Text

NRC Operator Licensing Exam Repts 50-317/97-10OL & 50-318/97-10OL (Including Completed & Graded Tests) for Tests Administered on 971112-21
	ML20198L551
Person / Time
Site:	Calvert Cliffs
Issue date:	01/08/1998
From:	Meyer G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20198L503	List: IR 05000317/1997010; ML20198L500;
References
	50-317-97-10OL, 50-318-97-10OL, NUDOCS 9801160055
	Download: ML20198L551 (78)
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U. S. NUCLEAR REGULATORY COMMISSION .

REGION 1-

. Docket Nos.:' 50 317 and 50-318-Report Nos.:: _9710 (OL) and 97-10 (OL)i License No.: DPR 53 and DPR 69 License ' Baltimore' Gas and Nectric

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- Facility:- Calvert Cliffs Units 1 and 2

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Location:- Lusby, Maryland

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Dates: - November 12- 21,1997 Chief Examiner: L. Briggs, Senior Operations Engineer / Examiner

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Examinors: J. Williams, Senior Operations Engineer / Examiner J. D' Antonio, Operations Engineer / Examiner Approved By: Glenn W. Meyer,' Chief, Operator Licensing and-Human Performance Branch Division of Reactor Safety J

J 9901160055 990109 PDR ADOCK 050003 V PM 4

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EXECUTIVE SUMMARY Calvert Cliffs Nuclear Power Plant,. Units 1 and 2 Inspectior Report Nos. 50 317/97-10(OL) and 50 318/97-10(OL)

Ooerations Three reactor operator (RO) and four senior reactor operator (SRO) candidates (two instant -

and two upgrades) were administered initiallicensing exams. Two SRO candidates did not pass the written portion of the exam. All other candidates successfully passed the exa Overall, candidate performance during the operating tests was determined to oe goo There were no significant generic weaknesses identified; however, several candidates experienced difficulty locating manual valve 1 during performance of in-plant JPM The original written exam submitted did not adequately meet the guidance of Interim Revision 8 of NUREG 1021. Although the initially submitted outline appeared acceptable, there were an excessive number of questions associated with certain systems on the initially subrnitted written exam. The SRO written exam also did not contain 6 sufficient number of questions at the SRO level. Those discrepancies were identified by the examiners and corrected by the licensee and their contractor following the exam preparation wee BG&E provided 13 written exam comments following the exam, and NRC deleted questions or revised answers on 8 questions based on the comments. This represents another indicatico of the low quality effort by 8G&E, given that the exam was generated and reviewed by BG&E and their contracto The examiners observed very good self and peer checking prior to non emergency activities and good peer post-checking of emergency activities during the simulator operating exa il

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Report Details 1. Operations 05 Operator Training and Qualifications 05.1 Reactor Ooerator and Senior Reactor Operator Initial Exgma Scope The initial exams were prepared by BG&E and contractor personnel using the guidelines in Intarim Revision 8 of NUREG-1021," Operator Licensing Exam Standards for Power Reactors." The NRC examiners administered the operating portion of the exam to all candidates. The written exams were administered by BG&E's training organization, Observations and Findinos The results of the exams are summarized below:

SRO Pass / Fail RO Pass / Fail Total Pass / Fail Written 2/2 3/0 5/2 Operating 4/O '3/0 7/0 Overall 2/2 3/0 5/2 The written exams, job performance measures (JoMs) and simulator scenarios were developed by BG&E and their contractor representatives using the guidance of Interim Revision 8 of NUREG 1021. The exam development team was comprised of BG&E training, operations, and contractor representatives. Allindividuals signed onto a security agreement once the development of the exam commenced. The NRC subsequently reviewed and validated all portions of the proposed exam Various changes and/or additions to the proposed exams were requested by the NRC during the on site review. BG&E and their contractor subsequertly incorporated the NRC's comments and finalized the exams, in particular, the NRC examiners noted that there was an excessive number of queations concerning certain systems and not enough questions on the SRO test that were at the SRO level. The originally submitted written exam had not adequately met the guidance of Interim Revision 8 of NUREG 1021, ES 401 Para D.2.d. and D. The written exams were administered on November 12,1997. The initial written exam consisted of 100 multiple choice questions. Subsequent to the written exam BG&E provided a total of thirteen (13) ccmments on the RO/SRO written exa The NRC reviewed the comrnents and requested additionalinformation concerning their justification for the proposed changes to several of the questions. On the SRO written exam the comments resulted in three question deletions, two questions with two correct answers, and one question had its answer changed. On the RO written exam there were two question deletions, and three questions that had two correct answers. BG&E comments and NRC reso!utions are detailed in Attachment 3 of this repor *

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The BG&E training department performed an analysis of questions missed on the written exam for generic and individual weaknesses and was in the process of developing an action plan to correct any identified problem areas. NRC review of BG&E's analysis determined that it was acceptabl During the performance of the simulator scenarios the examiners noted that candidates frequently performed self and peer checks of each other's operation During non-emergency activities the peer checks were performed prior to the activity. During emergency operations the peer checks were conducted as soon after the activity as possibl bering performance of in plant JPMs several candidates experienced difficulty locanng some small, manually operated valves. This did not prevent completion of the JPMs but did delay completion. Some cases required the candidate to go to the system operating procedure to determine the valve location, c. Conclusions The candidates performed well on the operatir9 L itions of the exam. Two SRO candidates did not pass the written portion of rl 4 xam and were not issued licenses. Candidates, in general, demonstrated good self and peer checking practice E8 Review of UFSAR commitments A recent discovery of a BG&E operating their facility in a manner contrary to the updated final safety analysis report (UFSAR) description highlighted the need for a special focused review that compares plant practices, procedures and /or parameters to the UFSAR descriptions. While performing the preexam activities discussed in this report, the inspectors reviewed applicable portions of the UFSAR that related to the selected exam questions or topic areas. No discrepancies were identified as a result of this revie V. Mananement Meetinqg X1 Exit Meeting Summary On November 21,1997, the excminers discussed their observations from the exams with Calvert Cliffs' operations and training management representative The examiners discussed generic candidate performance detailed above, concerning qeneral candidate performance and written exam comments and how they would ssbsequently be reviewed and resolved by the NRC. The examiners also expressed then appreciation for the cooperation and assistance that was provided during both the preparation and exam week by licensed operator training personnel and operations personnel. Calvert Cliffs' personnel present at the exit meeting included the following partial listing in alphabetical order:

Since there were no observed discrepancies between the simulator and the plant,

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-n PARTIAL LIST OF PERSONS CONTACTED, .

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CALVERT CLIFFS -

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. Edward Chrzanowski, Sr. Operations instructor (simulator) !

. James Lemons, Manager, Nuclear Support Services Department ;

Norman Millis, General Supervisor,- Nuclear Training ;

Michael Navin, General Supervisor, Nuclear Plant Operations !

- Robert Niedzielski, Supervisor Initial Training -

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Robert Scott, Sr. Operations instructor-. ,

"- Craig Sly, Nuclear Regulatory Matters . .

Charles Zepp,' Assistant General Supervisor,- Operations Training ;

j' !NBC _ _ q LLarry Briggs, Senior Operations Engineer, Chief Exarniaer

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Joseph D' Antonio, Operations Engineer Scott Stewart; Senior Resident inspector, Calvert Cliffs ,

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- Julian Williams, Senior Operations Engineer >

Attachments:

1 1; Calvert Cliffs SRO Written Exam w/ Answer Key-2 Calvert Cliffs RO Written Exam w/ Answer Key _

3. NRC Resolution of Calvert Cliffs SRO and RO Written Exam Comments e

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Attachment 1 CALVERT CLIFFS SRO WRITTEN EXAM W/ ANSWER KEY

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. * #" ' ' senior Reactor Operator ExaminationL

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L1:.' Due to a ' design change to the main turbine lube oil cooler, it has been determined the periodicity :

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of recording the temperature reading is to be increased from once every four hours to once every -

- two hours during the first week of service,i

Which one of the following is the minimum approval for this change in recording requirements per

NO-1-2047 - g

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b : b. Piard General Manager -

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2 During *, performance of a routine valve line up while the ordt is in MODE 5, a valve listed as OPEN is discovered to be CLOSE s

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! Which one of tne following aescribes the correct action to be'taken for this valve line up condit!on? ,

a. - Since' the unit is not in MODE 1 or 2,- an entry in the CRO log is required.

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. b.- The valve position is noted in the " discrepancy section" of the coversheet, and evaluated by the

Senior Licensed Operator. -

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c. - With concurrence of the Control Room Operator, the valve is immediately returned to the recommended positio d. An abnormal valve position tag is attached to the valve and the step is signed off as

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complete : 3L Unit 1 is operating et 83% power. The RO (operator at the plant & reactivity controls) is needed in >

[ - the Shift Sunervisor's office to discuss a surveillance the RO performed previousl ~

L The CRO is to relieve the RO for this meetin Which of the following describes the minimum action the RO is REQUIRED to perform per

, NO-1-200? -

a. Verbally brief the CR b. - Walkdown the panels with the CR *

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c. Inform the CRS of the meeting subject, duration, and his/her location for the short meetin d.' C_omplete all turn over requirements listed in the NO-1-207, " Nuclear Operations Shift Tumover". -

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... _ . _ . _ . _ . ._ _ .. . _ _ _ _ _ __. i Senior Reactor Operator Examin: tion

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4 .You are tho' Day Shift CRS and R has been brought to your attention that a non emergency call-in is needed for the.CRO next shift. At 1620 you reach an operator who is willing to come to work and was the last one on the call-in list.-- The individual states tney are fit for duty but, just completed

, drinking one glass of wine during a late lunch at about 1330 hour0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months Which of the below describes your actkms required for filling the call-in need? :

a. Direct the employee to come to work and report to the Nuclear Security Shift Superviso b.' inform the employee they can not come to work since the five hour edstinence period -

requirement would be violated, c. Inform the employee that the Shift Supervisor will waive the abstinence pe.iod since greater <

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than one half of the five hours will have passed by the time the shift starts and they should corne to work.- :

d. Revise the watch bill such that they could stand a Non-licensed watch and another licensed operator could stand the CRO watc .'During your Control Room Supervisor shift tumover pancI walkdown, you observe the handswitch for the 11 HPSI pump to be in the pull-to-lock position. The unit is !n MODE 1 at about 88% power and the time is 0535 hours0.00619 days 0.149 hours 8.845899e-4 weeks 2.035675e-4 months .

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Which one of the following is the required administrat!ve action?

a. Inform the RO and continue with the board walkdow '

L b. Direct the RO to retum the switch to automatic and continue with the board welkdow c. Inform the Nuclear Engineering Department and assure a review of the situation and governing design bases is completed by 0935 hours0.0108 days 0.26 hours 0.00155 weeks 3.557675e-4 months , d, Assure the redundant counterpart it verified operable within two hours and an entry in the CRO's log shall be mad .Which one of the following is the lowest level of authority that can authorize deviation from the Technical Specifications in the interest of providing immediate protection to the public?

a. Superintendent- Nuclear Operations

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'b. Shift Supervisor c. Control Room Supervisor-d. Reactor Operator

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Senior Reactor Operator Ex: min:tirn 7 .The unit is in a "reduct,d inventory" condition with the 13 Service Water Pump out of servic Emergent or priotity repair is needed on the 11 Service Water Pump breake What is the lowest authority to approve this work in the reduced inver. tory condition?

a. Superintendent - Nuclear Operations b. General Supervisor - Nuclear Plant Operations c. . Shift Supervisor d. Control Room Supervisor plus an independent Senior Reactor Operator 8 . A valve on the independent position check list is listed as "six tums OPEN" and has no local or remote position indicatio Which one of the following describes the method used to perform the independent ventication? w

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a. The valve is not checked by a second checker. The space for the second checker on the Locked Valve Deviation Sheet for the valve in question is marked "N/A" by the CR b. The second check is performed simultaneously with the initial positioning of the valve, c. Remove the locking device and operate the hand wheel in BOTH the open and closed position, noting number of turns, and retuming the valve to the as found position. Then re-install the locking device, d. The valve is listed on the Valve Lineup Coversheet as a discrepancy until the use of system parameters can be employed to verify the valve positio . Select the condition when compensatory actions are NOT required when removing a nuisance annunciator alarm from service?

a. The system / plant conditions are out of their " normal" operating range, b. Annunciator window already has a " magenta" do c. The annunciator has multiple inpute with one or more OUT OF SERVIC d. The alarm is not providing useful information and has been " intermittent" for greater than thirty minute Page 3 of 33

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,. Seni r R^cctor Operat:r Examination

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i 10 .When reviewing for approval an IMMEDIATE CHANGE TEMPORARY APPROVAL FORM for i Category 1 equipment, which one of the following is criteria that would allow you as the Control Room Supervisor (CRS) to approve this change?

a. A section is being added to include the valve line up for non-safety equipment associated with the surveillanc b. The valve lineup for safc+y equipment intended not to be operated will be changed such that the ncrmally open discharge valve will be closed during performance of the procedure, c. The periodicity will be increased from daily to, "once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ."

d. The materiallist is being changed. (supported by an approved engineering evaluation)

11. Surveillance is in progress on a 4 KV breaker which causes you to question the operability of a safety related componen T he correct response for this condition is:

a. inform the Manager - Nuclear Engineering Department to verify the engineer ng configuration is within the goveming bases, b an appropriate entry in the CRO's Shift Turnover Information Shee c. Inform the Shift Supervisor to determine operabilit d. Inform the Maintenance Superintendent to have work order prerequisites reviewe .

12 . A new electric motor has been installed on an existing pump. The work order requires the motor to be checked for proper rotatio Which one of the following actions are required to remove the red tag from the motor power supply? The suction and discharge valves are to remain tagged, a. Process a supplementary clearance, b. Process a modification to the tagou c. Authorize the clearance for all tags in the series and invoke the use of human danger tags for equipment that is not ready to be returned to operatio d. Verbally authorize the " lifting" of the tag for the power supply and re-install the same tag after the rotation chec l

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Senior Reactor Operator Examination'-

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, m 13 . During refueling operations, which one of the following indicates' the periodiolty for demonstrating _

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> direct communications between the Control Room personnel and the personnel et the refueling .-

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al 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1 b. . 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months i ,

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c.:o 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 I

. d.124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months ~

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1 J14 . Fuel handling has been suspended at 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months due to machN problems. - As these difficulties :

i continue onto the day shift, which one of the following indicates the periodicity for monitoring 1/M?-l

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- a. : 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; i b. -4 hours

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c.f 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s-- -

d 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

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15 'The unit is in MODE 6, fuel handling is in progress and 35% of the fuel has been removed from the 1 - core.

P The FHS informed you at 1710 hours0.0198 days 0.475 hours 0.00283 weeks 6.50655e-4 months that a fuel bundle that was on the refueling machine had become disengaged and was dropped into the vesse The control room received a valid " Fuel Handling Area Vent"(Rl-5420) alarm at 1720 hour0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months ' At 1745 hours0.0202 days 0.485 hours 0.00289 weeks 6.639725e-4 months the site experiences a power outage and the diesels fall to automatically star : Two diesels were subsequently started at 1835 hour0.0212 days 0.51 hours 0.00303 weeks 6.982175e-4 months Using ERPIP 3.0, which of the below is the classification for this event (s)?

o a. UnusualEvent .

~ b . Site Emergency

- c.1 Unusual Event d. Alert

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- Senior Reactor Operator Examination

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16 ."Any area at CCNPP accessible to individuals, in which radiation levels could result in an u lindhridual receiving an Effective Dose Equivalent (EDE) in excess of 10 rems in~one hour it 30 cm - ;

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(12 inches) from the radiation source or from Sny surface that the radiation penetrates "

LTo which one of the following does th s definition refer?.

a. a very high radiatioriare ' b. an exclusion high radiation area. - +

C ~c. a radiation are d. a locked high radiation are .The Safety Function Hierarchy is divided into six prioritie .

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a. Core & RCS Heat Removal -

b. RCS Pressuro & Inventory c. Radiation Level Extemal To Containment -

d. Containment Environment 18 .On Unit 2, if a Control Element Assembly (CEA) lift coil fails on a fully withdrawn CE .

Which one of the following Indicates the response of that CEA?

The CEA will;

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a. fall into the core and is considered non-trippabl b. not fall into the core but w!il respond to motion commands only in the inward direction and is

- considered non-idppable, c. not fall into the core and will not respond to any motion commands and is consTdered trippable,

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d. fall into the core when CEA motion is attempted and is considered trippabl ;

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Senior Reactor Operator Examination -

19.Given the following:

- A Unit i reactor startup is in progres The Reactor Operator is withdrawing Regulating Group 1 CEAs in the MANUAL GROUP mod Regulating group 1 is at 120 inche No CEA deviations exis WHICH ONE (1) of the following will be the FIRST to automatically stop CEA movement?

a. Highest CEA reaches the Upper Group Stop (UCS).

b. Lowest CEA reaches the Upper Group Stop (UCS).

c. Highest CEA reaches the_ Upper Electrical Limit (UEL).

d. Lowest CEA reaches the Upper Electrical Limit (UEL).

20 . An engineering test is scheduled on your shift. Test prerequisites specify the RdS temperature be at 180 F. The time is 0830 and present RCS temperature is 210 Which one of the following is the earliest time that temperature can be at 180 'F?

a. 0848 b. 1000 c. 1012 d. 1130 21.lf the Reactor Vessel Level Moni*oring System (RVLMS) indicates sensors 1 through 5 are lit, which one of the following is correct?

a. The entire core is voide b. RCS level is at or below the Fuel Alignment Plat c. Suffblent inventory exists to suppor' Shutdowr, Cooling flo d. The upper head region above the core is full.

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i' age 7 of 33

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- Senior Reactor Operator Examination

22 . Charging pumpspre running on Unit 1 and an SIAS is present. (Assume no operator action)

When the BASTS are emptied, the charging pumps will:

a. trip on low oil pressure, b. trip on low suction prescure, c. automatically align to the RW d. continue to run and become gas boun Which, one of the following describes the expected positioning of valves in the CVCS system on SIAS that wil! allow boration flow?

The flow path for boration is created by flow from the Boric Acid Storage Tanks (BAST Tanks),:

a. through the gravity feed valves, through the Boric Acid pumps, through the Boric Acid Strainer, through manual boration valve CVC-174, directly to the Charging Pump suctio b. bypassing the gravity feed valves, through the Boric Acid Pumps, through the Boric Acid Strainer, throuph CV-210Y, directly to the Charging Pump suction, c. through the Boric Acid pumps, through Emergency Borate Valve (CVC-514), directly to the Charging Pump suctio d. through the gravity feed valves, through the Bor!c Acid Pumps, Emergency Borate Valve (CVC-514), directly to the Charging Pump suctio .

24 , Low Pressure Safety injection pumps recirculation valves SI-659 and SI-660 are manually closed on RAS actuatio Which one of the following is the reason these valves are closed?

a. Recirculation flow is not required for pump protection since the LPSI pumpe are tripped on RA b. Prevent release to the environment of activated airborne particles from the containment sump water via the RWT ven c. Ensure NPSH for LPSI pumps following P.A d. - Ensure maximum flow c' woter to the RC .

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Senior Reactor Operator Examination;

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255 Unit 1 is on SDC when RCS pressure inst;&ty drifts up to 325 psia. Which one of the z .

following will protect the SDC. system from over pressurizing? j

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s. LTOP will actuate to reduce RCS pressur _ {

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- bc Operator action is required to reduce RCS pressure and protect SDC syste c. ~ LPSI pumps will trip and their discharge check valves will shu ]

d. SDC retum isolation valves Sl4514.*0V & S1452-MOV shut and SDC suction line relief will lift

to protect the rotum header.-

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i ' 26_.Given the following Unit 1 control room and chemistry reports:

RCS pressure is 1600 psi '

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a RCS temperature'is 360 * F. ,

- . Safety injection Tank 11 A boron concentration = 2250 pp ,

a 1 Safety injection Tank 11 A level = 194" ~

. -Safety injection Tank 11A pressure = 225 psig

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All rods are inserte '

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Which one of the following identifies the operabil;ty status of 11 A Safety injection Tank?

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a. The Safety injection Tank is not required to be operai '

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b. Safety injection Tank level is above the ' allowable leve c. ' Safety injection Tank pressure is above allowable pressur ,

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. d. Boroti concentration is bebw allowable concentration.

27 .Un;t 1 is on SDC when RCS pressure as read on PT-103 and 103-1 inadvertently drifts up to 350

- psia. What automatic functions will protect the SDC system from overpressure? -

a. RV-468, SDC suction line relief downstream of SI-651, willlift to protect the retum header.

< b. Since MPT is enabled, two PORVs will open when RCS pressure exceeds 340-psi c. LPSI pumps wi!!! trip and their discharge valves will shu: d. SL651-MOV and SI-652-MOV shut and relief valve RV-469, SDC suction line relief between

- SI-651 and SI-652 will lift to protect the retum header.

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Senior Reactor Operator Ex:minati:n 28 .On a loss of the "11" 4 KV bus, which ONE of the following occurs preventing either train of Shutdown Coolireg (SDC) from being placed in service on Unit 17 .

a. One SDC Hot Leg Suction Valve is de-energized, b. The SDC Temperature Control Valve (CV-657) is de-energized, c. One Loiv Pressure Safety injection Header Isolation Valve in each train is de-energized, d. The Sr,C Heat Exchanger Bypass Valve (FCV-306) fails closed due to a loss of instrument Ai . Following a LOCA, RCS pressure !s at 1300 psi Which one of the following statements describes the status of Si flow?

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a. Constant HPSI flow exists with no LPSI flo b. No HPSI or LPSI flow exist ~

c. Incteasing HPSI flow exists, no LPSI flo d. Constant HPSI and LPSI flow exist .The following plant conditions exist:

-Steady state operation at 100% powe The PZR pressure Selected Controller setpoint is inadvertently changed to 2360 psia (step change).

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-Pressurizer pressure control is in automati Which one of the following will be the IMMEDIATE response of the system?

a. Power operated relief valve RC-402 opeos and proportlenal heaters go to minimu b. Power operated rel:ef valves RC402 and RC404 open and spray valves open if previously close c. Spray valves open if previously closed and proportional heaters go to minimum, d. Spray valves close if previously open and proportional heaters go to maximu .

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Senior Reactor Operator Ex: min:ti:n 31.Which one of the following describes the response of a Pressurizer Level channel falling low?

Assume the failed channel is the selected channel and n) operator action is taken, j a. All heaters will deenergize, letdown goes to minimum, standby charging pump starts, actual pressurizer level and pressure increase, the reactor trips on High Pressurizer pressur !

l b. All heaters will deenergize, pressurizer pressure decreases, the reactor trips on TM/L l c. All heaters remain energized, letdown goes to maximum, only one charging pump remains ON, Actual pressurizer pressure and level decrease, the reador trips on TM/L d. ' All heaters remain energized, letdown goes to minimum, actual pressurizer level and pres,sure increase, the reactor trips on High Pressurizer Pressur d 32 You aro the dedicated SRO during a normal power ascension. The RO has just reset the Variable Over Power Trip (VOPT). At what power level would you expect the RO to respond to the next VOPT reset demand alarm? .

Given the following information:

Delta T power indicates 43%

Nuclear power indicates 41.8%

a. 47.6%

b. 48.8%

c. 50.2%

d. 51.4%

33 .Which one of the following describes the plant response to a loss of 120 VAC Bus 117 a. - A loss of power will occur to 1/2 of the CEDM b. ESFAS Sensor channel ZE comp 7nents tri c. 4 Trip Circuit Breakers will open with unit tri d.10 RPS Channel A trip units are trippe Page 11 of 33 '

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Senior Reactor Operator Examinationv

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34, Removing an ISOLATION module from one of the Engineered Safety Features cabinets places ~

the LOGIC modules logic in:" -

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'a.~: 2 out of 4

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' b. ~ 1 out of 3 c.; 2 out of 3:

d. - 1 out of 4 ,

d J

35 Whils in Hot Standby, the "ALTUATION SYS SIAS TRIPPED" alarm has annunciated at 1C08. .

Which of the following conditions indicates actuation of a "VAll0" SIAS? -

a.- Containment Pressure at 1_C10 indicates 2.0 psig and slowly increasing, and PZR pressure

- displays at 1C06 indicates 1760 pela and decreasing slowl *

b. Containment Pressure at 1C10 indicates 1.6 psig and slowls

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) increasing, and the TM/LP pre-trip and trip unit lights are illuminated on at least three RPS channel .

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c. = Containment Pressure at _1C10 indicates 4.0 psig and slowly increasing, and the Containment.- ,

Pressure pre-trip and trip unit lights are illuminated on all RPS channel id, PZR Pressura displays at 1C06 indicate '1760 psia and slowly decreasing, and all1 M/LP ,

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pre-trip and trio unit lights illuminated on all RPS channel .The Diverse Scram System (DSS) accomplishes a reactoi trip signal independent and diverse of the Noactor Protection System (RPS) by:

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r. Tripping Engineered Safety Features Actuation System (ESFAS) input parameters which are independent / diverse of RPS .

bl Tripping the reactor by using non-safety related control channels for inputs to the RP c. : Tripping the reactor by opening the CEA MG set input breaker through the ESFA d. Tripping the reactor by opening the contactors upsiream of the Reactor Trip breakers which RPS open _

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Senior Reactor' Operator Ex minstion ;

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37; During reactor startup, power is raised to the Point-of-Adding-Heat. All Wide Range Channels are :

-indicating approx.1% The Operator-At-the-Controls observes power range indication at 4% -j zWhat action is required by OP-2 " Plant Startup from Hot-Standby to Minimum Load"? -

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s. Continue the reactor etartup per OP-2, indications of proper overiap have been verifie /

b. Continue the reactor wtartup per OP-2 and declare MODE 1 at LEL c. Stop the reactor startup; Observe linear power indication on 1C15 to determine proper NI -

response, d. Stop the reactor startup. Observe Wide Range indication on 1C05 to determine pro;.or Ni response. -

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38 .Which one of the following is'the reason that CEDM fans are operated when RCS temperature ,

are less than 300 F durin0 accident conditions?

a.1 Minimize the build up of condensation on the CEDM winding ~

b. Aid in the collapse of voids that may have formed in the RCS during the event, c E Aid in the cooling of the containment atmosphere during the even d. Minimize the buildup of condensation on components, other than CEDMs, attached to the vessel head.- ;

- 39 . Unit i reactor power is 82%. Reactor Cavity Cooling fan 11 is in service when it trips due to electrical faul Which one of the following describes the responso, if any, of the remaining cooling fan?

. a. Autornatically starts after 10 seconds.

b L Must be started manuall , ' c. Must be started manually within 10 second d. Automatically starts immediately.

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i Senior Reactor Operator Examination 4 .. .

.-40l. Prior to an RAS, containment pressure is'SO psig. Following RAS contain nent pressure isL i reduced below the CSAS 'setpointJ Which one of the following describes the response of the; 3 containment spray system?2

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CS flow will: "

a.Enot change as~oontainment pressure fus negligible effect on spray flo *

b. decrease during the injection phase of containment spray actuatio .j

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c. increase during the recirculation phase of containment spray actuatio . _

fd. decrease during the recirculation. phase of containment Spray actuatio ;

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41.? As the CRS, you receive a report that a . spurious CSAS has been received. What system 1 ,

response, if any, would you expect to confirm the report?

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a. One Containment Spray pump starts and SI 4150/4151 open.

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i b'.- One Containment lodine Removal unit start c.n Only.Sl-4150/4151 ope ;d. The system lineup does not chang *

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> (42 U The Trisodium Phosphate Dodecahydrate (TSP) stored in the Unit 2 containment basement will

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maintain the pH of the water in the basement following a LOCA:

~a , less than 7.0 to ensure radioactive lodine is scrubbed from Containment Spray Wate h. greater than 7.0 to ensure radioactive lodine is scrubbed from Containment Spray Water.

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c. less than 7.0 to prevent corrosion cracking of metals inside containmen <

d. greater than 7.0 to prevent corrosion cracking of metals inside conta'nment.-

43 .Which one of the following describes the Containment lodine Removal System flow path?

a. Moisture Separator, HEF A Filter, Charcoal Filter, Circulating Fan.

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b. Charcoal Filter, Moisture Separator, HEPA Filter, Circulating Fan, c. Moisture Separator,-Charcoal Filter, HEPA Filter, Circulating Fa ?d. Circulating Fan, Moisture Separator, HEPA Filter, Charcoal Filte .

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Senior Reactor Operator Examination -<

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I 144 .Given the following plard conditions:-

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Unit 2 tripped from 80% power due to a loss of vacuum : ~h

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c All systems i::;+M+1 as expected

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1Tavg is $33 degrees-F g g vas.s.,eciosed

if Tavg begins to increase above 535 degrees-F the steam dumps will:

a. immediately begin to modulate open until T-avg reaches 540 degrees-F, at which tinee they will quick-ope .,

b. . immediately begin to modulate open until T-avg reaches 548 degrees-F, at which time they willl

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be fully open.-

c. remain closed until T-avg reaches 540 degrees-F, at which time they will begin to modulate -

,ope ,

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i d.c remain closed until T-avg reaches 540 degroes-F, at which time they will quicli-open, j

. 45). As CRS, prior to paralleling the unit, you receive a report that a high level alarm on i f S/G has : ;

been actuated and that 11 Feed Water Regulating Valve Bypass Valve does not respond t ,

manual controller operation. Assuming the remaining systems respond as expected, what manual -t actions are required per AOP 3G to mitigate this condition.'

= a. ~ Shut both S/G Feedwater Isolation Valve ,

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b. Dspress the feed regulating and bypass valve resat pushbutto c. Trip one Main Feed Pump.

d.' Shut the effected S/G Feedwater ! solation Valv .Which one of the following will result in the initiation of an AUTOMATIC trip of the "11" Main Feedwater-pump when Unit 1 is at 100% power? _

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at: Pump discharge pressure increases to 1500 psig

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b.- Suction pressure decreases to 250 psig.

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c. Pump discharge pressure decreases to 1100 psig.

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l d, Trip of the "11" condensate pum .

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Senior. Reactor Operator Examinati n - ,

47 ,Which one of the following describes the operation of the Steam lVl S upp y a ves for the Turbine Driven AFW Pump?--

J s. When opening, CV-4070 and CV-4070s open simultaneousl . o b. When closing, CV-4070s closes fhst followed by CV-407 c. When opening, CV 4070a opens first followed by CV-4070.-

d. W.ien opening, CV-4070 opens first followed by CV-4070 !

48 . Select the function of ths, kr/ switches located in the Auxiliary Feed Water (AFW) Pump room for the Turbine Driven AFW Pump Trip / Throttle (T/T) valve, s. Enable the T/T valve trip function from the AFW Pump Room, b. Trip the T/T valve locally, c.' Disable the T/T valve trip function from the AFW Pump Roo ,

d. . Disable the T/T valve trip function from the control room handswitche . ,

49 ! Unit 1 is operating at full power when 4 Reactor Trip Breakers open. The reactor does NOT trip and NO other TCB's ope Wnich one of the following equipment failures is the cause of this event?

a. 208/120 VAC Instrument Bus

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b.125 VDC Reserve Battery Bus c.125 VDC Bus d. CEA MG set

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50 .Which one of the following indicates the pressurizer heaters that would be available following a Loss of Off-site Power (LOOP)? Assume the DGs start and cany the emergency load _

- a. Proportional Heater Bank-1 and Backup Heater Bank- b. Proportional Heater Bank- c. Backup Heater Bank-1 & 'd. Backup Heater Bank-1 and Propotional Heater Bank- P i -.

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Senior Reactor Operator Ex:mination

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51 ?.The 125VDC Battery Charger 11 has failed due to an electrical faul Which ONE of the following identifies the remaining sources of power to 120VAC vital Bus 117 a. 125VDC Battery Charger No.12,-

125VDC Battery 11, 120VAC _ Inverter Back;;p Bus 21

. b.125VDC Battery Charger No. 23, !

125VDC Battery 11, 120VAC Inverter Backup Bus 1 j c. 125VDC Battery Charger No. 23, 125VDC Battery 11,-

120VAC Inverter Backup Bus 21 d.125VDC Battery Charger N;. 2, .

__125VDC Battery 11, 120VAC Inverter Backup Bus 11 ,

52 Which one of the following is the source of control power for breakers on the 4KV Unit Bus 117

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a. 120 V Vital AC b. 125 VDC c. 250 VDC -

d. 208/120 VAC 53 '.Which one of the following statements best describes the relationship of the 120 VAC and 125 VDC power to the plant computer?

a. The static inverter feeding the computer has both a 120 VAC and a 125 VDC power supply and it automatically switches on a loss of the 125 VD _

b. - The static inverter feeding the computer has both a 120 YAC and 125 VDC power supply which has to be manually switched to the 120 VAC when M 125 VDC is lost.-

c. The static inverter is a backup to the normal 120 VAC power source. When 120 VAC is lost, power is automatically switched to the 125 VDC powered inverte d. The 125 VDC powered static inverter supplies the #11 120 VAC inverter bus which in turn supplies power to the lant compute .

Page 17 of 33

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.j 8enior Reactor Operator Extmination 3 l

_54 .The annunc iator "125 VDC Power Supply Failure" has energized on the 1 A Diesel Generator control pane When a diesel generator start signal is received, the diesel gencretor_will:

s. start because only 1 of the 4 air start dist!ibutor solenoid valves are affected by the loss of DC

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volt b. : start because backup power supplies will allow power to be supplied to the air start distributor .

solenoids.- ;

c. not start since DC power will only be supplied to 2 of the 4 air start distributor solenoid valve d. not start because DC power is unavailable to any of the air start distributor solenoid valve '

55;Which ONE of the following 1 A Diesel Generator trips will also actuate the Emergency Shutdown

. Signal alarm on the Annunciator panel? .

a.1 Generator Differential Protection b. Generator Overvoltage c. G6nerator bearing HlH3 temperature d. Push Button 2A (Emergency Stop pushbutton on local control panel) depressed 56 .The 1 A Diesel Generator (DG) is running under load during periodic testing. The DG is paralled to the ESF 4KV bus 1 What is the diesel generator response to a Loss of Offsite Power?

The diesel generator output breaker will:

a. remain closed, will pick up all required loads, ant.' continue to supply power to the emergency loads on bus-1 b~ remain closed, will try to pick up the required loads but will trip on overcurrent,

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c. immediately trip open and remain'open until manually close =.d.- will trip open and reclose to bus 17 if no faults exist and normal and alternate feeder breakers are ope + .

Page 18 of 33

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Senior Reactor Operator Examinati:n 57 .WHICH ONE of the following is the expected respor:se of the Instrument Air System to a major Turbine Building Instrument Air header rupture on Unit 17 a. Instrument air pressure will decrease on Unit i unUl the air compressors trip on high curren b. Instrument air cross tie valve to Un:t 2 will open, then reciosa if the Unit 2 Instrument Air System pressure drops below setpoin c. The normally open Instrument air cross tie valve to Unit 2 will close when Unit 1 instrument Air l System pressure drops belo".'setpoin ,

d. The Plant Air System cross tie valve will open to supply the Unit 1 instrument Air System when pressure drops below setpoin . AOP-18 "CEA Malfunction", requires reactor power to be maintained constant during the

'

recovery of a single dropped CE Which one of the following is used to maintain Reactor power?

a. Turbine t.oad b. Boration c. Gh-@ 0 CEAs d. Diintion 59 .The follow'ng plant conditions exist: Two CEAs have dropped into the cor . Pressurizer level decreases to <05". Reactor power decreases from 100% to 85%. Presssurizer pressure decreases to 2225 pal ~

WHICH ONE of the following is the min! mum action required?

a. Trip the reactor and perform Standard Post Trip Action b. Reduce Turbine load to match Reactor powe c. Commence a reactor shutdown to subcritica d. Reduce power to less than 70%.

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. Senior Reactor Operator Examination 60 . Unit 2 has been operating at 100% power when a load decrease to 50% is initiated. During the load decrease ONE CEA remains at its fully withdrawn position while the other CEAs in the Group are t>eing inserte Which one of the following annunciator alarms would provide indication that the CEA failed to :

move? ;

a. "CEA WITHDRAWAL PROHIBl b. "CEA MOTIONINHIBI :

I c. " SECONDARY CEA GROUP SEQUENCE".

d. * SECONDARY POWER DEPEN INSERTION".

61. During performance of Unit 1 EOP 0, which one of the following radiation monitors in an alarm states would require Attemate Actions to be performed?

a. Containment b. Wide Range Noble Gas c. Main Vent Gaseous d. Main Steamline 02 .Given the following conditions:

A RCS heatup is in progres * RCS pressure is.2260"pffi a ?22CO The acoustic monitor for a PORV Indicates valve leakag Which ONE of the following describes the expected tall pipe temperature and how tall pipe temperature will respond as RCS pressure decreases to 500 psla?

(Assume pressure downstream of the PORV remains constant.) -

a. Tall pipe temperature will be higher than if the PORV opened at teormal operating pressur As pressure decreases tail pipe temperature w!Il increas b. Tail pipe temperature will be higher than if the PORV opened at normal operating pressur As pressure decreases tall pipe temperature will decreas c. Tall pipe temperature will be lower than if the PORV opened at normal operating pressure. As pressure decreases tall pipe temperature will increas d. Tall pipe temperature will be lower than if the PORV opened at normal operating pressure. As pressure decreases tail pipe temperature will decrease.

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, Sanior Reactor Operator Examination ,

63 ,Which ONE of the following parameters wH discriminate between a Small Break LOCA and an equivalent Steam Line Break, both occurring inside containment?

a. Pressurizer Level b. Pressurizer Pressure c. Containment Pressure d. Cold Leg Ternperature l 64 .Which ONE of the following is an approved alternate method of establishing hot leg injection during a LOCA event on Unit 17 a. LPSI pump discharging to the pressurizer auxiliary spray line, b. LPSI pump discharging to the hot legs via the shutdown cooling suction line, c, HPSI pumps discharging to the normal pressurizer spray line, d. Con.ainment Spray Pumps discharging to the hot legs vb the normal pressurizer spray lin .Which one of the following mechanisms is utilized to satisfy the Core and RCS Heat Removal Safety function during a Large Break LOCA event?

a. Steam Generator Heat Remova b. Charging pump operation ,

c. Reactor Coolant .' ump operation d. ESFAS pump injectio l 66 .With power at 94%, which ONE of the following lists ALL RCP temperatures that can exceed 195 * 4

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F and allow the RCP to continue to operate?

a. Upper or lower guide bearing temperatures and controlled bleedoff temperatures, b. Upper or downward thrust bearing temperature c. Upper or lower guide bearing and upper or downward thrust bearing temperatures, d. Controlled bleed off temperature ,

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. Senior Reactor CpercNr Examination

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87 . A loss of MCC 104R has ooourred.-

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Which one of the following describes a boration flow path that remains available?

a. RWT, CVC-508, CVC-504, charging pump suction.

. b. BAST, CVC-210Y, CVC-512, VCT, charging pump suction j c. RWT, CVC 608; chasing pump suction i ;

d. BAST, CVC-514,' charging pump suction

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68 . At what point in shutdown operations do administrative restrictions relating to REDUCED INVENTORY take effect?' .

- s. the middle of the hot leg

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b. the bottom of the Hot Log c. 3 feet below the reactor vessel flange ^

d. 7 feet below the reactor vessel flange - ;

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69 .The reactor is shutdown with shutdown cooling (SDC) in progress when the operating LPSI pump !

becomes air bound and trips due to low RCS water level. Alter RCS water level is restored, ,

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neither LPSI pump can provide significant flo l What other pumps can be aligned to the SDC system to provide SDC flow?

a. HPSI pumps b. Containment spray pumps ,

c. Charging pumps d. Spent fuel pool cooling pumps .

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Seni:r Rocctor Oper;ttr Excmin:tisn 70 .The air supply to the Comper ent Cooling Water retum line containment isolation valve (CC-3833)

has been broken while sce.ffcidine was being erecte _j

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Which ONE of the following der cribes tho effect, if any, this wil; have on Reactor Coolant Pump i operation? $!

I a. RCPs will have to be tripped immediatel b. F CP temperatures on two of the four pumps willincreas . gA c. RCPs will be able to operate for 10 minute d. RCP cooling will be unaffecte . Accoiding to the Abnormal Operating Procedure for Loss of Component Cooling Water (CCW),

which one of the following CCW malfunctions would require the Reactor to be TRIPPED?

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a. Low level alarm in the CCW Head Tan .

b. Cavitation of running CCW pump c. A trip of the 11 CCW Pump while runnin d. Low RCP CCW flow alan .The following plant conditions exist:

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1. Unit 2 is at 100% powe . All control systems are in AUTOMATI . Pressurizer spray valve is stuck OPE . NO operator action is take WHICH ONE of the following describes the effect of RCS pressure DECREASING to 2210 psla?

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a. Pressurizor "PZR CH 100 PR2SS" alarm is energized, b. Proportional heaters are fully energized, c. Proportional heaters are partially energize 'd. All backup heaters energize .

Page 23 of 33

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2. , Senior Reactor Operator Examinatkm

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i ;73 .Which one of the following would be the' primary hazard if fuel were damaged within the pressure

'W , .ssel during refueling operations?

. t: y inadvertent crbality.

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6 kMiine 131 exposure, to personnel, c. Chronio Gamma radiation exposure to refueling machine operato d. Neutron radiation exposure to refueling machine opeistor.

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l 74 . Unit 1 is being shutdown to hot standby due to a Steam Generator Tube Lea i

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Which ONE of the following indicates the tube leak has become a tube rupture? -

e. With one charging pump running, leidown isolated, and pressurizer level can no longer be . 1 controlled at setpoin j

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< bi With one charging pump running, and letdown flow at minimum and pressurizer level can no i

longer be controlled at setpoin ]

t c.6 When letdown flow combined with the tube rupture flow exceeds 45 GP l

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d. When charging flow reaches 88 GP l

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75 .With AOP 2A b61ng implemented, soled the valve that is required to be CLOSED for isolation of ;

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a tube leak on steam generator 21, and is normally maintained open? ;

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c a. Steam Generator 21 Steam Supply valve (MS4070-CV) _

l b. ~ Steam Generator 21. Steam Supply Bypass Valve (MS4070A CV) ;

j c. Steam Generator 21 Flow Control Valve (AFW4511-CV) l

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. d. AFW Pump 21 Trip Throttle Valve (MS-3986) j

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~ Senior Reactor Operator Examination .

i 76.Given the fohuwing conditions:

1. A Steam Generator Tube Rupture has oocurre . All systems responded as expecte . The performance of EOP-6 is in progres !

3. One Steam Generator has been isolated,

' 4. All RCPs have been stoppe ,

5. RCS cooldown using natural circulation is in progres Which one of the following describes the reason that the isolated SG pressure is of concern before the RCS can be placed on SDC?

a. The isolated SG pressure would be too low due to excessive cooldown causing RCS water to enter the SG and reducing RCS Inventory, b. SG pressure is being maintained slightly less than RCS pressure to prevent secondary water entering the RC ^

c. Since the RCS cooldown rate was maintained less than 35 F/hr, the affected loop has not been cooled suff.ciently to allow SG depressurization, d. The affected SG pressure is high due to thermal stratification of the secondary wate .The foilowing plant conditions exist: A steam line break exists upstream of 21 MSIV on Unit . SGIS has automatically initiate WUch one of the following conditions could result if a steaming flowpath from the unaffected stearn generator is not established immediately following dryout of the affected steam generator?

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a. Rapid repressurization of the RCS and subsequent Pressurized Thermal Shock (PTS)

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condition b. Inability to open 22 S/G MSIV due to pressure difference created when affected steam generator reaches dryout condition ,c. A rapid decrease in T-cold of the unaffected loop resulting in an interruption of natural circulatio d. A decrease in the core exit temperatures resulting in an interruption of natural circulatio Page 25 of 33

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a

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, - Senlot eteactor Operator Examination

78,Given the following:

-During an Excess Steam Demand event, BOTH steam generators are suspected of being

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- affecte Which one of the following identifies the steam generator (s) that should be isolated?

a. Both steam generators, since a potential exists to over-cool the RC ;

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b. Only the steam generator w;th the highest T i c. Either steam generator, since it will aid in identification of the affected S/ d. Only the steam generator with the lowest ressur ;

79 . A loss of condenser vacuum occurred on Unit 1 with reactor power at 60% The operators are reducing power and are able to maintain condenser vacuum at 24 inches H Which ONE of the following indicates the power level at which the turbine will have to be tripped if vacuum can NOT be increased to greater than 25 inches Hg?

a. 88 MWE.

b. 176 MW c. 270 MW d. 440 MW '

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80 .Which one of the following is used to check that Two Phase Natural Circulation is sufficient to maintain core heat removal in EOP-7 " Station Blackout"?

a. Sub-cooled Margin between 30 F and 50 b. Thot - Tcold delta T is less than 50 c. Core Exit Thermocouples indicate less than superhea . o. Steaming the S/G with the TBV :l

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. Senior Reactor Operator Examination

.81.Which one of the Safety Functions is of primary 'ir.portsnoe

. in the mitigation of a Station Blackout, prior to power evallability?

a. Souctivity Control ,

b. RCS Pressure Control l c. Core and RCS Heat Removal l d. RCS Inventory Control l

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82 .During the performance of EOP-7 " Station Blackout" On Unit 1, which one of the following describes the actions performed in aligning the electrical system for power restoration?

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Ensure the:

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a.13KV Feeder breakers are CLOSE b. 4KV Bus LOCl/SD sequencer is OF l

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c. DG output breakers are CLOSE l d. 14 4KV Bus Altemate Feeder Breaker is OPE .

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83 .Which one of the following describes the method used to operate AFW flow control valves during the performance of EOP-7," Station Blackout"?

a. Local manual control by an operato h. Control room operation after aligning N2 to the AFW amplifier air syste '

c. Placing the controller in Auto-Full open and controlling speed of the Steam Driven AFW pum '

d. Local manual control after al%ning N2 to the AFW amplifier air syste .Following a Loss cf Offsite Power, natural circulation flow can not be accurately verified for appro minute . Which one_of the following is the cause of this time delay?

a. ' Reactor Coolant Pump Coastdown, t b. - Steam Generator inverted Delta c. Low Steam Generator, Levels. d, increased loop cycle time. . 4 l ,

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, Senior Reactor Operator Examination

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85 . Following a loss of 12120 VAC bus, the performance of steos in AOP-7J requires the ESFAS SENSOR cabinets be reenergized prior to the LOGIC cabinets.

> Which ONE of the following is the basis for the order of th6 steps? !

a. Prevent inadvertent actuation since the Logic modules are doenergized to actuate snd the sensor modules are energized to actuate.

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b. Prevent inadvertent actuation since the Logic modules are energized to actuate and the sensor modules are deenergized to actuat c. Properly align the Under Voltage Logic relays, d. Properly align the Under Voltage Sensor Relays.

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86 . A loss of which one of the following power supplies for 15 minutes will require entry into the ;

Emergency Plan?

a. 11 120 VAC

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b. 21125 VDC

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c. 13 250 VDC d. 21208/120VAC Inst. Bus .

87 . During the performance of a waste gas release from the 11 Waste Gas Decay Tank, WGS-2191-CV is found to be close Which valve must be closed as soon as possible to prevent a possible waste gas decay tank discharge to the waste gas surge tank?

a. Waste gas discharge flow control (WGS-2191 PCV)

b. Waste gas decay tank outlet (WGS-623)

c. Waste gas discharge to Unit 1 plant vent (WGS 683)

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d. Waste gas discharge final filter bypass (WGS-630)

88 .Which one of the following is correct concerning a loss of Instrument Air Pressure?

a. Condensate Demineralizer Bypass Valve falls ope b. Pressurizer Spray Valves fail open, c, Pressurizer Auxiliary Spray Valve falls close d. Containment Spray Control Valves fall close .

Pago 28 of 33 ,, ,

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Senior Reactor Operator Examination 89 . During a loss of instrument air in MODE 1 operation, when would the reactor and turbine be tripped and EOP 0 implemented?

a. If instrument air pressure decisases to less than 40 psig and Feed Regulating Valve control is !

lost, b. If instrument air pressure dec# eases to 40 psig or in the opinion of the SS or CRS continued plant operation may cause equipment damag :

c. If component cooling containment isolation vue6, CC-3832-CV or CC-3833-CV, begin to go shut and low flow alarms received on the RCP d. If component cooling containment isolation valves, CC-3832 CV or CC 3833-CV, begin to go shut or in the opinion of the SS or CRd continued plant operation may cause damage to the RCP .Given the following:

A fire has been ddtected in a panelin the control room

+ Supervision has determined that the control room is to be evacuated

Prior to fire discovery, both units were opemting in Mode 1

Prior to control room evacuation the required actions of AOP gA " CONTROL ROOM EVACUATION..." have been performed Which one of the following describes the initial response of RCS temperature upon abandoning the control room?

Temperature will be controlled:

a. at 515 F - 535 F by TBV b. at 515 F - 535 F by ADV c. by the Main Steam Safety Valves cycling, d. by Auxiliary Feedwater flow and ADVs operating in automatic contro _

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Senior Reactor Operator Ex:m! nation

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91.Which one of the following describes the timing of actions that are accomplished during the performance of AOP 9B," Safe Shutdown due to a Severe Cable Spreading Room Fire"?

a. Establish charging flow within 60 minutes and AFW flow within 30 minutes, b. Establish AFW flow within 60 minutes and charging flow within 30 minutes, c. Stop Steam Generator Feed Pumps within 60 minutes and start 1 A Diesel Generator within 30 minutes, d. Start i A Diesel Generator within 60 minutes and stop Steam Generator Feed Pumps within 30 minute I 92 .Given the following information:

Reactor Poweris 100%

i Dose Equivalent lodine 131 = 156 Micro Cl/g E Bar = 0.65 What actions are required?

a. Maximize CVCS purification flow and continue current operatio b. Reduos power to <56% or be in at least Hot Standby with Tave <500 F within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

c. Be in at least Hot Standby with Teve <500 F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , d. Maximize CVCS purification flow and increase RCS sampling frequency to once every two hour . One of the first actions the operator is instructed to take IAW AOP-6A " Abnormal Reactor Coolant Chemistry / Activity" on increased RCS activity is to adjust letdown flow.

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Which one of the following statements is correct as to the adjustment and the reason?

a. Increase letdown to maximum so that more RCS water can be diverted and processed by the waste management syste b. Decrease letdown to minimum to minimize the amount of radioactive letdown that is flowing throughout the auxiliary buildin c. Isolate letdown until the cause of the activity increase can be determine d. Increase letdown flow to obtain the maximum purification flo % *

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Senior Reactor Operator Examination . !:

94 .Given the following parameters: .l i

l 0830 084 That 482 482'

CETTemp. 587 585- -

Toold 467 466 ,

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Which ONE of the followinvo scribes the conclusion that can be made about natural circulation? !

Adequate natural circulation has:

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a not been established because Thot is remaining constan b. been established because the delta between Thot and Toold is decreasin c. been estabhshed because Toold is decreasin :

d. not beeri established because the CET temp. is decreasin .

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i 95_. A natural circulation cooldown is in progress. While cooling down with ADVs, which ONE of ther following will cause the most restrictive limitation on cooldown rate? !

a. Isolating one steam generato j

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b. Complying with Technical Specifications cooldown restrictio c. Cooling down without main feidwater ava!!abl ,

d, Complying with Pressurizer cooldown restrictions, !

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.g6 .Given the fo! lowing Unit 1 conditions: l

+ 11 Steam Generator has a .03 gpm tube lea $

' RCS Identified leakage is g.2 gp Which ONE of the following is the maximum allowable leakage from 12 Steam Generator?

a. 03 gpm .

b. 06 gpm ,

c. -.08 gpm j

- d. 97 gpm ..

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Senior Reactor Operator Examination 97 Which one of the following is a basis for the Technical Specification limit (s) for steam generator leakage?

The Technical Specification limit: .

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a. assures that the leakage rate used in the analysis for a steam line break accident is not exceeded, b. essures that the exposure to plant personnel that could occur following a Steam Generator :

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Tube Rupture is limite c. assures that at the minimum rate, a leak can be reliably detecte d. assures that the exposure to plant personnel that could occur if an atmospheric dump were to open is limited.

98 While operating Unit 1 @ 100% power, one Steam Generator Feed Pump (SGFP) tripped due to a mechanical fault. Reactor power was reduced to 60% while troubleshooting the failed pum Operation may CONTINUE at this power level as long as which one of the following parameters is maintained, a. SGFP suction flow rate is 19500 gp b. SGFP suction pressure is 265 psi c, SGFP speed is 5375 RP d. SGFP discharge pressure is 1350 psig.

90 , A Main Feedwater Regulating valve (FRV) is being operated manually at the F3V when a reactor trip occur Which ONE of the following describes the required action?

a. Locally close the FR b. Close the Main Feedwater Isolation Valve, c. Position the FRV to 5% open, d. Vent air from the FR .

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100 .Which one of the following describes the length of time from a valid ' m steam generator level condition ( 170") to open the main steam suppy valves (MS-4070&*071) to the turbine driven !

Auxiliary Feedwater Pumps? (

a. 10 se b. 20 se c. 45 se d. 65 se l

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Reactor Operator Examination 1 Duringin erformance of a routine valve line up while the unit is in MODE 5, a valve listed as OPEN is ,. wered to be CLOSE ,

Which one of the following desenber, the correct action to be taken for this valve line up condition? ;

e a. Since the unit is not in MODE 1 or 2, an entry in the CRO log is required, b. The valve position is noted in the " discrepancy section" of the coversheet, and evaluated by the Senior Licensed Operator, c. Wrth concurrence of the Control Room Operator, the valve is immediately retumed to the ,

recommended positio d. An abnormal valve position tag is attached to the valve and the step is signed off as complete . Unit 1 is operating at 83% power. The RO (operator at the plant & reactivity wntrols) is needed in the Shift Supervisor's office to discuss a surveillance the RO performed previousl The CRO is to relieve the RO for this meetin Which of the following describes tie minimum action the RO is REQUIRED to perform per NO-12007 a. Verbally brief the CR b. Walkdown the panels with the CR c. Inform the CRS of the meeting subject, duration, and his/her location for the short meeting, d. Complete all turn over requirements listed in the NO-1-207, " Nuclear Operations Shift Turnover".

3 Which one of the following is the lowest level of authority that can authorize deviation from the Technical Specifications in the intere,st of providing immediate protection to the public?

a. Superintendent. Nuclear Operations b. Shift Supervisor c. Control Room Supervisor d. Reactor Operator Page 1 of 33

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Reactor Operator Examination l 4 . A valve on the independent position check list is listed as "six turns OPEN" and has no local or remote position indicatio Which one of the following describes the method used to perform the independent verification?

a. The valve is not checked by a second checker. The space for the second checker on the Locked Valt'e Deviation Sheet for the valve in question is marked "N/A" by the CR ;

b. The second check is performed simultaneously with the initial positioning of the valv c. Remove the locking device and operate the hand wheel in BOTH the open and closed position, noting number of tums, and retuming the valve to the as found position. Then re install the locking devic d. The valve is listed on the Valve Lineup Coversheet as a discrepancy until the use of system parameters can be employed to verify the valve positio .You are performing a " Continuous Use" techn! cal procedure to conduct an 114KV bus

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disconnect operation. You are in the 27' switch gear room and the procedure states, " To open disconnect 189-1111 in the 45'switchgear room".

Which of the below describes the action required?

a. Draw a line through the error, change the "45" to "27" and initial the chang b. Draw a line through the error, change the "45" to "27" and inform the CR c. Continue the procedure and note the nomenclature error and process an " Issue Report" as described in QL-2-10 d. Receive concurrence from the Shift Supervisor that this is a clerical error and proceed with the tas . Select tha condition when compensatory actions are NOT required when removing a nuisance annunciator alarm from service?

a. The system / plant conditions are out of their " normal" operating range, b. Annunciator window already has a " magenta" do c. The annunciator has multiple inputs with one or more OUT OF SERVIC d. The alarm is not providing usefulinformation and has been " intermittent" for greater than thirty minute Page 2 of 33 i

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Reactor Operator Examination -

7 . Surveillance is in progrsss on a 4 KV breaker which causes you to question ths operability of a safety related componen Tho correct response for this condition is: ,

a. Inform the Manager Nuclear Engineering Department to verify the engineering conf ~guraSon

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is within the goveming base b. an appropriate entry in the CRO's Shift Tumover Information Shee !

c. Infonn the Shift Supervisor to determine operabilit d. Inform the Maintenance Superintendent to have work order prerequisites reviewed.

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8 . Equipment requiring a post maintenanoa test or evaluation is identified by:

a. the safe 4 lag which initially took the equipment out of servic b. the Technical Specification LCO tracking syste v. :s btw tag sitached to the equipment controls,

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d. yehv. oots on the component annunciator (s) in the control room, g . During refueling operations, which one of the following indicates the periodicity for demonstrating direct communications between the Control Room personnel and the personnel at the refueling ,

stations?

a. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months c. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months d. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 10 . Fuel handling has been suspended at 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months due to machine problems. As these difficulties continue onto the day shift, which one of the following indicates the periodicity for monitoring 1/M7 a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months b. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months d. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Page 3 of 33

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11.Which one of the following desortbes the onuse of the 1/2 C06 panel annunciator " Unit 1/2 j SPDS*7 ;

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' A orttioni safety function box on the SPD8 has changed color from:

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a. red to magents l b. green to yellow

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, red to green 7

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green to red l d._-

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12 .*Any area at CCNPP socessible to individuals, in which radiation levels could result in an individual receiving an Effective Dose Equivalent (EDE) in excess of 10 roms in one hour at 30 cm j

, t (12 inches) from the radiation source or from any surfeos that the radiation penetrates." :

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s. a very high radiation sto ;

b. en exclusion high radiation are t c. a radiation are d. a locked high radiation are ,

i 13 .The Safety Function H6tarchy is divided into six prioritie ;

What is the third priority safety function?

a. Core & RCS Heat Removal

, b. RCS Pressure & Inventory

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i c. Radiation Level Extemal To Containment ,

d. Containment Environment-

14 .With one MG tot running and the CEDM bus x-tie (TCB g) closed, what is the minimum number of b TCBs which must open for a FULL reactor trip to occur?

a. 1 h b. 2 :

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c; 4 d. 8

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Reactor Operator Examination 15 .Given the fcilowing:

- A Unit i re.ctor startup is in progres The Reactor Operator is withdrawing Regulating Group 1 CEAs in the MANUAL GROUP mod l Regulating group 1 is at 120 inche No CEA deviations exis .

WHICH ONE (1) of the following will be the FIRST to automatically stop CEA movement?

a. Highest CEA reaches the Upper Group Stop (UCS).

b. Lowest CEA reaches the Upper Group Stop (UCS).

i c. Highest CEA reaches the Upper Electrical Limit (UEL).

d. Lowest CEA reaches the Upper Electrical Limit (UEL).

16 .Which one of the following pro-trips / conditions will generate a CEA Hotion Inhibit? Assume logic has been me a. UCS b. High SUR c. PDIL d. Tavg/ Tref Deviation 17 . lf the Reactor Vessel Level Monitoring System (RVLMS) indicates sensors 1 through 5 are lit, which one of the following is correct?

a. The entire core is volded, b. RCS levelis at or below the Fu-l Alignment Plat c. Sufficient inventory exists to surort Shutdown Cooling flow, d. The upper head region above the core is full.

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Reactor Operator Examination '

18 .Which one of the following describes how continuous spray flow is maintained?

a. PZR main spray valves, RC-21g and 220, are throttisd open to maintain spray line ;

temperatures betwoon 500 F and 605 i b. PZR pressure controller meintained in automatic with a setpoint of 220 psi j c. PZR main spray valves have a small ortflos drilled through their seats to allow a continous l bypass fic l

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d. PZR main spray valves, RC-219 and 220, are throttled open to maintain spray line temperatures between 550 F and 20 i

' ig . During normal full power operations, one RCP experiences increased bearing friction causing ,

RCS flow to decrease by 0.5%

Which one of the following describes the RCS parameter response? ,

s. T hot increases, Delta T increases,' and Reactor power remains the sam l b. T-hot increases, Delta T decreases, and Reactor power increases, c. T-hot decreases, Delta T increases, and Reactor power remains the sam d. T-hot doorosses, Delta T decreases, and Reactor power decreases, 20.Given the following conditions:

- RCS Pressure - 2250 psia

- Middle seal cavity 2200 psia

- Upper seel cavity - 2050 psia Bloedoff cavity - 130 pela

- Sealleakoff flow- 1.7 gpm t Which one of the following indicates the seal (s) that have or are falling?

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s. Lower seal b. Lower and Middle seal c. Middle seal d. Middle and Upper seal Page 6 of 33

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Reactor Operator Examination 21.Which one of the following is indication of a leak in the Reactor Coolant Pump (RCP) shaft seal I (integral) heat exchanger?

a. High RCP Component Cooling Water (CCW) outlet temperatur !

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b. Low levelin the CCW Head tan c. High RCP bloedoff flow, d. High RCP CCW outlet flo .The following plant conditions exist: ;

' Unit 2 is in MODE . VCT makeup is l- SUTOMATI . CVC-500 contn Automatic Divert) is m the " AUTO" positio . VCT level tronov - er LT-226 channel fails LO ; No operator action is take .

WHICH ONE of the following describes the system response?

a. VOT Inlet / Divert valve CVC-500 opens and divstts flow to the radweste syste b. VCT makeup valve CVC-512 opens, c. Recolpt of VCT low level annunciato '

d. Charging pump suction shifts to the RW . Charging pumps are running on Unit 1 and an SIAS is present. (Assume no operator action)

When the BASTS are emptied, the charging pumps will:

a. trip on low oil pressur b. trip on low suction pressure, c. automatically align to the RW d. continue to run and become gas boun Page 7 of 33 6' _ - _ .

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Reactor Operator Examination 24 .Which one of the following describes the expected positioning of valves in the CVCS system on SlAS that will allow boration flow?

The flow path for boration is created by flow from the Boric Acid Storage Tanks (BAST Tanks),:

a. through the gravity feed valves, through the Boric Acid pumps, through the Boric Acid Strainer, through manual boration valve CVC-174, directly to the Charging Pump suctio b. bypassing the gravity feed valves, through the Boric Acid Pumps, through the Boric Acid Strainer, through CV 210Y, directly to the Cha ilng Pump suction,

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c. through the Boric Acid pumps, through Emergency Borate Valve (CVC 514), directly to the Charging Pump suctb d. through the gravity feed valves, through the Boric Acid Pumps, Emergency Borate Valve (CVC-514), directly to the Charging Pump suctio .Which one of the following describes the method of controlling RCS cooldown while on shutdown cooling on Unit 17 a. Manually adjust the SDC flow Controller (FIC-306) and manually adjust the SDC heat exchanger temperature controller (HIC 3657) to attain the desired cooldown rat b. Manually adjust the SDC Flow Controller (FIC-306) and allow automatic control of the SDC heat exchanger temperature controller (HIC-3657) to attain the desired cooldown rat ,

c. Allow automatic control of the SDC Flow Controller ( FIC-306) and manually adjust the SDC heat exchanger temperature controller (HIC-3657) to attain the dosired cooldown rat d. Allow automatic control of the SDC Flow Controller (FlC-306) and automatic control of the SDC heat exchanger temperature controller (HIC-3657) to attain the desired cooldown rate.

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Reactor Operator Examination

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26 . Low Pressure Safety In}ection pumps recirculation valves SI-669 and SI-660 are manually closed on RAS actuatio Which one of the following is the reason these valves are closed?

a. - Recirculation flow is not require.s for pump protection since the LPSI pumps are tripped on RA b. Prevent release to the environment of activated altbome particles from the containment sump water via the RWT vent, c. Ensure NPSH for LPSI pumps following RA d. Ensure maximum flow of water to the RC .UrM 1 is on SDC when RCS pressure inadvertently drifts up to 325 psia. Which one of the following will protect the SDC system from over pressurizing?

a. LTOP will actuate to reduce RCS pressur b. Operator action is required to reduce RCS pressure and protect SDC syste c. LPSI pumps will trip and their discharge check velves will shu d. SDC return isolation va!ves SI-651 MOV & SI 652-MOV shut and SDC suction line relief will lift to protect the retum heade . Unit 1 is on SDC when RCS pressure as read on PT 103 and 103-1 inadvertently drifts up to 350 pala What automatic functions will protect the SDC system from overpressure?

a. RV-468, SDC suct:on line relief downstream of SI-651, will lift to protect the retum header, b. Since MPT is enabled, two PORVs will open when RCS pressure exceeds 340 psi c. LPSI pumps willl trip and their discharge valves will shu d. SI-651-MOV and SI-652-MOV thut and relief valve RV-469, SDC suction line relief between SI-651 and SI-652 will lift to protect the return heade Page 9 of 33

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29 . On a loss of the "11" 4 KV bus, which ONE of the following occurs preventing either train of Shutdown Cooling (SDC) from being placed in service on Unit 17 ,

s. One SDC Hot Log Suction Valve is de-energized, b. The SDC Temperature Control Valve (CV 657) is de energize c. One Low Pressure Safety injection Header isolation Valve in each train is de-energize d. The SDC Heat Exchanger Bypass Valve (FCV 306) fails closed due to a loss of instrument Ai I 30 .Following a LOCA, RCS pressare is at 1300 psi Which one of the following statements describes the status of Si flow?

a. Constant HPSI flow exists with no LPSI flo l' No HPSI or LPSI flow exists, c. Invenslng HPSI flow exists, no LPSI(Io d. Constant HPSI and LPSI flow exist '

31. Select the Normt.1 and Alternate sources of makeup water to the Component Cooling Water Head Tank?

a. Normal- Condensate System Altemate - Firewster System b. Normal- Demineralized Water Alternate - Reactor Makeup Water c. S'ormal- Condensate System Alternate - Demineralized Water System d. Normal- Demineralized Water System Attemate - Condensate System Page 10 of 33

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32 .During full power ope 1wis, the annunciator alarm "CCW PPS SIAS Blocked Auto Start" on C13 has sounded, i

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Which one of the following describes the cruse of the annunciator?

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a. CC pump 13 Breaker is open and its disconnect is close b. SIAS signal to CC pump 13 and the pump breaker falls to close, c. CC pump 13 handswitch is in Pull-To-Lo $

d. CC pump 11 Breaker is open and its disconnect is close ;

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33 .The following plant conditions exist:

-Steady state operation at 100% powe The PZR pressure Selected Controller setpoint is inadvertently changed to 2360 psia (step '

change).

-Pressurizer pressure control is in autornati Which one of the following will be the IMMEDIATE response of the system?

a. Power operated relief valve RC-402 opens and proportional heaters go to minimu b. Power operated relief valves RC-402 and RC-404 open and spray valves open if previously close .

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c. Spray valves open if previously closed and proportional heaters go to minimu d. Spray valves close if previousiy open and proportional heaters go to maximu :

34 .Given the following conditions on Unit 2:

- operating at 0 % power-

- pressurizer love! and pressure controls in automatic, selected to channel Y

- channel X pressurizer level and pressure at setpoint You observe the backup charging pump starts and all pressurizer heaters have de-energize '

Which one of the following is the cause of this event?

a." The controlling pressurizer pressure transmitter failed lo t

- b. The controlling pressurizer pressure transmitter failed hig c. The controlling pressurizer level transmitter failed lo d. The controlling pressurizer level transmitter failed hig t Page 11 of 33 s

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Reactor Operat:r Ex:mination 35 .Which one of the following describes the response of a Pressurizer Level channel failing low?

Assume the failed channel is the selected channel and no operator action is take a. All heaters will deenergite, letdown goes to minimum, standby charging pump stcrts, actual pressurizer level and pressure increase, the reacht trips on High Pressurizer pressure, b. All heaters will deenergize, pressurizer pressure decreases, the reactor trips on TM/L c. All heaters remain energized, letdown goes to maximum, only one charging pump remaino ON, Actual pressurizer pressure and ievel decrease, the reactor trips on TM/L d. All heaters remain cnergized, letdown goes to rrinimum, actual pressurizer level and pressure increase, the reactor trips on High Pressurizer Pressur .Which one of the following describes the plant response to a loss of 120 VAC Bus 117 a. A loss of power will occur to 1/2 of the CEDM b. ESFAS Sensor channel ZE components tri c. 4 Trip Circuit Breakers will open with unit trip, d. 10 RPS Channel A trip units are trippe .When the High Pressurizer Pressure Trip inhibit key is installed in the bistable trip unit in the Reector Protection System (RPS) panel, it closes contacts Ir.hibiting which portion of the High Pressurizer Pressure trip?

a. Blocks the Diverse Scram System (DSS) input from that channel of RP b. Disah'es PORV motor operated isolation valv c. Prevents Power Operated Relief Valve (PORV) operation by use of the key on CO d. Bypasses the PORV actuation from that channel of RP . Under which condition will the low S/G pressure trip be bypassed?

a. Automatically bypassed when the auctioneered high S/G pressure is <767 psia b. Manually bypassed with a key when the auctioneered high S/G pressure is < 767 psia, c. Automatically bypassed once the main turbine trip d. Manually bypassed with a key once the main turbine trip Page 12 of 33

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Reactor Operator Examinati::n

- 39 .Upon Recirculation Actuation Signal, valves are repocitioned after verifying HPSI pump flo Which one of the following describes the valve repositioning that occurs on an RAS? -

RWT outlet valves are CLOSED:

a. automatically and containment sump discharge valves open automaticall b. manually after the containment sump discharge valves are opened manuall c. manually and containment sump discharge valves are opened automatically, d. automatically and the containment sump discharge valves are opened manuall . Removing an ISOLATION module from one of the Engineered Safety Features cabinets places the LOGIC modules logic in:

a. 2 out of 4

- b. 1 out of 3 c. 2 out of 3 d.1 out of 4

, 41.While in Hot Standby, the " ACTUATION SYS SlAS TRIPPED" alarm has annunciated at 1C0 Which of the following conditions indicates actuation of a ' VALID" SlAS?

a. Containment Pressure at 1C10 indicates 2.0 psig and slowly increasing, and PZR ' pressure displays at 1C06 Indicates 1760 psia and decreasing slowly, b. Containment Pressure at 1C10 indicates 1.6 psig and slowly increasing, and the TM/LP pre-trip and trip unit lights are illuminated on at least three RPS channels.

" c. Containment Pressure at 1C10 indicates 4.0 psig and slowly increasing, and the Containment Pressure pre-trip and trip unit lights are illuminated on all RPS channel .d. PZR Pressure displays at 1C06 indicate 1760 psia and -!owly decreasing, and all TM/LP ,

pre-trip and trip unit lights illuminated on all RPS channels. ~

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Reactor Operator Ex:mination

42 .The Diverse Scram System (DSS) accomplishes a reactor trip signal independent'and diverse of the Reactor Protection System (RPS) b '

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a; Tripping Engineered Safety Features Actuation System (ESFAS) input parametens which are independent / diverse of RPS.-

b. Tripping the reactor by using non-safety relateo control channels for inputs to the RP c: Tripping the reactor by opening the CEA MG set input breaker through the ESFAS.--

d. : Tripping the reactor by opening line contactors upstream of the Reactor Trip breakers which RPS opens.

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43 .During a normal reactor startup, which one of the following is used to monitor count rate doublira?

a. WR Count Rate Channe ,

b. : Audio amplifier circuits,

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c. - Linear Power Channe d. Shutdown' Monito . During reactor startup, power is raised to the Point-of-Adding-Heat. All Wide Range Channels 'are indicating approx.1%. The Operator-At-the-Controls observes power range indication at 4%.

What action is required by OP-2 " Plant Startup from Hot-Standby to Minimum Load"? .

a. Continue the reactor startup per OP-2, indications of proper overlap have been verified, b. Continue the reactor startup per OP-2 and declare MODE 1 at 5%.

c. Stop the reactor startup. Observe linear power indication on 1C15 to determine proper NI

, respons d. Stop the reactor startup. Observe Wide Range indication on 1C05 to determine proper NI response. -

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45 .Which orie of the following describes the result of de-energizing the Gamma-Metrics LRNI level 2

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bistable?--- ,

l a.L Enables APD trip. -

- b;L Initiates power _ trip test interlock circuit (PTTl)~ . ;

c. Energizes channelin test LE d. Enables loss ofload tri ,

46 ,Which one of the following is the reason that CEDM fans are cperated when RCS temperatures - 1 are less than 300 F during accident conditions? .

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a., Minimize the build up of condensation on the CEDM winding " b? Aid in the collapse of voids that may have formed in the RCS during the event.-

c. Aid in the cooling of the containment atmosphere during the even de Minimize the buildup of condensaton on components, other than CEDMs, attached to the -

1 vessel hea :

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- 47 . Unit i reactor power is 82%. Reactor Cavity Cooling fan 11 is in service when it frips due to

- electrical fault. - 5 Which one of the following describes the response, if any, of the remaining cooling fan?

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a. Automatically starts after 10 second b. Must be started manuall c. Must bo started manually within 10 second '

d. Automatically starts immediately.

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48 . Prior to an RAS, containment pressure is 50 psig. - Following RAS containment pressure is reduced below the CSAS setpoint. Which one of the following describes the response of the containment spray system?

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. CS flow will:

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[ a. _- not change as containment pressure has negligible effect on spray flo b decrease during the injection phase of containment spray actuatio '

t c. le: crease during the recirculation phase of containment spray actuatio .

~ d.-: decrease during the recirculation phase of containment Spray actuatio '

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Reactor Operator Ex: mination l 14g .Which one of the following describes the Containment lodine'Remova,l System flow path?_

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- a? Moisture Separator, HEPA Filter, Charcoal Filter, Circulatira Fan.'_ q b. , Charcoal Filter, Moisture Separator, HEPA Filter, Circuisting Fanc , ,

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l c. Moisture Separator, Charcoal Filter, HEPA Filter, Circulating Fa d.i Circulating Fan, Moisture Separator, HEPA Filter, Charcoal Filte .

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~50. lGiven the following plant conditions:

Unit 2 tripped from 80% power due to a loss of vacuum All systems responded as expected ;

Tavg is 533 degrees-F -

D mgvalves are closed i ilf Tavg begins to increase above 535 degrees-F the steam dumps will: ,

s. immediately begin to modulate _open until T-avg reaches 540 degrees-F, at which time they' will

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quick-open. .

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b. immediately begin to modulate open untilT-avg reaches 548' degrees-F, at which time they_will '

be fully ope ,

c. remain closed until T-avg reaches 540 degrees-F, at which time they will begin to modulate open, d. remain closed until T-avg reaches 540 degrees-F, at which time, my will quick-open, 51.Ti;e T eedwater Control System is in manual with the plant holding at 80% power. The feedwater regulating bypass valve for Steam Generator 12 drifts fully ope '

Assuming no operator action,12 Steam Generator level will:

a. increase to the Mi Level set point, the feedwater regulating valve and Bypass vahre close, with Steam Flow > Feed Flow, a reactor trip from Lo Steam Generator Level will occur.

' b. - will remain constant as the feedwater regulating valve closes to compensate for the increasing leve c, will remain constant as feed pump speed decreases to maintain feedwater regulating valve L

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delta Pc

- d. increase to the Hi level trip setpoint closing the feedwater regulating valve and the bypass valve and causing _a turbine trip and reactor tri .

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. Reactor Operator Ex: min tion 52 .Which one of the following will result in the initiation of an AUTOMATIC trip of the "11" Main Feedwater pump when Unit 1 is at 100% power?

a Pump discharge pressure increases to 1500 psig b. Suction pressure decreases to 250 psi "

cf Pump discharge pressure decreases to 1100 psi d. Trip of the "11" condensate pum .The plant was operating at 20% power when it tripped on low Steam Generator level. The Main g Feed Water Regulating Valves closed and their bypass valves ramped to 5% feed flow.-

Which one of the following conditions caused this valve response?

a. Auxiliary contacts on the Reactor Trip Circuit Breaker 'b. Auxiliary contacts in the Steam Dump Permissive Circui c. Undervoltage on the Control Element Drive Mechanism buses, d. Steam Generator water level less than -170 inche .Which one of the following describes the opemtion of the Steam Supply Valves for the Turbine Driven AFW Pump?

a. When opening, CV-4070 and CV-4')70a open simultaneously, b. When closing, CV-4070a closes first followed by CV-407 c. When opening, CV-4070a opens first followed by CV-407 '

d. When opening, CV-4070 opens first followed by CV-4070 . Select the function of the keyswitches located in the Auxiliary Feed Water (AFW) Pump room for the Turbine Driven AFW Pump TripRhrottle (T/T) valv '

a. Enable the T/T valve trip function from the AFW Pump Roo b. Trip the TIT valve locally, c. Disable the T/T valve trip function from the AFW Pump Room, d. Disable the T/T valve trip function from the control room handswitche Page 17 of 33

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Reactor Operator Examination

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. 56 . Unit 1 is operating at full power when 4 Reactor Trip Breakers open. .The reactor does NOT trip --

.. and NO other TCB's ope x ;

Which one of the following equipment failures.is the cause of this event?

- a. 208/120 VAC Instrument Bus ' -

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b. - 125 VDC Reserve Battery Bus '

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- c. 125 VDC Bus d. CEA MG set 57 .Which one of the following irdicates the pressurizer heaters that would be available following a

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' Loss of Off-site Power (LOOP)? ~ Assume the DGs start and carry the emergency load a. Proportional Heater Bank-1 and Backup Hester Bank- '

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. b. ' Proportional Hester Bank- c. Backup Hester Bank-1 & d. Backup Heater Bank-1 and Propotional Heater Bank- '

!58 .The 125VDC Battery Charger 11 has failed due to an electrical faul Which ONE of the following identifies the remaining sources of power to 120VAC vital Bus 117

a. 125VDC Battery Charger No.12, .

125VDC Battery 11 120VAC Inverter Backup Bus 21 L b. 125VDC Battery Charger No. 23, 125VDC Battery,11, 120VAC Inverter Backup Bus 11, c. 125VDC Battery Charger No. 23, 125VDC Battery 11, 120VAC Inverter Backup Bus 21 d.125VDC Battery Charger No.12,.

125VDC Battery 11,

-120VAC Inverter Backup Bus 11

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Reactor Operator ExaminatiSn - :i

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15g ![Which one of the following is the source of control power for breakers on the'4KV Unit Bus 117 - 1 a. .120 V Vital AC ' ;

b. 125 VDC c. - 250 VDC d. 208/120 VAC

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" 60 .Which one of the following statements best desenbos the relationship of the 120 VAC and 125

~ VDC power to the plant computer?

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a.~ The static invester feNing the computer has both a 120 VAC and a 125 VDC power supply . ~

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and it automatically switches on a loss of the 125 VDC.-.

b? The static inverter feeding the computer has both a 120 VAC and 125 VDC power rupply-which has to be manually switched to the 120 VAC when the 125 VDC is lost.-

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c? The static inverter is a backup to the normal 120 VAC power source. When 120 VAC is lost, _ ,

power is automatically switched to the 125 VDC powered inverte ,

d. The 125 VDC powered static invester supplies the #11 120 VAC inverter bus which in tum l supplies power to the plant compute . .When stopping Diesel Generator 1 A following a periodic test, load is first reduced to approximately 450 KW before the output breaker is opene Why is load reduced to this power level?

a. Allows for cooldown of the engine, b. The engine may overspeed if power is higher.

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c. - The breaker has a manual interlock above 450 K d. . The reverse power trip circuit is energized below 400 KW, l r q i

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82 .The annunciator "125 VDC Power Supply Failure" has energized on the _1 A Diesel GeneratorL

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control panel,; .

When a diesel generator start signal is received, the diesel generator will:

a; start because only 1 of the 4 air start distributor solenoid valves are affected by the loss of DC volts, b. start because backup power supplies will allow power to be supplied to the air start distributor !

solenoid c. not start since DC power will only be supplied to 2 of the 4 air start distributor solenoid valve '

Ed. not start because DC power is unavailable to any of the air start distributor solenoid valve ' 63 .Which ONE of the following' 1 A Diesel Generator trips will also actuate the Emergency Shutdown Signal alarm on the Annunciator panel?

a. Generator Differential Protection b. Generator Overvoltage .

c. - Generator bearing HiHi temperature d. Push Button 2A (Emergency Stop pushbutton on local control panel) depressed

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64 .WHICH ONE of the following is the expected response of the instrument Air System to a major Turbine Building Instrument Air header rupture on Unit 17 a. Instrument air pressure will decrease on Unit i until the air compressors trip on high curren b. Instrument air cross-tie valve to Unit 2 will open, then reclose if the Unit 2 Instrument Air System pressure drops below setpoin c. The normally open instrument air cross-tie valve to Unit 2 will close when Unit 1 Instrument Air System presrire drops below setpoin d. The Plant Ar. System cross-tie valve will open to supply the Unit 1 instrument A,ir System when pressure drops below setpoint.

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Reactor Operator Examination- ;-e 3 ;

65.. AOP-18, "CEA Malfunction", requires reactor power to be maintained constant during the -- l-

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recovery of a single dropped CEA; =

Which one of the following is'used to maintain Reactor power?

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d

'a.1 Turbine Load !

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b.- Boration '

c. Group C_CEAs; l

. d. l Dilution -

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j j 66 ;The following plant conditions exist: ,

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- Two CEAs have dropped into the cor _

i2. Pressurizer levei decreases to <95".

3;1 Reactor power decreases from 100% to 85%. =,

- ,f 4f Pressurizer pressure decreases to 2225 psi WHICH ONE of the following is the minimum action required? _

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a. Trip the reactor and ' perform Standard Post Trip Action b. Reduce Turbine load to match Reactor powe c. Commence a reactor shutdown to subcritica d. Reduce power to less than 70%. 1

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k 67 . Unit _2 has been operating at 100% power when a load decrease to 50% is initiated.. During the

- load decrease ONE CEA rema!ns at its fully withdrawn position while the other CEAs in the Grou are being inserted.

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Which one of the following annunciator alarms would provide indication that the CEA failed to move?

m. "CEA WITHbRAWAL ' PROHIBIT". ,

bl "CEA' MOTION INHIBIT".

"

- SECONDARY CEA GROUP SEQUENCE".

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. d. " SECONDARY POWER DEPEN INSERTION".1 i'

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R: actor Operctor Excmin:ti:n a

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08 .The basis for the RCP Trip Strategy in tiOF-0 and any of the succeeding EOPs will:

a. Ensure that during a cold leg break LOCA, RCPs remain running as long as possible, and during non-LOCA conditions, pressurizer spray is maintained, b. Ensure that during a hot leg break LOCA, RCPs are secured early enough to prevent a deep uncovery of the core, and during non-LOCA conditions pressurizer spray is maintaine c. Ensure that during LOCAs, sufficient flow is maintained to aid heat removal from the reactor vessel head, and during non-LOCA events pressurizer spray heat losses are minimize d. Ensure that during all events (LOCA and non LOCA) the core is kept from too deep of an uncovery and that the use of aux. Spray is minimize .Given the following conditions:

A RCS heatup is in progres RCS pressure IO250 hsl * The acoustic monitor for a PORV indicates valve leakag Which ONE of the following describes the expected tail pipe temperature and how tall pipe temperature will respond as RCS pressure decreases to 500 psia?

(Assume pressure downstream of the PORV remains constant.)

a. Tall pipe temperature will be higher than if the PORV opened at normal operating pressur As pressure decreases tail pipe temperature will increase, b. Tail pipe temperature will be higher than if the PORV opened at normal operating pressur As pressure decreases tall pipe temperature will decrease, c. Tail pipe temperature will be lower than if the PORV opened at normal operating pressure. As pressure decreases tall pipe temperature will increas d. Tail pipe temperature will be lower than if the PORV opened at normal operating pressure. As pressure decreases tail pipe temperature will decreas *

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Page 22 of 33

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i Reactor Operator Examination >

70g.Which CNE of the following is an approved altemate method of establishing hot leg injecten -

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during a LOCA event on Unit.17

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a. LPSI pump discharging to the pressurizer auxiliary spray lin b. LPSI pump discharging to the hot legs via the shutdown cooling suction lin .

c. HPSI pumps discharging to the normal pressurizer spray line, d. : Containment Spray Pumps discharging to the hot legs via the normal pressurizer spray lin .

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171.With power at 94%, which ONE of the following lists ALL RCP temperatures that c' an exceed 195 *

F and allow the RCP to continue to operate? ;

a. Upper or lower guide bearing temperatures and controlled bleedoff temperature b. Upper or downward thrust bearing temperatures, cE Upper or lower guide bearing and upper or downward thrust bearing temperature Td . Controlled bleed off temperatures.-

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72 . A loss of MCC-104R has occurre Which one of the following describes a boration flow path that remains available?

I a. RWT, CVC-508, CVC-504, charging pump suctio '

b. BAST, CVC-210Y, CVC 512, VCT, charging pump suction

, c. RWT, CVC-508, charging pump suction

'd. BAST, CVC-514, charging pump suction i

73 , The reactor is shutdown with shutdown cooling (SDC) in progress when the operating LPSI pump

.

becomes air bound and trips due to low RCS water level. After RCS wster level is restored, neither LPSI pump can provide significant flo ,

What other pumps can be aligned to the SDC system to provide SDC flow?

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1 HPSI pumps g b. Containment spray pumps c. Charging pumps d. Spent fuel pool cooling pumps i

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- y t 1 Reactor Operator Ex: mination 1

'li L 74 ;The air supply to the Component Cooling Water retum line containment isolation valve (CC-3833) :

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has been broken whl!tscaffolding was belig erocled. - >

nWhich'ONE of the following describes the effect, if any; this will have on Reactor Coolant Pump ; ;

operation?7 ;

s,[RCPs will have to bs tripped immediately.' f

L b.f RCP temperatures on two of the four pumps will increas c.E RCPs will be able to operate for 10 minute d.1 RCP cooling will be unaffected.

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75 . According to the Abnormal Operating Procedure for Loss of Component Cooling Water (CCW), - ,

which one of the following CCW malfunctions would require the Reactor to be TRIPPED? - ,

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a.1 Low level alarm in the CCW Head Tan b, Cavitation of running CCW pumps, 3 c. A trip of the 11 CCW Pump while runnin ,

d. - Low RCP CCW fiow alar . Given the following conditions:

Unit 1 is operating at normal operating temperature and pressure,

All systems are in automatic; Pressurizer Pressure Channel X la selected for contro ;

Pressurizer Pressure Controller PIC-100X is placed in MANUAL.

- PIC-100X output is reduced to 10%. ,

- With no further action, which one of the following describes the plant response?

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s. Pivportional heater output increases causing pressure to increase until spray valves open.

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b; Proportional heater output decreases causing pressure to decrease until backup heaters energiz c. Proportional heater output increases causing pressure to increase until a reactor trip cecur '

d.- Proportional heaters will cycle at a lower setpoint.

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Reactor Operator Examination- !

77 .The following plant conditions exist:

1.- Unit 2 is at 100% powe .

2. All control systems are in AUTOMAlE 3. Pressurizer spray valve is stuck OPE . NO operator action is take WHICH ONE of the following describes the effect of RCS pressure DECREASING to 2210 psla?

a. Pressurizer "PZR CH 100 PRESS" alarm is energize b. Proportional heaters are fully energized, c. Proportional heaters are partially energize d All backup heaters energize . Unit 1 is being shutdown to hot standby due to a Steam Generator Tube Lea Which ONE of the following indicates the tube leak has become a tube rupture?

a. With one charging pump running, letdown isolated, and pressurizer level can no longer be controlled at setpoin b. Wdh one charging pump running, and letdown flow at minimum and pressurizer level can no longer be controlled at setpoin A c. - When letdown flow combined with the tube rupture flow exceeds 45 GP d. When charging flow reaches 88 GPn .With AOP-2A being implemented, select the valve that is required to be CLOSED for isolation of a tube leak on steam generator 21, and is normally maintained open?

a. Steam Generator 21 Steam Supply valve (MS-4070-CV)

b, Steam Generator 21 Steam Supply Bypass Valve (MS-4070A-CV)

c. Steam Generator 21 Flow Control Valve (AFW-4511-CV)

d. AFW Pump 21 Trip Throttle Valve (MS-3986) !

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Reactor Operator Extmination - ;

= 80 .Given the following conditions: 4 1. A Steam Generator Tube Rupture has occurre l 2. All systems responded as expecte i 2. The performance of EOP-6 is in'progros . One Steam Generator has been isolate . All RCPs have been stoppe . RCS cooldown using natural circulation is in progres Which one of the fo!!owing describes the reason that the isolated SG pressure is of concern before the RCS can be placed on SDC7 l

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s. The isolated SG pressure would be too low due to excessive cooldown causing RCS water to enter the SG and reducing RCS inventory.-

b. . SG pressure is being maintained slightly less than RCS pressure to prevent secondary water ;

. entering the RC c. Since the RCS cooldown rate was maintained less than 35 F/hr, the affected loop has not

. been cooled sufficiently to allow SG depressurizatio d. The affected SG pressure is high due to thermal stratification of the secondary wate . A S/G tube rupture has occurred on Unit 1 and the RCS is being depressurized to restore -

pressurizer level. The following plant conditions exist:

SIAS has been blocked RCS pressure is 1200 psia Tcold is 508 F and Thot is 530 F CET subcooling is 37 F All RCPs are tripped Pressurizer level is 40 inches and rising Which one of the following actions should be taken in order to reduce the primary to secondary leak rate?

a.- -

Throlltle HPSI flo . b. l.ower RCS subcooling.

- c. Raise the RCS cooldown rat d. Open the S/G blowdown control valve .

Page 26 of 33

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3, Reactor Operator Examinati n 82 .Given the following:

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-During an Excess Steam Demand event, BOTH steam generators are suspected of being affecte Which one of the following' identifies the' steam generator (s) that should be isolated?

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a. Both steam generators, since a potential exists to over-cool the RC b. Only the steam generator with the highest Tc.

, c. Either steam generator, since it will aid in identification of the affected S/ .

d. Only the steam generator with the lowest pressure.

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~ 83 . A loss of condenser vacuum occurred on lait 1 with reactor power at 60%. The operators are reducing power and are able to maintain condenser vacuum at 24 inches H r

' Which ONE of the following indicates the power level at whlah the turbine will have to be tiipped if vacuum can NOT be increased to greater than 25 inches L a. 88 MW b. 176 MW c. 270 MW d. 440 MW :

84 .During the performance of EOP-7 " Station Blackout" On Unit 1, which one of the following describes the actions performed in aligning the electrical system for power restoration?

,

s Ensure the:

a.13KV Feeder breakers are CLOSE i b. 4KV Bus LOCl/SD sequencer is OF c. DG output breakers are CLOSE d. 14 4KV Bus Altemate Feeder Breaker is OPE ,

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Reactor Operator Ex mination t a

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85;.Which one of the following describes the' method used to operate AFW flow control valves during

' the performance of EOP-7, TStation Blackout"? -

a. Local manual control by an operator.'

b. $mtrol room operation after aligning N2 to the AFW ampitfier air syste c. Placing the controlle.-in Auto-Full open and controlling speed of the Steam Driven AFW pum '

d. Local manual control after aligning N2 to the AFW amplifier air syste . 86 . Following a loss oi 12120 VAC' bus, the performance of steps in AOP-7J requires the ESFAS SENSOR cabinets be remergized prior to the LOGIC cabinet ,

Which ONE of the following is the basis for the order of the steps?

a., Prevent inadvertent actuation since the Logic mooules are doenergized to actuate and the

. sensor modules are energized to actuat b. Prevent inadvertent actuation since the Logic modules are ensgtzed to actuate and the sensor modules are doenergized to actuate, c, - Properly align the Under Voltage Logic relay d Properly align the Under Voltage Sensor Relay . During the performance of a waste gas release from the 11 Waste Gas Decay Tank, WGS-2191-CV is found to be close Which valve must be closed as soon as possible to prevent a possible waste gas decay tank discharge to the waste gas surge tank?

a. Waste gas discharge flow control (WGS-2191-PCV)

b. Waste gas decay tank outlet (WGS-623)

c. - Waste gas discharge to Unit 1 plant vent (WGS-683)

d. Waste gas discharge final filter bypass (WGS-630)

.

d

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Reactor Operator Examination ~ ;

' 88 .Which one of the following is correct conoeming a loss of Instrument Air Pressure? -

Ts. Condensate Domineralizer Bypass Valve fails open.

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b. Pressurizer Spray Valves fail open -

c. Pressurizer Auxiliary Spray Valve fails closed,

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d. Containment Spray Control Valves fail closed.

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. 8g . During a loss of instrument air in MODE 1 operation, when would the reactor and turbine be :

tripped and EOP-0 implemented?

4' a. If instrument air pressure decreases to less than 40 psig and Feed Regulating Valve'controlis

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b. - if instrument ' air pressure decreases to 40 psig or.in the opinion of the SS or CRS continued

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_ plant operation may cause equipment damage, c. . lf component cooling containment isolation valves, CC-3832-CV or CC-3833-CV, begin to go 4 . shut and low flow alarms received on the RCP d. If component cooling containment isolation valves, CC-3832-CV or CC-3833-CV, begin to go

- shut or in the opinion of the SS or CRS continued plant operation may cause damage to the ,

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- RCPs.-

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90 .Why must the handswitch for the Containment Instrument Air Isolation, IA-2085-CV, NOT be held in the OPEN position when restoring instrument air to containment?

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a. Valve "OPEN" relay may tse damage b. Valve will not open until released to " AUTO" position.

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c. Protective feature will deenergize the "OPEN" circuit after 5 second , d. Valve time delay dropout relay will be defeated.

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Reactor Operator Excminati:n 91'.Given the following:

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. A fire has been detocted in a panel in the control room 1 Supervision has determined that the control room is to be evacuated

. - Prior to fire discovery,' both units were operating in Mode i f

= .- Prior to control room evacuation the required actions _of AOP DA " CONTROL ROOM '

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EVACUATION...".have been performed ;

Which one of the following describes the initial response of RCS temperature upon abandon 3ng the control room? -

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Temperature will be controlled:

a. at 515 F - 535 F by TBV . b. . at 515 F - 535 F by ADV l c. by the Main Steam Safety Valves cycling.-

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d.- by _ Auxiliary Feedwater flow and ADVs operating in automatic contro .Which one of the following describes the timing of actions that are accomplished during the performance of AOP-98, " Safe Shutdown due to a Severe Cable Spreading Room Fire"? -

a. = Establish charging flow with 60 minutes and AFW flow within 30 minutes, b. Establish AFW flow within 60 minutes and charging flow within 30 minutes, c. Stop Steam Generator Feed Pumps within 60 minutes and start 1 A Diesel Generator within 30 minutes, d. Start 1 A Diesel Generator within 60 minutes and stop Steam Generator Feed Pumps within 30 minute .

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4 - Reactor Operator Examination

93 . Given the following parameters:-

20830 _

0845 Thot -4821 .

482, .

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1 CET Temp. _ 587: _.585-

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' 467-

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Tcold' -

486 ,

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L Which ONE of the following describes the conclusion that can be made about natural circulation?

Adequate natural circulation' has:

af not been established because Thot is remaining constan b,- been established beceuse the delta between Thot and Toold is decreasing.-

c; been established because Tcold is decreasing, _ m m d. - not been established because the CET temp, is decreasin !

94 . A natural circulation cooldown is in progress. While cooling down with ADVs, which ONE of the-following will cause the most restrictive limitation on cooldown rate?

a. Isolating one steam generator, b. . Complying with Technical Specifications cooldown restrictions, c. Cooling down without main feedwater availabl d. Complying with Pressurizer cooldown restriction . During EOP-0, plant conditions warrant a safety injection actuation. Inaddition to the "SIAS ACTUATED" annunciator alarm, select the condition which ensures that SIAS has occurre ,.

a. HPSI and LPSI pumps running and proper flow exists for existing RCS pressur ; b. : HPSI pumps running and discharge pressure greater than or equal to RCS pressur '

c. HPSI pumps running and the auxiliary and main HPSI header isolation valves are open, d - HPSI, LPSI, and Containment Spray pumps running with HPSI and LPSI discharge valves

open.

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7, Reactor Operator Examination

' 96 .While operating Unit 1 @ 100% power, one Steam Gene stor Feed Pump (SGFP) tripped due to !

a mechanical fault. Reactor power was reduced to 60% while troubleshooting the falled pum l l

Operation may CONTINUE at this power level as long as which one of the following parameters is i maintalae l l

a. SGFP suction flow rate is 19500 gp b. SGFP suction pressure is 265 psi c. SGFP speed is 5375 RP d. SGFP d!scharge pressure is 1350 psi . A Main Feedwater Regulating valve (FRV) is being operated manually at the FRV shen a reactor trip occur .Which ONE of the following describes the required action?

a. Locally close the FR b. Close the Main Feedwater isolation Valv c. Position the FRV to 5% oper.,

d. Vent air from the FR Which one of the following describes the length of time from a valid low steam generator level condition (-170") to open the main steam supply valves (MS-4070&4071) to the turbine driven Auxiliary Feedwater Pumps?

a. 10 se b. 20 se c. 45 se d. 65 se .Which one of the following would require the tripping of only one RCP in each loop?

a. A Steam Generator tube rupture has occurred, RCS pressure is 1825 psi b. : A Containment isolation Signal has been received. RCS pressure is 1800 psi c. A Small Break LOCA has occurred, RCS pressure is 1725 psia, d. A Loss of Coolant Accident has occurred, RCS pressure is 900 psia.

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, - Reactor Operator Examinati:n

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100.Which one of the following states a condition requiring EOP-8 entry?

a. if two or more Safety Functions cre not met in EOP-1 with parameters returning to expected value :

b. . If a Reactor Trip occurs due to an unexplained generator prott.ctior' faul c. lf any single event has been diagnosed with parameters not retuming to expected value .

d. If a condition exists post trip for which an optimal EOP has not been identifwx l Page 33 of 33

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ATTACHMENT 3 RESOLUTION OF BG&E COMMENTS ON THE WRITTEN Exam SRO Exam Question 10 BG&E's comment: " Delete question. The role of CRS is not clear from the question, change of intent evaluator, safety screener, plant management staff or SRO. If he is to sign for SRO,it only requires that the change does not affect current plant operation and all answers are correct. Additionally, procedures do not contain a "materiallist," so the correct answer raay be eliminated as a distractor."

NRC response: Agree with BG&E comment, delete the question. The question concerns authorization to approve an immediate change temporary approval form. The correct answer addresses a change to a materiallis Materiallists are not addressed in Attachment 11,immediate Change Temporary Approval Form, of PR1-101, Preparation and Control of Calvert Clifis Technical Procedure Question 15 BG&E's comment: " Change answer key from b to d. The Station Blackout criterion is only Modes 1-4."

NRC response: Agree with BG&E's comment. The question posed was for classification of a fuel handling event Mode 6; the answer was applicable only in Modes 1 through 4. The answer was changed from "b.," " Site Area ,

Emergency" to "d.," " Alert."

Question 23 BG&E's comment: " Accept answers e and d, poor wording. Asks two questions, what provides boration, how do valves position on SIAS."

NRC response: Disagree, the question asks what the expected positioning of valves would be to allow boration flow on SlAS. The question also stipulates flow from the BAST. A review of the question determined that the answer stated to the question (c.) is correct. SRO and RO candidates should be able to assimilate conditions and develop a correct response. This question is within the expected abilities of SRO and RO candidate The above also applies to RO question number 2 Question 36 BG&E's comment: " Accept answer a and d, poor wording. Correct answer d infers that DSS is not independent of RPS. Eliminating this answer makes answer a the most correct choice since DSS is actuated by ESFAS."

NRC response: Disagree with BG&E comment, no change to the questio Answer "d." is correct, answer "a." would not be correct. The "a." answer:

" Tripping Engineered Safety Features Actuation System (ESFAS) input parameters which are independent / diverse of RPS," is not correct because input parameters are not tripped, outputs devices are tripped based on inputs. SRO and RO candidates are expected to know functions and

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c Attachment 3 - 3

connections of safety related systems. In addition, this question was reviewed by BG&E prior to exam administration and they stated that this was expected candidate knowledg The above.also applies to RO question number 42.

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Question' 40 BG&E's comment: " Accept answers c and b. Flow decreases during injection phase as RWT level decreases and containment pressure increase Flow increases after RAS due to lower total head, enntainment pressure does not need to be overcome."

NRC response: Disagree with BG&E's comment, no change to questio The question quite clearly states that the flow rate in question is subsaquent to the RAS signal and in f act gives further information that containment - ,,

pressure had decreased. The "b." answer solicited in the BG&E's comment ;

is a distractor that is correct during the initial injection phase but is not applicable during the recirculatinn phase, i.e., a good distractor. This-

- question is a besic knowledge question and expected SRO and RO knowledge. BG&E's comment also states that flow increases after a RAS

. due to lower total hea The above also applies to RO question number 4 Qu.stion 50 BG&E's comment: " Delete question. No incorrect answer--all are available."

NRC response: . Agree with BG&E's comment, question deleted. The question asked which pressurizer heaters would be available following a loss of offsite power assuming the diesel generators started and carried the 4160 vac buses. BG&E provided information that all heaters in question would be

- available with manual action required for eer h answer give The above also applies to 30 queelon numN,r 5 Question 55 BG&E's comment: " Accept answer a and d.1 HS-1711 causes the alarm as well as the lockout. No pushbuttons are labeled 2A in the plant, it is a reasonable assumption that HS-1711 is the 2A push-button."

NRC response: Agree, accept answer "a." or "d." as correct. 1 A DG Local

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Control Panel Alarm Manual,1C188 ALM, states that 1 HS 1711 (engine bay) will cause an emergency shutdown of the diesel generator. The alarm manual also states that depressing both local emergency stop push-buttons will cause an emergency shutdown of the diesel generato The above also applies to RO question number 63.

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Attachment 3 4 Question 67 BG&E's comment: " Delete question. No correct answer. "a" includes 508, not part of the flowpath from RWT. "b" does not include the boric acid pump and is not a credited flowpath, "c" contains 508 which is a BAST gravity feed valve. "d" equipment is not available due to power loss."

NRC response: Disagree with BG&E's comment, question not change Additional information supplied (P&l)) clearly shows that answer *b." is correct. BG&E's own comment states that a., c., and d. are not correc The b answer is correct and the flaw path was verified by P&lD and discussions with BG&E. BG&E's matement that the boric acid pump was not stated makes the flow path not tredible; however, the transfer pump is not necessary for gravity feed. Other components such as check valves and filters were also not stated in th i various answer The above also applies to RO question number 7 OLostion 74 BG&E's comment: " Accept answers a and b. Formally, there is no definition 9 of a S/G tube rupture vs tube leak at CCNPP. Going through the steps of AOP 2A would lead to either a shutdown or a trip. If a trip is warranted, EOP-6 may be entered. This may be a convoluted way of defining a tube rupture, but references were not available."

NRC response: Disagree with BG&E's comment, no change to questio Although there may not be a formal definition, it is generally understood that a tube rupture exixts when the leak is above the capacity of one charging pump, if this were not understood the barrier tables could not be used to classify an event because they refer to tube rupture for determination of a barrier f ailure. Also AOP 2A distinguishes between a RCS loak within the capacity (shutdown) of one charging pump and requires a reactor trip when leakage exceeds the capacity of one charging pump. In addition, during discussions with candidates during walkthroughs, this criterion was understood by most candidate The above also applies to RO question number 7 Question 90 BG&E's comment: " Accept answers b and c. Poorly worded. " Initial response" is unclesr. Immediately, temperature would be controlled by ADV quick open. Safeties would open as natural circulation is develope Temperature is not maintained until ADVs are shifted to 1C43."

NRC response: Disagree with BG&E's comment to accept both "b." and "c."

Based on the review of BG&E's justifications the question was deleted because there was no correct answer. Subsequent information requested by the chief examiner to better understand the comment justification indicated that temperature is controlled by a combination of ADVs and safeties, which was not one of the answer selection The above also applies to RO question number 9 _ ________ _ -___-_______ _ _

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Attachment 3 5 Question 99 BG&E's comment: " Answers a and b are correct. Answer key assumes an

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overfeed condition occurs but does not give the complete operator response required per EOP-0. EOP 0 also assumes the FRVs to be in a normal control room mode of operation."

NRC response: Agree with BG&E's comment, accept answer "a." Locally

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close the FRV, or "b." Close the main feedwater isolation valve. Subsequent

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Information requested by the chief examiner provided additional justification for BG&E's comment. There are two procedures that discuss operation of the feed regulating valve (FRV) in local manual. Under Ol 12A the unit must be in Mode 2 and the FRV isolation valves would be closed no no action would be required but the FRVs would be locally closed. _ The other procedure AOP 3G, Malfunction of Main Feedwater System, directs the ,

operator to go to EOP-0, Post Trip immediate Actions which requires closure of the FRV isolation valves if an overfeed cond; tion exist The above also applies to RO question number 9 RO Exam Question 22 BG&E's comment: " Accept answers b and c. See O22 attached."

NRC response: Agree with BG&E's comment. The question asked for VCT system response to LT-226 failing low. The P&lD shows that LT 226 provides an input to makeup valve CVC-512 (answer b.) and gives a low level alarm (answer c.).

Question 76 BG&E's comment: " Change answer key from c to b. Sec Q 76, (validated on simulator)."

NRC response: Agree with BG&E's comment, changed correct answer to

"b." 'The question asked what the plant response would be if pressurizer pressure controller was placed in manual and output reduced to 10 percent (desired pressure setpoint). The correct answer "b." states that the

proportional heater output would decrease and pressure would decrease until backup heaters energized to control plant pressure.

v t e Inspection Report - Calvert Cliffs - 1997010
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \|
1997 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 9(0) 10(0) 61(0) Security Operator Exams Emergency Planning Other

IR 05000317/1997010

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