient inputs to provide statistically accurate indicatio This specification ensures the combined LPRM signal through the flux amplifier is sufficient to provide on scale readings, even at-lower power levels when the core flux profile is not symmetrica This specification ensures an averaged indication from multiple inputs which increases the probability that protective action (rod block or scram) can be initiated prior to exceeding local thermal limit POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-315-0024-001 K/A: 215005 K5.04 [2.9/3.2)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0024-001-01-05 EXAM BANK NO: None SOURCE: New USE: N/A i

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SENIOR REACTOR OPERATOR QUESTION: '67 With the plant operating at full power, an earthquake has caused severe

' damage to the main condenser shell and hotwell. Condenser vacuum cannot be maintained, and water from the hotwell is leaking to the point where

~

condensate pumps cannot be operated. A Turbine Trip and Reactor Scram occurred due to the loss of condenser vacuum. The valve body for E1150-F008, RHR Shutdown Cooling Outboard Suction Isolation Valve, has been cracked, eliminating ncrmal shutdown cooling operation Which of the following options should be followed to establish decay heat removal from the core? Maintain Core Spray operating in a throttled condition, and place the RWCU system in blowdown operatio . Maintain a Reactor Recirculation pump operating, and maximize heat removal through the RWCU non-regenerative heat exchange Feed the reactor using the CRDH System, and bleed down through the recirculation loop sample line Close the MSIVs, and cool down the reactor using RHR to recirculate flow through the.SRVs to the suppression pool and maximizing cooling through the RHR heat exchanger POINT VALUE: 1.00 , ,

. ANSWER: REFERENCE: 20.205.01 K/A 290004'2.4.09 (3.3/3.9) l COGNITIVE LEVEL: 3 OBJECTIVE: OP-802-2011-001-01-04 EXAM BANK NO: None SOURCE: New

.USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 68 Main Condenser hotwell temperature is required to be maintained greater than

,

'40*F when hotwell level is in the normal operating ban ,

This limit is based'on i: nil-ductility limits for the condenser hotwell reactivity transients caused by cold water addition during startup maintaining operating efficiency of the LP turbines-d. ; preventing brittle fracture 'of the condenser pump seals POINT VALUE: 1.00 ANSWER: . REFERENCE: 23,107, ST-OP-315-0006-001-K/A 294001 2.1.32 [3.4/3.8}

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0006-001-01-0 EXAM BANK.NO: None

- SOURCE: New

' USE: N/A" s

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SENIOR REACTOR OPERATOR QUESTION: 69 The plant has been operating at full power with the following conditions:

Reactor power 96%

RPV. level 197 inches Both RR pumps 79% speed Following a trip of the A Reactor Recirculation Pump, the following conditions exist: .;

Reactor Power 62%

RPV Level .

190 inches increasing '

Recirc A & B Flow Limiter 2/3 Defeat Switch in NORMAL Which one of the following describes the Recirculation. System's respontje to these conditions? B Recirculation Pump runs back to 30% speed, B Recirculation Pump runs back to 45% spee B Recirculation Pump runs back to 75% speed, B Recirculation Pump continues to operate at 79% spee POINT VALUE: 1.00 ANSWER: REFERENCE: 20.138.01, 23.138.01 K/A: 295009 AA1.03 [3/3.1)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2003-001-01-15f EXAM BANK NO: None SOURCE: New USE: N/A I I

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SENIOR REACTOR OPERATOR QUESTION: 70 During a LOCA, the STA verified plant parameters were within the DWSIL using ERIS indication, and DW Sprays were initiated. Shortly after spray initiation, MCC 72C-3A was lost due to an electrical fault, causing the DW Spray valves to fail as-is. The STA then reported that the drywell temperature and pressure inputs to ERIS were failed when the DWSIL was verifie Investigation revealed that parameters were above the DWSIL'when DW Sprays were initiate Which of the following would be the result of initiating DW Sprays outside of the DWSIL? The rapid pressure drop would cause a drywell-below-torus differential pressure that would result in containment failur The rapid pressure drop would cause drywell pressure be relieved to the torus through the drywell to suppression chamber vacuum breaker The rapid pressure drop would result in rapid depressurization of the RPV through the break and render RPV level instrumentation inoperable due to massive reference leg flashin The rapid pressure drop would change the sensed differential pressure for the SRV tail pipe vacuum breakers, resulting in failure of these vacuum breakers to open and torus damage following additional SRV opening POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-802-3002-001 K/A 226001 K3.01 [3.6/3.7)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-3002-001-01-04 EXAM BANK NO: None SOURCE: New USE: N/A

- - _ _ - _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - _ _ _ - - - _ _ _ - _

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. SENIOR REACTOR OPERATOR QUESTION: 71 A station blackout has occurred. The following plant conditions exist:

- Breakers GD, GK, amd GM are ope Breaker GH is close Performance of AOP 20.300.01, " Loss of Offsite and Onsite Power" is in progres An NPPO has placed the breaker control switches for GD and GM in

"NON-AUTO".

- The breaker control switch for breaker GK is in AUT 'The control room operator has started CTG-11 and subsequently closes the output breaker energizing transformer 1 Which one of the following offsite sources has become a load on CTG-117 Swan Creek Luzon Shoal Brownstown 2 POINT VALUE: 1.00

' ANSWER: REFERENCE: 20.300.01 K/A 262001 K2.01 [3.3/3.6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0057-001-01-02c, d EXAM BANK NO: None SOURCE: New USE: N/A t -

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SENIOR REACTOR OPERATOR'

QUESTION: 72 The plant is shut down. RHR Loop A was in Shutdown Cooling, but tripped and could NOT be restarted. RHR Loop B is NOT available. You have been directed to verify RPV level greater than 215 inche Which one of the following is the reason for this action? Assures adequate NPSH for starting a Recirc Pump, Assures adequate NPSH to the RHR Pumps for subsequent restart Verifies the necessary pressure head to prevent boiling in the cor ' Assures a flow path through the steam separators for natural circulatio POINT VALUE: 1.00 ANSWER: REFERENCE: 20.205.01 K/A: 295021 AK1.02 [3.3/3.4]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-2011-001-01-04 EXAM BANK NO: None

- SOURCE: New USE: N/A l

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SENIOR REACTOR OPERATOR

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-QUESTION: 73 i

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'With the plant at 58%. power, an operator is preparing to start Reactor

.

l Recirculation Pump A in preparation for returning to two' loop operatio Which one of the following parameters meets the requirements for starting Recirculation Pump A?

a. ' Bottom Head Drain temperature is 360*F Recirc loop A temperature is 505*F Recirc loop B flow is 24,500 gpm Thermal power is outside of the scram region of the power to flow ]

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POINT VALUE: 1.00 ANSWER: REFERENCE: 23.138.01 K/A: 294002 2.2.01- [3.7/3.6] j COGNITIVE LEVE OBJECTIVE: OP-315-0004-001-01-09 EXAM BANK NO: None SOURCE: New

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USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 74 The plant is operating at full power when annunciator 1D66, Steam Leak j Detection Ambient Temp High, is received, and RWCU isolates. An operator sent to RR H11-P614 reports the following:

G33-TSE-N600A, RWCU Pump Rm A, indicates 181' G33-TSE-N600B, RWCU Pump Rm B, indicates 138' G33-TSE-N600C, RWCU Hx Rm, indicates 122* Which one of the following actions is required?

a. Restore RWCU System operation using only RWCU Pump b. Verify RWCU System is isolated in Pump Room c. Place the Mode Switch in SHUTDOW d. Place the Mode Switch in SHUTDOWN, and initiate Emergency Depressurizatio POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 K/A: 295032 EA1.02 [3.4/3.5)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-802-3005-001-01-03 EXAM BANK NO: None SOURCE: New USE: N/A

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QUESTION: 75 ( The EOPs direct inhibiting ADS whenever RPV level is above TAF.

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What is the basis for this actions?

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l With no high drywell pressure signal present, the low pressure ECCS pumps have not auto started. Inhibiting ADS allows time to ensure these pumps will be available.

,

- Preventing emergency depressurization before level drops to the top

'

of active fuel allows time to defeat MSIV interlocks, reopen the MSIVs, and dump steam to the main condenser to minimize heat loading on the containmen Adequate core cooling exists as long as there is steam flow through an SRV, and the delay in depressurizing allows time to align alternate injection system Adequate core cooling exists as long as level la above the top of active fuel.(0 inches), and the time for level to decrease to this point can be used to attempt to reverse the decreasing level trend before emergency depressurization is necessar POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-802-3003-001 K/A: 295031 EA2.03 [4.2/4.3]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-3003-001-01-13b EXAM BANK NO: None SOURCE: New j USE: N/A l

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QUESTION: 76 Contact K4G in the Div II Low-low Set Logic (see attached Figure 1) has failed in the' closed position. . With reactor pressure starting at 944 psig and continuing to increase, at what pressure will the first SRV open?

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- POINT VALUE: 1.00'

. ANSWER: REFERENCE: 23.201

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K/A 239002 K4.01 [3.9/4)

COGNITIVE LEVEL * 3 OBJECTIVE: OP-315-0005-001-01-27 EXAM BANK NO: None SOURCE: New- l

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' SENIOR REACTOR OPERATOR QUESTION: 77 Which one of the following signals will actuate the Emergency Diesel Generator (EDG) Fire Suppression System?

a. 2 of 7 EDG area smoke detectors activate b. Air temperature within the EDC Room between 215'F and 235* c. 2 of 7 combination ionization and smoke detectors activate d. Any smoke detector activated confirmed by a temperature above 190* POINT VALUE: 1.00 ANSWER: REFERENCE: 23.501.02 K/A: 286000 K5.05 [3/3.1)

COGNITIVE LEVEL: 1 3 OBJECTIVE: OP-315-0072-001-01-03c EXAM BANK NO: None SOURCE: New

-- USE : . N/A

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SENIOR REACTOR OPERATOR QUESTION: 78 A discharge permit has been submitted to the NSS for approval. The permit indicates the water to be discharged is potentially contaminated and will be discharged from an area subject to radiological restrictions. The actions required by MRP18, Release of Potentially Clean Fluids, have been complete Upon deciding to approve the discharge permit, the NSS should assign an expiration not to exceeds hours end of the shift in which the discharge is scheduled hours days POINT VALUE: 1.00 ANSWER: c.

REFERENCE: MCE06 K/A: 294003 2.3.06 [2.1/3.1)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-4101-0003b EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 79 The plant is in Hot Shutdown at 85 psig RPV Pressure. B loop of RHR is operating in Shutdown Cooling, and the A loop of RHR is in Standb A large break LOCA on the A Recirculation Loop suction pipe occurs causing RPV Level to drop to 18 inche l

RHR Valves F008 and FOO9 receive an isolation signal and begin to close; }

HOWEVER, both valves trip on Thermal Overload while partially close !

Which one of the following statements describes the response of the LPCI Loop Injection Outboard Isolation Valve, E1150-F017A?

I E1150-F017A can be reopened by depressing the SDC isolation reset pushbutto ( E1150-F017A cannot be opened until F008 and F009 are close E1150-F017A receives a CLOSE signal for 10 minute E1150-F017A closes and remains closed until RHR pump suction lineup to the Torus is establishe POINT VALUE: 1.00 ANSWER: REFERENCE: 23.205 K/A: 203000 A3.01 (3.8/3.7)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0041-001 01-03

- EXAM BANK NO: None SOURCE: New USE: N/A j l

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SENIOR REACTOR OPERATOR QUESTION:- 80 With the plant operating at full power, a small steam leak has resulted in Drywell pressure increasing to 2.4 psig, which one of the following identifies SRVs which are capable of operation only in the Safety mode? SRVs A, ~D, K, R' SRVs H,' J, L, N SRVs B, F, E, R- SRVs C, F, K,~M

. POINT VALUE: 1.00 ANSWER: REFERENCE: ST-OP-315-0005-001 K/A : '223002 K1.01 [2. 7/2. 9)

COGNITIVE LEVEL: 3-OBJECTIVE: ~ OP-315-0005-001-01-10b EXAM BANK NO: None SOURCE: .New

.USE: N/A

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- SENIOR REACTOR OPERATOR QUESTION: 81 The plant is operating at 100% power. The CRNSO reports that Off Gas hydrogen level is showing a slow, steady increase, and is presently at 1.0%.

Failure of which of the following is indicated by the increased hydrogen concentration?

< " Manifold Dilution Steam Controller In-Service Recombiner Chain Aftercooler In-Service Sand Filter d. Charcoal Adsorbers POINT VALUE: 1.00 ANSWER:- REFERENCE: 23.712 K/A 271000 K4.04 [3.3/3.6)

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0035-001-01-04 l

EXAM BANK NO: None l SOURCE: New

- USE: N/A

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SENIOR REACTOR OPERATO QUESTION: 82 With the plant operating normally at power, which one of the following statements' describes the Normal Reactor Water Cleanup flow path to and from- .

the RPV? Suctions from RPV Bottom Vessel Drain, A and B Recirc Pump Discharges; returns through the A Feedwater Line Suctions from A and B Recirc Pump Suctions; returns through the B Feedwater Line Suctions from RPV Bottom Vessel Drain, A and B Recirc Pump Suctions; returns through the B Feedwater Line Suctions from RPV Bottom Vessel Drain, A Recirc Pump Discharge; returns through the A Feedwater Line POINT VALUE: 1.00'

ANSWER: REFERENCE: 23.707, DWG M-5711-1 K/A: 204000 K1.01 [3.1/3.3]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0008-001-01-03b, i EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 83 Annunciator 2D1, Fuel Pool Water Level Low has been received followed by a trip of the FPCCU pumps. Investigation by a plant operator reports level in the Fuel Pool is 21'10".

Immediate action is taken to provide makeup to the Fuel Pool to: ensure a minimum of 8 feet of shielding over the irradiated fuel in the Spent Fuel Poo ensure sufficient water depth to remove 99% of the iodine gap activity released from a ruptured fuel assembl provide sufficient volume of water to assure adequate cooling to prevent exceeding pool maximum temperature limi supply adequate volume of water to allow restoring FPCCU pumps to ensure adequate decay heat remova POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 2D1, Tech Specs B3. K/A 233000 A2.02 (3.1/3.3]

COGNITIVE LEVEL: 1 OBJECTIVE: OP-315-0015-001-01-07 EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 84

.At full power, the plant has experienced a rupture of the Div II NIAS header. The Control Air Compressors have auto started, and valve P5000-F441 has closed. Checking indications within the Control Room, partial containment isolations have been received on Groups 6, 8, 13, 17, 18, and ventilation dampers have closed in both Division of SGTS and in CCHVA Attempting to cross tie IAS with DIV 1 and 2 NIAS by opening P5000-F403 failed to restore DIV 2 NIAS air pressure, and F403 reclosed. DIV 2 Drywell pneumatics have isolate ekmaj p<~ s h*g

,

Which of the following actions 6s),be directed at this time?

a. - Start all available air compressors, and cross tie NIA Vf Y p Connect Div'2 Drywell Pneumatics to a nitrogen bottle, c. - Reduce Recirc flow to 55%, and commence a reactor shutdow i Place the Reactor Mode Switch in SHUTDOW POINT VALUE: 1.00 ANSWER: g d ,v, 'N

// [ I 8[Y N 8[ 8 REFERENCE: 20.129.01, ST-OP-315-0048-001 }

K/A: 295020 2.1.07 (3.7/4.4)

COGNITIVE LEVEL: 3 OBJECTIVE:~ OP-315-0048-001-01-05n EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR

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' QUESTION: 85

With'the plant operating at full power, a fire develops in 2PC3-17,resulting -

in-loss of BOP 125 VDC Powe Which one-of.the-following actions is appropriate? Verify plant equipment, control. room indications,.and the process

. computer are operating. properly and monitor remote annuciator

. panel ~ Commence an'immediate power reduction while restoring 2PC3-17, or c- aligning an alternate power suppl Verify control room indication'and controls are operating properly,.

then commence'a' reactor shutdown while trying to restore power to the annunciator ' Reduce Core Flow to 55 - 60% of rated and place the Reactor Mode switch in SHUTDOW !

I POINT VALUE: 1.00 1

~ ANSWER: REFERENCE .621 Sect 8. K/A:' 294004 2.4.32 [3.3/3.5)~

COGNITIVE LEVEL: -2

. OBJECTIVE: OP-315-0089-001, 01-07 EXAM BANK NO: None

, SOURCE: New

'USE: N/A

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QUESTION: 86 The plant is operating at 96% power with the following indications on the A Recirculation Pump Seals Seal #1 Pressure 980 psig Seal #2 Pressure 10 peig Annunciator 3D123, RECIRC PHP A STAGING SEAL FLOW HIGH/ LOW is alarming Flow indication indicates 0.4 gp Which one of the following seal conditions exist? Seal # 1 has failed Seal # 2 has failed # 1 Seal Labyrinth is plugged # 2 Seal Labyrinth is plugged POIhT VALUE: 1.00 ANSWER: c. b,d,. pb[I #[N% _

1. 8d REFERENCE: DWG M-5702-1; ARP 3D121, 3D123 K/A 202001 A1.09 [3.3/3.3)

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0004-001-01-03b,01-04a EXAM BANK NO: None SOURCE: Bank Modified USER 9701 RO Audit Exam i

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l SENIOR REACTOR OPERATOR QUESTION: 87 Following an ATWS event which occurred at full power,.SRV K failed in the full open position resulting in a rapid torus temperature increas Terminate and prevent actions were taken to stop injection to the vessel except for CRD and Boron. SLC injection was initiated to control reator power. Level in the CLC storage tank is now 15 inche Which of the following actions is directed at this time?

a. Terminate boron injection,' and go to 20.000.21, Reactor Scra b. Restore RPV level between 173 and 214 inches, Initiate Emergency Depressurization, and maximize torus coolin Exit to 20.000.21, Reactor Scram, and SOP 23.139, SLC syste ' POINT VALUE: 1.00 ANSWER: REFERENCE: 29.100.01 SH 1A K/A: 295037 EK1.05 [3.4/3.6)

COGNITIVE LEVEL: 2 OBJECTIVE; EXAM BANK NO: None SOURCE: New -

USE: N/A'

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SENIOR REACTOR OPERATOR QUESTION: 88;

. Which one of the following is a pre-requisite to Purging /Deinerting the Primary Containment?

a. ' Both divisions of RBHVAC rad monitoring must be verified operable -

within four hours prior.to purging /deinerting, The'drywell and torus pressure must be equalized within one hour prior to commencing purge /deinerting operation Both the drywell and torus must be sampled within eight hours prior to purging /deinertin ' Torus must be vented for four hour 1 prior to initiating drywell purg POINT VALUE:- 1.00 ANSWER: REFERENCE: 23.406 Sect 8. K/A: 223001 K1.03 [2.5/3.3)

COGNITIVE LEVEL: 1

. OBJECTIVE: OP-315-0019-001-01-04 EXAM BANK NO: None SOURCE: New-TYSE : . 'N/A l

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SENIOR REACTOR OPERATOR QUESTION: 89 During a declared emergency the NSS/NASS may, with concurrence of Radiation Protection Supervision, authorize maintenance performed in a high radiation area without a Specific RWP provided which one of the following conditions is met? All personnel involved in performing the work are volunteers and have been fully briefed on the hazards involve The job is provided with continuous Rad Protection coverage, All work is documented in the Control Room Unit log with the total dose receive A full Rad Protection Survey of the area to be worked in has been performed within the past 30 day POINT VALUE: 1.00 ANSWER: REFERENCE: MRP05 K/A: 294003 2.3.10 [2.9/3.3)

COGNITIVE LEVEL: 1 OBJECTIVE: GN-508-0001-A015 EXAM BANK NO: None SOURCE: New USE: N/A l

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SENIOR REACTOR OPERATOR QUESTION:- 90 Following a single Recirc Pump trip, the plant is operating at 48% power with 41% core flow. As the plant stabilizes you notice a loss of feedwater heating has also occurre Which one of the following describes the significance of these events?

a. Colder feedwater will increase the NSPH to the operating Recirc Pump increasing Core Flow and increasing the margin to Neutron Flux Instability, Lower steam flows and loss of extraction steam to the feed heaters will cause a further decrease in plant outpu c. Increased subcooling will result in an increased core differential I

pressure which decreases core flow and reactor powe I d. Decreased feedwater temperatures will result in a power increase that may cause a scram or Neutron Flux Instabilit j l

POINT VALUE: 1.00 ANSWER:- REFERENCE: 20.107.02 K/A .2.36 [2.8/3.2]

COGNITIVE LEVEL: 1 OBJECTIVE:- OP-315-0044-001,02-06

- EXAM BANK NO: None

' SOURCE: New USE: N/A

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L SENIOR' REACTOR OPERATOR QUESTION: '91

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l Following a fire in the plant, AOP 20.000.18, Control of the Plant From the

'

Dadicated Shutdown Panel,.has been entered.

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Which one of the following will result from aligning DC panels per this procedur , All EDG aut'omatic start signals are defeate ~ b. .RCIC Turbine Level 8 trip is defeated, c. - Control Power has been removed .from all 4160V AC Breakers supplied from the BOP buses, The EF1 Supervisory Control system will be deenergized requiring local control of CTG-11 Unit POINT VALUE: 1.00 ANSWER: REFERENCE: 20.000.18 K/A 295016 AA1.07 [4. 2 /4. 3) '

COGNITIVE LEVEL: 1 OBJECTIVE: r- OP-315-0099-001-01-05 EXAM BANK NO: None SOURCE:~ New USE: .N/A j i'

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.. SENIOR REACTOR OPERATOR QUESTION: 92 While operating at 75% power, only the in-service Reactor Pressure Regulator signal' fails lo Which one'of the following control valve responses is expected?

a. Turbine Control valves fully ope b. Turbine Control Valves open slightl c. Turbine Control Valves fully close, d. Turbine Control valves close slightl POINT VALUE: 1.00 ANSWER: REFERENCE: 20.109.02 K/A: 245000 A3.05 [3/3.1)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2002-001-01-13, 01-14 EXAM BANK NO: None SOURCE: New-USE: N/A

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SENIOR REACTOR OPERATOR QUESTION: 93 l .

l During an outage, replacement.'of a RWCU valve will require 3 man-hours of-work without a respirator, or 5 man-hours with a respirator. External dose rate for the area is 75 mr/hr, and airborne activity is 15 DA Using'TEDE ALARA principles, what is the least dose a worker would receive performing this job? mr b. - 262. 5 mr .5 mr mr POINT VALUE: 1.00 ANSWER: REFERENCE: 10 CFR 20 K/A 294003 2.3.04 (2.5/3.1)

L COGNITIVE LEVEL:- 1 OBJECTIVE: GN-508-0000-001-A062 EXAM BANK NO: None SOURCE: Bank USE -New

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SENIOR REACTOR OPERATOR

. QUESTION:' 94

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i A fire' alarm has been received in Zone 8, Relay Room. The Fire Brigade Leader reports the fire is under control, but superficial damage to numerous

' cables and cable runs is apparent. The Control Room has lost indication on the;following systems:

- Power Range Neutron Monitoring

.Startup Range Neutron Monitoring ,

- Residual Heat Removal '

- Core Spray

- RCIC

- HPCI

- Turbine Protection and Control

- Control Rod Position Information which one of the following actions is required?

a. Maintain control of the plant in the Control Room and investigate failure of the equipment. Equipment failure is not associated with the fir b. , scram the reactor by placing the mode switch in SHUTDOWN and .;

maintain control in the Control Room. Send two operators to man the Dedicated Shutdown Pane . Scram the reactor using the manual scram pushbuttons, trip the Main Turbine, open the Generatcr Breakers, and transfer control to the Dedicated Shutdown Pane d. Transfer control of the plant to the Dedicated' Shutdown Panel and cool down the plant to cold shutdown conditions as soon as possibl ' POINT VALUE: '1.00 ANSWER: REFERENCE: 20.000.22, 20.000.18

.K/A: 600000 AK3.04 (2.8/3.4)

COGNITIVE LEVEL: 2 OBJECTIVE: OP-802-2017-001-01-01 EXAM BANK NO: None SOURCE: New l

USE: N/A I

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SENIOR REACTOR OPERATOR QUESTION: 95

- The plant is operating at full power. Annuciator 8D41, Div 1 Drywell Temperature High, is received. Review of indications shows all DW Fans operating, and that the alarm was caused by Point 16 exceeding 155* Drywell average temperature has increased from 132*F to 135'F during the last B hour Which one of the following actions is appropriate?

a. Increase GSW cooling to RBCCW per ARP BD4 b. Operate all available Drywell Cooling per 29.100.0 c. Manually initiate EECW and EESW Systems per 20.127.0 d. shift DW Cooling Fans 1,2,3 and 4 to low speed per 23.41 POINT VALUE: 1.00 ANSWER: REFERENCE: 8D41, 23.415 K/A: 295012 AA1.01 (3.5/3.6]

COGNITIVE LEVEL: 2 OBJECTIVE: OP-315-0017-001-01-05 EXAM BANK NO: None

. SOURCE: New USE: N/A l

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I SENIOR REACTOR OPERATOR QUESTION: 96-Which one of the following DC loads would be lost on a loss of Div I ESS Battery? HPCI Turbine Speed Control EDG #11 Local Control Main Turbine Generator Protection d. Recire MG Set Emergency Oil Pump C POINT VALUES 1.00 ANSWER: REFERENCE: 23.309, 20.300.09 K/A 263000 K2.01 [3.1/3.4)

COGNITIVE LEVEL: 1 OBJECTIVES- OP-315-0064-001-01-03a EXAM BANK NO: None SOURCE: New USE: N/A

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SENIOR REACTOR OPERATOR QUESTIONS 97

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During a LOCA the following conditions exist: l I

RPV Level 138 inches, slowing rising '

RPV Pressure 64 psig Drywell Pressure 6.0 psig Torus Water Temperature 137* A and C RHR Pumps injecting in the LPCI Mode which one of the following actions is required if RHR Pump B trips?

I Immediately start RHR Pumps D and continue Torus Spray / Cooling I Place RHR Pump B in OFF/ RESET and isolate discharge paths to the Toru ! Shut RHR Heat Exchanger B Outlet and Bypass Valves, then start RHR Pump I d. Attempt to restart the B RHR Pump and reestablish Torus Spray / Coolin !

POINT VALUE: 1.00 ANSWER: REFERENCE: 23.205 l K/A: 294004 2.4.1 [4.3/4.6]'

COGNITIVE LEVEL: .3-OBJECTIVE: OP-315-0041-001, 01-09 EXAM BANK NO: None SOURCE: New

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I SENIOR REACTOR OPERATOR

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l LQUESTIONs. 98 The plant is shutdown with the following conditions:

C RHR' Pump operating in Shutdown Cooling Mode Both RHRSW Pumps are operating to supply the A RHR H/ ,

RPV Level is 220 inches

'Which one of the following actions should be taken for an Overcurrent Trip of the C RHRSW Pump?

' Throttle E1150-F068A Div l'RHR HX Serv Wtr Outlet FCV, in the closed direction.to establish proper RHRSW flow and enter 20.205.01, loss of S/D Coolin l b.. ' Re-open E1150-F068A, Div_1 RHR HX Serv Str Outlet FCV to restore RHRSW flow to the heat exchanger after the pump trip, and-estaablish decay heat removal'per 23.800.04,- Alternate Coolant Circulation and Decay Heat removal.

! Fully open E1150-F048A, RHR' Heat Exchanger Bypass Valve, to reduce heat exchanger load and establish decay heat removal per 23.800.05, l '

Alternate Remote Coolant Circulation and Decay Heat Remova d. . Throttle open E1150-F0068A, Div 1 RHR EX Serv Wtr Outlet FCV, to maximize service water flow and cross tie RHRSW per 23.208, RHR Complex Service Water Syste POINT VALUE: 1.00

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ANSWER: '

REFERENCE: ARP 1D45,.'20.205.01

'K/A: 205000 K6.08 [3.5/3.7)

COGNITIVE LEVEL: 3

' OBJECTIVE: OP-315-0041-001-01-07a EXAM BANK NO: None SOURCE: New

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SENIOR REACTOR OPERATOR QUESTION: ' -99 ~

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Following a LOCA with a failure of several injection sources, Condensate has been lined up as an injection' system per SOP 23.10 Which one of the following lineups will provide the highest rate of Condenser Hotwell Makeup? Normal Hotwell Supply Pump operating and Hotwell Normal Makeup

. Valve full ope b',

Emergency Hotwell Supply Pump operating and Emergency Makeup Valve

, full open.

! Emergency Hotwell Supply Pump operating with Emergency and Emergency Makeup B/P Valves open Normal and Emergency Hotwell Supply Pumps operating and Normal, Emergency and Emergency Makeup B/P Valves open POINT VALUE: 1.00 ANSWER: REFERENCE: ARP 5D123 l K/A: -256000 K4.08 [3.6/3.6]-

COGNITIVE LEVEL: '2 OBJECTIVE: OP-315-0006-001-01-03p, q EXAM BANK NO: 'None SOURCE: New i USE: N/A I i l l;

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1 SENIOR REACTOR OPERATOR I

QUESTION: 100 i

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With the plant in Mode 4 for turbine repair, shutdown cooling is allowed to i cool the reactor coolant system to 65' Which one of the following concerns apply to this event?  ! Shutdown margin calculations are only valid at temperatures above 70* Vessel flange and head flange temperatures must be verified above 71* Minimum pressure vs. temperature curves are not valid below 75* A reactor vent path must be open through the main steam lines to prevent exceeding low temperature pressurization limit POINT VALUE: 1.00 ANSWER: i REFERENCE: Tech Specs 3/4. l

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K/A: 290002 K5.05 [3.1/3 . 3 ]

COGNITIVE LEVEL: 3 OBJECTIVE: OP-315-0002-001-01-07

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EXAM BANK NO: None j SOURCES- New ,

USE: N/A

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44 cAs @ cCs cDs cEs __ ._ _ 94 cAs tB3 ,at s cDs cEs

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45 c A s geen cC s rDs cEs , g  !

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95 'ess' c B ' 'C, cD, 'E1 l """ 46 gghsf c B s <Cs cDs cEs ,d g y y g

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96 cAs , Eels cCs cDs cEs ,

" F

= 47 c As cB' p cDs cEs il M -4 m

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97 (A, es rC, 'D, rE' -

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48 g,'c C s cDs cEs N ~

98 h 5s cCs cDs cEs

= """"

gg cA, rB' <C," E 3. """ 49 g ,cBs cCs cDs cE3 rE'

3 ens 50 cAs g gscs cDs cE= '5

___i M 'un's 100 c As .cCs cDs cEs E